e ,/ a ar g) .e . UNITED STATES , } g%e 7; NUCLEAR RL JULATORY COMMISSION ; ; E WASHINGTON, D C.20555 \; 6 / ' ..... THE YANKEE ATOMIC ELECTRIC COMPANY DOCKET NO. 50-29 Y'NKEE NLICLEAR POWER STATION AMENOMINT TO FACILITY OPERATING LICENSE i | Arendment No. 66 License No. DPR-3 1. The Nuclear Regulatory Ccmmission (the Co cission) has found that: A. The application for amendment by the Yankee Atomic Electric * Company (the licensee) dated October 22, 1980, complies with tne standards and requirements of the Atomic Energy Act of 1954, as arended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; S. The facility will o;erate in conformity with the application, the provisions of the Act, and the rules and regulations of the Co =ission; C. There is reasonable assurance (i) that the activities authorized by this arendrent can be conducted without endangering the health ^ and safety of the public, and (ii) that such activities will be conducted in co pliance with the Co . mission's regulations; ~ D. The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Co mission's regulaticns and all applicable requirements have been satisfied. 81041600 9
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UNITED STATES,
} g%e 7; NUCLEAR RL JULATORY COMMISSION; ; E WASHINGTON, D C.20555
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THE YANKEE ATOMIC ELECTRIC COMPANY
DOCKET NO. 50-29
Y'NKEE NLICLEAR POWER STATION
AMENOMINT TO FACILITY OPERATING LICENSEi
|Arendment No. 66License No. DPR-3
1. The Nuclear Regulatory Ccmmission (the Co cission) has found that:
A. The application for amendment by the Yankee Atomic Electric *
Company (the licensee) dated October 22, 1980, complieswith tne standards and requirements of the Atomic EnergyAct of 1954, as arended (the Act), and the Comission'srules and regulations set forth in 10 CFR Chapter I;
S. The facility will o;erate in conformity with the application,the provisions of the Act, and the rules and regulations ofthe Co =ission;
C. There is reasonable assurance (i) that the activities authorizedby this arendrent can be conducted without endangering the health^
and safety of the public, and (ii) that such activities will beconducted in co pliance with the Co . mission's regulations;
~D. The issuance of this amendment will not be inimical to the comon
defense and security or to the health and safety of the public;and
E. The issuance of this amendment is in accordance with 10 CFR Part51 of the Co mission's regulaticns and all applicable requirementshave been satisfied.
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2. Accordingly, the license is amended by changes to the TechnicalSpecifications as indicated in the attachment to this licenseamendment, and paragr:ph 2.C(2) of Facility Operating LicenseNo. DPR-3 is hereby amended to read as follows:
(2) Technical Specifications,
The Technical Specifications contained in Appendix4
A, as revised through Amendment No. &6, are hereby4 incorporated in the license. The licensee shalll operate the facility in accordance with the Techni-'
cal Specifications.!
3. This license amendment is effective as of the date of its issuance.
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FOR THE HUCLEAR REGULATORY COMMISSION
leb4 b|. hy JYl'
Dennis P. Crutchfield ChiefOperating Reactors Branch #5Division of Licensing
Attachment:Changes to the Technical
Specifications>
Date of Issuance: April 6,1981
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ATTACH"ENT TO LICEriSE AMEf;:e:I tit tiO. 66
FACILITY OPERATIfiG LICEtiSE |40. DPR-3
DOCKET fi0. 50-29
Replace the following pages* of the Appendix "A" Technical Specificationswith the enclosed pages as indicated. The revised pages are identified byAr.endr.ent number and contain vertical lines indicating the area of change.
Delete Pace Insert Pace
IV IV..
VII VII
XII XII
3/4 4-1 3/4 4-1
3/4 4-2 3/4 4-2
- 3/4 4-2A
- 3/4 4-25
3/4 4-2C-
3/4 9-9 3/4 9-9
- 3/4 9-9A
S3/4 4-1 B3/4 4-1
53/4 9-2 B3/4 9-2
*0verleaf pages III, VIII, XI. 3/4 9-10. B3/4 4-2, and B3/4 9-1 areincluded for docunient corpleteness.
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INDEX
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LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS
SECTION Page'
3/4.0 A P P L I'CA B I L ITY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 0-1
3/4.10.1 SHUTDOWN MARGIN ........................................... B 3/4 10-1.
3/4.10.2 CONTROL ROD OPERABILITY AND INSERTION LIMITS . . . . . . . . . . . . . . B 3/4 10-1
3/4.10.3 PRESSURE / TEMPERATURE LIMITATIONS-REACTOR CRITICALITY . . . . . . B 3/4 10-1
3/4.10.4 PHYSICS TESTS ............................................. B 3/4 10-1
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YANKEE-ROWE XIIAmendment No. 46, 49, 66
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3 /4.4 MAIN COOLAhT $YSTEM'
3/4.4.1 MAIN COOLANT LOOPS
COOLANT CIRCULATION - STARTUP AND POWER OPERATION
LIMITING CONDITION FOR OPERATION
3.4.1.1.1 All main coolant loops shall be in operation with all loopisolation valves, open with power re=oved per Specification 4.5.2.b.3.
APPLICABILITY: MODES 1 and 2 .
ACTION:
a. With the requirements of the above Specification not satisfied, bein at least HOT STANDBY within 1 hour.
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SURVEILLANCE REQUIREMENTS
4.4.1.1.1.1 'The above required main coolant loops shall be verified 'to be in '
operation and circulating main coolant at least once per 12 hours.
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YANKEE-P.O'.;E 3/4 4-1 Amendment No. jdI 66f.
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MAIN COOLANT SYSTEM
COOLANT CIRCULATION - HOT STANDBY |
LIMTING CONDITION FOR OPERATIO'N
3.4.1.1.2 a. All main coolant loops shall be OPERABLE with all loop~
isolation valves, open with power removed per Specification4.5.2.b.3.
b. At least one main coolant loop shall be in operation.*
APPLICABILITY: MODE 3
ACTION:
a. With less than the above required main coolant loops OPERABLE,restore the required loops to OPERABLI status within 72 hours or be fin HOT SHUTDOWN within the next 12 hours,
b. With no main coolant loop in operation, suspend all operationsinvolving a reduction in boron concentration of the Main CoolantSystem and immediately initiate corrective action to return therequired coolant loop to operation.
With the reactor vessel and connecting pressurizer system isolatedc.
from the heat removal system by closing the loop isolation valve (s),leak testing may be performed provided that the coolant temperaturein the reactor vessel does not increase at a rate exceeding 500per hour, the maximum temperature increase during the test period
I does not exceed 100 F, and pressurizer pressure does not exceed0
2485 psig. -
SURVEILLANCE REQUIREMENTS-
N 4.4.1.1.2.1 At least the above required cain coolant pumps, if not ins,soperation, shall be determined to be OPERABLI once per 7 days by verifyingcorrect breaker alignments and indicated power availability.
4.4.1.1.2.2 At least one Main Coolant loop shall be verified to be inoperation and circulating main coolant at least once per 12 hours.
*All main coolant pumps =ay be de-engergized provided (1) no operations arepermitted that would cause dilution of the main coolant system boron
| concentration, and (2) core outlet teeperature is maintained at least 100Fbelow saturation te=perature.
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YANKEE-ROWE 3/4 4-2 Amendment No. fsf. 66
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" MAIN COOLAhi SYSTEM
SURVEILLANCE REQUIREMEh7S
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4.4.1.1.2.3 Determine that the steam generators associated with the maincoolant loops required to be in operation are capable of decay heat removal byverifying at least once per 24 hours that:
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The Main Coolant System is closed and pressurized to > 100 psi abovea.,
: saturation pressure.
b. The Main Coolant System loop cold and hot leg stop valves are fullyopen, with the bypass valve closed.
The steam generator water level is above the top of the tube bundle.c.
i d. An inventory of over 85,000 gallons of primary grade feedwater isavailable.
3.4.1.1.3 a. A: leas: two of the coolant, loops listed below shall beOPERA 3LE:**
1. Main Coolant Loop 1 and its associated steam genera:or and=ain coolant pu=p,
2. Main Coolant Loop 2 and its associated stea: generator and
| =ain c oolant pe=p, ,i1 3. Main Coolan: Loop 3 and its associa:ed steam generator and' =ain coolant pu=p,
4 Main Coolant Loop 4 and its associated s:ca= generator and=ain coolant punp,
5. Shutdown Cooling Sys:e=, (Shutdown Cooling Pu=p and Cooler)
6. Shutdown Cooling Syste=, (Low Pressure Surge Tank CoolingPu=p and Cooler)
b. At least one of the above coolant loops shall be in operation.*,
APPLICABILI"Y: MODES 4** and 54
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a. With less than the above required loops OPERA 3LE, i==ediatelyini:iate correc:ive action to return the required loops to '"
OPERA 3LE status as soon as possible; be in COLD SHL*TDOWN within20 h our s .
b. Wi:5 no coolan: loop in operation, suspend all operations.involving a reduction in baron concentration of the MainCoolant Syste= and i==ediately initiate corrective ac: ion toreturn the required coolan: loop to opera: ion.
*All =ain coolant pu=ps and decay heat re= oval pu=ps =ay be de-energicedprovided (1) no operations are permi::ed that would cause dilution of the =aincoolant syste= boron concen: ration, and (2) core outle te=perature is' aintained at leas: 100F below saturation te=perature.=
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l.**All =ain coolant loops shall be OPERABLE with all loop isolation valves, jopen with power re=oved per Spe:ification 4.5.2.b.3 when in Mode 4
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Amendment No. 66
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MAIN COOLANT SYSTEM
LIMITING CONDITIONS FOR OPERATION (Continued)
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'*ith the reactor vessel and connecting pressurizer systemc. -
isolated from the heat re= oval system by closing the loopisolation valve (s), leak testing may be performed provided thatthe coolant temperature in the reactor vessel does not increaseat a rate exceeding 500 per hour, the =axi=us te=peratureincrease during the test period does not exceed 1000F, andpressurizer pressure does not exceed 2485 psig.i
SURVEILLANCE REOUIREMEh*IS
4.4.1.1.3.1 The required residual heat removal loop (s) shall be deter =inedOPERA 312 per Specification 4.0.5.
4.4.1.1.3.2 The required main coolant pu=p(s), if not in operation, shall bedetermined to be OPERA 31I once per 7 days by verifying correct breakeralignments and indicated power availability.
4.4.1.1.3.3 Determine that the steam generator (s) associated with the mainc oolan t loop (s) required to.be in operation are capable of decay heat removalby verifying at least once per 24 hours that:
The Main Coolant System is closed and pressurized to 100 psi abovea.
saturation pressure.
- b. The Main Coolant System loop cold and hot leg stop valves are fullyopen, with the bypass valve closed. .
c. The stea= generator water level is above the top of the tube bundle.w
d. An inventory of over 85,000 gallons of pri=ary grade feedwater isavailable.
e. A boiler feed pu=p is 0? ERA 3LE.i
4.4.1.1.3.4 At least one coolant loop shall be verif'ied to be in operation -
and circulating main coolant at least once per 12 hours.
4 . 4 .1.1. 3. 5 Verify that the Shutdown Cooling System isolation valves arelocked closed within one hour prior to increasing Main Coolant System pressureabove 300 PSIG.
;4. 4.1.1. 3. 6 At least once per 18 months, during shutdown, demonstrate mainI koolant loop isolation valve operability by cycling each valve through at
'least one co=plete cycle of full travel fec= the control roc =.
{ YANKEE-ROWI3/4 4-2C
Amendment No. 66
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REFUELZ?IG OPERATZONS
RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION ,
ALL WATER LEVELS -
LIMITING CONDITION FOR OPERATION
3.9.8.1 At least one residual heat removal (RHR) loop, either the ShutdownCooling pu=p and Cooler or the Low Pressure Surge Tank Pa=p and Cooler, shallbe in operation.
APPLICABILITY: MODE 6
ACTION:
a. With less than one residual heat re= oval loop not in operation,e xce p t as provided in b. below, suspend all operations involving anincrease in the reactor decay heat load or a reduction in boronconcentration of the Main Coolant Syste=. Close all containmentpenetrations providing direct access from the containment atmosphereto the outside atmosphere within 4 hours.
b. The residual heat removal loop may be re=oved from operation for upto 6 hours in any 24 hour period during the performance of COREALTERATIONS, or during changeover to the backup pump and cooler.
c. The provisions of Specification 3.0.3 are not applicable.
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SURVE!LLA::CI FIOUIREME CS
4.9.8 At least one residual heat removal loop shall be determined to be inoperation and circulating main coolant at a flow rat'e of 950 gpm at leastonce per 24 hours. .
3.9.8.2 Two Residual Heat Re= oval (RHR) loops shall be OPERABLE.<
APPLICABILITY: MODE 6 when the water level above the top of the irradiatedfuel asse=blies seated within the reactor pressure vessel isless than 32 feet.
ACTION:
With less than the required RHR loops OPERABLE, i= mediately initiatea.corrective action to return the required RHR loops to CPERABLEstatus as soon as possible.
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b. The provisions of Specification 3.0.3 are not applicable.
S'JRVEILLANCE REOUIPIMENTS
4.9.8.2 The required Residual Heat Re= oval loops shall be determined CPERABLEper Specification 4.0.5.
3.9.9 The containment purge fan shutdown system shall be OPERABLE.
APPLICABILITY: During CORE ALTERATIONS.5:.:... . . ..
ACTION: {;.~.;;.;.;_.g.
With the containment purge fan shutdown system inoperable, remove power~~
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to the purge fan. The provisions of Specification 3.0.3 are'not ap- . . . . . . .
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34.9.9 The containment purge fan shutdown system shall be demonstrated,
OPERABLE within 100 hours prior to the start of and at least once per 7 =
days during CORE ALTERATIONS by verifying that containment purge fan=".!!
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shutdown occurs on manual initiation from the primary auxiliary building |.:.T.fan room. ...;..
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YANKEE-ROWE 3/4 9-10Amendment No. 66
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'3/4.4 MAIN C00LA' SYSTEM*
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3/4.4.1 MAIN COOLAhT LOOPS
The plant is designed to operate with all main coolant loops 5r.cperation, and maintain DNER above 1.30 during all normal operatims andanticipated transients.
In MODE 3, a single =ain coolant loop provides sufficient * re= oval,
capability for removing decay heat; however, single f ailure consihration'srequire that two loops be OPERAELE. Safety Injection System conmiiisrationsrequire f our loops to be OPERABLE.
In MODES 4 and 5, a single main coolant loop or RER loop prsidessufficient heat removal capability for removing decay heat; but single failurecensiderations require that at least two loops be OPERABLE. Thus,if the =aincoolant loops are not OPERABLE, this specification requires two M loops tobe OPERABLE. Safety Injection System considerations require four!aops to beOPERABLE in Mode 4.
The operation of one Main Coolant Pump or one RHR pu=p provits adequateflow to ensure mixing, prevent stratificat. ion and produce gradualmactivitychanges during boron concentration reduction in the Main Coolant Setem. Thereactivity change rate associated with boron reduction will, thesusTure, bewithin the capability of operator recognition and control.
The requirement to maintain the boren concentration of an isehted loopgreater than or equal to the boron concentration of the operating 3 sopsensures that no reactivity addition to the core could occur durig startup ofan isolated loop. Verification of the boron concentration in an implated loop!
| prior to opening the stop valves provides a reassurance of the asisumancy of thepboren concentration in the isolated loop. Startup of an isolated'inop will'
inject cool water from the loop into the core. The reactivity trasientresulting c= this cool water injection is minimized by delayingirolated
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loop startup until its te=perature is within 300F of the operatig loops.;".aking the reacter suberitical prior to loop startup prevents anewwer spike'which could result from this cool water induced reactivity tran n .
The prohibition on starting a main coolant pump without a bdKe in thepressurizer or with a SG/MCS temperature difference of 1000F reami=ement isnecessary to prevent exceeding the isother=al Appendix G curve limirs underthe =ost restrictive MC flow initiation transient if the PORV or EE reliefvalves fail.
3/4.4.2 and 3/4.4.3 SAFETY VALVES
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The pressurizer code safety valves operate to prevent the Main Coolant' | System from being pressuri:ed above its Safety Limits of 2735 psip Each
j :sfety valve is designed to relieve 92,000 lbs per hour of saturaad steam atthe valve set peint. The relief capacity of a single safety valwis adequateto relieve any overpressure condition which ceuld occur during sewn. In'
the event that no safety valves are OFERABLE, an operating Shutdcum Cooling/ System connected to the Main Coolant Syste= provides overpressure mlief
:spability and will prevent Main Coolant Sys t em overpre s suri:a tiza duringsaatdown.
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YANKEE-ROWE S 3/4 4-1 Amendment ht.47, 59, 66
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MAIN COOLANT SYSTEM
BASES.
SAFETYVALVES(Continued)
During operation, all pressurizer code safety valves must beOPERABLE to prevent the Main Coolant System from being pressurized aboveits safety limit of 2735 psig. The ec=bined relief capacity of all ofthese valves is greater than the maximum surge rate resulting frem acomplete loss of 1cLd assuming no reactor trip until the first ReactorProtective System trip set point is reached (i.e., no credit is takenfor a direct reactor trip on the loss of load) and also assuming no-
operation of the power operated relief valves or steam dump valves.
Demonstratien of the safety valves' lift settings will occur onlyduring shutd:wn and will be performed in ac:ordance with the provisionsof Section XI of the ASME Soiler and Pressure Code.
The SCS passive code safety valves, SV-204 and SV-205, are availableto relieve expansien or mass addition at all MCS temperatures < 300'F.Each of the two valves has the capacity to relieve 101 g;m of TOO*Fwater at a set pressure of 425 psig plus 10 accurulation. The 1ew _
setooint PORV, PR-50V-g0, is available to relieve expansion or ass "~ ~
addition at MCS temperature < 324*F.
3/4.2.4 PRESSURIZER.
A bubble in the pressurizer ensures that the Main Coolant|System is. net a hydraulically solid system and is capable of accom-
modating pressure surges during operation. The bubble also \protects the pressuri:er code safety valves and power c;erated reliefvalve against water relief. The ;cwer operated relief valve and
|bubble function to relieve Main Cociant System pressure during allj design transients up to and including the design step load decrease with
steam dump. Operation of the pcwer operated relief valve minimizes the'
undesirable opening of the spring-loaded pressuri:er code safety valves.3
| The pressurizer surge volume of > 198 ft requirement providesl sufficient time for corrective operator action to prevent exceeding
the isothermal Appendix G curve ifmits under the most restrictive mass'
' input accident should the PORY fail to operate at the icw setpoint.-
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i^YAN KEE-RO'4E B 3/4 2-2 Amend ent No. 59,
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J /4. 9.1 REACTIVITY
The limitations on reactivity ensure that: 1) the reactor will ~==re, ain substantially suberitical during CORE ALTERATIONS, and 2) a ==
uniform boron concentration is maintained for reactivity control in the ~
water volume having direct access to the reactor vessel. E
3/4.9.2 INSTRUMENTATION " +.:
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The OPERABILITY of the source range neutron flux monitors ensures =
that redundant monitoring capability is available to detect changes in ..i.the' reactivity condition of the core during CORE ALTERATIONS. One 31.:.monitor is acceptable whenever CORE ALTERATIONS are not in progress on ~ ~ " .the basis of the core stable reactivity condition. ~~'
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3/4.9.3 DECAY TIME-5!
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==3/4.9.4 CO'!TAINMENT BUILDING PENETRATIONS
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Th'e requirements on containment building penetration closure and,
OPERABILITY ensure that a release of radioactive material within con- .92tainment will be restricted from leakage to the environment. The ;3OpERASILITY and closure restrictions are sufficient to restrict radio- . ._ i=.=active material release from a fuel element rupture based upon the lack %:.of containment pressurization potential while in the REFUELING MODE. ]p
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3/4.9.5 COMMUNICATIONS a.
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The requirement for coimunications capability ensures that re-fueling station personnel can be prcmptly informed of significant changes-
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3/4.9.6 SHIELD TANK CAVITY MANIPULATOR CRANE' OPEPA3ILITY;
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The OPERABILITY require =ents for the manipulator cranes ensure that: 1)the manipulator crane and universal handling tool will be used for movement ofcontrol rods and fuel assemblies, 2) each erane and tool has sufficient loadcapacity to lift a control rod or fuel asse=bly, and 3) the core internals and,
1 pressure vessel are protected from excessive lif ting force in the event they'
are inadvertently engaged during lif ting operations.!I 3/4.9.7 CPANE TRAVEL - SPENT FUEL PIT
The restriction on move =ent of loads in excess of the nominal weight of afuel assembly over fuel asse=blies in the spent fuel pit ensures that in theevent this load is dropped (1) the activity release will be limited to thatcontained in a single fuel asse=bly, and (2) any possible distortion of thefuel in the storage tanks will not result in a critical array. This;
assumption is consistent with the activity release assu=ed in the accidenti
| analysis.'
Handling of the present fuel pit building roof hatches for infrequenttransfers of spent fuel racks by ad=inistrative control will assure safe
.handling of the roof hatches. The restriction of movement of the spent fuel
d storage racks and spent fuel inspection stand over spent fuel ensures that arack or stand cannot be dropped on spent fuel. Dropping of a rack or stand !
from a =aximum height will not result in loss of integrity of the fuel pit'
floor. Handling of the fuel handling equip =ent for infrequent maintenance byadministrative control will ensure the safe handling of any fuel handling
| ce=ponents. Handling of fuel casks over the spent fuel pit is not pe r=i t t ed
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until such ti=e as NRC has reviewed and approved the spent fuel cask drop
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{3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATIONi
The requirement that at least one residual heat removal (RHR) loop be ini operation ensures that (1) sufficient cooling capacity is available to remove
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decay heat and maintain the water in the reactor pressure vessel below 1400Fas required during the REFUELING MODE, and (2) sufficient coolant circulation
I is maintained through the reactor core to minimize the effect of a borondilution incident and prevent boron stratification.
The require =ent to have two RER loops OPERABLE when there is less than 32feet of water above the core ensures that a single failure of the operating
| RHR loop will not result in a co=plete loss of residual heat removalt
capability. With the reactor vessel head re=oved and 32 feet of water abovethe core a large heat sink is available for core cooling. Thus, in the event
, of a f ailure of the operating RHR loop, adequate time is provided to initiateI e=ergency procedures to cool the core.i
