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BOSTON EDIEON COMPANYBOO BovLaTON STREET

Tf sTON, M AssAcHusETTs 02199

WILUAM D. HARRINGTONesusom viss passessui

u .ss .

October 25, 1983

BEco 83-265

Mr. Domenic B. Vassallo, ChiefOperating Reactors Branch #2Division of LicensingOffice of Nuclear Reactor RegulationU.S. Nuclear Regulatory CommissionWashington, D.C. 20555

License No. DPR-35Docket No. 50-293

Proposed Technical Specification: Single Loop Operation

Reference: (1) Telecon Boston Edison, NRC & Lawrence Livermore Labs (LLL)9/27/83 (BECo #4.83.013)

Dear Sir:

During our telecon with your Mr. J. Donahue and Mr. T. Donich (LLL), Mr. Donahuerequested written confirmation of the items discussed regarding the administra-tive controls at PNPS for Single Loop Operation.

Enclosed, please find a copy of our procedure for Single Loop Operation Greaterthan 24 hours. This is a draft procedure and is subject to change pending final

iNRC approval. However, your areas of concern - APRM Rod Block and Scram Setpoints,

! and the MCPR and MAPLHGR - are addressed.

The Technical Specifications for PNPS do not allow changes to the APRM gain. Our|

proposed plan for Single Loop Operation does not require a change to this gainand consequently we have not requested Technical Specification revision to this

| area.|

| With regards to the flow bias compensation for the idle recirculation pump, pleasebe advised that PNPS flow bias is derived from recirculation pump flow measurement,!

therefore, the idle loop is automatically accounted for in the flow bias,

j Finally, you addressed isolation of the idle loop. Although not specified in our| Technical Specification submittal, by procedure (see attached) the discharge (or||

| .AN

i 8310310290 831025DR ADOCK 0500029

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EO3 TON ECICON COMPANY

.Mr. Domenic B. Vassallo, ChiefPage 2

suction) valve in the idle loop would be closed. This is per General ElectricReport "PNPS Single Loop Operation," NED0-24268, June,1980, which is referencedin our proposed Technical Specification change (page 13).

We trust this satisfies your concerns in this area, however, should you havefurther questions, please do not hesitate to contact us.

Very truly yours,

MTL/ mat

cc: Mr. J. Donahue (NRC)

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Single loop Operation Greater Than 24 Hours

I. PURPOSE

The purpose of this procedure is to provide a mechanism for documentingthat the specific technical specifications associated with single loopoperation are in effect when one recirc loop is ou service and arereturned to normal when both loops are back in op Compliancewith these specifications is necessary for opera single loopconfiguration for periods greater than 24 hours

s

II. DISCUSSION

culationa singThe capability of operating at reduced powery/ outage /zecningloop is highly desirable, from a plant a bi

re or otherstandpoint, in the event maintenance o 6 * K' ulation pumcomponent renders one loop inoperative

III. REFERENCE MATERIAL -

A. Proposed technical specificat on't nge con g single loop

operation (Proposed Change #80-6).

B. NE00-24268, Pilgrim Nuclear Power Station $1 le Loop Operation.

QsofcoolantanalysisinC. NEDO-20566, Analytica mode3accordance with 10 CF .

NIV. PREREQUISITES

A. The idle loop recirculation p electrically disarmed with the

discharge valv losed preclud peration of the pump or

injection of co slug into vessel. In the event that thedischarge is i c le of closure, the idle loop flow will be

prevented cl ng 4 lve.

I B. The re rcul n.

11 be placed in the manual mode,there limina the need for control system analyses.

I C. The settings the ro lock monitor, APRM rod block trip, andflow scram b modified as necessary to provide for single1 opera [.

D. PLHG stric ions will result in a percent reduction for all

1.1

ECo wil'l.1,im he power level to 50%.

V. APPARATUS

None

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VI. PRECAUTIONS

A. When the station is in a single loop operational modfollowing steps should be performed. This procedur wil_1maintained by Reactor Engineering when in effect. -

1. The Watch Engineer should notify the Reactor er theI&C Engineer when operating with ene loop o,u rvice. /

?j(a) Rx Engineer notified 37^

Watch eer

f&.(b) I&C Engineer notified -

Watc in h

Theprocesscomputercurveofdriveflowvs.corhowisbeing2.updated by Nuclear Technici ncorporated inTo thecomputer data banks by Nuc ar Techn in der for thecomputer to calculate the t ore flow u single loopoperation.

/% /h r Technician

|.k ~

edits.Verification by wingcf

Reactor Engineer.

Watch Engineer,

3. T MA %f all fuel types have been reduced by Myrcent and .t,he MCM perating limit has raised by, and have

corporate,d the process computer data banks by theNuclea chnicl

,

~

Nuclear Technician

-. . . . _ _

.-

Verification by reviewing computer edits. -

kNReactor Engi er

Watch Engi /K ~J

,~-ThesettingsfortherodAlockmonitorha'veb4. odified to

nt A % isS f (.65W + 38.7)I FRP as per at cprocedure. MFLPD

-

" '

.

'

I&C Enginee) '

.

Watch EngT r

5. The settings for the_APRQodbloc( i) have been modifiedto 5 * ( .65W + 38.7) FRP 1 asper aT ent B to thisprocedure. 2MELP() g

#,

T -t I&C Engineer

'/ Watch Engineer

,

,

|! 6. The s for th APR ( lux scram trip have been modified to! S 65W + RP las per attachment B to this

( pr e LPDj! T.

.

I&C Engineer,

Watch Engineer

-.

7. The idle recirculation loop recirculation pump haselectrically disarmed.

~

-

Watch Eng K

8. The recirculation controls have been pla d e manual mod .

Mhf'" %

9. Caution tags have been placed on the ret tro s, the

APRM-RBM recorders and the APRM-RBM cabinets (Pa 937),stating that " single loop" on is in effec nd the APRMscram and rod block and ro lock m set ngs have been

4modified.

OEngineer

1/~

10. Core thermal po be . ed to 50%.

W]Watch Engineer

..

a. When tion r rn to two loop operation the

fo wing s shou, e performed.

NThe h En ineer should notify the Reactor Engineernd the C gineer.

'

(a) R'x.E,ng r notified.

,

Watch Engineer

(b) I&C Engineer notified.

Watch Engineer

-w- -- '' - ,.-w- es-v ---w--- _ _ _ - _ _ _ _ __ ____m

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(2) The process computer curve of drive flow vs. c re flowhas been returned to the two loop operation bythe Nuclear Technician.

Nuclear Te~

n

U. 7Verification by reviewing computer d

..~N> L

Wa Engine

.

\ '#Reactor % neer

(3) The MAPLHGR curves a d the operating MCP ave beenreturned to the two ration valves by theNuclear Technician.

mea M echnician

Verificati eviewing to er edits.

N. QWatch Engineer

.

4Reactor Engineer

( tting or the rod block monitor has been returned

+42){MFLPDJFRP lby performing procedureto S .65

L8.M.2 ~1.Z, block monitor calibration.

_

Watch Engineer

~

I&C Engineer

__ _- . - - _ _ . _. _ ___ -__ _____ _ __ ___ _

.,

N

(5) The setting for the APRM rod block trip hareturned to S 6 (0.65W + 42) ~ FRP ' by p orming

,MFLPDJprocedure 8.M.1-4, APRM flow bias signa calib on.

'

~

''Watch inM,n.

e AI nginear

(6) The settinc tor the APRM TJ ram tr as beenreturned to 5 0 (0.65W + 55) F by perf ing

,MFLPD'.gproceda e 8.M.1-4, flow breakers signal,c ibration.

f

A i

Watch Engi er

~

y g ngineer

(7) The id i cu'htion loop r rculation pump has been

return s rvig'.

,'r*

- Watch Engineer|

( n tag h e been removed from the recirc.ntrolle the RM-RBM recorders and the APRM-RBMb9qets ( el 937).

t

i. Watch Engineers

' dure will be filed in the Reactor Engineering(9) This r e

file er section 10.11.

Reactor Engineer

|i

|1

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...

SINGLE LOOP OPERATION SURVEILLANCE

t.TTACHMENT A s.

ROD BLOCK MONITOR SINGLE LOOP CALIBRATI

DISCUSSION: ,m ,#

For single recirculation loop operation, the normal r bloc , ip in the rod

block monitor must be recalibrated per technical sp atiop.y .

~

APPARATUS: N ,-

None. VPRECAUTIONS: 3

A. A rod block occurs if any of the followi ons e st unless themonitor is bypassed:

1. Either RBM upscale trip. ~

2. Either RBM inoperative trip. '. >

it e fun positi rod block occurs ifB. With the reactor mode switceither RBM downscape trip s unl&ss lhe monitor is bypassed.

8 Th

PROCEDURE:

| A. Obtain shift supervisor's' issio rform the calibration.

B. Bypass the RBM to b ated el 05).

C. Place the RBM m ch to e te's power flow position.

D. Place the fr tp 1 me n ion switch to the FLOW position.,

E. Adjust the otentiometer an indication of 100% flow on the f ront'

panel meter.

F. Place the meter functio sw ch to the average position.

G. Adjust the POWER potentio ter for an indication of 102% power on thefront panel meter.

H. Momentarily depress the local setup switch and verify the " Alarm Ref SetH", light is illuminated.

1. While holding the trip reset switch depressed, adjust R S on the FlowControl trip reference unit (234) until the "High" light just illuminates.

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...

J. Place the RBM mode switch to the operate position.

K. Perform independent verification of setpoint ( f 102% power @ 10 flow).

L. Inform shift supervisor on completion of this procedure for b andcomplete documentation.

RBM I&C IndependentChannel Technician Verification Date

A /

.hB -

.

.

,

3

h\bT b,,,/..

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,

_ . _ _____ _ __ . __ _

....

SINGLE LOOP OPERATION_

ATTACHMENT B

APRM SINGLE LOOP CALIBRATION- (.-

DISCUSSION: /Pf

For single recirculation loop operation, the APRM flow booed,W ip functionsmust be recalibrated per technical specifications. /

,

s

?APPARATUS:

'

.

None.

*'

PRFCAUTIONS:

any of the following conditions exist u-' - themonitor[willoccurifA. With the reactor mode switch in any ition, a

s bypassed.

.

1. Any APRM upscale high trip.2. Any APRM inoperative trip.

B. With the reactor mode switch in the run posit rod block will occur,

if any APRM downscale trip c trips unles e monitor is bypassed.

C. With the reactor mode swi ny ty M on a half scram trip will occur3;

if any APRM high high or opera ve trip Uc rs unless the monitor is

! bypassed.

D. Only one APRM will be rated t,me.

E. When calibrating APRM A or D b s bo to avoid inadvertant trips due to

error, also when APRM o F bypass both for the same reason..

| PROCEDURE:

|

A. Obtain shi ervisor's pe i sion to calibrate.| ,

|| B. Bypass APRM channe be c rated.

NOTE: See Precaution ecti E.

C. Place APRM mode switch EST POWER FLOW position.

|

D. Place the meter function switch to the FLOW position.'

E. Adjust the FLOW potentiometer for an indication of 100% flow on the frontpanel meter.

_ _ _ __ _ _ . _ _ _ . _ _ _ _ .

'\

....

F. Place the meter function switch to the AVERAGE position.

G. Adjust the POWER potentiometer for an indication of 102X powerfront panel meter.

H. While holding the TRIP RESET switch depressed, adjust R3 o thecontrol trip reference unit (233) until the "High" light illumi es.

- ri'

I. Adjust the POWER potentiometer for an indication of 115 r onfront panel meter.

J. While holding the TRIP RESET switch depressed, adju he flowcontrol trip reference unit (233) until the "High ht just"

illuminates. (&

K. Place the APRM mode switch to the operate posi on.'

L. Return the APRM bypass switch to normal (Panel 905).

M. Perform independent verification of setpoint 102% power f or ro block and115% for scram @ 100% flow.

N. Inform the shift supervisor on comple {allAPRMchannels and complete documentation.

APRM 1&C In ntI Channel -lechnician Veri ci tion Date

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