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3.1.2 Pressurization, Heatup, and Cooldown Limitation

Specification

3.1.2.1 The reactor coolant pressure and the system heatup and cooldownrates (with the exception of the pressurizer) shall be ILnitedas follows:

Heatup:

Heatup rates and allowable combinations of pressure and tempera-tures shall be limited in accordance with Figure 3.1.2-1A Unit 1

3.1.2-1B Unit 23.1.2-lC Unit 3

Cooldown:i

Cooldown rates and allowable combinations of pressure and tempera-ture shall be limited in accordance with Figure 3.1.2-2A Unit 1

3.1.2-23 Unit 23.1.2-2C Unit 3

3.1.2.2 Leak tests required by Specification 4.3 and ASME Section XI shallbe limited to the heatup and cooldown rates and allowable combinationsof pressure and temperature provided in Figure 3.1.2-3A Unit 1

3.1.2-3B Unit 23.1.2-3C Unit 3

3.1.2.3 For thermal steady state system hydro tests required by ASME Section XIthe system may be pressurized to the 1Laits set forth in Specification2.2 and 3.1.2.2.

3.1.2.4 The secondary side of the steam generator shall not be pressurizedabove 237 psig if the temperature of the vessel shell is below110 F.

3.1.2.5 The pressurizer heatup and cooldown rates shall not exceed 100 F/hr.The spray shall not be used if the temperature difference betweenthe pressurizer and the spray fluid is greater than 410 F.

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3.1.2.6 Prior to exceeding eight (Unit 1)

four (Unit 2)four (Unit 3)

effective full power years of operation.

Figures 3.1.2-1A (Unit 1), 3.1. 2-2A (Unit 1)3.1.2-1B (Unit 2), 3.1.2-2B (Unit 2)3.1.2-lC (Unit 3) , 3.1. 2-2C (Unit 3)

and 3.1.2-3A (Unit 1)3.1.2-3B (Unit 2)3.1.2-3C (Unit 3)

and Technical Specification 3.1.2.1, 3.1.2.2 and 3.1.2.3 shallbe updated for the next service period in accordance with10 CFR 50, Appendix G, Section VmB.

3.1.2.7 The updated proposed technical specification referred to in3.1.2.6 shall be submitted for NRC review at least 90 daysprior to the end of the service period.

Appropriate additional NRC review time shall be allowed forproposed technical specifications submitted in accordance with10 CFR 50, Appendix G, Section V.C.

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Bases - Units 1, 2 and 3-

All components in the Reactor Coolant System are designed to withstand theeffects of cyclic loads due to system temperature and pressure changes.These cyclic loads are introduced by normal load transients, reactor trips,startup and shutdown operations, and inservice leak and hydrostatic tests.The various categories of load cycles used for design purposes are providedin Table 4.8 of the FSAR.

The major components of the reactor coolant pressure boundary have beenanalyzed in accordance with Appendix G to 10 CFR 50. Results of this analysis,

including the actual pressure-temperatur g imitations g the reactor antpressure boundary, are given in BAW-1436 , BAW-1437 and BAW-1438

The Figures specified in 3.1.2.1, 3.1.2.2 and 3.1.2.3 present the pressure-temperature limit curves for normal heatup, normal cooldown and hydrostatictests respectively. The limit curves are applicable up to the indicatedeffective full power years of operation. These curves are adjusted by 25 psiand 10 F for possible errors in the pressure and temperature sensing instruments.The pressure limit is also adjusted for the pressure differential between thepoint of system pressure measurement and tne limiting component for all operatingreactor coolant pump combinations.

The pressure-temperature limit lines shown on the figure specified in 3.1.2-1for reactor criticality and on the figure refered to in 3.1.2.3 for hydrostatic |testing have been provided to assure compliance with the minimum temperaturerequirements of Appendix G to 10 CFR 50 for reactor criticality and for inservicehydrostatic testing.

The actual shift in RT f the beltline region material will be establishedNDT

periodically during operation by removing and evaluating, in accordance withAppendix H to 10 CFR 50, reactor vessel material irradiation surveillancespecimens which are installed near the inside wall of this or a similar reactorvessel in the core region, or in test reactors.

The limitation on steam generator pressure and temperature provide protectionagainst nonductile f ailure of the secondary side of the steam generator. At

| metal temperatures lower than the RT of +60 F, the protection against non-

| ductilefailureisachievedbylimitEngthesecondarycoolantpressureto20 percent of the preoperational system hydrostatic test pressure. The lim-itations of 110 F and 237 psig are based on the highest estimated RT of+40Fandthepreoperationalsystemhydrostatictestpressureof131[psig.r

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The average metal temperature is assumed to be equal to or greater than thecoolant temperature. The limitations include margins of 25 psi and 10 F forpossible instrument error.

The spray temperature difference is imposed to maintain the thermal stressesat the pressurizer spray line nozzle below the design limit.

3.1-4

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REFERENCES

(1) Analysis of Capsule OCI-E from Duke Power Company Oconee Unit 1 Reactor |Vessel Materials Surveillance Program, BAW-1436, September 1977.

(2) Analysis of Capsule OCII-C from Duke Power Company Oconee Unit 2Reactor Vessel Materials Surveillance Program, BAW-1437, May 1977.

(3) Analysis of Capsule OCIII-A from Duke Power Company Oconee Unit 3Reactor Vessel Materials Surveillance Program, BAW-1438, July 1977.

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REACTOR COOLANT SYSTEM;

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| INSERVICE LEAK AND HYDRO- )STATIC TEST HEATUP AND 1'

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APPLICABLE FOR FIRST 8.0 |'

EFFECTIVE FULL POWER YEARS1' '

OCONEE gLEAR STATIONocu roma

Figure 3.1.2-3A' --

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THE BABCOCK & WILCOX COMPANY I,

POWER GENERATION GROUP

To |DISTRIB1TrION

FromA. L. LOWE, JR. TECHNICAL STAFF sos 663.s

Cust. File No.DUKE POWER COMPANY (OCON'EE UNIT 1) or Ref. BAW-1436

Subj. ANALYSIS OF CAPSULE OCI-E FROM DUKE POWER COMPANY DateOCONEE hTCLEAR STATION, UNIT 1 - REPORT BAW-1436 JANUARY 25, 1978

| m . i.n., e. ...., ... ..o.... ..d ... .. %. ..i r.

Errors have been discovered on pages 8-2 and 8-3 of report BAW-1436 and shouldbe corrected as follows:

1. Page 8-2, second paragraph, first sentence: Should read ". . .at the endof the eighth full-power year." instead of "...at the end of the sixthfull power year."

2. Page 8-2, third paragraph, first sentence: Should read "...end of theeighth full-power year are. . ." instead of ". ..end of the sixth full poweryear are..." '

3. Page 8-3, second sentence: Should read "...up to the ninth effective..."instead of "...up to the seventh effective..."

ALL:dah,

Distribution:

Duke Power Company (70) Merchent, JW Helmbrecht, HL/NED Barbertonc/o CD Russell, OFR Moore, KE Young, DE/NED BarbertonBehnke, HW/Mt. Vernon rgan, A g es, PS/ AllianceBorsum, RB/Bethesda ewt n, ulick, ET/M C W

Palme, HS (2) Gross, LB/LRC,

d M***Durant, WP/Mt. Vernon * #' """*

Schuler, TM Rowe, JP/ Alliance#*7'

Sivashankaran, S/Mt. Vernon ZurLippe, CF/LRC (2),Smith, RM

(3)eyw rt ,Travis, CC/TRGevstek, DFWhitmarsh, CL (2)

o (4) Wimmer, LB

!

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