ML15223A767

Proposed Revisions to Tech Spec Section 3.1.2 Re Heatup Cooldown & Inservice Test Limitations for RCS

ML15223A767
Person / Time
Site:	Oconee
Issue date:	01/12/1982
From:	DUKE POWER CO.
To:
Shared Package
ML15223A766	List: ML15223A765 ML15223A767 ML20040B068 ML20040B071
References
NUDOCS 8201250089
Download: ML15223A767 (13)

Text

DUKE POWER COMPANY OCONEE NUCLEAR STATION Proposed Technical Specification Revision Pages 3.1-3a 3.1-7 3.1-4 3.1-7a 3.1-5 3.1-7b 3.1-6 3.1-7c 3.1-6a 3.1-7d 3.1-6b 3.1-7e QPDR CO 9 e~O I ~

~

0 00 D~~O~O269 PDR I

3.1.2.6 Prior to exceeding fifteen (Unit 1) fifteen (Unit 2) fifteen (Unit 3) effective full power years of operation Figures 3.1.2-lA (Unit 1), 3.1.2-2A (Unit 1) 3.2.3-1B (Unit 2), 3.1.2-2B (Unit 2) 3.1.2-1C (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 shall be updated for the next service period in accordance with 10 CFR 50, Appendix G,.Section V.B.

3.1.2.7 The updated proposed technical specification referred to in 3.1.2.6 shall be submitted for NRC review at least 90 days prior to the end of the service period for Units 1, 2, and 3.

Bases -

Units 1, 2, and 3 All components in the Reactor Coolant System are designed to withstand the effects 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 provided in Table 4.8 of the FSAR.

The major components of the reactor coolant pressure boundary.have been analyzed in accordance with Appendix G to 10 CFR 50. Resilts of this analysis, including the actual pressure-temperature limitations of the reactor coolant pressure boundary, are given in BAW-1699 and BAW-1697.

Because the material behavior is conservatively predictable and the similarity between Oconee Unit 1 and Oconee Units 2 and 3 in the areas of reactor vessel construction materials, RVMSP capsule contents, capsule irradiation history, plant operation and fuel management,. the operating limits for Oconee Unit 1 have been extended through 15 EFPY based on the surveillance capsule evalua tions of Oconee Units 2 and 3.

The Figures specified in 3.1.2.1, 3.1.2.2 and 3.1.2.3 prevent the pressure temperature limit curves for normal heatup, normal cooldown and hydrostatic tests respectively. The limit curves.are applicable up to the indicated effective full power years of operation. These curves are adjusted by 25 psi and 100 F for possible errors in the pressure and temperature.sensing instru ments. The pressure limit is also adjusted for the pressure differential between the point of system pressure measurement and the limiting component for all operating reactor coolant pump combinations.

The cooldown limit curves are not applicable to conditions of off-normal operation (e.g., small LOCA and extended loss of feedwater) where cooling is achieved for extended periods of time by circulating water from the HPI through the core.

If core cooling is restricted to meet the cooldown limits under other than normal operation, core integrity could be jeopardized.

The pressure-temperature limit lines shown on the figures specified in 3.1.2.1 for reactor criticality and on the figures referred to in 3.1.2.3 for hydro static testing have been provided to assure compliance with the minimum temperature requirements of Appendix G to 10 CFR 50 for reactor criticality and for inservice hydrostatic testing.

The actual shift in RT of the beltline region material will be established NDT periodically during operation by removing and evaluating, in accordance with Appendix H to 10 CFR 50, reactor vessel material irradiation surveillance specimens which are installed near the inside wall of this or a similar reactor vessel in the core region, or in test 'reactors.

The limitation on steam generator pressure and temperature provide protection against nonductile failure of the secondary:side of the steam generator. At metal temperatures lower than the RT of +600 F, the protection against nonductile failure is achieved by liN Ting-the secondary coolant pressure to 20 percent of the preoperational system hydrostatic test 'pressure. The 3.1-4

limitations of 1100F and 237 psig are based on the highest' estimated RT of +400F and the preoperational system hydrostatic test pressure of 131 psig.

The average metal temperature is assumed to be equal to or greater than the coolant temperature. The limitations include margins of 25 psi and 100 F for possible instrument error.

The spray temperature difference is imposed to maintain the thermal stresses at the pressurized spray line nozzle below the design limit.

REFERENCES (1) Analysis of Capsule OCII-A from Duke Power Company Oconee Unit 2 Reactor Vessel Materials Surveillance Program, BAW-1699, December 1981.

(2) Analysis of Capsule OCIII-B from Duke Power Company Oconee Unit 3 Reactor Vessel Materials Surveillance Program, BAW-1697, October 1981.

THE ACCEPTABLE PRESSURE AND TEMPERATURE COMBINATIONS ARE BELOW AND TO THE RIGHT OF THE LIMIT CURVE. THE REACTOR MUST NOT BE MADE CRITICAL UNTIL THE PRESSURE-TEMPERATURE COMBINATIONS ARE TO THE RIGHT OF THE CRITICALITY LIMIT CURVE. MARGINS OF 25 PSIG AND IOF ARE INCLUDED FOR POSSIBLE INSTRUMENT ERROR.

W APPLICABLE FOR HEATUP RATES OF.< 100oF/HR

0.

(< 50aF IN ANY 1/2 HOUR PERIOD) 2500' 200-con tr-s 2000 CRITICALITY LIMIT Lu 1500 POINT PRESSURE TEMPERATURE A

287 100 B

287 180 C

1050 350 0

2250 415 C

G 1000 E

0 292 F

287 292 6

1050 390 H

2250 455 500 F

A B

E 0

100 200 300 400 500 600 700 800 Inuicatea Reactor Coolant System Temperature, Tc,.*F OCONEE UNIT 1 REACTOR COOLANT SYSTEM NORMAL OPERATION-HEATUP LIMITATIONS APPLICABLE FOR FIRST 15.0 EFFECTIVE FULL POWER YEARS UKEPOWR OCONEE NUCLEAR STATION Figure 3.1.2-1A

THE ACCEPTABLE PRESSURE-TEMPERATURE COMBINATIONS ARE BELOW AND TO THE RIGHT OF THE LIMIT CURVE(S).

THE LIMIT CURVES INCLUDE THE PRESSURE DIFFERENTIAL BETWEEN THE POINT OF SYSTEM PRESSURE MEASUREMENT AND THE PRESSURE ON THE REACTOR VESSEL REGION CONTROLLING THE LIMIT CURVE, THEY INCLUDE AN ADDITIONAL MARGIN OF SAFETY FOR POSSIBLE INSTRUMENT ERROR (25 PSI AND 10-F).

THE.REACTOR MUST NOT BE MADE CRITICAL UNTIL THE PRESSURE-TEMPERATURE COMBINATIONS ARE TO THE RIGHT OF THE CRITICALITY LIMIT.

2500 OH HEATUP RATE: <100*F/HR

(<500 F IN ANY 1/2 HOUR PERIOD) 2000 CRITICALITY LIMIT 1500 POINT PRESSURE PSIS TEMP. OF A

281 100 B

281 170 C

750 335 0

2250 425 1000 E

0 313 F

281 1

313 G

750 375 H

2250 Ass 500 F

A B

E 100 200 300 400 500 600 700 800 Indicated Reactor Coolant System Temperature, Tc, OF OCONEE UNIT 2 REACTOR COOLANT SYSTEM NORMAL OPERATION HEATUP LIMITATIONS APPLICABLE FOR FOR FIRST 15.0 EFPY SOR OCONEE NUCLEAR STATION 3.1-6a Figure 3.1.2-1B

THE ACCEPTABLE PRESSURE TEMPERATURE COMBINATIONS ARE BELOW AND TO THE RIGHT OF THE LIMIT CURVE(S).

THE LIMIT CURVES INCLUDE THE PRESSURE DIFFERENTIAL BETWEEN THE POINT OF SYSTEM PRESSURE MEASUREMENT AND THE PRESSURE ON THE REACTOR VESSEL REGION CONTROLLING THE LIMIT CURVE. THEY INCLUDE AN ADDITIONAL MARGIN OF SAFETY FOR POSSIBLE INSTRUMENT ERROR (25 PSI AND 10aF).

THE REACTOR MUST NOT BE MADE CRITICAL UNTIL THE PRESSURE-TEMPERATURE COMBINATIONS ARE TO THE RIGHT OF THE CRITICALITY LIMIT.

6 2500 E

j

-HEATUP RATE: <00oF/HR T

2000 (40aFIN ANY 1/2 HOUR PERIOD)

CRITICALITY LIMIT CL 1500 POINT PRESSURE PSIG TEMP. *F A

300 70 B

300 180 C

550 290 0

925 330 1000 E

2250 405 0

I F

0 326 G

300 326 H

550 330 925 370 500 C

H

__2250 445 A

B 100 200 300 400 500 600 700 Indicated Reactor Coolant System Temperature, Tc, OF OCONEE UNIT 3 REACTOR COOLANT SYSTEM NORMAL OPERATION HEATUP LIMITATIONS APPLICABLE FOR FIRST 15.0 EFPY.

DlE POWER OCONEE NUCLEAR STATION 3.1-6b Figujre 3. 1. 2-1C

THE ACCEPTABLE PRESSURE AND TEMPERATURE COMBINATIONS ARE BELOW AND TO THE RIGHT OF THE LIMIT CURVE.

MARGINS OF 25 PSIG AND IOF ARE INCLUDED FOR POSSIBLE INSTRUMENT ERROR.

I. WHEN THE DECAY HEAT REMOVAL (DR) SYSTEM IS OPERATING WITH NO RC PUMPS OPERATING.

THE INDICATED 0HR SYSTEM RETURN TEMPERATURE TO THE REACTOR VESSEL SHALL BE USED.

2. A MAXIMUM STEP TEMPERATURE CHANGE OF 75eF IS ALLOWABLE WHEN REMOVING ALL RC PUMPS FROM OPERATION WITH THE DHR SYSTEM OPERATING THE STEP TEMPERATURE CHANGE IS DEFINED AS THE RC TEMP IPRIOR TO STOPPING ALL AC PUMPS) MINUS THE DNR RETURN TEMP (AFTER STOPPING ALL RC PCNPS)

THE 100 F/HR RAMP DECREASE IS ALLOWABLE BOTH BEFORE AND AFTER THE STEP TEMP CHANGE.

2500 APPLICABLE FOR COOLDOWN RATES

< 100aF HR (< 50OF IN ANY 1/2 0

HOUR PERIOD) 2000 COI)

C caC. 150D POINT PRESSURE TEMPERATURE A

76 7o B

500 225 SaC 1800 320 D

2250 377 t

-10 00 500 B

0 A

C 100 200 300 400 500 400 700 8oo Inoicatso Reactor Coolant Systenm Temperature. TC,oF 1

OCONEE UNIT 1 REACTOR COOLANT SYSTEM LIMITATIONS APPLICABLE FOR FIRST 15.0 EFPY 3UKEPOWER OCONEE NUCLEAR STATION 3.1-7 500r 31.-2

1. WHEN.THE DECAY HEAT REMOVAL (DH) SYSTEM IS OPERATING WITH ND RC PUMPS OPERATING, THE INDICATED DHR SYSTEM RETURN TEMPERATURE TO THE REACTOR VESSEL SHALL BE USED.

2. A MAXIMUM STEP TEMPERATURE CHANGE OF 75OF IS ALLOWABLE WHEN REMOVING ALL RC PUMPS FROM OPERATION WITH THE OH SYSTEM OPERATING. THE STEP TEMPERATURE CHANGE IS DEFINED AS THE RC 7

TEMP (PRIOR TO STOPPING ALL RC PUMPS) MINUS THE ON RETURN TEMP (AFTER STOPPING ALL RC PUMPS)

THE 100*F/HR RAMP DECREASE IS ALLOWABLE BOTH BEFORE AND AFTER THE STEP TEMP CHANGE.

2500 0

COOLOOWN RATE: <t00.F/HR 20Z

(<50-F IN ANY 1/2 HOUR PERIOD)(2)

~. 2000 C

POINT PRESSURE PSIG TEMP. OF 1500 -A 160 70

. B 375 215 C

192534 0

2250 378 1000 THE ACCEPTABLE PRESSURE-TEMPERATURE COMBINATIONS ARE BELOW AND TO THE RIGHT OF THE LIMIT CURVE(S).

THE LIMIT CURVES INCLUDE THE PRESSURE DIFFERENTIAL BETWEEN THE POINT OF SYSTEM PRESSURE MEASUREMENT AND THE PRESSURE ON THE REACTOR VESSEL 500 -

REGION CONTROLLING THE LIMIT CURVE, THEY INCLUDE AN ADDITIONAL MARGIN OF SAFETY FOR POSSIBLE INSTRUMENT ERROR (25 PSIS AND 10-F) 0A 100 200 300 400 500 6oo 700 Inoicated Reactor Coolant System Temperature, Tc, oF OCONEE UNIT 2 REACTOR COOLANT SYSTEM NORMAL OPERATION COOLDOW1 LIMITATIONS APPLICABLE FOR FIRST 15.0 EFPY oDtPows OCONEE NUCLEAR STATION 3.1-7a WFigure 3.1.2-2B

1. WHEN THE DECAY HEAT REMOVAL (OH) SYSTEM IS OPERATING WITH NO RC PUMPS OPERATING. THE INDICATED OHR SYSTEM RETURN TEMPERATURE TO THE REACTOR VESSEL SHALL BE USED.

2. A MAXIMUM STEP TEMPERATURE CHANGE OF 75eF IS ALLOWABLE WHEN REMOVING ALL RC PUMPS FROM OPERATION WITH THE OH SYSTEM OPERATING.

THE STEP TEMPERATURE CHANGE IS DEFINED AS THE RC TEMP. (PRIOR TO STOPPING ALL RC PUMPS) MINUS THE OH RETURN TEMP (AFTER STOPPING ALL RC PUMPS).

THE 100*F/HR TEMP DECREASE IS ALLOWABLE BOTH BEFORE AND AFTER THE STEP TEMP.

CHANGE.

g 2500 COOLDOWN RATE: <100OF/HR 2000 C(<

50OF IN ANY 1/2 HOUR PERIOD)(2 )

0.POINT PRESSURE PSIG TEMP. *F 00 A

150 0

150B 50-0 Lu

=

-1850 315 1000 THE ACCEPTABLE PRESSURE-TEMPERATURE COMBINATIONS ARE BELOW AND TO THE RIGHT OF THE LIMIT CURVE(S).

THE LIMIT URVES INCLUDE THE PRESSURE DIFFERENTIAL BETWEEN THE POINT OF SYSTEM PRESSURE MEASUREMENT AN THE PRESSURE ON THE

.. ~ 500 BREACTOR VESSEL REGION CONTROLLING THE LIMIT CURVE.

THEY INCLUDE AN ADDITIONAL MARGIN OF SAFETY FOR POSSIBLE INSTRUMENT ERROR (25 PSIG AND 10*F).

AA10I 100 200 300 400 500 500 Indicatec Reactor Coolant System Temperature, Tc. *F OCONEE UNIT 3 REACTOR COOLANT SYSTEM NORMAL OPERATION COOLDOWN LIMITATIONS APPLICABLE FOR FIRST 15.0 EFFY 3.1-7b DE OCONEE NUCLEAR STATION Figure 3.1.2-2C

THE ACCEPTABLE PRESSURE AND TEMPERATURE COMBINATIONS ARE BELOW AND TO THE RIGHT OF THE LIMIT CURVE.

MARGINS OF 25 PSIS AND IOF ARE INCLUDED FOR POSSIBLE INSTRUMENT ERROR.

FOR COOLDOWN, NOTES I AND 2 ON FIGURE 3.1.2-2A ARE APPLICABLE.

C, G

2500 D

APPLICABLE FOR HEATUP AND COOLDOWN RATES OF < 100oF/HR

(<50aF IN ANY 1/2 HOUR PERIOD) 152 t

2000 0

-L w

-1500 POINT PRESSURE TEMPERATURE Cu CA 275 75 Bn 556 255 C1425 350 D

2500 408 1000 500 B

A 0

II25 0

100 200 300 400 500 600 700 00 Indicate0 Reactor Coolant SystemI Temperature, Tc *F OCONEE UNIT 1 REACTOR COOLANT SYSTEM INSERVICE LEAK AND HYDROSTATIC TEST HEATUP AND COOLDOWN LIMITATION APPLICABLE FOR FIRST 15.0 EFFECTIVE FULL POWER YEARS UKEPOWE OCONEE NUCLEAR STATION 0

Figure 3.1.2-3A

THE ACCEPTABLE PRESSURE-TEMPERATURE COM'BINATIONS ARE BELOW AND TO THE RIGHT OF THE LIMIT CURVE(S). THE LIMIT CURVES INCLUDE THE PRESSURE DIFFERENTIAL BETWEEN THE POINT OF SYSTEM PRESSURE MEASUREMENT AND THE PRESSURE ON THE REACTOR VESSEL REGION CONTROLLING THE LIMIT CURVE. THEY INCLUDE AN ADDITIONAL MARGIN OF SAFETY FOR POSSIBLE INSTRUMENT ERROR (25 PSI AND 10*F).FOR COOLDOWN, NOTES I AND 2 ON FIGURE 3.1.2-28 ARE APPLICABLE.

2500 C

APPLICABLE FOR HEATUP AND COOLOOWN RATES OF

< 100*F/HR (<50*F IN ANY 1/2 HOUR PERIOD) 2000 POINT PRESSURE PSIG TEMP. OF 1500 A

225 70 B

1000 325 C

2500 410 1000 B

500 A

II I

I I

I 100 200 300 400 500 600 700 800 Indicated Reactor Coolant System Temperature, Tc, OF OCONEE UNIT 2 REACTOR COOLANT SYSTEM INSERVICE LEAK AND HYDRO STATIC TEST HEATUP AND COOLDOWN

.LIMITATIONS APPLICABLE FOR 15.0 EFFY OCONEE NUCLEAR STATION 3.17d Figure 3.1.2-3B

THE ACCEPTABLE PRESSURE-TEMPERATURE COMBINATIONS ARE BELOW AND TO THE RIGHT OF THE LIMIT CURVE(S).

THE LIMIT CURVES INCLUDE THE PRESSURE DIFFERENTIAL BETWEEN THE POINT OF SYSTEM PRESSURE MEASUREMENT AND THE PRESSURE ON THE REACTOR VESSEL REGION CONTROLLING THE LIMIT CURVE.

THEY I..L=DE AN ADDIT:fAL MARGIN OF SAFETY FOR POSSIBLE INSTRUMENT

ERROR, (25 PSI AND 10.F).

FOR COOLDOWN NOTES 1 AND 2 ON FIG. 3.1.2-2C ARE APPLICABLE.

2500 C

APPLICABLE FOR HEATUP AND COOLDOWN RATES OF < 100*F/HR (<50OF IN ANY 1/2 HOUR PERIOD) 2000 CL POINT PRESSURE PSIG TEMP. OF 1500 A

250 70 571 255 C

2500 408 c

1000 500 B

100 200 300 400 500 600 700 Inoicatea Reactor Coolant System Temperature,. Tc. OF OCONEE UNIT 3 REACTOR COOLANT SYSTEM INSERVICE LEAK AND HYDROSTATIC TEST AND COOLDOWN LIMITATIONS APPLICABLE FOR FIRST 15.0 EFPY 0ounom OCONEE NUCLEAR STATION 3.1-7e Figure 3.1.2-3C