ML15113A060
| ML15113A060 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 02/22/1982 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Duke Power Co |
| Shared Package | |
| ML15113A061 | List: |
| References | |
| DPR-38-A-107, DPR-47-A-107, DPR-55-A-104 NUDOCS 8203040377 | |
| Download: ML15113A060 (19) | |
Text
NUCEA REULTOYCMMSSO UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO.
50- 269 OCONEE NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.107 License No. DPR-38
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Duke Power Company (the licensee) dated January 12, 1982, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Com mission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the pro visions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations.
D. The issuance of this amendment will not be inimical to the common 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 Commission's regulations and all applicable requirements have been satis fied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.B of Facility Operating License No. DPR-38 is hereby amended to read as follows:
3.B Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 107are hereby incorporated in the license. The licensee shall operate the facility in.accordance with the Technical Specifications.
.2030403 20222 PPD
_____05000269_
-2
- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION oh F. Stolz, Chief Ope ating Reactors Branc #4 D* ision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: February 22, 1982
UNITED STATES i
NUCLEAREGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-270 OCONEE NUCLEAR STATION, UNIT NO.2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
107 License No. DPR-47
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Duke Power Company (the licensee) dated January 12, 1982, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Com mission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the pro visions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations.
D. The issuance of this amendment will not be inimical to the common 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 Commission's regulations and all applicable requirements have been satis fied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.B of Facility Operating License No.
DPR-47 is hereby amended to read as follows:
3.B Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.107 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
-2
- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION ohn F. Stolz, Chief Ope ating Reactors Branch #4 Di sion of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: February 22, 1982
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 104 License No. DPR-55
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Duke Power Company (the licensee) dated January 12, 1982, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Com mission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the pro visions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations:
D. The issuance of this amendment will not be inimical to the common 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 Commission's regulations and all applicable requirements have been satis fied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.B of Facility Operating License No. DPR-55 is hereby amended to read as follows:
3.B Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.104 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
-2
- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REG ATORY COMMISSION oh F. Stolz, Chief Op rating Reactors Branch #4 vision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: February 22, 1982
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 107 TO DPR-38 AMENDMENT NO. 107 TO DPR-47 AMENDMENT NO. 104 TO DPR-55 DOCKETS NOS. 50-269, 50-270 AND 50-287 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by amendment numbers and contain vertical lines indicating the area of change.
Remove Pages Insert Pages 3.1-3a 3.I-3a 3.1-4 3.1-4 3.1-5 3.1-5 3.1-6 3.1-6 3.1-6a 3.1-6a 3.1-6b 3.1-6b 3.1-7 3.1-7 3.1-7a 3.1-7a 3.1-7b 3.1-7b 3.1-7c 3.1-7c 3.1-7d 3.1-7d 3.1-7e 3.1-7e
3.1.2.6 Prior to exceeding fifteen (Unit 1) fifteen (Unit 2) fifteen (Unit 3) effective full power years of operation Figures 3.1.2-1A (Unit 1), 3.1.2-2A (Unit 1) 3.1-.2-1B (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 CUnit 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.
Amendments Nos.
- 107, 107, & 104 3.1-3a
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.
Results of this analysis, including the actual pressure-temperature limitations of the reactor coolant pressure boundary, are given in BAN-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, KVMSP 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 present 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 10oF 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 minmm 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 +600F, the protection against nonductile failure is achieved by limi ing the secondary coolant pressure to 20 percent of the preoperational system hydrostatic test pressure.
The Amendments Nos.
1-07,
107, & 104 3,1-4
limitations of 110oF and 237 psig are based on the highest estimated of +40oF and the preoperational system hydrostatic test pressure of 131Ksig.
The average metal temperature is assumed to be equal to or greater than the coolant temperature.
The limitations include margins of 25 psi and 10o 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, RAW-1699, December 1981.
(2)
Analysis of Capsule OCIII-B from Duke Power Company Oconee Unit 3 Reactor Vessel Materials Surveillance Program, BA-1697, October 1981.
Amendments Nos.
107.
107
& 104 3.1-5
TME ACCEPTABLE P3133151 AM TEMPEATURE CasSuaTsMw ARE KIM An To TM RIOT OF TME LIMIT CMlL IN REACTOR OWT NOT KS WOnE CRITICAL UNSTIL TN PIflhU3-TBPMaUTM COMNATIN ARE To TIE NINT OF T CRITICALITY LIMIT CURVE.
Minl OF 25 Psi16 AN lOF AM lEcLUDD Pol p133.l@U STRUKT URNS.
1500 2110CIICLT II
.1 0 O N 019 1 aM N
A 1
1 28 In
.m 1000 A
3750 o
Ic 20 3060 350no S
2210IM APIAI F
IS
- 15.
20 ETV FULOERYER AmnmnsNs50,00;00 COE ULA TTO Fiur 3.12 1
tndlcated Reaco Colant System Pr essur Ie, psi "g (Loo witht Pressiri zef-).
CD.
I 5
U 20 UIO "ji a
I z
-4 IIC rIN 0
zU4 2_
THE ACCEPTABLE PRESSURE TEMPERATURE CONINATIONS ARE ELOW AND TO TUE Rig1T OF THE LIMIT CURVE(S).
THE LIMIT CURVES INCLUDE THE PRESSURE DIFFERENTIAL BETWEEN THE POINT OF SYSTEM PRESSURE EASUREMBENT AND THE PRESSURE N THE REACTOR VESSEL REGION CONTROLLING THE LIMIT CURVE.
THEY INCLUDE AN ADDITIONAL MARGIN OF SAFETY FOR POSSIBLE INSTRUMENT ERROR (25 PSI AND 18F).
THE REACTOR RUST NOT BE MADE CRITICAL UNTIL THE PRESSURE-TEMPERATURE COMINATIONS ARE TO THE RIGHT OF THE CRITICALITY LIMIT.
E j
aL HEATUP RATE:SI8F/HR m
0(FIN ANT 1/2 NUR PERID)
CRITICALITY LIMIT IO
.POINT PRESSURE PSIG TEMP. *F A
pno aF7 g 0 1
D as 0
I j Im E
25 550 338
.:C HJ U044
.22
.. 5 AB 100 200 380 460 500 60 7g6 Inalcates Aacter Coalent Systm Tenperators. T, Of OC EE UNIT 3 REACTOR COOLANT SYSTE NOUMAL OPERATION EEATP LIMITATIONS APPLICABLE FOR 9
FIRST 15.0 EFPT.
OCONEE NUCLEAR STATION Amendments Nos.
- 107, 107 * & 104 3.1-6b Fiere 3.1.2-IC
To( ACCEPAIL PREM11l &AD TDIEfUAT021 CONIUATIOS All BELOW AGD TO 711 UEI Om Tod LIMIT CDIOL NUINS OF 25 PSIG A10 IOF A19 INCLUOEO FDA POSSIBLE IuBTU29iBT KAWL
- 1.
- E0 TRI DCAY NEAT RUIOVAL (DNA) VISTM IS @PIBATIB WITHM m C PgNPS OPATI14J TUE INDICATIED DUB 11518 RMAIN lIP9IBlBE TO lIE BEACTDI VESSE AL IIAUE lL L. A uzIin STEP TENVERATIBE CISAWB OF noll 1S £LLBLEI Nl BEMOIN AL. IC P3W! FUNM OPENATION WITN TNE ONB 512781 OIIETING TUE STEP TEMPEATURE MIAIBE IS WIND AS TUE 2C lTDI PIOI TO atop ING ALL NC PUMPS) NINO THE ONI 11CM11 TEMP LAFTE STOPPING ALL IC PgIP)
TUE 10-/I A1 BECEAS1 IS A"IODUANE IOTh 3110K ASO £11 THE STEP TEMP CISANL Applicable For Cooldown Rates
<100 0F HR (<50 0 F In Any 1/2
~~
Hour Period) 2 2000
-C S
1500 POINT PRIESUBE IMPEATMN U7S 3.C two M
-~n 5
Tool Sa a
ice log 300 400 500 400 Too
&Do Inaicatoo RuctDI gouut Sytxuu Toweraure. Te.!F (1)
OCONEE UNIT 1 REACTOR COOLANT SYSTEM NORMAL OPERATION COOLDOWN LIMITATIONS APPLICABLE FOR FIRST 15.0 EFPY Amendments Nos.
107.
107
& 104 3.1-7 PW'OCONEE NUCLEAR STATION Figiwe 3.1.2-2A
- 1. When the decay heat removal (DHR) system is operating with no RC pumps operating, the indicated DHR system return temperature to the reactor vessel shall be used.
- 2. A maximum step temperature change of 750F is allowable when removing all RC pumps from operation with the DHR system operating. The step temperature change is defined as the RC temp (prior to stopping all RC pumps) minus the DHR return temp (after stopping all RC pumps). The 1000 F/HR ramp decrease is allowable both before and after the step tem change.
Zo COOOW0N RAT!: 90U/R 2000-(0r IN Af 1/2 NO0 PtloIU)(2)
C POINT PRESSURE PSi.
TEIP. OF I.-
A 160 7O II 375 215 C
182
-4 0
2250 378
- loo THE ACCPTABLE PRESSURE-TIPERATURE CCHAINATIOMS ARE BELOW AND TO THE AltT OF THE LIMIT CUAIE(S).
THE LIMIT CURVES INCLUDE THE PRESSURE DIFFERENTIAL BETWEEN TIE POINT OF SYSTER PRESSURE MEASUREMENT AND THE PRESSURE ON THE REACTSA VESSEL RESION CONTROLLING THE LIMIT CURVE, THEY INCLUDE AN ADDITIONAL MARSIN OF WET FOR POSSIBLE INSTURENT ERWA (25 PSIS AND 1OF) 100 200 300 400 500 0o 700 Isitate Reactor Coat Systm Taptagr. TC. Of OCONEE UNT 2 REACTOR COOLANT SYSTM NORMAL OPERATION COOLDOwI.
LDMITATIONS APPLICABLE FOR FIRST 1.5.0 EFPT OCONEE NUCLEAR STATION Amendments Nos.
107,
107, & 104 3.1-7a Figure I3.1.2-2B
- 1. When the decay heat removal (DHR) system is operating with no RC pumps operating, the indicated DHR system return temperature to the reactor vessel shall be used.
- 2. A maximum step temperature change of 750F is allowable when removing all RC pumps from operation with the DHR system operating.
The step temperature change is defined as the RC temp (prior to stopping all RC pumps) minus the DHR return temp (after stopping all RC pumps).
The 100oF/HR temp decrease is allowable both before and after the step temp. change C011111 2000S18" ll m
q 0 *o-F IN AtY 1/2 Mout ?f110)
P gINT PrSUt PsiS TrIP.
V
£ISO I
A 1 50 I
C 8I li lo -
39 100 15E A=CPTABLE PRtSSURE-TEPERATURE COMBINATIOS AE IILOi AND TO TE NIGHT OF THE LIlIT CURVE(S).
THE LIgIT 0RVES INCLUDE THE PRESSURE DIFFERENTIAL EITEEN THE POINT OF SST11 PRESSURE hEAISUREENT AMg THE PRESSURE ON THE REACTUR VESSEL REGION CONTROLLINs THE LIIT CURVL THEY INCLOE AN ADITIONAL UMA IN Of SAFETT FOR POSSIBLE INSTINlENT [RA51 (25 PSIS Ag 10F).
A, to 28 3011 400 5S 501 Iadicatso isactar Colast System Tmerature. T. OF OCONE UNIT 3 REACTOR COOLANT SYSTM NOEMAL OPRATION COOLDOWN LIMTATIONS APPLICABLE FOR FIRST 15.0 EFP.Y Amendments Nos.
107, 107, & 104 3-1-7b OCONEE NUCLEAR STATION Figure 3.1.2-2C
TWS ACCPTABLE P11131t AlS TEMPHATest COMINATION8 AA IELOW All TO TIE 16g Of T" LIMIT CURVE. MAR8I8S SF 2s Psi$ All lop AlE INCL88tB FOR POSSIBLE faSTaSwIaT 91101.
FO COSL8OWW, NOTES I Al 2 O8 Pleast 3.1.2*A AlE APPASLSU.
m E
2509 APPLICABLE PE ATW Ag seessesW earts *I
&se**Ples a
C-**F INS T Mi Pt 1169) 5002*
.3 j
0P?
PCABEm FOR FIRTu1.a EFCTV Am1OCONEE NU C EATO N
Figure 3.1.2-3A
THE ACCEPTABLE PRESSURE*TEMPERATURE COMSINATIONS 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 (2 PSI AND W0F).FOR COOLDOIN, NOTES I AND 2 ON FIGURE 3.1.2*28 ARE APPLICABLE.
APPLICABLE FOR HEATUP AND COOLDOWN RATES SF oe I terF/a (go*F IN ANY 1/2 HOUR PERIOD)
POINT PRESSIRE PSIG TEMP. *F EMA A
225 70 8
0loo 325 C
00 410 50 IV SA ss 100 200 300
.400 500 688 700 BA0 Iaicated Reactor Coolant System Temperature, Tc. *F OCONEE UNIT 2 REACTOR COOLANT SYSTmR INSERVICE LEAK AND NYDRO STATIC TEST EEATUP AND COOD.0N LIITATIONS APPLICABLE FOR FIRST 15.0 EFFT Amendments Nos.
107,
07, & 104 OCONEE NUCLEAR STATION Figue 3.1.2-33
00
".4 THE ACCEPTABLE PRESSURE*TEMPERATURE CONVINATIONS ARE BELOW AND TO THE RIGHT OF THE LIlIT CURVE(S).
THE LIMIT CURVES INCLUDE THE PRESSURE DIFFERENTIAL BETWEEN THE POINT OF SYSTEg PRESSURE MEASUREMENT AND THE PRESSURE ON THE REACTOR VESSEL REGION CONTROLLING THE LIMIT CURVE.
THEY I.ICL!!!e A A:::T L EARG;N OF SAfETY FQA POSSIBE INSTRUMENT E8R80.
(25 PSI AND 18*F).
FOR COOLDOWN NOTES i AND 2 ON FIG. 3.1.2*2C ARE APPLICABLE.
.C APPLICABLE FOR lEATUP AND CODLDON RATES OF < tOrFiR (9rF IN ANt 1/2 on RlE) 00 4
POINT PRESSURE PSIG TEW. *F 1500 250 70 42-I 50255 0
C, 4.6500 *8
!0 C
A 0
.uoI
- 0)
V A
188 200 300 400 500 600 711 Indicatu Re2acor Culant Systm Teperature, Tc, *F OCONEE UNIT 3 REACTOR COOLANT SYSTEM INSERVICE LEAK AND HYDROSTATIC TEST HEATUP. AND COLDOWN LIMITATIONS APPLICABLE FOR FIRST 15.0 EFPY OCONEE NUCLEAR STATION Amendments Nos.
107.
- 107,
& 104 3.1-7e egu*e 3.1.2-3C