ML16138A717
| ML16138A717 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 05/14/1991 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML16138A718 | List: |
| References | |
| NUDOCS 9105290279 | |
| Download: ML16138A717 (23) | |
Text
o, UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-269 OCONEE NUCLEAR-STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
188 License No. DPR-38
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the Oconee Nuclear Station, Unit 1 (the facility) Facility Operating License No. DPR-38 filed by the Duke Power Company (the licensee) dated November 15, 1989, as supplemented March 28 and August 29, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions 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 set forth in 10 CFR Chapter I; D. The issuance of this license 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 satisfied.
- 2. Accordingly, the license is hereby amended by page 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:
9105290279 910514 FDR ADOCK 05000269 P.
-2 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 188, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION David B. atthews, Director Project Directorate 11-3 Division of Reactor Projects -
I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
May 14, 1991
ap REG&
o0 UNITED STATES 0
NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-270 OCONEE NUCLEAR-STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 188 License No. DPR-47
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the Oconee Nuclear Station, Unit 2 (the facility) Facility Operating License No. DPR-47 filed by the Duke Power Company (the licensee) dated November 15, 1989, as supplemented March 28 and August 29, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions 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 set forth in 10 CFR Chapter I; D. The issuance of this license 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 satisfied.
- 2. Accordingly, the license is hereby amended by page 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:
-2 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 188, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications-.
- 3. This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Day d B. Ma thews, Director Project Directorate 11-3 Division of Reactor Projects -
I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
May 14, 1991
, AOUNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-287 OCONEE NUCLEAR-STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 185 License No. DPR-55
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the Oconee Nuclear Station, Unit 3 (the facility) Facility Operating License No. DPR-55 filed by the Duke Power Company (the licensee) dated November 15, 1989, as supplemented March 28 and August 29, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions 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 set forth in 10 CFR Chapter I; D. The issuance of this license 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 satisfied.
- 2. Accordingly, the license is hereby amended by page 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:
-2 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 185, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION David B. atthews, Director Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
May 14, 1991
ATTACHMENT TO LICENSE AMENDMENT NO.
188 FACILITY OPERATING LICENSE NO. DPR-38 DOCKET NO. 50-269 AND TO LICENSE AMENDMENT NO.
188 FACILITY OPERATING LICENSE NO. DPR-47 DOCKET NO. 50-270 AND TO LICENSE AMENDMENT NO.
185 FACILITY OPERATING LICENSE NO. DPR-55 DOCKET NO. 50-287 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Remove Pages Insert Pages 3.1-3a 3.1-3a through 3.1-7e through 3.1-7e
3.1.2.7 Prior to exceeding fifteen (Unit 1) fifteen (Unit 2) fifteen (Unit 3) effective full power years of operation.
Figures 3.1.2-IA (Unit 1), 3.1.2-2A (Unit 1) 3.1.2-1B (Unit 2), 3.1.2-2B (Unit 2) 3.1.2-IC (Unit 2), 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. and V.E.
3.1.2.8 The updated proposed technical specification referred to in 3.1.2.7 s hall be submitted for NRC review-at least 90 days prior to the end of the service period for Units 1, 2 and 3.
3.1.2.9 Two trains of the low temperature overpressure protection (LTOP) system shall be operable.
< 500 psig for Units 1 and 2, <~ 480 psig for Unit 3. The PORV shall be operable when:
a) The temperature of one or more of the RCS cold legs is
< 325 0F, and b) When RCS pressure is > 100 psig or HPI pumps are operating.
- 2.
The second LTOP train is comprised of the controls which assure that 10 minutes are available for operator action to mitigate an LTOP event.
The second LTOP train shall be operable when the temperature of one or more of the RCS cold legs is < 3250F and a RCS vent path equivalent to the PORV is not open. The following controls comprise the second LTOP train:
a) RCS pressure is limited to < 350 psig for Units I and 2, 345 psig for Unit 3 below an RCS temperature of 220*F.
..b) Deactivating train A and B of HPI.
c) Deactivating both core flood tanks.
d) Pressurizer level shall be controlled such that 10 minutes are available for operator action to mitigate an LTOP event.
Amendment No. 188 (Unit 1)
Amendment No. 188(Unit 2)
Amendment No. 18 5(Unit 3) 3.1-3a
e) Makeup flow shall be restricted such that 10 minutes are available for operator action to mitigate an LTOP event.
f) Alarms shall be provided such that 10 minutes are available for operator action to mitigate an LTOP event.
- 3.
a.1 If the PORV is inoperable, the PORV shall be returned to operable status or the RCS shall be heated above 3256F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
a.2 If the provisions of a.1 above cannot be fulfilled, the RCS shall be depressurized to < 100 psig and HPI shall be removed from service within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- b. If the second LTOP train is inoperable, action shall be initiated to restore the second train to operable status and compensatory measures shall be provided to monitor for initiation of an LTOP event within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
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 5.2-1 of the PSAR.
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 BAW-1699 and BAW-1697.
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 10F for possible errors in the pressure and temperature sensing instruments. 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 Hater 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 one the figures referred to in 3.1.2-3 for hydrostatic 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.
Amendment No.188 (Unit 1)
Amendment No. 188 (Unit 2) 3.]-3b Amendment No.18 5 (Unit 3)
The actual shift in RT of the beitline region material will be established periodically during oper tion 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 limitations on steam generator pressure and temperature provides protection against nonductile failure of the secondary side of the steam generator. A t metal temperatures lower than the RT of +60F the protection against nonductile failure is achieved by liging the scondary coolant pressureto 20 percent of the preoperational system hydrostatic test pressure.
The limitations of 110oF and 237 psig are based on the highest estimated RT of +40eF and the preoperational system hydrostatic test pressure of 1312pT.
The average metal temperature is assumed to be equal to or greater than the coolant temperature.
The limitations include margins of 25 psi and 10oF for
-possible instrument error.
The requirements to perform leakage tests of systems outside of containment which could potentially contain radioactivity were established by the NRC following Ta. Oconee performs the leak test of LPI by establishing RCS pressure at about 300 psig and with LPI_ at this same pressure, checking for leakage.
Such a test is within the scope of testing upon which the curves referenced in Specification 3.1.2.2 are based--that is, they are not routine evolutions, such as heatup and cooldown, but rather infrequent leak tests conducted on a refueling outage basis. As such, the hydrostatic/leak test pressure-temperature limitations are applicable for the RCS when performing leak tests of the LPI system.
The spray temperature difference is imposed to maintain the thermal stresses at the pressurized spray line nozzle below the design limit.
The reactor vessel is protected against damage due to excessive pressures at low temperatures by the Low Temperature Overpressure Protection (LTOP) System.
LTOP vulnerability is assumed when RCS cold leg temperature is < 325'F and a RCS vent path equivalent to the PORV is not open.
The LTOP System consists of two trains. One train is the pressurizer PORV calibrated to a low setpoint of less than or equal to 500 psig for Units I and 2 and 480 psig for Unit 3. The PORV block valve must be open for the PORV to be operable.R The capacity of the pressurizer PORV is sufficient to maintain the RCS pressure below the appropriate brittle fracture pressure limits during LTOP events in which boiling does not occur in the core. The remaining t rain is operator action and is based on an operating philosophy that precludes the plant from being in a water solid condition (except for system hydrotests).
The fact that the Oconee units are operated with a steam or gas space in the eessurizer allows sufficient time for operator action to termin ate an LTOP event prior to exceeding the appropriate brittle fracture pressure limits. Assuming an LTOP event was to occur at Oconee, and a single failure disables either train, the remaining train must be capable of maintaining RCS pressure below the appropriate brittle fracture pressure limits.
Amendment No.188 (Unit 1)
Amendment No.188 (Unit 2)
Amendment.No.185 (Unit -3) 3.1-4
The Oconee LTOP System provides protection from pressure transients at low temperatures, by limiting the pressure of such a transient to below the limits set by 10CFR 50 Appendix G utilizing a conservative safety factor of 1.5.
In addition, the following conditions are imposed by the NRC for the evaluation of the acceptability of LTOP Systems:
- a.
The most limiting initial conditions must be used.
- b.
The most limiting single failure, distinct from the initiating event, must be used.
- c.
No credit can be taken for mitigative operator action until 10 minutes after the operators become aware that a pressure transient is in progress.
For the Oconee units, the most limiting single failure is failure of the single pressurizer PORV to open at its low pressure setpoint. Operator aware ness is assumed to be achieved by actuation of control room alarms. The following scenarios have the potential to result in an LTOP event:
- 1) Makeup Control Valve (HP-120) fails full open.
- 2)
Erroneous opening of a core flood tank (CFT) discharge valve.
- 3)
Erroneous actuation of the HPI system.
- 4)
All pressurizer heaters erroneously energized.
- 5)
Temporary loss of decay heat removal.
- 6)
Thermal expansion of the RCS after starting an RCP due to stored energy in the steam generator.
Specification 3.1.2.9.2 requires that both CFTs and both HPI trains be isolated from the RCS, thus preventing these scenarios. Physical restriction of makeup flow, control of pressurizer level, and alarms ensure that at least 10 minutes are available for operator action to mitigate the remaining events.
Units specific values required to meet the 10 minute operator action criterion are provided within the Selected Licensee Commitment Manual.
In order to assure 10 minutes are available for operator action, the opera tional restrictions of Specification 3.1.2.9.2 must be implemented:
Deactivating train A of HPI is accomplished by one of the following methods:
- 1) Shutting and deactivating valve HP-26 by tagging open the valve breaker and tagging the valve handwheel in the closed position, shutting valve HP-410 and tagging the valve switch in the closed position.
- 2)
Deactivating all HPI pumps aligned to A HPI train and tagging the pump breakers open.
Amendment No. 188 (Unit 1)
Amendment No. 188 (Unit 2)
Amendment No. 185 (Unit 3) 3.1-4a
Deactivating train B of HPI is accomplished by one of the following methods:
- 1) Shutting and deactivating valve HP-27 by tagging open the valve breaker and tagging the valve handwheel in the closed position, shutting valve HP-409 and tagging the valve switch in the closed position.
- 2)
Deactivating all HPI pumps aligned to B HPI train and tagging the pump breakers open.
Deactivating both core flood tanks is accomplished by shutting valves CF-i and CF-2, tagging open the valve breaker, and tagging the valves in the closed position. Alternately, core flood tanks may be deactivated by maintaining core flood tank pressure below the maximum allowable RCS pressure for the existing RCS temperature (per Figures 3.12-1 and 3.1.2-2).
Makeup flow must be restricted such that 10 minutes are available for operator action to mitigate the event.
Audible alarms must be provided such that 10 minutes are available for operator action to mitigate the event.
The intent of the action statements provided in Specification 3.1.2.9.3 is to place the reactor vessel in a condition in which it is not vulnerable to a LTOP event via the safest and most prompt course of action. In some cases, it may be more prudent to heat up above 325*F (cold leg temperature) rather than depressurize and open an RCS vent.
The allowable outage times (AOTs) provided in Specification 3.1.2.9.3 have been established based on the following considerations:
- a.
The most rapid LTOP scenarios exist with KPI pumps in operation, or with RCS pressure Z~ 100 psig.
As such, the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> AOT is suf ficiently brief to assure a minimal period of operation while vulnerable to a single failure of the PORV.
- b.
In the event of a
2nd train' inoperabilities, a time period of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is sufficient to return the train to operable status or to implement the compensatory measures.
REFERENCES (1)
Analysis of Capsule OCII-E from Duke Power Company Oconee Unit 2 Reactor VesseT-Materials Surveillance Program, BAW-205l, October, 1988.
(2) Analysis of Capsule OCIII-a from Duke Power Company Oconee Unit 3 Reactor Vessel Materials Surveillance Program, BAW-1697, October, 1981.
(3) Analysis of Capsule OCI-C from Duke Power Company Oconee Unit 1 Reactor Vessel Materials Surveillance Program, BAW-2050, October, 1988.
Amendment No. 188 (Unit 1)
Amendment No. 188 (Unit 2) 3.1-4b Amendment No. 185 (Unit 3)
TABLE 3.1-1 OPERATIONAL SPECIFICATIONS FOR PLANT HEATUP I. RC Temperature Constraints RC TemperatureM Maximum Heatup Rate T < 280 0F 500F/HR T > 280 0F 100oF/HR II. RC Pump Constraints RC Temperature(1)
Allowed Pump Combination T > 250oF Any T < 250 0 F No more than 1 pump per loop
(
p)
RC Temperature is cold leg temperature if one or more RC pumps are in operation; otherwise it is the LPI cooler outlet temperature.
Amendment No. 188 (Unit 1)
Amendment No. 188 (Unit 2)
Amendment No. 185 (Unit 3) 3.1-5
TABLE 3.1-2 OPERATIONAL SPECIFICATIONS FOR PLANT COOLDOWN I. RC Temperature Constraints RC Temperature(1)
Maximum Cooldown Rate (2)
T > 280 0F
< 500F in any 1/2 hour period 150 0F < T < 280 0F.
< 25cF in any 1/2 hour period T < 150 0F
< 10oF in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period RCS depressurized (3) 50'F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period II. RC Pump Constraints For Validity of Guidance RC Temperature(1)
Allowed Pump Combinations T > 270oF Any 200 0F < T < 270 0F No more than 1 pump per loop T < 200F No more than 1 pump (1) RC Temperature is cold leg temperature if one or more RC pumps are in operation or if on natural circulation cooldown; otherwise it is the LPI cooler outlet temperature.
(2) These rate limits must be applied to the change in temperature indication from cold leg temperature to LPI cooler outlet temperature per Note (1).
(3) When the RCS is depressurized such that all three of the following conditions exist:
a) RCS temperature < 2000F, b) RCS pressure < 50 psig, c) All RC Pumps off, the maximum cooldown rate shall be relaxed to < 50*F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period.
Amendment No. 188 (Unit 1)
Amendment No. 188 (Unit 2) 3.1-SaAmendment No. 185 (Unii 3)
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Unit 3 Oconee Nuclear Station Reactor Coolant System Normal Operation Cooldown Limitations Applicable for First 15.0 ErPY 2400 (Reg. Guide 1.99. Revision 2) 2200 Pea inMie stace runce = 0.730 o" n/cmi THE REGIONS OF ACCEPTABLE OPERATION ARE BELOW AND TO THE RIGHT OF THE LIMIT CURVES. MARGINS ARE INCLUDED FOR THE PRESSURE DIFFERENTIAL BETWEEN POINT O SYSTEM PRESSURE MEASUREMENT AND THE PRESSURE ON 2000 THE REACTOR VESSEL REGION CONTROLLING THE LIMIT CURVE. MARGINS oF 25 PSIS AND 10* F ARE INCLUDED FOR POSSIBLE INSTRUMENT ERROR.
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Unit 2 Oconee Nuclear Station Reactor Coolant System Inservice teak and Hydrostatic Test Heatup and Cooldown Limitations Applicable for 15.0 EFPY 2600 (Reg. Guide 1.99. Revision 2)
- Peat, isl Surface Fluence = 0.50 x 1019 n/cm' 2200 n/m THE RESIONS OF ACCEPTABLE OPERATION ARE BELOW AND TO THE RIGHT OF THE LIWITCURVES. MARGINS ARE INCLUDED FOR THE PRESSURE DIFFERENTIAL BETWEEN POINT OF SYSTEM PRESSURE MEASpREMENT AND THE PRESSURE ON 2000 -
THE REACTOR VESSEL REGION CONTROLLING THE LIMIT CURVE. MARGINS OF 25 PSIG AND 1O* F ARE INCLUDED FOR POSSIBLE INSTRUMENT ERROR.
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