ML20091A646
| ML20091A646 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 03/16/1992 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | Georgia Power Co, Oglethorpe Power Corp, Municipal Electric Authority of Georgia, City of Dalton, GA |
| Shared Package | |
| ML20091A653 | List: |
| References | |
| NPF-68-A-050, NPF-81-A-029 NUDOCS 9203300098 | |
| Download: ML20091A646 (9) | |
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UNITED STATES
- // h NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 70555
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- GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA V0GTLE ELECTRIC GENERATING PLANT. UNIT 1 AMENDMENT TO FACIllTY OPERATING LICENSE Amendment No. 50 License No. NPF-68 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Vogtle Electric Generating Plant, Unit 1 (the facility) Facility Operating License No. NPF-68 filed by the Georgia P >wer Company, acting for itself, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees), dated November 20, 1991, as suoplemented February 7, 1992, complies with the standards and requirements of tha Atomic Energy Act of 1954, as amended (the Act),
and the Commission : rules and regulations ac set forth in 10 CFR Chapter I; l
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of.he 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 amendment will not be inimical to the common defence 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.
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. 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 2.C.(2) of Facility Operating License No, NPF-68 is hereby amended to read as follows:
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 50, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license.
GPC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/L Day d B. M tthews, Director Project Directorate II-3 Division of Reacton' Projects-l/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes i
i Date of Issuance:
March 16, 1992 l
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GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGif V0GTLE ELECTRIC GENERATING PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 29 License No. NPF-81 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Vogtle Electric Generating Plant, Unit 2 (the facility) Facility Operating License No. NPF-81 filed by the Georgia Power Company, acting for itself, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees), dated-November 20, 1991, as l
supplemented February 7, 1992, complies with the standards and l
requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations as 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 Commi:sion; 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 l
In 10 CFR Chapter I; 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 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 2.C.(2) of f acility Operating License No. NPF-81 is hereby amended to read as follows:
Technical Specifications and Environmenta! Protection Plan.
The Technical Specifications contained in Appendix A, o.evised through Amendment No. 29
, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license.
GPC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation l
Attachment:
Technical Specification Changes Date of Issuance:
March 16, 1992 l
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ATTACHMENT TO LICENSE AMENDMENT NO. 50 FACILITY OPERATING LICENSE NO, NPF-68 DOCKET NO, 50-424 AND TO LICENSE AMENDMENT NO, 29 FACillTY OPERATING LICENSE NO. NPF-91 1
DOCKET N0, 50-421 Repic.e 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 Paaes Insert Paags 3/4 4-35a*
3/4 4-35a*
3/4 4-36 3/4 4-36
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3/4 5-3*
3/4 5-3*
3/4 5-4 3/4 5-4
- overleaf page - no change I
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UNIT 2 800 (382,738)
(350,738) s 3
5 700 f
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J (70,505) soo 460 50 100 150 200 250 300 3M TRTD-AUCTIONEERED LOW MEASUMED MCS TEWERATURE (*F)
FIGURE 3.4-4b UNIT 2 MAXIMUM ALLOWABLE NOMINAL PORV SETPOINT FOR THE COLD OVERPRESSURE PROTECTION SYSTEM V0GTLE UNITS - 1 & 2 3/4 4-35a
REACTOR COOLANT SYSTEM OVERPRESSl'RE PROTECTION SYSTEM SURVEILLANCE REQUIREMENTS 4.4.9.3.1 Each PORV shall be demonstrated OPERABLE by:
a.
Performance of an ANALOG CHANNEL OPERATIONAL TEST on the PORV actuation channel, but excluding valve operation, within 31 days prior to entering a condition in which the PORV is required OPERABLE and at least once per 31 days thereafter when the PORV is required OPERABLE; b.
Performance of a CHANNEL CALIBRATION on the PORV actuation channel at least once per 18 months; and c.
Verifying the PORV isolation valve is open at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when the PORV is being used for overpressure protection.
4.4.9.3.2 Each RHR suction relief valve shall be demonstrated OPERABLE when the RHR suction relief valves are being used for cold overpressure protection as follows:
a.
For RHR suction relief valve PSV-8708A by verifying at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> that RHR RCS suction isolation valves HV-8701A and HV-8701B l
are open; b.
For RHR suction relief valve PSV-8708B by verifying at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> that RHR RCS suction isolation valves HV-8702A and HV-87028 l
are open; and c.
Testing pursuant to specification 4.0.5.
4.4.9.3.3 The RCS vent (s) thall be verified to be open at least once per 12 heurs* when the vent (s) is being used for overpressure protection.
"Except when the vent pathway is provided with a valve which is locked, sealed, or otherwise secured in the open position, then verify these valves open at least once per 31 days.
V0GTLE UNITS - 1 & 2 3/4 4-36 Amendment No. 50 (Unit 1) l Amendment No. 29 (Unit 2)
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EMERGENCY CORE COOLING SYSTEMS 3/4.5.2 ECCS SUBSYSTEMS - T GREATER THAN OR EQUAL TO 350*F avg LIMITING CONDITION FOR OPERATION 3.5.2 Two independent Emergency Core Cooling System (ECCS) subsystems shall be OPERABLE with each subsystem comprised of:
a.
One OPERABLE centrifugal charging pump, b.
One OPERABLE Safety Injection pump, c.
One OPERABLE RHR heat exchanger, d.
An OPERABLE flow path capable of taking suction from the refueling water storage tank on a Safety Injection signal and semi-automatically transferring suction to the containment emergency sump during the recirculation phase of operation.
APPLICABILITY:
MODES 1, 2, and 3.*
ACTION:
l a.
With one ECCS subsystem inoperable, restore the inoperable subsystein to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, b.
In the event the ECCS is actuated and injects water into-the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.8.2 within 90 days describ-ing the circumstances of the actuation and the total accumulated actuation cycles to date.
The current value of the_ usage factor for each affected Safety injection nozzle shall be provided in this Special Report'whenever its value exceeds 0.70.
- The provisions of Specification > 3.0.4 and 4.0.4 are not applicable for entry into MODE 3 for the Safety Injection Pumps declared inoperable pursuant to Specification 3.5.3.2 provided'the Safety Injection Pumps are restored to OPERABLE status.within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or prior to the temperature of one or more of.
the P.CS cold legs exceeding 375 F, whichever occurs first.
V0GTLE UNITS-- 1 & 2 3/4'5-3
EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the following valves a.
are in the indicated positions with power lockout switches in the lockout position:
Valve Number Valve Function Valve Position-HV-8835 SI Pump Cold leg Inj.
OPEN HV-8840 RHR Pump Hot Leg Inj.
CLOSED HV-8813 SI Pump Mini Flow Isol.
OPEN HV-8806 SI Pump Suction from RWST OPEN HV-8802A, 8 SI Pump Hot Leg Inj.
CLOSED HV-8809A, B RHR Pump Cold Leg Inj.
OPEN*
b.
At least once per 31 days by:
1)
Verifying that the ECCS piping is full of water by ve'nting the ECCS pump casings and accessible discharge piping high points, and 2)
Verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or _otherwise secured in position, is in its correct position.
By a visual inspection which verifies that no loose debris (rags, c.
trash, clothing, etc.)'is present in the containment which could be transported to the Containment Emergency Sump and cause restriction of the pump suctions during LOCA conditions.
This visual inspection shall be performed:
1)
-For all accessible areas of the_ containment prior to establish-ing CONTAINMENT INTEGRITY, and 2)
Of the areas affected within containment-at'the completion of each containment entry when CONTAINMENT INTEGRITY is established.
d.
At least once per 18 months by:
1)
Verifying automatic isolation action of the RHRLsystem from the l
Reactor Coolant' System by ensuring that with a simulated or actual Reactor Coolant System pressure signal greater than or-equal to 365 psig the interlocks prevent the valves from being opened.
l 2)
A visual inspection of-the Containment Emergency Sump and verify-i ing that the subsystem suction inlets are not restricted by_ debris and that the sump components (trash racks, screens, etc.) show no evidence of-structural distress or abnormal corrosion.-
- Either valve may be realigned in Mode 3 for testing pursuant to Specification I
i 4.4.6.2.2.
.V0GTLE UNITS 1 & 2
-3/4 5-4 Amendment No. 50 (Unit 1) l Amendment No. 29 (Unit 2)
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