ML20053C579
| ML20053C579 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 05/26/1982 |
| From: | Leasburg R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Clark R, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.1, TASK-2.B.2, TASK-2.B.3, TASK-2.D.1, TASK-2.E.1.2, TASK-2.E.4.1, TASK-2.F.1, TASK-TM 313, NUDOCS 8206020339 | |
| Download: ML20053C579 (8) | |
Text
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O VINGINIA ELECTRIC AND POWER COMPANY H acinxown, VIHOINIA 20261 H.H.LEANHUNG vic....... n May 26, 1982 Nrrtman oramation.
Mr. Harold R. Denton, Director Serial No. 313 Office of Nuclear Reactor Regulation N0/JHL:acm Attn:
Mr. Robert A. Clark, Chief Docket No. 50-339 Operating Reactors Branch No. 3 License No. NPF-7 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen:
AMENDMENT TO OPERATING LICENSE NPF-7 NORTH ANNA POWER STATION UNIT NO. 2 PROPOSED OPERATING LICENSE AMENDMENT Pursuant to 10 CFR 50.90, the Virginia Electric and Power Company requests an amendment to Operating License NPF-7 for North Anna Power Station Unit No. 2.
The proposed change to the Operating License is enclosed.
License Condition 2.C(21)(d) of the North Anna Unit 2 Operating License states, "VEPCO shall complete modifications to assure adequate access to s cal areas and protection of safety equipment following an accident resulting in a degraded core no later than the implementation schedule of NUREG-0737." The implementation schedule stated in NUREG-0737 is July 1, 1982.
The proposed change to the Operating License is to complete modifications to assure aidequate access to vital areas and protection of safety equipment following an accident resulting in a degraded core no later than January 1,
1983.
The l
proposed amendment is enclosed in Attachment 1.
A discussion of the proposed i
change is provided in Attachment 2.
l This request has been reviewed and approved by the Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control staff.
It has been determined that this request does not involve an unreviewed safety question as defined in 10 CFR 50.59.
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We have evaluated this request in accordance with the criteria in 10 CFR 170.22.
Since this request involves a safety issue which the Staff should be able to determine does not pose a significant hazard consideration for Unit 2, a Class III license amendment fee is required for Unit 2.
Accordingly, a voucher check in the amount of $4000.00 is enclosed in payment of the required fees.
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Ver truly yours,
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wl.m 5/J h R.'H.'Leasburg
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8206020339 820526 PDR ADOCK 05000339 M
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VinoixA ELECTRIC AND POWER COMPANY 70 Attachments:
1.
Proposed Operating License Amendment 2.
Discussion of Proposed Operating License Amendment 3.
Voucher Check No. 28138 for $4000.00 cc:
Mr. James P. O'Reilly Regional Administrator Region II i
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COMMONWEALTH OF VIRGINIA )
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CITY OF RICHMOND
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i The foregoing document was acknowledged before me, in and for the City and Commonwealth aforesaid, today by W.
L.
Stewart, who is Manager-Nuclear Operations and Maintenance, of the Virginia Electric and Power Company. He is duly authorized to execute and file the foregoing document in behalf of that Company, and the statements in the document are true to the best of his knowledge and belief.
Acknowledged before me this AA ay of M
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ATTACHED CHECK ISSUED AS PAYMENT OF ITEMS USTEJ ABOVE - PLEASE DETACH STU CASH CHECK PROMPTLY.
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ATTACHMENT 1 PROPOSED OPERATING LICENSE AMENDMENT 1
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. (c) Reactor Coolant System Vents (Section 22.2 Item II.B.1)
VEPC0 shall submit procedural guidelines and analytical bases for the reactor coolant system vents. The reactor coolant system vents shall be installed no later than the implementation schedule of NUREG-0737.
(d) Plant Shielding (Section 22.3 Item II.B.2)
VEPC0 shall complete modifications to assure adequate access to vital areas and protection of safety equipment following an accident resulting in a degraded core no later than January 1, 1983.
(e) Post-Accident 3ampling (Section 22.3 Item II.B.3)
VEPCO shall complete corrective actions needed to provide the capability to promptly obtain and perform radioisotopic and chemical analysis of reactor coolant and containment atmosphere samples under degraded core conditions without excessive exposure at the first outage of sufficient duration but no later than July 1, 1982.
(f) Relief and Safety Valve Test Requirements (Section 22.3 Item II.D.1)
VEPCO shall complete tests to qualify the reactor coolant system relief and safety valves under expected operating conditions for design basis transients and accidents no later than July 1, 1982.
(g) Auxiliary Feedwater Initiation and Indication (Section 22.3 Item II.E.1.2)
VEPCO shall implement the modification to upgrade the safety-grade indications of AFW flow from semi-vital bus power to vital bus power no later than January 1, 1981.
(h) Containment Dedicated Penetrations (Section 22.3 Item II.E.4.1)
VEPC0 shall install redundant remote actuated valves in series to isolate the containment vacuum pumps from the combustible gas control system.
VEPCO shall also convert the manual valves in the hydrogen recombiner piping to remote manual actuation no later than the implementation schedule of NUREG-0737.
(1) Additional Accident Monitoring Instrumentation (Section 22.3 Item II.F.1)
VEPCO shall install and demonstrate the operability of instruments for continuous indication in the control room of the following variables.
Each item shall be completed by the specified date in the condition:
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e ATTACHMENT 2 DISCUSSION OF PROPOSED OPERATING LICENSE AMENDMENT l
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O DISCUSSION OF PROPOSED OPERATING LICENSE AMENDMENT North Anna Unit 2 License Condition 2.C(21)(d) states "VEPC0 shall complete modifications to assure adequate access to vital areas and protection of safety equipment following an accident resulting in a degraded core no later than the implementation schedule of NUREG-0737."
stil requirements of License Condition 2.C(21)(d) will have been met when the installation of remotely (parated valves and associated piping in the Atmosphere Cleanup System is complete.
The delay in completing this modification was caused by equipment delivery problems.
Unit 2 is currently in a refueling outage and Unit 1 is scheduled for a refueling outage in early summer.
Since portions of the Atmosphere Cleanup System are shared, completion of the Unit 1 modification is necessary in order for the Unit 2 system to be fully operable.
The intent is to complete these modifications by the end of the Unit 1 outage which may exceed the July 1,
1982 date.
The proposed License Condition change will state "VEPCO shall complete modifications to assure adequate access to vital areas and protection of safety equipment following an accident resulting in a degraded core no later than January 1, 1983.
The probability of occurrance or the consequences of a malfunction of equipment important to safety and previously evaluated in the FSAR is not increased because of a delay in installation of modifications to assure adequate access in vital areas and protection of safety equipment following an accident resulting in a degraded core.
The possibility of a different type of accident or malfunction than was previously evaluated in the FSAR has not been created because a delay in installation would not disallow the use of other safety related equipment following an accident reaulting in a degraded core.
The margin of safety as described in the BASIS section of any part of the Technical Specifications is not reduced because other safety related equipment following an accident resulting in a degraded core can be utilized.
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