ML19208A268
| ML19208A268 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 09/11/1979 |
| From: | Stallings C VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Parr O Office of Nuclear Reactor Regulation |
| References | |
| 740, NUDOCS 7909130310 | |
| Download: ML19208A268 (4) | |
Text
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VING I NI A ELECTHIC AN D POWE H C O M PA NY nicuwoxn,vanonwzA uocon September 11, 1979 Mr. Harold R. Denton, Director Serial No. 740 Office of Nuclear Reactor Regulation LQA/ESG:pwc Attn: Mr. O. D. Parr, Chief Light Water Reactors Branch No. 3 Docket No. 50-338 Division of Project Management License No. NPF-4 U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Dear Mr. Denton.
AMENDMENT TO OPERATING LICENSE NORTH ANNA POWER STATION UNIT NO. 1 Pursuant to 10CFR50.90, the Virginia Electric and Power Company hereby requests an amendment to Operating License NPF-4 for the North Anna Power Station, Unit No. 1.
The requested amendment is enclosed.
As has been discussed with the Staf f on September 10 and 11,1979, it has become necassary to extend operation of Unit 1 beyond the September 15, 1979 refueling date originally anticipated. Accordingly, we request that License Condition 2.D(3)p be revised to permit the refueling outage to begin no later than October 5,1979.
Our original application for a license anendment to defer certain Technical Specification surveillance requirements to the refueling outage (dated March 13, 1979, and supplemented by letters dated July 23 and July 31, 1979), noted that deferral of a f ew surveillance requirements for several weeks would have no significant ef fect on the ability of the systems to respond and perform under accident conditions.
In its Safety Evaluation for Anendment No. 13, the Staff agreed with this conclusion.
Based on our anticipated refueling schedule, the Staff specified that the outage begin no later than September 15, 1979. We now request that this be extended to October S.
Two groups of surveillance requirements are involved in this extension re-quest: Reactor Protection and Engineered Safety Features (ESP) response time testing, and Safety Injection (SI) and Containment Depressurization Actuation (CDA) testing. As our previous letters indicated, both trains and all channels of protection and ESF functions were checked during preoperational testing and found to have response times in tolerance with a margin of 10 to 40 percent.
We have also agreed to perform additional response tine testim; during the upcoming outage, as noted in the Staf f's Safety Evaluation for Auendment No.
13.
Based on the preoperational test results, and the additional testing to be performed, the short additional delay requested should not result in any significant ef fect on the ability of the equipment to perform satisfactorily.
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7909130 W O
moim Eucraic no Pown conwy To Mr. Ilarold R. Denton 2
The SI and CDA testing involves cycling of valves and pumps in response to test signals. Each of these valves and pumps responded satisf actorily to test signals during pre-operational testing.
In accordance with Technical Specification 4.0.5, many of the valves and all of the pumps involved are f unctionally tested on a f requency greater than 18 months to assure operability.
In addition, the reactor trip and ESF actuation system logic is tested monthly in accordance with Specifications 4.3.1.1.1 and 4. 3.2.1.1.
Based on these tests, the Staf f concluded in its Safety Evaluation that deferrals of these tests would be reasonable. This conclusion continues to be supported on the basis of testing conducted since Amendment 13 was issued.
This request has been approved by the Station Nuclear Safety and Opera-ting Committee and the System Nuclear Safety and Operating Committee.
It has been determined that this request does not involve an unreviewed safety ques-tion.
Based on the test results previously obtained, the additional testing to be performed during the outage, and the short additional delay being requested, the Staf f should be able to conclude that this request does not involve a significant hazards consideration, and is acceptable. Therefore, we have determined that this request is in Class III per 10CFR170.22, and a check in the amcunt of $4,000.00 is enclosed in payment of the amendment fee.
Your prompt approval of this request will be greatly appreciated.
Very truly yours, l<
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l C. M. Stallings Vice President-Power Supply and Production Operations Enclosures ec:
Mr. James P. O'Reilly, Director Of fice of Inspection and Enforcement Region 11 nvt-
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t COMMONWEALTH OF V IRGINI A
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S. S.
CITY OF RICHMOND
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Before me, a Notary Public, in and for the City and Common-wealth aforesaid, today personally appeared C. M. Stallings, who being duly sworn, made oath and said (1) that he is Vice President-Power Supply and Production Operations, of the Virginia Electric and Power Company, (2) that he is duly authorized to execute and file the fore-going Amendment in behalf of that Company, and (3) that the statements in the Amendment are true to the best of his knowledge and belief.
Given under my hand and notarial seal this //6 day of
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r-EilCLOSURE REQUESTED REVISI0il TO LICErlSE C0tlDITI0tl e
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7The end of-the current surveillance period for
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- -the Surveillance Requirements listed balow may be i
extended beyond the time limit specified by Technical Specification 4.0.2.a.
In each case, the required surveillance shall be completed by
._ the revised due date.. Upon acccmplish.ent. of th'e
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":g 7,T: 3 2.weillance, the provisions of Technical Specifi-
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- 4 (1) Specifications:i: : 4. 3.1.1.3,
- :- za-4.3.2.1.3 4.6.2.1.c
- 4. 6. 2. 2.1.c
- 4. 6. 2. 3.c
'~ 4. 6. 3.1.2.a
- 4. 6. 3.1. 2.b
- 4. 7. 4.1.d.2
- 4. 7. 8.1.d. 2 Revised due date: Prior to startup after first-refueling outage which will begin no later than October 5,1979.
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