ML20155D215
| ML20155D215 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 09/30/1988 |
| From: | Cartwright W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML20155D219 | List: |
| References | |
| 88-306, NUDOCS 8810110132 | |
| Download: ML20155D215 (3) | |
Text
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e o VIHOINIA 13LECTHIC AND POwsu COMPANY Hrenxoxo, VinoixrA 2 00 61 September 30, 1988 United States Nuclear Regulatory Commission Serial No.88-306 Attention: Document Control Desk NL/DJV:jmj Washington, D.C.
20555 Docket Nos.
50-338 50-339 License Nos. NPF-4 NPF-7 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY
~
NORTH ANNA POWER STATION UNITS 1 AND 2 PROPOSED TECHNICAL SPECIFICATIONS CH&LGE Pursuant to 10 CFR 50.90, the Virginia Electric and Power Company requests amendments, in the form of changes to the Technical Specifications, to Operating Licenses No. NPF-4 and NPF-7 for North Anna Power Station Units 1 and 2, respectively.
These amendments would allow the direct reactor trip on turbine trip to be blocked below 30?. of the rated thermal power.
Currently, Permissive P-7 is used to block the reactor trip on turbine trip below 107. of rated thermal power.
The proposed modification would rewire the Solid State Protection System so that Permissive P-8 is used to block the reactor trip on turbine trip below 307. power.
A Virginia Electric and Power Company (Virginia Power) review of historical trip data shows that the most commonly cccurring reactor trip on turbine trip events are well below 307. of rated thermal power.
- Thus, it was concluded that the use of the existing P-8 bistable to block the direct reactor trip on turbine trip will be an effective means of reducing unneeded trips at low power.
Direct reactor trip on turbine trip will be available above 307. power.
The plant's designed load rejection capability is 50% of full load.
The proposed Technical Specification changes are presented in Attachment 1 (Unit 1) and Attachment 2 (Unit 2).
A safety evaluation in support of the proposed changes is provided in Attachment 3.
This request has been reviewed 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 or a significant hazards consideration as defined in 10 CFR 50.92.
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e t We have evaluated this request in accordance with the criteria in 10 CFR 170.12. A check in the amount of $150 is enclosed as an application fee.
Very truly your,
f W. R. Cartwrig t Vice President - Nuclear Attachments
- 1. Proposed Technical Specification Changes (Unit 1) l
- 2. Proposed Technical Specification Changes (Unit 2)
- 3. Safety Evaluation
- 4. 10 CFR 50.92 Evaluation cc:
U. S. Nuclear Regulatory Commission 101 Marietta Street, N.W.
Suite 2900 Atlanta, GA 30323 Mr. J. L. Caldwell NRC Senior Resident Inspector North Anna Power Station l
Commissioner Department of Health l
Room 400 l
109 Governor Street Richmond, Virginia 23219
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COMM0flWEALTH OF VIRGitilA )
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C0VilTY OF HEtlRICO
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The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by W. R.
Cartwright who is Vice President -
fluclear, of Virginia Electric and Power Company.
He is duly authorized to execute and file the foregoing document in behalf of that Company, and the statements in the document are true to the best of his knowledge and belief.
Acknowledged before me this Ma day of
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, 19 '$ l, My Commission expires:
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