ML20155C098
| ML20155C098 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 09/30/1988 |
| From: | Cartrwight W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML20155C101 | List: |
| References | |
| 88-605, NUDOCS 8810070236 | |
| Download: ML20155C098 (3) | |
Text
,_____-___- - - --
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VinointA ELucTn:C Ann Powan COMPANY Hacn woxo,Vamo xtr u 090:
September 30, 1988 t
l U. S. Nuclear Regulatory Comission Serial No.88-605 i
Attn: Document Control Desk N0/J0E l
Washington, D.C.
20555 Docket No.
50-338 50-339 i
License No. NPF-4 NPF-7 Gentlemen:
AMEN 0 MENT TO OPERATING LICENSES NPF-4 AND NPF-7 RRTFAJOIK P5HT3TATRTUNIT5 NO.1 AND 2 lllEREK5 Tin FQ(Z) LIMIT FOR 18F5TEAFCDIERATOR 103E PLUGGING l
Pursuant to 10 CFR 50.90, Virginia Electric and Power Company requests amendments, in the form of Technical Specifications chsnges, to Operating
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Licenses NPF-4 and NPF-7 for North Anna Units 1 and 2. respectively. We I
request that the proposed changes be approved for implementation prior to the l
upcoming refueling outage for Unit 1, currently scheduled to begin in April, 1989.
A LOCA-ECCS reanalysis for North Anna Units 1 and 2 has been performed using the NRC approved Westinghouse 19N ECCS Large Break Evaluation Model with the
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BART Code, in compliance with Appendix K to 10 CFR 50.
The results meet the l
acceptance criteria delineated in 10 CFR 50.46. This analysis was performed by
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the Company's Engineering Staff and will support continued full power operation l
for both North Anna units at steam generator tube plugging levels of up to 18%.
The results of this reanalysis also support a new maximum FQ limit of 2.19.
i T provides the proposed Technical Specifications changes for Units 1
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and 2.
The safety evaluation of the proposed changes is presented in l.
These changes and the supporting documentation have been
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approved by the Statien Nuclear Safety and Operating Comittee and by the c
Safety Evaluation and Control Staff.
It has been determined that this request i
does not pose any unreviewed safety question as defined in 10 CFR 50.59 nor does it pose a significant har:rds consideration as defined in 10 CFR 50.92.
i The basis for the determination that no significant hazards consideration 13 involved is presented in Attachment 3.
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fl50 Nfch S810070236 8S0930 PDR ADOCK 05000333 P
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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 yours #
4 W. R. Cartrwight Vice President - Nuclear Attachments 1.
Proposed Technical Specifications Changes - Units 1 and 2 2.
Safety Evaluation for North Anna Units 1 and 2 3.
10 CFR 50.92 Significant Hazards Evaluation cc:
U. S. Nuclear Regulatory Commission Region !!
101 Marietta Street, N.W.
Suite 2900 Atlanta, Georgia 30323 Mr. J. L. Caldwell NRC Senior Resident Inspector North Anna Power Station Commissioner Department of Health 109 Governor Street Richmond, Virginia 23219 9
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COMMONWEALTH OF VIRGIN!A )
COUNTY OF HENRICO The foregoing document was acknowledged before me, in and for the County and 4
Comonwealth aforesaid, today by W. R. Cartwright who is Vice President Nuclear, 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 3D, day of.,
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My Comission expires:
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