ML20244E270

Suppl 1 to AEC SER Re Licensee Conversion from Provisional OL to full-term OL for Util

ML20244E270
Person / Time
Site:	Nine Mile Point
Issue date:	11/15/1974
From:	US ATOMIC ENERGY COMMISSION (AEC)
To:
Shared Package
ML17055E652	List: IA-89-101, Informs of Completion of Review of Application by Niagara Mohawk Power Corp for Conversion of Util Provisional OL to full-term OL During ACRS 740905-07 Meeting.Concurs in Subj License Conversion IA-89-114, Confirms 740624 Meeting Re Author Review of Util SER & Concurrence Subj to Revs Discussed ML20244C683 ML20244C712 ML20244C715 ML20244C728 ML20244C740 ML20244C768 ML20244C776 ML20244C791 ML20244C807 ML20244C810 ML20244C813 ML20244C816 ML20244C818 ML20244C821 ML20244C825 ML20244C827 ML20244D471 ML20244D475 ML20244D485 ML20244D499 ML20244D512 ML20244D553 ML20244D969 ML20244D979 ML20244D984 ML20244D995 ML20244E011 ML20244E026 ML20244E032 ML20244E123 ML20244E128 ML20244E141 ML20244E163 ML20244E184 ML20244E223 ML20244E231 ML20244E248 ML20244E270 ML20244E353 NUREG-1125, Final Response to FOIA Request for Documents.Forwards App a Documents.App a Documents Also Available in Pdr.Acrs Rept Subj to Request Published in NUREG-1125,Vol 2, Compilation of ACRS Repts
References
FOIA-89-101, FOIA-89-114 NUDOCS 8904240387
Download: ML20244E270 (5)

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y SUPPLEMENT NO. 1 TO THE SAFETY EVALUATION REPORT BY THE DIRECTORATE OF LICENSING U. S. ATOMIC ENERGY COMMISSION

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NIAGARA MOHAWK POWER CORPORATION CONVERSION FROM PROVISIONAL OPERATING LICENSE TO FULL-TERM OPERATING LICENSE

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NINE MILE POINT UNIT 1 i

l DOCKET NO. 50-220 NOVEMBER'15,'1974

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'I 8904240387 890413 PDR FOIA WETTERH89-101 PDR ,

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TABLE OF CONTENTS e

1.0 INTRODUCTION

2.0 REPORT OF ADVISORY C0!C41TTEE ON REACTOR SAFECUARDS (ACRS)

!' 2.,1 Main Steam Line Isolation Valve Leakage T 2.2 Reactor Pressure Vessel In-Service Inspection 2.3 Possible Additional Backfit Improvements t

3.0 QUALITY ASSURANCE PROGRAM

, 440 CONCLUSIONS I

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l APPENDICES *-

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62PENDIX A Report of ACRS f

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1.0 INTRODUCTION

The AEC Regulatory staff's Safety Evaluation Report (SER), in the matter of the Niagara Mohawk Power Corporation (herein l

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referred to as hHPC or the licensee) application for conversion s

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of Provisional Operating License No. DPR-17 to a full-term

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operating license for Mine Mile Point Unit 1 (KMP-1) was issued I

on July 3, 1974. Copics of this report were made available to the Advisory Committee on Reactor Safeguards (ACRS or Committee) to assist it in its review of this application. The Comittee I completed its review of the licensee's application in September 1974 and reported its fir. dings to the Commission by letter dated September 10, 1974.

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. 2.0 REPORT OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS A copy of the ACRS report to.the Commission is included as 1

Appendix A. We have considered the comments and recommendations I made by the ACRS in this report and the actions which we have

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j taken or will take relative to these comments and recommendations

, are described in the following paragraphs. The Committee identified three matters for further surveillance: these matters consist of maintaining leak tightnesa of main steam line isolation valves; possible improvements in accessibility for in-service inspection of the reactor pressure vessel to assure continued vessel integrity; and consideration to the possible advisability of additional backfitting where significant and practical safety improvements can be made. The Committee concluded t' hat there

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exists reasonable assurance that' the Nine Mile Point Nuclear Station Unit 1 can continue to be operated at power levels up to 1850 MWt without undue risk to the health and safety of the public. Moreover, the Ccmmittee concurred in conversion of the c

i present provisional operating license to a full-term operating license.

I 2.1 Main Steam Line Isolation Valve Leakage The Cor.mittee 16dicated its awareness of the difficulty that has

, been experienced at hMP-1 in maintaining the required leak tightness of the main steam line isolation valves (MSLIV) and stated that the Regulatory sta'ff should continue to follow this matter closely.

The licensee stated its belief that leakage through these valves will be maintained at acceptable rates below the Technical 5h Specification limits as a result of changes in maintenance J

'k procedures involving the valve seats and plugs, initiated during the 1974 refueling shutdown. The next Icakage rate test of the' I

g MSL1Vs will be performed during the 1975 refueling shutdown.

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. The Regulatory staff will follow his matter to confirm that the problem is corrected.

r 2.2 Reactor Pressure Vessel In-Service Inspection The Committee expressed its belief that additional means for l

assuring continued vessel integrity, including possible improvement g in accessibility for inspection,should continue to be actively studied and implemented to the degree practical. The licensee has stated its interest to continue to seek possible improvements in the matter of vessel accessibility and to implement sucli m_ _ _ _ _ . . ._ _ _ _ _ . __ _ _.

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f-improvements to the degree practical. Our on-going review of the operating f acility will monitor progress in this area.

.2.3 Possible Additional Backfit Improvements l

l The Committee recommended that the Regulatory staff and the licensee

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' give further consideration to additional backfitting where significant 3

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and practical safety improvements can be made. The licensee has indicated that it has a continuing program of review to determine the conf ormance of NMP-1 with new Regulatory Guides as these are l: The Regulatory staff will continue its on-going review of issued.

NMP-1, including consideration of backfitting where significant and practical safety improvements can be made, i

3.0 QUALITY ASSURANCE (QA) PROGRM4

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Lt i As stated in our SER, we have reviewed the licensee's QA Program l, '

1 and concluded that it is acceptable. The licensee's QA Program j , was described in four different submittals. This information was Lj' superseded by the licensee's submittal of August 28, 1974, entitled,

! " Tenth Supplement to the Final Safety Analysis Report" which consolidates and unifica the earlier submittals. We have reviewed

' and determined that the Tenth Supplement to the FSAR is the same as the QA Program which we had previously reviewed and found acceptable.

4.0 CONCLUSION

S Our conclusions as stated in the Safety Evaluation Report remain I unchanged.

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