ML18037A306
| ML18037A306 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 12/01/1980 |
| From: | Dise D NIAGARA MOHAWK POWER CORP. |
| To: | Robert Carlson NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, NUDOCS 8012090345 | |
| Download: ML18037A306 (6) | |
Text
REGUL'ATORY MFORRATION DISTRIBUTION SY R (RIDS)
ACCESSION NBR!80}2090345>>,
DOC ~ DATE: 80/12/01 NOTARIZED!
NO DOCK KIT FACIL:50-410 Nine Rile Point Nuclear Stationi Unit< 2i Niagara aloha 05000410 AUTH~NAME'UTHOR AFFCLll'ATION DISKiD.P.
Niagara Rogawk Power Corp.
RECIP, NAME RECIIP>>IE>>VT< AFFILrIATION CARLSONFR AT ~
Region- }s Philadelphiai Reactor Construction
& Ehgineerf
SUBJECT:
Interlim deficiency reptEotiginally submitted 800902qr e spent fuel. pool cop>>liing water heat'xcha'nger s ~ Addi infog furnished by vendo>>rrbeing eva'luted,Affected heat exchanger s'ejected.Frinal rept wi 1 l be submit ted by 8'10430.
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LI V NIAGARA A V MOHAWK NIAGARAMOHAWKPOWER CORPORATION/300 ERIE BOULEVARDWEST. SYRACUSE. N.Y. 13202/TELEPHONE (315) 474-1S11 Office of Inspection and Enforcement Region I Attention:
Mr. R. T. Carlson, Chief Reactor Construction and Engineering Support Branch U.
S. Nuclear Regulatory COWIission 631 Park Avenue King of Prussia, PA 19406
Dear Mr. Carlson:
December 1,
1980 cn<<f COC C/)
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~CO KN 1C Re: Nine Mile Point Unit 2 Docket No. 50-410 In accordance with Paragraph 50.55 (e) (3) of the Commission's regulations, attached is an interim report regarding the potential deficiency involving the spent fuel pool heat exchangers at Nine Mile Point Unit 2.
A final report will be provided by April 30, 1981.
Very truly yours, NIAGARA MOHAWK POWER CORPORATION
(," '..
Donald P. Disc Vice President Engineering PEF:ja Attachment xc;~Directo>=ot Inspect onmnd Enforcement U. S. Nuclear Regulatory Commission Washington, D.
C.
20555
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INTERIM REPORT SPENT FUEL POOL COOLING WATER HEAT EXCHANGERS POTENTIALLY REPORTABLE DEFICIENCY 10CFR50.55(e)
NINE MILE POINT UNIT 2 Docket No. 50-410 Descri tion of Deficienc As reported to Mr. R. Feil of the Nuclear Regulatory Coranission Region I staff on September 2,
- 1980, a potentially reportable deficiency involving the spent fuel pool cooling water heat exchangers was discovered during a review of documentation.
This was the subject of our letter to Mr. R. Carlson of the NRC on October 2,
1980.
The impact test data for several heat exchanger shell materials do not contain sufficient information to determine whether or not the specification and ASME Code impact test acceptance criteria are met.
Descri tion of Findin s
and Corrective Action The heat exchanger Vendor has furnished additional information necessary to evaluate the problem.
The information is being evaluated and its safety implications analyzed.
Initial corrective action to date has been to temporarily reject the affected heat exchangers for use.
Final corrective action to resolve the problem will be made after reviewing the analysis of the information recently furnished by the heat exchanger Vendor.
Additionally, possible corrective actions to prevent future problems of this nature are being evaluated and will be addressed in the final report.
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