ML19210E865
| ML19210E865 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 11/07/1979 |
| From: | Counsil W NORTHEAST UTILITIES |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| IEB-79-14, NUDOCS 7912130113 | |
| Download: ML19210E865 (13) | |
Text
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We NOIFI111!AST IFFII.ITII!S 1
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L a ::'=;0; 2,"TJ'#J':l November 7, 1979 Docket No. 50-336 Mr. Boyce H. Grier, Director Region I Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406
References:
(1)
B. H. Grier letter to W. G. Counsil dated July 2, 1979, forwarding I&E Bulletin No. 79-14.
(2)
B. H. Grier letter to W. G. Counsil dated August 15, 1979, forwarding I&E Bulletin No. 79-14, Supplement.
(3)
W. G. Counsil letter to B. H. Grier dated September 10, 1979.
Gentlemen:
Millstone Nuclear Power Station, Unit No. 2 I&E Bulletin No. 79-14 Reference (1), as amended by Reference (2), requested Northeast Nuclear Energy Company (NNECO) to initiate a program aimed at verifying the accuracy of input information for seismic analysis of safety-related piping.
NNECO submitted the available results of inspections performed on both accessi-ble and inaccessible piping systems, as required by Items 2 and 3 of Reference (1),
in Reference (3).
Reference (3) also documented NNECO's intention to examine / verify the remaining portions of the inaccessible systems during the 1980 refueling outage. A final report containing the results of the remaining inspections was scheduled to be submitted upon completion of the inspections.
Due to an extended outage re-quired to effect repairs of feedwater piping crack indications, it is expected that sufficient opportunity will exist to complete the inspections of inaccessi-ble piping systems prior to plant startup, from the current outage.
NNECO has determined that system operability, and hence, the ability of the plant to withstand a postulated seismic event, has not been adversely affected by any of the deviations found to date based on preliminary engineering er detailed stress analysis / support reviews. Attachment 1 contains the results of the inspections and analyses performed to date and is provided as an update to Reference (3).
1543 292 7 91nso lla i g
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. A final report containing the results of the remaining inspections is scheduled to be submitted upon completion of the inspections.
We trust this information is responsive to the NRC Staff's requests.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY b
d W. G. Counsil Vice President Attachment
\\
DOCKET NO. 50-336 ATTACHMENT 1 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 I&E BULLETIN No. 79-14 1543 294 NOVEMBER, 1979
NNECO has completed the inspection and measurement phases for all accessible piping and supports contained in the systems under investigation. Table 1 lists the approximate percentages of both accessible and inaccessible systems which have been inspected as of October 31, 1979.
Table 2 lists the piping stress calculations which have been evaluated as of October 26, 1979.
Also listed is the corrective action required for each deviation in a particular stress problem.
Of the fifty (50) calculations evaluated, eighteen (18) contain deviations.
Twelve (12) are undergoing reanalysis and should be resolved upon completion. Three (3) will be re-solved by support modifications, and the remaining three (3) will be resolved by a combination of support modifications and reanalysis.
NNECO has determined that system operability, and hence, the ability of the plant to withstand a postulated seismic event, has not been adversely affected by any of the deviations found to date based on preliminary engineering or detailed stress analysis / support reviews.
1543 295
TABLE 1 MILLSTONE UNIT 2 EXTENT OF SYSTEMS INSPECTED AS OF OCTOBER 26, 1979:
% COMPLETE
% COMPLETE OUTSIDE INSIDE SYSTEM CONIAINMENT CONTAINMENT Main Steam 90 90 Feedvater 100 100 Containment Spray
~100 100 Safety Injection Tanks 100 60 RBCCW 100 40 CVCS 100 40 Service Water 100 N/A Chilled Water 100 N/A HPSI 100 100 LPSI 100 95 Spent Fuel Pool 100 85 Diesel Generator Systems 100 N/A Auxiliary Feedwater 100 100 Reactor Coolant Systems N/A 0
Containment Penetrations 100 20 1543 29~6 ~
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