ML20071P844

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Forwards Evaluation of Pressurizer Safety & Relief Valve Sys for Point Beach Nuclear Plant, in Further Response to NUREG-0737,Item II.D.1 Re Relief & Safety Valve Testing
ML20071P844
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 12/23/1982
From: Fay C
WISCONSIN ELECTRIC POWER CO.
To: Clark R, Harold Denton
Office of Nuclear Reactor Regulation
Shared Package
ML20071P846 List:
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM NUDOCS 8212290095
Download: ML20071P844 (2)


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231 W. MICHIGAN, P.O. BOX 2046, MILWAUKEE, WI 53201 December 23, 1982 Mr.

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R.

Denton, Director Office of Nuclear Reactor Regulation U.

S. NUCLEAR REGULATORY COMMISSION Washington, D. C.

20555 Attention:

Mr. R. A. Clark, Chief Operating Reactors, Branch 3 Gentlemen:

DOCKET NOS. 50-266 AND 50-30]

FURTHER RESPONSE TO NUREG-0737, ITEM II.D.1 RELIEF AND SAFETY VALVE TESTING POINT BEACH NUCLEAR PLANT, UNITS l 'AliD 2 This is to provide the current stabus of,our continuing evaluations and analyses regarding relief and safety valve operability in response to NUREG-0737 requirements.

The enclosure to this letter provides the results of piping and support analyses for the existing installations at Point Beach Nuclear Plant, Units 1 and 2, and discussion of valve operability based upon EPRI Test Program results.

The detai*

  • piping and support analyses described in the enclosure have ic..t&fied modifications which will be implemented to provide the,,d;4 ity of piping and supports to accommodate the calculatet ;,;V ctuation loads during transient conditions.

Conceptual supgort c.. signs and piping stress analyses using the conceptual designs have been completed for Unit 1 and are in progress for Unit 2.

A detailed walkdown was performed during the recent Unit 1 refueling outage to verify that supports and support modifica-tions can be installed as indicated by the conceptual study.

Final support designs will be developed for Unit 1 and are expected to be installed during the steam generator replacement outage scheduled to begin in October 1983.

A similar walkdown will be conducted in Unit 2 during the refueling and steam generator sleeving outage scheduled to begin in late March 1983.

Based upon the walkdown, final support designs will be developed.

We expect to complete the installation or modification of Unit 2 supports during the 1983 refueling and sleeving outage. /

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Mr. H. R. Denton December 23, 1982 Should you.have questions concerning this submittal, please contact us.

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Very truly yours, d2u', f

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Assistant Vice President C. W. Fay Enclosure Copy to NRC Resident Inspector

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