ML20198P769

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Provides Suppl Response to GL 97-01, Degradation of Control Rod Drive Mechanism Nozzle & Other Vessel Closure Head Penetrations
ML20198P769
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 01/05/1998
From: Muench R
WOLF CREEK NUCLEAR OPERATING CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
ET-98-0001, ET-98-1, GL-97-01, GL-97-1, NUDOCS 9801220239
Download: ML20198P769 (3)


Text

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J W49LF CREEK NUCLEAR OPERATING CORPORATION Richard A. Muench -

Vee President Caineering January 5, 1998 ET 98-0001 U. S. Nuclear Regulatory Commission ATTN:

Document Contrs1 Desk Mail Station Pl-137 Washington, D C.

20555

Reference:

1) Letter ET 97-0085, dated July 24, 1997, from R. A. Muench, WCHOC, to the NRC
2) Letter dated December 31, 1997 from D.

J.

Modeen, NEI, to G. C. Lainas, NRC

Subject:

Docket No.

50-482: Supplemental Response to Generic Letter 97-01 Gentlemen:

Reference 1 transmitted Wolf Creek Nuclear Operating Corporation's (WCNOC) 120 day response to Generic Letter 97-01,

" Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations." This response indicated that WCNOC would provide, based on Nuclear Energy Institute (NEI) and Westinghouse Owners Group (WOG) activities:

An industry histogram that groups plants without names based on the time to initiate and propagate a crack to 75%.through wall and An industry activity timeline/ schedule.

b Figure 1 of Reference 2 provided an. interim industry, " Histogram of Head Penetration Susceptibility, Cracking to Match D.

C.

Cook 2."

Wolf Creek Generating Station (WCGS) falls in the greater than 15' effective full power

. years category of Figure 1 of Reference 2.

The histogram comparison is based on the cumulative probability of cracking in at least one penetration in the entire head of each plant evaluated. The analysis results are reported as the time (offective full power years of operation beginning January 1, 1997) for a subject plant to reach a reference probability level.

This reference probability level was defined using the results of one D.

C.

Cook Unit 2 inspection in 1994 and predictions made for D.

C. Cook Unit 2 using the same methodology as for the subject plant.

Attachment A of Reference 2 ' provided an industry activity timeline/ schedule.

'WCGS falls within the greater - than 15 years time period discussed in Attachment A of Reference 2, and therefore has no plans to inspect Reactor Vessel head penetrations at this time.

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- If you - have any questions concerning this matter, please contact me at (316) 364-8031,- extension 4034, or Mr. Michael J. Angus, at extension 4077.

Very truly yours, I /A$4h Richa d A. Muench RAM /jad cc: W. D. Johnson (NRC)

E. W. Morschoff (NRC)

J. F. Ringwald (NRC)

K. M. Thomas (NRC)

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' STATE OF KANSAS

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COUNTY OF COFFEY

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m Richard A. Muench, _of lawful age, being first'. duly sworn upon oath'says that-he'is Vice Presiden'; Engineering of Wolf Creek Nuclear Operating Corporation;

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that he has. read the' foregoing document and knows the content-thereof; that he has' executed that same for and on behalf of.. said Corporation -with full

, power.and authority to do'soi-and that~the facts therein stated lare true and correct to the best of his knowledge, information and belief.

By 48 Richard

..Muench Vice Pr sident Engineering h

SUBSCRIBED and sworn to before me this 5 day of 1998.

rn m. 8. CLA,

MARY E. GIFFORD '

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