ML20198E142
| ML20198E142 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 12/01/1992 |
| From: | Withers B WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| WM-92-0184, WM-92-184, NUDOCS 9212040238 | |
| Download: ML20198E142 (2) | |
Text
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i WOLc CREEK
~
' NUCLEAR OPERATING CORPORATION Bart o witner, Decembt,' 1, 1992 President and Chief E necubva othcer WM 92-0184 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-137 Washington, D. C. 20555 3
Subject:
Docket No. 50-482:
Pump and Valve Inservice Testing Program Relief Request Gentlemen:
This lutter transmits relief request VR-24 to the Wolf Creek Generating Station (WCGS) Inservice Testing (IST) program in accordance with 10 CFR 50.55a(g)(3)(111).
This relief request proposes the adoption of ASME/ ANSI OMa-1988, Part 10 with an exception that referenced Part 1 requirements shall not be included.
Wolf Creek Nuclear Operating Corporation (WCNOC) intends to include Part I requirements in the IST program plan for the second ten year interval.
For WCGS, the second inspection interval starts in September 1995.
This relief request is being submitted so that the improved methods allowed by Part 10 may be incorporated into the IST program as part of WCNOC's review of the program.
WCNOC requests that the attached relief request be approved by February 26, 1993.
If you have any questions concerning this matter, please contact me at (316)364-8831 Ext. 4000 or Mr. Kevin J. Moles of my staff at Ext. 4565.
Very truly yours, Bart D. Withers President and Chief Executive Officer BDW/jra Attachment ec:
A. T. Howell (NRC), w/a J. L. Milhoan (NRC), w/a G. A. Pick (NRC), w/a W. D. Reckley (NRC), w/a i
J l
9212040238 921201 p
PDR ADOCK 05000, 2 o gox 43 3, Burhngton, KS 66839 - Phone. (316) 364-8831 I
P e tauar opportunny Ernpimer M F HC VET
'd 9
Attachment to WM 92-0184 Page 1 of 1 RELIEF REQUEST VR-24 VALVES:
All listed valves in the following categories l
CATEGORY:
A, B, C, and D FUNCTION:
Various, depending on component and system.
TEST REQUIREMENT:
Section XI, 1980 Edition through the Winter 1981 Addenda, Subsection IW except where prior relief has been granted.
BASIS FOR RELIEF:
Wolf Creek Nuclear Operating Corporation (WCNOC) has committed to perform a technical review of and incorporate required changes to all valve test procedures by February 28, 1993.
To improve the IST program during these changes WCNOC desires to adopt ASME/ ANSI OMa-1988 Part 10.
Part 10 incorporates later industry provisiens for valve testing and is considered by WCNOC to be a better methm of testing than Section XI IW.
However, adoption of Part i requirements referenced in Part 10 would place an undue burden - on WCNOC to incorporate Part 1 and Part 10 by February 28, 1993.
Therefore, WCNOC will continue to use the existing requirements of IW-3100, -3200, -3510, -3700, and -6000 of the 1980 Edition through Winter 1981 addenda of Section XI for pressure relief device testing in lieu of the reference to Part 1 contained in Part 10.
ALTERNATE TESTING:
By February 28, 1993, adopt all of ASME/ ANSI OMa-1988, Part 10, except references to Part 1.
In addition to Part 10, leakage rates for category A containment isolation valves that do not provide a reactor coolant system pressure isolation function will be analyzed in accordance with paragraph 4.2.2.3(e) of Part 10, and corrective actions for these valves will be made in accordance with paragraph 4.2.2.3(f) of Part 10, as required by 10 CFR 50.55a approved in the Federal Register dated August 6, 1992.
WCNOC will continue using IW-3100, -3200, -3510
-3700, and -6000 and will continue using the alternate testing approved through WCNOC's relief requests, i
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