ML20247L299
| ML20247L299 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 03/29/1989 |
| From: | Withers B WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20247L304 | List: |
| References | |
| WM-89-0097, WM-89-97, NUDOCS 8904050427 | |
| Download: ML20247L299 (3) | |
Text
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WQLF CREEK NUCLEAR OPERATING CORPORATION l
Bart D. Withers Pr. sed.nl and cni.e Ex.cutiv. omcer March 29, 1989 WM 89-0097 U. S. Nuclear Regulatory Commission ATTN:
Document Control Desk Mail Station P1-137 Washington, D. C. 20555
Reference:
- 1) KMLNRC 85-264 dated December 6, 1985 from G. L. Koester, KG&E, to H. R. Denton, NRC
- 2) Letter dated May 24, 1988 from P. W. 0'Connor, NRC, to B. D. Withers, WCNOC Subj ect :
Docket No. 50-482:
Revision to Technical Specification 3/4.6.1.6 - Containment Vessel Structural Integrity Gentlemen:
The purpose of this letter is to transmit changes to an application for amendment (Reference 1) to Facility Operating License No.
NPF-42 for Wolf I
Creek Generating Station.
Reference 1 transmitted an amendment request to revise Technical Specification 3/4.6.1.6, Containment Vessel Structural Integrity. On March 16, 1988, Wolf Creek Nuclear Operating Corporation and Union Electric Company representatives met with the Staff to discuss the amendment request.
Based on that meeting, the amendment request has been revised as shown on the marked-up Technical Specification pages provided as.
The changes to the original request are as follows:
1)
Proposed Action 3.6.1.6.c will include a 30 day preliminary Special Report as well as a 90 day Special Report.
2)
Surveillance 4.6.1.6.1.d, which addresses tendon lift-off stress, will be tied to AcH on 3.6.1.6.a, which addresses tendon lift-off force.
3)
Surveillance 4.o.l.6.1.e is revised to include the 5% grease void q
criteria, visual inspection of the containment to assure no widespread j
grease leakage, and considerations for determining the maximum grease pumping pressure.
q Reference 2 transmitted a request for additional information regarding the 15 day allowed outage time in proposed action 3.6.1.6.a. 1 to this letter provides an evaluation which concludes that the rate of change in prestressing levels is extremely slow, such that if occasional low lift-off readings are encountered there is not an immediate concern with regard to prestressing system capacity.
The re fore,
the 15 day period to restore the lift-off stress to within limits is reasonable.
l P.O. Box 411/ Burlington, KS 66839 / Phone: (316) 364-8831 f$,E288!!$s8886 w o-nuna> m-mova l-PDC
se WM 89-0097
^
Page 2 of 2 March 29, 1989 The conclusions of the Safety Evaluation and Significant Hazards Consideration determiitation transmitted by Reference 1 remain valid for the revised amendment request.
l l
If you have any questions concerning tnis matter please contact me or l
Mr. O. L. Maynard of my staff.
Very truly yours,
__=2 Bart D. Withers President and Chief Executive Officer l
BDW/jad l
Attachments (2) cc:
B. L. Bartlett (NRC), w/a E. J. Holler (NRC), w/a R. D. Martin (NRC), w/a D. V. Pickett (NRC), w/a L-___________________-.____
STATE OF KANSAS
)
) SS COUNTY OF COFFEY
)
Bart D. Withers, of lawful age, being first duly sworn upon oath says that he is President and Chief Executive Officer of Wolf Creek Nuclear Operating Corporation, that he has read the foregoing document and knows the content thereof; that he has executed that same for and on behalf of said i
Corporation with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.
By Bart D. Withers President and Chief Executive Officer SUBSCRIBED and sworn to before me this S f day of M/d4CA,1989.
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