ML20151U471
| ML20151U471 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 02/05/1986 |
| From: | Koester G KANSAS GAS & ELECTRIC CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| KMLNRC-86-024, KMLNRC-86-24, NUDOCS 8602110025 | |
| Download: ML20151U471 (4) | |
Text
o KANSAS GAS AND ELECTRIC COMPANY THE ELECTAC COMPANY CLENN L FOESTER vaca poss ct%t - envo.gae February.5, 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 KMLNRC 86-024 Re:
Docket No. STN 50-482 Ref:
1)KMLNRC 86-007 from G.L. Koester, KG&E, to H.R. Denton, NRC, dated 1/20/86 Subj :
Supplemental Information Regarding Revision to Technical Specification 4.6.1.2
Dear Mr. Denton:
The purpose of this letter is to provide information inadvertently omitted from Attachment I to the Reference.
This information consists of five additional valves and associated information that did not appear in the table in Attachment I.
- However, the information was accurately provided in Attachment II to the Reference.
A revision to Attachwnt I is provided as an enclosure to this letter.
Please replace the affected pages of the Reference with the enclosure.
If you have any questions concerning this matter, please contact me or Mr.
O. L. Maynard of my staff.
Very truly yours, Nf Glenn L. Koester Vice President - Nuclear GLK:see Enclosure cc: P0'Connor (2)
JCummins EJohnson
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8602110025 060200
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201 N. Market -Wictuta, Kansas - Mail Address: RO. Box 208 I Nchita, Kansas 67201 - Telephone: Area Code (316) 2616451
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ENCLOSURE ATTACHMENT 1 Rev. I
Mr. H. R. Denton KMLNRC 86-024 February 5, 1985 Attachment I Rev. I to KMLNRC 86-007 Page 1 of 2 SAFETY EVALUATION This application requests a revision to the Wolf Creek Generating Station, Unit No.
1, Technical Specifications Section 4.6.1.2.d to allow a one-time only deferment of the specified 24 month maximum surveillance interval on the below listed containment penetrations for the first operating cycle only (Cycle 1);
provided these surveillances are performed prior to startup following the first refueling outage (Refuel 1).
These surveillances cannot be safely perfor'med at POWER OPERATION.
The proposed changes to the Technical Specifications are provided as Attachment IV.
Refuel 1 is the next scheduled shutdown and is currently scheduled to begin in October, 1986.
In the event of any unanticipated delays in the refueling schedule a unit shutdown to perform these surveillances will be initiated by October 31, 1986. Therefore this request entails an approximate seven month extension in the most limiting case.
If an unscheduled shutdown of sufficient duration and resulting in appropriate plant conditions occurs prior to Refuel 1, Kansas Gas and Electric Company intends to perform any surveillances that can reasonably be completed.
Since refueling outages normally occur approximately every twelve to eighteen months, extensions beyond the twenty four month maximum interval allowed by the Technical Specifications are not usually necessary.
However, due to the extended plant startup program and plant performance during Cycle 1, Kansas Gas and Electric Company is requesting the aforementioned Technical Specificatiot Revisions.
Without the requested revisions Wolf Creek Generating Statio.
would be forced into an outage for the purpose of surveillance testing.
Penetration Valve Surveillance Due Date P-41............. BB-V118 12/12/86 BB-HV8351A 07/12/86 P-22...
. BB-V148 07/06/86 BB-HV8351B 07/07/86 P-39............. BB-V178 07/09/86 BB-HV8351C 07/11/86 P-40............. BB-V208 07/09/86 BB-HV8351D 07/09/86 P-24.....
....... BG-V135 03/01/86 BG-Hv8100 03/01/86 BC-HV8112 08/25/86 P-74............. EG-V204 07/19/86 g
EG-HV58 12/04/86 EG-HV127 12/04/86 P-80...
....... BG-8381 04/13/86 BG-HV8105 07/18/86 P-23............. BG-HV8160 04/19/86 BC-HV8152 04/22/86 P-71............. EF-HV31 07/12/86 EF-HV33 07/12/86 l
1* Note these valves included only for completeness
6, Mr. H. R. Denton KMLNRC 86-024 Attachment.I Rev. I to KMLNRC 86-007 Page 2 of 2 P-73............. EF-HV45 06/09/86 EF-HV47 06/09/86 EF-HV49 06/09/86 l
P-28............. EF-HV32 09/25/86 EF-KV34 09/25/86 l
'P-29.............. EF-HV46 09/25/86 EF-HV48 09/25/86 EF-HV50 09/25/86 For each of the penetrations considered in the request for extension of the surveillance interval, it can be shown that one or both of the following design parameters apply:
1.
A closed ASME piping system (inside and/or outside containment) precludes the release of containment atmosphere to the environs.
2.
Should an isolation valve leak slightly when
- closed, the pressurized fluid seal within the pipe precludes release. of containment atmosphere to the~ environs.
Specific details for each containment penetration are included as Attachment II and III..
In each case, possible degradation of a containment leakage barrier does not' result in a release of radioactive materials from the containment atmosphere.
Therefore, the proposed amendment does not increase the probability or consequences of an accident previously evaluated.
The proposed change does not involve hardware changes nor a change in the manner in which the isolation systems at each-penetration functions.
Therefore, the possibility of creating a new or different kind of accident from any accident previously evaluated does not exist.
The proposed change does not alter the leakage rate limitations established in the Technical Specifications.
Therefore, the margin for possible deterioration of the containment integrity during the service intervals between tests has not been reduced.
Additionally, the integrity o f.
the closed systems has been verified by the Containment Integrated Leak Rate Test (ILRT).
The impact of extending the testing interval of penetrations bounded by these closed systems is reduced by satisfactory ILRT results.
The requested revisions would not have a significant impact on safe operation of the plant when compared to the transient associated with a shutdown for the purpose of performing these surveillances.
Based on the above and the considerations presented in Attachment III, the aforementioned proposed revisions to the Wolf Creek Generating Station, Unit No.
1, Technical Specifications do not adversely affect or endanger the health or safety of the general public or involve a significant safety hazard.
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