05000482/LER-2008-002, Regarding Technical Specification Allowed Outage Time Exceeded Due to Room Cooler Leak

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Regarding Technical Specification Allowed Outage Time Exceeded Due to Room Cooler Leak
ML081080040
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 04/10/2008
From: Matthew Sunseri
Wolf Creek
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
WO 08-0010 LER 08-002-00
Download: ML081080040 (5)


LER-2008-002, Regarding Technical Specification Allowed Outage Time Exceeded Due to Room Cooler Leak
Event date:
Report date:
Reporting criterion: 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications

10 CFR 50.73(a)(2)(i)

10 CFR 50.73(a)(2)(vii), Common Cause Inoperability

10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded

10 CFR 50.73(a)(2)(viii)(A)

10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition

10 CFR 50.73(a)(2)(viii)(B)

10 CFR 50.73(a)(2)(iii)

10 CFR 50.73(a)(2)(ix)(A)

10 CFR 50.73(a)(2)(iv)(A), System Actuation

10 CFR 50.73(a)(2)(x)

10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor

10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat

10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown

10 CFR 50.73(a)(2)(v), Loss of Safety Function
4822008002R00 - NRC Website

text

WLF CREEK

'NUCLEAR OPERATING CORPORATION Matthew W. Sunseri Vice President Operations and Plant Manager April 10, 2008 WO 08-0010 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555

Subject:

Docket No. 50-482: Licensee Event Report 2008-002-00, Technical Specification Allowed Outage Time Exceeded due to Room Cooler Leak Gentlemen, As a result of repairs being performed on the "A" Centrifugal Charging Pump Room Cooler, Wolf Creek Nuclear Operating Corporation (WCNOC) requested and was granted a Notice Of Enforcement Discretion to exceed the Allowed Outage Time of four hours.

The enclosed Licensee Event Report (LER) 2008-002-00 is being submitted pursuant to 10 CFR 50.73(a)(2)(i)(B) to document this condition for any operation or condition which was prohibited by Technical Specifications.

This letter contains no commitments. If you have any questions concerning this matter, please contact me at (620) 364-4008, or Mr. Richard D. Flannigan, Manager Regulatory Affairs at (620) 364-4117.

Sincerely, Matthew W. Sunseri MWS/rlt Enclosure cc:

E. E. Collins (NRC), w/e V. G. Gaddy (NRC), w/e B. K. Singal (NRC), w/e Senior Resident Inspector (NRC), w/e P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HCNET

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)

, the NRC may (See reverse for required number of not conduct or sponsor, and a person is not required to respond to, the digits/characters for each block) information collection.

3. PAGE WOLF CREEK GENERATING STATION 05000 482 1 OF 4
4. TITLE Technical Specification Allowed Outage Time Exceeded due to Room Cooler Leak
5. EVENT DATE
6. LER NUMBER
7. REPORT DATE J
8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DY YEAR AI NUMBER NO.

MONTH D

05000 FACILITY NAME DOCKET NUMBER 02 14 2008 2008 002-00 04 10 2805000

9. OPERATING MODE
11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply) 1 20.2201(b)

E] 20.2203(a)(3)(i)

E] 50.73(a)(2)(i)(C) j] 50.73(a)(2)(vii) fl 20.2201(d)

E] 20.2203(a)(3)(ii)

[] 50.73(a)(2)(ii)(A)

[] 50.73(a)(2)(viii)(A)

[] 20.2203(a)(1)

E] 20.2203(a)(4)

[

50.73(a)(2)(ii)(B)

E] 50.73(a)(2)(viii)(B)

[J 20.2203(a)(2)(i)

E] 50.36(c)(1)(i)(A)

[j 50.73(a)(2)(iii)

[j 50.73(a)(2)(ix)(A)

10. POWER LEVEL LI 20.2203(a)(2)(ii)

[] 50.36(c)(1)(ii)(A)

[] 50.73(a)(2)(iv)(A)

J] 50.73(a)(2)(x) 1l 20.2203(a)(2)(iii)

[J 50.36(c)(2)

El 50.73(a)(2)(v)(A) j]

73.71(a)(4) 100 20.2203(a)(2)(iv)

El 50.46(a)(3)(ii)

El 50.73(a)(2)(v)(B) j]

73.71(a)(5)

I] 20.2203(a)(2)(v)

[] 50.73(a)(2)(i)(A)

El 50.73(a)(2)(v)(C)

[] OTHER

[]

20.2203(a)(2)(vi)

[]

50.73(a)(2)(i)(B) 7] 50.73(a)(2)(v)(D)

Specify in Abstract below or in (If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A)

To further mitigate the risk impact, WCNOC implemented a series of compensatory actions to minimize challenges to the dominant core damage frequency (CDF) contributor of Loss of Offsite Power. These measures included avoidance of testing and maintenance impacting availability of the "A" train safety bus, ensure no switchyard work was allowed, continual monitoring by the grid operator regarding grid conditions, and availability of the Sharpe Station to mitigate a Station Blackout (SBO).

OPERATING EXPERIENCE/PREVIOUS EVENTS:

None.