05000482/LER-2007-001, Emergency Diesel Generator Out of Service Longer than Technical Specification Allowed Outage Time
| ML072550496 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 09/06/2007 |
| From: | Hedges S Wolf Creek |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| WO 07-0017 LER 07-001-00 | |
| Download: ML072550496 (6) | |
| 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 |
| 4822007001R00 - NRC Website | |
text
W0 SPLF CREEK
'NUCLEAR OPERATING CORPORATION Stephen E. Hedges Vice President Operations and Plant Manager September 6, 2007 WO 07-0017 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Subject:
Docket No. 50-482: Licensee Event Report 2007-001-00, Emergency Diesel Generator Out of Service Longer than Technical Specification Allowed Outage Time Gentlemen:
As a result of repairs being performed on the Emergency Diesel Generator 'A', Wolf Creek Nuclear Operating Corporation (WCNOC) requested and was granted a Notice of Enforcement Discretion to exceed the Allowed Outage Time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
The enclosed Licensee Event Report (LER) 2007-001-00 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.
Commitments made by WCNOC in the enclosed LER are identified in the Attachment to this letter.
If you have any questions concerning this matter, please contact me at (620) 364-4190, or Mr.
Kevin Moles at (620) 364-4126.
)hen E. Hedges SEH/rlt Attachment Enclosure cc:
J. N. Donohew (NRC), w/a, w/e V. G. Gaddy (NRC), w/a, w/e B. S. Mallett (NRC), w/a, w/e Senior Resident Inspector (NRC), w/a, w/e P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HCNET
Attachment to WO 07-0017 Page 1 of 1 LIST OF COMMITMENTS The following table identifies those actions committed to by Wolf Creek Nuclear Operating Corporation in this document. Any other statements in this letter are provided for information purposes and are not considered regulatory commitments. Please direct questions regarding these commitments to Mr. Kevin Moles, Manager Regulatory Affairs at Wolf Creek Generating Station, (620) 364-4126.
REGULATORY COMMITMENT DUE DATE Core work instructions will be generated for the intercooler 2/15/2008 and jacket water pumps to incorporate the deficiencies identified and the lessons learned in this event.
Maintenance training will be developed and presented that 12/26/2008 addresses the less than adequate workmanship practices.
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 Emergency Diesel Generator Out of Service Longer than Technical Specification Allowed Outage Time
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL' REV MFAR FACILITY NAME DOCKETA NUMBER NUMBER NO.
05000 IFACILITY NAME DOCKET NUMBER 07 08 2007 2007 001 00 09 06 2007 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply)
[]
20.2201(b)
[
20.2203(a)(3)(i)
[j 50.73(a)(2)(i)(C)
[
50.73(a)(2)(vii)
El 20.2201(d)
El 20.2203(a)(3)(ii)
J] 50.73(a)(2)(ii)(A) j]
50.73(a)(2)(viii)(A)
El 20.2203(a)(1)
[
20.2203(a)(4)
[]
50.73(a)(2)(ii)(B)
E] 50.73(a)(2)(viii)(B)
[
20.2203(a)(2)(i)
E] 50.36(c)(1)(i)(A)
[
50.73(a)(2)(iii)
El 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL I]
20.2203(a)(2)(ii)
[]
50.36(c)(1)(ii)(A) fj 50.73(a)(2)(iv)(A)
El 50.73(a)(2)(x) 10 20.2203(a)(2)(iii) 5 50.36(c)(2)
El 50.73(a)(2)(v)(A) 5 73.71 (a)(4) 100 20.2203(a)(2)(iv)
E] 50.46(a)(3)(ii) 5 50.73(a)(2)(v)(B) 5 73.71 (a)(5) 5 20.2203(a)(2)(v)
El 50.73(a)(2)(i)(A) 5 50.73(a)(2)(v)(C) 5 OTHER 5
20.2203(a)(2)(vi)
[
50.73(a)(2)(i)(B)
[] 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)
SAFETY SIGNIFICANCE
The WCNOC final quantitative risk analysis indicated that the incremental conditional core damage probability (ICCDP) for the 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> extension was 1. 15E-06, and the incremental conditional large early release probability (ICLERP) for the 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> extension is 2.25E-09. The value for ICLERP is less than the guidance threshold in Inspection Manual Part 9900 Technical Guidance.
Although the value for ICCDP exceeded the guidance threshold of less than or equal to 5.OE-07, the calculated ICCDP did not consider the implied risk of shutting down the plant with only one available diesel generator, the availability of the Sharpe Station to mitigate a station blackout event, and a favorable weather forecast for the duration of the requested time period.
To mitigate the risk impact, WCNOC committed to implement a series of compensatory actions for the duration of the enforcement discretion period. Although the risk analysis indicated that the ICCDP and ICLERP would increase slightly as a result of the enforcement discretion, the compensatory measures committed to by the licensee would substantially reduce this risk increase. The compensatory measures were sufficient to result in no net increase in radiological risk.
OPERATING EXPERIENCE/PREVIOUS EVENTS:
None.