LER-2005-001, Regarding Corrective Action to Fire Wrap Raceway for Valve EMHV8803A Not Included in Design Change Package |
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| Report date: |
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| Reporting criterion: |
10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
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)(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
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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| 4822005001R00 - NRC Website |
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text
'NUCLEAR OPERATING CORPORATION Stephen E. Hedges Vice President Operations and Plant Manager March 8, 2005 WO 05-0013 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Subject:
Docket No. 50-482:, Licensee Event Report 2005-001 -00 Gentlemen:
The enclosed Licensee Event Report (LER) 2005-001-00 is being submitted pursuant to 10 CFR 50.73(a)(2)(ii)(B) regarding an unanalyzed condition from a cable separation issue that could potentially affect post-fire safe shutdo'wn-equipment availability at Wolf Creek Generating' Station.
Commitments made by Wolf Creek Nuclear. Operating Corporation 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.'
Very truly yours,,
Step en E. Hedges SEH/rlg Attachment*
Enclosure cc:
J. N. Donohew (NRC), w/a D. N. Graves (NRC), w/a B. S. Mallett (NRC), w/a Senior Resident Inspector (NRC), wla' P.O. Box 4111 Burlington,KS 66839 IPhone: (620) 364.8831
- - An EquaI Opportunij Employer WF/FHCNET
Attachment to WO 05-0013
- - A Page I of 1
'_-LIST OF COMMITMENTS
- -The following table identifies those actions committed to by Wolf Creek Nuclear Operating Corporation (WCNOC) in this document. -Any other statements in this submittal are provided for information purposes and are not considered to be commitments. Please direct questions -
regarding these commitments to Mr. Kevin Moles, Manager Regulatory Affairs at Wolf Creek Generating Station, (620) 364-4126.
COMMITMENT
Due Date/Event A design modification change package will be initiated and implemented to fire wrap the subject cable.- The interim action of maintaining an hourly roving fire watch in the affected fire - --
area remains in place until resolution of this condition is irmlemented.
' - I January 20, 2006. -- -
I- -1
___ I
11 1, ;, ".,. :I..
t : -, -
- - i -
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 digitstcharacters for each block)
Information collection.
I. FACILITY NAME
- 2. DOCKET NUMBER
- 3. PAGE WOLF CREEK GENERATING STATION 05000 482 I
OF 4
- 4. TITLE Corrective Action to Fire Wrap Raceway for Valve EMHV8803A not Included in Design Change Package.
- 5. EVENT DATE
- 6. LER NUMBER
- - 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTLAL REV MONTH DAY YEAR FACILITY NAME DCKET NUMBER NUMBER NO.
05000 FACILITY NAME DOCKET NUMBER 01 07 2005 2005
- - 001-00 08 2005 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check al that apply) 1 a 20.2201(b) 5 20.2203(a)(3)(i)
D 50.73(a)(2)(i)(C) 5 50.73(a)(2)(vii) 20.2201(d) 0 20.2203(a)(3)(ii) 5 50.73(a)(2)(ii)(A) a 50.73(a)(2)(viii)(A) 20.2203(a)(1) 0 20.2203(a)(4)
[I 50.73(a)(2)(ii)(B) 5 50.73(a)(2)(viii)(B)
I] 20.2203(a)(2)(i) a 50.36(c)(1)(i)(A)
D 50.73(a)(2)(iii) 5 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL E5 20.2203(a)(2)(ii)
D 50.36(c)(1)(ii)(A)
D 50.73(a)(2)(iv)(A) 5 50.73(a)(2)(x) 5 20.2203(a)(2)(iii) 5 50.36(c)(2) a 50.73(a)(2)(v)(A) a 73.71(a)(4) 100 o 20.2203(a)(2)(iv) 5 50.46(a)(3)(ii) 5 50.73(a)(2)(v)(B) 73-71(a)(5) 20.2203(a)(2)(v)
E5 50.73(a)(2)(i)(A) a 50.73(a)(2)(v)(C) 5 OTHER 20.2203(a)(2)(vi) 5 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)
Operating Experience/Previous Events:
An occurrence of a similar event was reported via licensee event report LER 1999-009-00. In LER 1999-009-00, it was determined that there was inadequate separation of cables for valves and level transmitters for the volume control tank. In the event of a fire, a potential existed for gas intrusion into the suction of the centrifugal charging pump. While corrective actions have been taken to address these conditions, an additional corrective action for LER 1999-009-00 was to validate the post fire safe shutdown analysis and to provide necessary correction to the Updated Safety Analysis Report (USAR).
The validation consists of two phases: phase one reverified the design criteria and phase two completes the post-fire safe shutdown analysis review. The conditions identified in LER 2005-001-00 were discovered during phase two and reported in LER 2002-004-02.
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| 05000482/LER-2005-001, Regarding Corrective Action to Fire Wrap Raceway for Valve EMHV8803A Not Included in Design Change Package | Regarding Corrective Action to Fire Wrap Raceway for Valve EMHV8803A Not Included in Design Change Package | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000482/LER-2005-002, Re Reactor Coolant System Pressure Boundary Leakage Due to Small Cracks in Steam Generator Lower Head Bowl Drain Lines | Re Reactor Coolant System Pressure Boundary Leakage Due to Small Cracks in Steam Generator Lower Head Bowl Drain Lines | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(x)(A) | | 05000482/LER-2005-003, Re Failure to Maintain Closure of Containment Penetrations During Fuel Movement | Re Failure to Maintain Closure of Containment Penetrations During Fuel Movement | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000482/LER-2005-004, Re Failure of Auxiliary Building Ventilation Dampers to Close on Safety Injection Signal | Re Failure of Auxiliary Building Ventilation Dampers to Close on Safety Injection Signal | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000482/LER-2005-005, Re Validation of Post Fire Safe Shutdown (PFSSD) Capabilities of Fire Area A-8 | Re Validation of Post Fire Safe Shutdown (PFSSD) Capabilities of Fire Area A-8 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000482/LER-2005-006, Regarding Uanalyzed Condition Related to Loss of RCP Seal Cooling During a Postulated Appendix R Fire Event | Regarding Uanalyzed Condition Related to Loss of RCP Seal Cooling During a Postulated Appendix R Fire Event | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000482/LER-2005-007, Unanalyzed Condition Related to Loss of EDG Field Flashing During an Appendix R Fire Event | Unanalyzed Condition Related to Loss of EDG Field Flashing During an Appendix R Fire Event | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 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)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) |
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