WO 10-0032, Cancellation of Licensee Event Report 2009-007-00, Removal of Equipment from Service Required by Technical Specifications and NRC Safety Evaluation: Difference between revisions

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=Text=
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{{#Wiki_filter:W0LF CREEK NUCLEAR OPERATING CORPORATION Rick L. Gardner May 3, 2010 Plant Manager WO 10-0032 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555  
{{#Wiki_filter:W0LF CREEK NUCLEAR OPERATING CORPORATION Rick L. Gardner May 3, 2010 Plant Manager WO 10-0032 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555


==Reference:==
==Reference:==
: 1) Letter WM 09-0065, dated December 9, 2009, from R. A.Muench, WCNOC, to USNRC 2) Letter WO 10-0004, dated January 11, 2010, from M. W. Sunseri, WCNOC, to USNRC 3) Letter dated March 4, 2010, from D. D. Chamberlain, USNRC, to M. W. Sunseri, WCNOC  
: 1)   Letter WM 09-0065, dated December 9, 2009, from R. A.
Muench, WCNOC, to USNRC
: 2)   Letter WO 10-0004, dated January 11, 2010, from M. W. Sunseri, WCNOC, to USNRC
: 3)   Letter dated March 4, 2010, from D. D. Chamberlain, USNRC, to M. W. Sunseri, WCNOC


==Subject:==
==Subject:==
Docket No. 50-482: Cancellation of Licensee Event Report 2009-007-00, "Removal of Equipment From Service Required by Technical Specifications and NRC Safety Evaluation" Gentlemen:
Docket No. 50-482: Cancellation of Licensee Event Report 2009-007-00, "Removal of Equipment From Service Required by Technical Specifications and NRC Safety Evaluation" Gentlemen:
The purpose of this letter is to notify the Nuclear Regulatory Commission (NRC) of the cancellation of Wolf Creek Generating Station (WCGS) Licensee Event Report (LER) 2009-007-00, "Removal of Equipment From Service Required by Technical Specifications and NRC Safety Evaluation," (Reference
The purpose of this letter is to notify the Nuclear Regulatory Commission (NRC) of the cancellation of Wolf Creek Generating Station (WCGS) Licensee Event Report (LER) 2009-007-00, "Removal of Equipment From Service Required by Technical Specifications and NRC Safety Evaluation," (Reference 2) consistent with the guidance in NUREG-1022, Rev. 2, "Event Report Guidelines 10 CFR 50.72 and 50.73."
: 2) consistent with the guidance in NUREG-1022, Rev. 2, "Event Report Guidelines 10 CFR 50.72 and 50.73." NRC Integrated Inspection Report 2009004 identified a green noncited violation of TS 3.8.1, Required Action B.4.2.2, for removing equipment from service that was required by TS 3.8.1 and the NRC safety evaluation for License Amendment No. 163. Reference 1 provided Wolf Creek Nuclear Operating Corporation's (WCNOC) denial of noncited violation 2009-004-06,"Performing Prohibited Elective Maintenance on Safety Bus NB02 Channel 4 during Emergency Diesel Generator Maintenance." P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HCNET U
NRC Integrated Inspection Report 2009004 identified a green noncited violation of TS 3.8.1, Required Action B.4.2.2, for removing equipment from service that was required by TS 3.8.1 and the NRC safety evaluation for License Amendment No. 163. Reference 1 provided Wolf Creek Nuclear Operating Corporation's (WCNOC) denial of noncited violation 2009-004-06, "Performing Prohibited Elective Maintenance on Safety Bus NB02 Channel 4 during Emergency Diesel Generator Maintenance."
WO 10-0032 Page 2 of 2 Reference 3 provided the NRC response to Reference
P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HCNET                   U (L.*
: 1. Reference 3 indicated that the staff, in consultation with NRC's Office of Nuclear Reactor Regulation and Office of Enforcement, had reviewed these reasons and the supporting information.
 
The staff concluded that WCNOC was correct in that the Technical Specification Required Action statement does not require that the limitations articulated in the NRC Safety Evaluation for License Amendment No. 163 are met.The staff determined that the performance deficiency associated with the original noncited violation is more appropriately characterized as a noncited violation of 10 CFR 50.65(a)(4) involving the failure to adequately assess and manage the risk associated with maintenance activities.
WO 10-0032 Page 2 of 2 Reference 3 provided the NRC response to Reference 1. Reference 3 indicated that the staff, in consultation with NRC's Office of Nuclear Reactor Regulation and Office of Enforcement, had reviewed these reasons and the supporting information. The staff concluded that WCNOC was correct in that the Technical Specification Required Action statement does not require that the limitations articulated in the NRC Safety Evaluation for License Amendment No. 163 are met.
The staff determined that the performance deficiency associated with the original noncited violation is more appropriately characterized as a noncited violation of 10 CFR 50.65(a)(4) involving the failure to adequately assess and manage the risk associated with maintenance activities.
Therefore, based on the determination that a condition prohibited by Technical Specifications did not occurr as described in Reference 2, WCNOC is cancelling WCGS LER 2009-007-00.
Therefore, based on the determination that a condition prohibited by Technical Specifications did not occurr as described in Reference 2, WCNOC is cancelling WCGS LER 2009-007-00.
This letter contains no commitments.
This letter contains no commitments. If you have any questions concerning this matter, please contact me at (620) 364-4156, or Mr. Richard D. Flannigan at (620) 364-4117.
If you have any questions concerning this matter, please contact me at (620) 364-4156, or Mr. Richard D. Flannigan at (620) 364-4117.Sincerely, Rick .Gardner RLG/rlt cc: E. E. Collins (NRC)G. B. Miller (NRC)B. K. Singal (NRC)Senior Resident Inspector (NRC)}}
Sincerely, Rick   .Gardner RLG/rlt cc:   E. E. Collins (NRC)
G. B. Miller (NRC)
B. K. Singal (NRC)
Senior Resident Inspector (NRC)}}

Latest revision as of 19:25, 13 November 2019

Cancellation of Licensee Event Report 2009-007-00, Removal of Equipment from Service Required by Technical Specifications and NRC Safety Evaluation
ML101310603
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 05/03/2010
From: Gardner R
Wolf Creek
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
LER 09-007-00, WO 10-0032
Download: ML101310603 (2)
v • d • e


Text

W0LF CREEK NUCLEAR OPERATING CORPORATION Rick L. Gardner May 3, 2010 Plant Manager WO 10-0032 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Reference:

1) Letter WM 09-0065, dated December 9, 2009, from R. A.

Muench, WCNOC, to USNRC

2) Letter WO 10-0004, dated January 11, 2010, from M. W. Sunseri, WCNOC, to USNRC
3) Letter dated March 4, 2010, from D. D. Chamberlain, USNRC, to M. W. Sunseri, WCNOC

Subject:

Docket No. 50-482: Cancellation of Licensee Event Report 2009-007-00, "Removal of Equipment From Service Required by Technical Specifications and NRC Safety Evaluation" Gentlemen:

The purpose of this letter is to notify the Nuclear Regulatory Commission (NRC) of the cancellation of Wolf Creek Generating Station (WCGS) Licensee Event Report (LER) 2009-007-00, "Removal of Equipment From Service Required by Technical Specifications and NRC Safety Evaluation," (Reference 2) consistent with the guidance in NUREG-1022, Rev. 2, "Event Report Guidelines 10 CFR 50.72 and 50.73."

NRC Integrated Inspection Report 2009004 identified a green noncited violation of TS 3.8.1, Required Action B.4.2.2, for removing equipment from service that was required by TS 3.8.1 and the NRC safety evaluation for License Amendment No. 163. Reference 1 provided Wolf Creek Nuclear Operating Corporation's (WCNOC) denial of noncited violation 2009-004-06, "Performing Prohibited Elective Maintenance on Safety Bus NB02 Channel 4 during Emergency Diesel Generator Maintenance."

P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HCNET U (L.*

WO 10-0032 Page 2 of 2 Reference 3 provided the NRC response to Reference 1. Reference 3 indicated that the staff, in consultation with NRC's Office of Nuclear Reactor Regulation and Office of Enforcement, had reviewed these reasons and the supporting information. The staff concluded that WCNOC was correct in that the Technical Specification Required Action statement does not require that the limitations articulated in the NRC Safety Evaluation for License Amendment No. 163 are met.

The staff determined that the performance deficiency associated with the original noncited violation is more appropriately characterized as a noncited violation of 10 CFR 50.65(a)(4) involving the failure to adequately assess and manage the risk associated with maintenance activities.

Therefore, based on the determination that a condition prohibited by Technical Specifications did not occurr as described in Reference 2, WCNOC is cancelling WCGS LER 2009-007-00.

This letter contains no commitments. If you have any questions concerning this matter, please contact me at (620) 364-4156, or Mr. Richard D. Flannigan at (620) 364-4117.

Sincerely, Rick .Gardner RLG/rlt cc: E. E. Collins (NRC)

G. B. Miller (NRC)

B. K. Singal (NRC)

Senior Resident Inspector (NRC)

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