IR 05000305/2006001: Difference between revisions

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=Text=
=Text=
{{#Wiki_filter:March 2, 2006 Mr. David Senior Vice President and
{{#Wiki_filter:rch 2, 2006


Chief Nuclear Officer
==SUBJECT:==
 
ANNUAL ASSESSMENT LETTER - KEWAUNEE POWER STATION (REPORT 05000305/2006001)
Innsbrook Technical Center
 
5000 Dominion Boulevard
 
Glen Allen, VA 23060-6711SUBJECT:ANNUAL ASSESSMENT LETTER - KEWAUNEE POWER STATION (REPORT 05000305/2006001)


==Dear Mr. Christian:==
==Dear Mr. Christian:==
On February 8, 2006, the NRC staff completed its performance review of Kewaunee Power Station. Our technical staff reviewed performance indicators (PIs) for the most recent quarter
On February 8, 2006, the NRC staff completed its performance review of Kewaunee Power Station. Our technical staff reviewed performance indicators (PIs) for the most recent quarter and inspection results for the period from January 1 through December 31, 2005. The purpose of this letter is to inform you of our assessment of your safety performance during this period and our plans for future inspections at your facility.
 
and inspection results for the period from January 1 through December 31, 2005. The purpose
 
of this letter is to inform you of our assessm ent of your safety performance during this period and our plans for future inspections at your facility.
 
This performance review and enclosed inspection plan do not include physical protection information. A separate letter designated and marked as "Exempt from Public Disclosure in
 
accordance with 10 CFR 2.390" will include the physical protection review and resultant
 
inspection plan.
 
Overall, Kewaunee Power Station operated in a manner that preserved public health and safety and met all cornerstone objectives with moderate degradation in safety performance. Plant
 
performance for the most recent quarter was within the Degraded Cornerstone Column of the
 
NRC's Action Matrix based on one Yellow finding within the Mitigating Systems cornerstone.
 
This Yellow finding involved the failure to provide adequate design control to ensure that Class I
 
equipment was protected against damage from tornado or seismic-induced flooding of the
 
turbine building.
 
On February 21, 2006, we were notified by your staff that your current reviews of corrective actions for the Yellow finding would be completed in the coming few weeks, which will support
 
an NRC supplemental inspection to review your ac tions taken. Therefore, we plan to conduct supplemental inspection 95002 beginning on May 1, 2006. This supplemental inspection will


also include a review of your actions taken as a result of a White finding associated with the
This performance review and enclosed inspection plan do not include physical protection information. A separate letter designated and marked as Exempt from Public Disclosure in accordance with 10 CFR 2.390 will include the physical protection review and resultant inspection plan.


design of the auxiliary feedwater system. You we re previously informed of this White finding in a letter dated September 16, 2005.
Overall, Kewaunee Power Station operated in a manner that preserved public health and safety and met all cornerstone objectives with moderate degradation in safety performance. Plant performance for the most recent quarter was within the Degraded Cornerstone Column of the NRCs Action Matrix based on one Yellow finding within the Mitigating Systems cornerstone.


D. Christian-2-While plant performance for the most recent quarter is within the Degraded Cornerstone column of the Action Matrix, there was an additional safety significant inspection finding affecting the
This Yellow finding involved the failure to provide adequate design control to ensure that Class I equipment was protected against damage from tornado or seismic-induced flooding of the turbine building.


first three quarters of the assessment cycle. This White finding within the Barrier Integrity
On February 21, 2006, we were notified by your staff that your current reviews of corrective actions for the Yellow finding would be completed in the coming few weeks, which will support an NRC supplemental inspection to review your actions taken. Therefore, we plan to conduct supplemental inspection 95002 beginning on May 1, 2006. This supplemental inspection will also include a review of your actions taken as a result of a White finding associated with the design of the auxiliary feedwater system. You were previously informed of this White finding in a letter dated September 16, 2005. While plant performance for the most recent quarter is within the Degraded Cornerstone column of the Action Matrix, there was an additional safety significant inspection finding affecting the first three quarters of the assessment cycle. This White finding within the Barrier Integrity cornerstone was associated with the inability to expeditiously close the containment hatch during reactor vessel head replacement activities during the refueling outage in the fall of 2004.


cornerstone was associated with the inability to expeditiously close the containment hatch
A supplemental inspection 95001 was completed in September 2005, and the finding was considered closed as of October 1, 2005.


during reactor vessel head replacement activities during the refueling outage in the fall of 2004.
In our mid-cycle assessment letter dated August 30, 2005, we advised you of a substantive cross-cutting issue in the area of Problem Identification and Resolution (PI&R) involving weaknesses in the corrective action program. The NRC staff continued to identify issues in 2005 that had a common performance theme of ineffective corrective actions to resolve known deficiencies. Since the mid-cycle assessment letter, you submitted a November 14, 2005, revision to your previous March 18, 2005, commitment letter. In your November revision, you committed to take additional actions to improve the overall effectiveness of your corrective actions program. However, the effectiveness of these corrective actions is still indeterminate.


A supplemental inspection 95001 was completed in September 2005, and the finding was
As a result of our inspections, we determined because the Yellow finding associated with the turbine building flooding contained PI&R cross-cutting issue elements and we continued to identify findings in the area of PI&R, the agency still considers corrective actions as an area of concern at Kewaunee Power Station. Because the substantive cross-cutting issue in the area of PI&R was previously identified in more than two consecutive assessment letters, we request that you discuss your actions to address the long-standing substantive PI&R cross-cutting issue at the 2005 end-of-cycle assessment meeting scheduled for March 22, 2006.


considered closed as of October 1, 2005.
The NRC plans to follow-up the substantive PI&R cross-cutting issue during the upcoming supplemental inspection 95002, and by performing the maximum allowable inspection samples in accordance with IP 71152, Identification and Resolution of Problems, Section 03.02, Selected Issue Follow-up Inspection.


In our mid-cycle assessment letter dated Augus t 30, 2005, we advised you of a substantive cross-cutting issue in the area of Problem Identification and Resolution (PI&R) involving
The enclosed inspection plan details the inspections, less those related to physical protection scheduled through September 30, 2007. In addition, we plan on conducting a Component Design Basis Inspection at your facility in early 2007. This inspection will also focus on the implementation of your corrective action program, along with routine baseline inspection activities. The inspection plan is provided to allow for the resolution of any scheduling conflicts and personnel availability issues well in advance of inspector arrival onsite. Routine resident inspections are not listed due to their ongoing and continuous nature. The inspections in the last 9 months of the inspection plan are tentative and may be revised at the mid-cycle assessment review. In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its enclosure will be made available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system, and is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).


weaknesses in the corrective action program. The NRC staff continued to identify issues in
If circumstances arise which cause us to change this inspection plan, we will contact you to discuss the change as soon as possible. Please contact Patrick Louden at 630-829-9627 with any questions you may have regarding this letter or the inspection plan.
 
2005 that had a common performance theme of ineffe ctive corrective actions to resolve known deficiencies. Since the mid-cycle assessment letter, you submitted a November 14, 2005, revision to your previous March 18, 2005, commitment letter. In your November revision, you
 
committed to take additional actions to improve the overall effectiveness of your corrective actions program. However, the effectiveness of these corrective actions is still indeterminate.
 
As a result of our inspections, we determined because the Yellow finding associated with the turbine building flooding contained PI&R cross-cutting issue elements and we continued to
 
identify findings in the area of PI&R, the agency still considers corrective actions as an area of
 
concern at Kewaunee Power Station. Because the substantive cross-cutting issue in the area
 
of PI&R was previously identified in more t han two consecutive assessment letters, we request that you discuss your actions to address the l ong-standing substantive PI&R cross-cutting issue at the 2005 end-of-cycle assessment meeting scheduled for March 22, 2006.
 
The NRC plans to follow-up the substantive PI&R cross-cutting issue during the upcoming supplemental inspection 95002, and by performing the maximum allowable inspection samples
 
in accordance with IP 71152, "Identification and Resolution of Problems," Section 03.02,
"Selected Issue Follow-up Inspection."
 
The enclosed inspection plan details the inspections, less those related to physical protection scheduled through September 30, 2007. In addition, we plan on conducting a Component
 
Design Basis Inspection at your facility in early 2007. This inspection will also focus on the
 
implementation of your corrective action pr ogram, along with routine baseline inspection activities. The inspection plan is provided to allow for the resolution of any scheduling conflicts
 
and personnel availability issues well in advance of inspector arrival onsite. Routine resident
 
inspections are not listed due to their ongoing and continuous nature. The inspections in the
 
last 9 months of the inspection plan are tentative and may be revised at the mid-cycle assessment review.
 
D. Christian-3-In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be made available electronically for public inspection in the NRC Public
 
Document Room or from the Publicly Ava ilable Records (PARS) component of NRC's document system, and is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
 
If circumstances arise which cause us to change this inspection plan, we will contact you to discuss the change as soon as possible. Please contact Patrick Louden at 630-829-9627 with
 
any questions you may have regarding this letter or the inspection plan.


Sincerely,
Sincerely,
/RA/James L. Caldwell Regional Administrator Docket No. 50-305 License No. DPR-43 Enclosure: Kewaunee Power Station Inspection/Activity Plan cc w/encl:M. Gaffney, Site Vice President C. Funderburk, Director, Nuclear Licensing
/RA/
 
James L. Caldwell Regional Administrator Docket No. 50-305 License No. DPR-43 Enclosure: Kewaunee Power Station Inspection/Activity Plan cc w/encl: M. Gaffney, Site Vice President C. Funderburk, Director, Nuclear Licensing and Operations Support T. Breene, Manager, Nuclear Licensing L. Cuoco, Esq., Senior Counsel D. Zellner, Chairman, Town of Carlton J. Kitsembel, Public Service Commission of Wisconsin Mayor of Kewaunee City Council President Chair, Manitowoc County Board County Executive Chair, Kewaunee County Board Director, Manitowoc County Emergency Management Agency Director, Kewaunee County Emergency Management Agency City Manager Village President INPO
and Operations Support
 
T. Breene, Manager, Nuclear Licensing
 
L. Cuoco, Esq., Senior Counsel
 
D. Zellner, Chairman, Town of Carlton
 
J. Kitsembel, Public Service Commission of Wisconsin
 
Mayor of Kewaunee
 
City Council President
 
Chair, Manitowoc County Board
 
County Executive
 
Chair, Kewaunee County Board
 
Director, Manitowoc County Emergency
 
Management Agency
 
Director, Kewaunee County Emergency
 
Management Agency
 
City Manager
 
Village President
 
INPO
}}
}}

Latest revision as of 21:38, 23 November 2019

(EOC) Annual Assessment Letter (Report 05000305/2006001)
ML060610413
Person / Time
Site: Kewaunee Dominion icon.png
Issue date: 03/02/2006
From: Caldwell J
NRC/RGN-III
To: Christian D
Dominion Energy Kewaunee
References
IR-06-001
Download: ML060610413 (7)
v • d • e


Text

rch 2, 2006

SUBJECT:

ANNUAL ASSESSMENT LETTER - KEWAUNEE POWER STATION (REPORT 05000305/2006001)

Dear Mr. Christian:

On February 8, 2006, the NRC staff completed its performance review of Kewaunee Power Station. Our technical staff reviewed performance indicators (PIs) for the most recent quarter and inspection results for the period from January 1 through December 31, 2005. The purpose of this letter is to inform you of our assessment of your safety performance during this period and our plans for future inspections at your facility.

This performance review and enclosed inspection plan do not include physical protection information. A separate letter designated and marked as Exempt from Public Disclosure in accordance with 10 CFR 2.390 will include the physical protection review and resultant inspection plan.

Overall, Kewaunee Power Station operated in a manner that preserved public health and safety and met all cornerstone objectives with moderate degradation in safety performance. Plant performance for the most recent quarter was within the Degraded Cornerstone Column of the NRCs Action Matrix based on one Yellow finding within the Mitigating Systems cornerstone.

This Yellow finding involved the failure to provide adequate design control to ensure that Class I equipment was protected against damage from tornado or seismic-induced flooding of the turbine building.

On February 21, 2006, we were notified by your staff that your current reviews of corrective actions for the Yellow finding would be completed in the coming few weeks, which will support an NRC supplemental inspection to review your actions taken. Therefore, we plan to conduct supplemental inspection 95002 beginning on May 1, 2006. This supplemental inspection will also include a review of your actions taken as a result of a White finding associated with the design of the auxiliary feedwater system. You were previously informed of this White finding in a letter dated September 16, 2005. While plant performance for the most recent quarter is within the Degraded Cornerstone column of the Action Matrix, there was an additional safety significant inspection finding affecting the first three quarters of the assessment cycle. This White finding within the Barrier Integrity cornerstone was associated with the inability to expeditiously close the containment hatch during reactor vessel head replacement activities during the refueling outage in the fall of 2004.

A supplemental inspection 95001 was completed in September 2005, and the finding was considered closed as of October 1, 2005.

In our mid-cycle assessment letter dated August 30, 2005, we advised you of a substantive cross-cutting issue in the area of Problem Identification and Resolution (PI&R) involving weaknesses in the corrective action program. The NRC staff continued to identify issues in 2005 that had a common performance theme of ineffective corrective actions to resolve known deficiencies. Since the mid-cycle assessment letter, you submitted a November 14, 2005, revision to your previous March 18, 2005, commitment letter. In your November revision, you committed to take additional actions to improve the overall effectiveness of your corrective actions program. However, the effectiveness of these corrective actions is still indeterminate.

As a result of our inspections, we determined because the Yellow finding associated with the turbine building flooding contained PI&R cross-cutting issue elements and we continued to identify findings in the area of PI&R, the agency still considers corrective actions as an area of concern at Kewaunee Power Station. Because the substantive cross-cutting issue in the area of PI&R was previously identified in more than two consecutive assessment letters, we request that you discuss your actions to address the long-standing substantive PI&R cross-cutting issue at the 2005 end-of-cycle assessment meeting scheduled for March 22, 2006.

The NRC plans to follow-up the substantive PI&R cross-cutting issue during the upcoming supplemental inspection 95002, and by performing the maximum allowable inspection samples in accordance with IP 71152, Identification and Resolution of Problems, Section 03.02, Selected Issue Follow-up Inspection.

The enclosed inspection plan details the inspections, less those related to physical protection scheduled through September 30, 2007. In addition, we plan on conducting a Component Design Basis Inspection at your facility in early 2007. This inspection will also focus on the implementation of your corrective action program, along with routine baseline inspection activities. The inspection plan is provided to allow for the resolution of any scheduling conflicts and personnel availability issues well in advance of inspector arrival onsite. Routine resident inspections are not listed due to their ongoing and continuous nature. The inspections in the last 9 months of the inspection plan are tentative and may be revised at the mid-cycle assessment review. In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its enclosure will be made available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system, and is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

If circumstances arise which cause us to change this inspection plan, we will contact you to discuss the change as soon as possible. Please contact Patrick Louden at 630-829-9627 with any questions you may have regarding this letter or the inspection plan.

Sincerely,

/RA/

James L. Caldwell Regional Administrator Docket No. 50-305 License No. DPR-43 Enclosure: Kewaunee Power Station Inspection/Activity Plan cc w/encl: M. Gaffney, Site Vice President C. Funderburk, Director, Nuclear Licensing and Operations Support T. Breene, Manager, Nuclear Licensing L. Cuoco, Esq., Senior Counsel D. Zellner, Chairman, Town of Carlton J. Kitsembel, Public Service Commission of Wisconsin Mayor of Kewaunee City Council President Chair, Manitowoc County Board County Executive Chair, Kewaunee County Board Director, Manitowoc County Emergency Management Agency Director, Kewaunee County Emergency Management Agency City Manager Village President INPO

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