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{{#Wiki_filter:September 18, | {{#Wiki_filter:September 18, 2006 | ||
Chief Nuclear | Virginia Electric and Power Company | ||
ATTN.: Mr. David A. Christian | |||
Sr. Vice President and | |||
Chief Nuclear Officer | |||
Innsbrook Technical Center - 2SW | |||
5000 Dominion Boulevard | 5000 Dominion Boulevard | ||
Glen Allen, VA 23060- | Glen Allen, VA 23060-6711 | ||
05000338/2007006, 05000339/ | SUBJECT: NOTIFICATION OF NORTH ANNA NUCLEAR POWER PLANT - COMPONENT | ||
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)Region II staff will conduct a component design bases inspection at your North Anna | DESIGN BASES INSPECTION - NRC INSPECTION REPORT NOS. | ||
February 5 - 9, 2007. | 05000338/2007006, 05000339/2007006 | ||
Dear Mr Christian: | |||
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC) | |||
Region II staff will conduct a component design bases inspection at your North Anna Nuclear | |||
Power Plant during the weeks of January 8 - 12, 2007; January 22 - 26, 2007; and | |||
February 5 - 9, 2007. The inspection team will be led by Mr. Bob Hagar, a Senior Resident | |||
Inspector in Region II. This inspection will be conducted in accordance with the baseline | |||
inspection procedure, Procedure 71111.21, Component Design Bases Inspection, issued June | |||
22, 2006. | |||
The inspection will evaluate the capability of risk significant / low margin components to function | |||
as designed and support proper system operation. The inspection will also include a review of | |||
selected operator actions, operating experience, and modifications. | |||
During a telephone conversation on September 13, 2006, Mr. Hagar confirmed with Mr. J. | |||
Leberstien of your staff, arrangements for an information-gathering site visit and the three-week | |||
onsite inspection. The schedule is as follows: | |||
* Information-gathering visit: December 12-14, 2006 | |||
* Onsite inspection: January 8 - 12, January 22 - 26, and February 5 - 9, 2007 | |||
The purpose of the information-gathering visit is to meet with members of your staff, to identify | |||
risk-significant components and operator actions, and to identify information and documentation | |||
needed to support the inspection. Mr. Walt Rogers, a Region II Senior Reactor Analyst, may | |||
accompany Mr. Hagar during the information-gathering visit to review probabilistic risk | |||
assessment data and identify risk significant components which will be examined during the | |||
inspection. | |||
The enclosure lists documents that will be needed prior to the information-gathering visit. | |||
Please contact Mr. Hagar prior to preparing copies of the materials listed in the enclosure. | |||
VEPCO 2 | |||
The inspectors will try to minimize your administrative burden by specifically identifying only | |||
those documents required for the inspection preparation. | |||
During the information-gathering visit, the team leader will also discuss the following inspection | |||
support administrative details: office space, supplemental documents requested to be made | |||
available to the team in the Region II office prior to the inspection preparation week of January | available to the team in the Region II office prior to the inspection preparation week of January | ||
2, 2007; arrangements for site access; and the availability of knowledgeable plant | 2, 2007; arrangements for site access; and the availability of knowledgeable plant engineering | ||
(404) 562-4605.Sincerely,/RA/Charles R. Ogle, | and licensing personnel to serve as points of contact during the inspection. | ||
Division of Reactor | In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its | ||
VEPCO | enclosure will be available electronically for public inspection in the NRC Public Document | ||
Room or from the Publicly Available Records (PARS) component of NRC's document system | |||
(ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading- | |||
rm/adams.html (the Public Electronic Reading Room). | |||
Thank you for your cooperation in this matter. If you have any questions regarding the | |||
information requested or the inspection, please contact Mr. Hagar at (843) 339-2822 or me at | |||
(404) 562-4605. | |||
Sincerely, | |||
/RA/ | |||
Charles R. Ogle, Chief | |||
Engineering Branch 1 | |||
Division of Reactor Safety | |||
Docket Nos.: 50-338, 50-339 | |||
License Nos.: NPF-4, NPF-7 | |||
Enclosure | |||
cc w/enc/: (See page 3) | |||
VEPCO 3 | |||
cc w/encl: | |||
Chris L. Funderburk, Director | |||
Nuclear Licensing and | Nuclear Licensing and | ||
Operations Support | |||
Virginia Electric and Power Company | Virginia Electric and Power Company | ||
Electronic Mail | Electronic Mail Distribution | ||
Jack M. Davis | |||
Site Vice President | |||
North Anna Power Station | North Anna Power Station | ||
Electronic Mail | Electronic Mail Distribution | ||
Electronic Mail | Executive Vice President | ||
Old Dominion Electric Cooperative | |||
Electronic Mail Distribution | |||
County Administrator | |||
Louisa County | |||
P. O. Box 160 | P. O. Box 160 | ||
Louisa, VA | Louisa, VA 23093 | ||
Lillian M. Cuoco, Esq. | |||
Senior Counsel | |||
Dominion Resources Services, Inc. | Dominion Resources Services, Inc. | ||
Electronic Mail | Electronic Mail Distribution | ||
Attorney General | |||
Supreme Court Building | |||
900 East Main Street | 900 East Main Street | ||
Richmond, VA | Richmond, VA 23219 | ||
_________________________ | |||
OFFICE RII:DRS RII:DRSP | |||
SIGNATURE /RA/ by email | |||
NAME E. Guthrie R. Hagar | |||
DATE 9/18/2006 9/18/2006 6/ /2006 6/ /2006 6/ /2006 6/ /2006 | |||
E-MAIL COPY? YES YES NO YES YES NO YES NO YES NO YES NO | |||
INFORMATION REQUEST FOR NORTH ANNA NUCLEAR POWER PLANT | |||
COMPONENT DESIGN BASES INSPECTION | |||
Please provide the information electronically in .pdf files, Excel, or other searchable format on | |||
CDROM. The CDROM should be indexed and hyperlinked to facilitate ease of use. Lists | |||
should contain enough information to be easily understood to someone who has a knowledge | |||
of pressurized water reactor technology. | |||
1. From your most-recent probabilistic safety analysis (PSA) excluding external events and | |||
fires: | |||
a. Two risk rankings of components from your site-specific probabilistic safety analysis | |||
(PSA): one sorted by Risk Achievement Worth (RAW), and the other sorted by | |||
Birnbaum Importance. | |||
b. A list of the top 500 cutsets. | |||
c. A risk ranking of all operator actions, sorted by RAW. | |||
2. From your most-recent probabilistic safety analysis (PSA) including external events and | |||
fires: | |||
a. Two risk rankings of components from your site-specific probabilistic safety analysis | |||
(PSA): one sorted by Risk Achievement Worth (RAW), and the other sorted by | |||
Birnbaum Importance. | |||
b. A list of the top 500 cutsets. | |||
c. A risk ranking of all operator actions, sorted by RAW. | |||
3. Human reliability worksheets for the operator actions included in your PSA model. | |||
4. Any pre-existing evaluation or list of components and calculations with low design margins | |||
(i.e., pumps closest to the design limit for flow or pressure, diesel generator close to design | |||
required output, heat exchangers close to rated design heat removal, MOV risk-margin | |||
rankings, etc.). | |||
5. A list of operating experience evaluations completed within the last two years, sorted by | |||
associated component and/or system. | |||
6. A list of design modifications implemented within the last two years, sorted by affected | |||
system. | |||
7. A list of corrective-action evaluations that involved plant equipment and were completed | |||
within the last two years, sorted by involved component or system. | |||
8. A list of common-cause failure of components that have occurred at North Anna and have | |||
been identified within the last five years. | |||
Enclosure | |||
VEPCO 2 | |||
9. A list of operability evaluations completed within the last two years, sorted by associated | |||
component or system. | |||
10. Contact information for a person to discuss PRA information prior to bag man trip: name, | |||
title, phone number, and e-mail address | |||
11. List of equipment currently on the sites Station Equipment Reliability Issues List, including | |||
a description of the reason(s) why each component is on that list and summaries (if | |||
available) of your plans to address those reasons. | |||
12. List of equipment currently in GL 91-18 status. | |||
13. List of equipment currently in MR (a)(1) status. | |||
Enclosure | |||
available) of your plans to address those reasons.12.List of equipment currently in GL 91-18 status. | |||
13.List of equipment currently in MR (a)(1) status. | |||
}} | }} |
Latest revision as of 15:02, 23 November 2019
ML062620025 | |
Person / Time | |
---|---|
Site: | North Anna ![]() |
Issue date: | 09/18/2006 |
From: | Ogle C NRC/RGN-II/DRS/EB1 |
To: | Christian D Virginia Electric & Power Co (VEPCO) |
References | |
IR-07-006 | |
Download: ML062620025 (6) | |
See also: IR 05000338/2007006
Text
September 18, 2006
Virginia Electric and Power Company
ATTN.: Mr. David A. Christian
Sr. Vice President and
Chief Nuclear Officer
Innsbrook Technical Center - 2SW
5000 Dominion Boulevard
Glen Allen, VA 23060-6711
SUBJECT: NOTIFICATION OF NORTH ANNA NUCLEAR POWER PLANT - COMPONENT
DESIGN BASES INSPECTION - NRC INSPECTION REPORT NOS.
05000338/2007006, 05000339/2007006
Dear Mr Christian:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
Region II staff will conduct a component design bases inspection at your North Anna Nuclear
Power Plant during the weeks of January 8 - 12, 2007; January 22 - 26, 2007; and
February 5 - 9, 2007. The inspection team will be led by Mr. Bob Hagar, a Senior Resident
Inspector in Region II. This inspection will be conducted in accordance with the baseline
inspection procedure, Procedure 71111.21, Component Design Bases Inspection, issued June
22, 2006.
The inspection will evaluate the capability of risk significant / low margin components to function
as designed and support proper system operation. The inspection will also include a review of
selected operator actions, operating experience, and modifications.
During a telephone conversation on September 13, 2006, Mr. Hagar confirmed with Mr. J.
Leberstien of your staff, arrangements for an information-gathering site visit and the three-week
onsite inspection. The schedule is as follows:
- Information-gathering visit: December 12-14, 2006
- Onsite inspection: January 8 - 12, January 22 - 26, and February 5 - 9, 2007
The purpose of the information-gathering visit is to meet with members of your staff, to identify
risk-significant components and operator actions, and to identify information and documentation
needed to support the inspection. Mr. Walt Rogers, a Region II Senior Reactor Analyst, may
accompany Mr. Hagar during the information-gathering visit to review probabilistic risk
assessment data and identify risk significant components which will be examined during the
inspection.
The enclosure lists documents that will be needed prior to the information-gathering visit.
Please contact Mr. Hagar prior to preparing copies of the materials listed in the enclosure.
VEPCO 2
The inspectors will try to minimize your administrative burden by specifically identifying only
those documents required for the inspection preparation.
During the information-gathering visit, the team leader will also discuss the following inspection
support administrative details: office space, supplemental documents requested to be made
available to the team in the Region II office prior to the inspection preparation week of January
2, 2007; arrangements for site access; and the availability of knowledgeable plant engineering
and licensing personnel to serve as points of contact during the inspection.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its
enclosure will be available electronically for public inspection in the NRC Public Document
Room or from the Publicly Available Records (PARS) component of NRC's document system
(ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-
rm/adams.html (the Public Electronic Reading Room).
Thank you for your cooperation in this matter. If you have any questions regarding the
information requested or the inspection, please contact Mr. Hagar at (843) 339-2822 or me at
(404) 562-4605.
Sincerely,
/RA/
Charles R. Ogle, Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos.: 50-338, 50-339
Enclosure
cc w/enc/: (See page 3)
VEPCO 3
cc w/encl:
Chris L. Funderburk, Director
Nuclear Licensing and
Operations Support
Virginia Electric and Power Company
Electronic Mail Distribution
Jack M. Davis
Site Vice President
North Anna Power Station
Electronic Mail Distribution
Executive Vice President
Old Dominion Electric Cooperative
Electronic Mail Distribution
County Administrator
Louisa County
P. O. Box 160
Louisa, VA 23093
Lillian M. Cuoco, Esq.
Senior Counsel
Dominion Resources Services, Inc.
Electronic Mail Distribution
Attorney General
Supreme Court Building
900 East Main Street
Richmond, VA 23219
_________________________
OFFICE RII:DRS RII:DRSP
SIGNATURE /RA/ by email
NAME E. Guthrie R. Hagar
DATE 9/18/2006 9/18/2006 6/ /2006 6/ /2006 6/ /2006 6/ /2006
E-MAIL COPY? YES YES NO YES YES NO YES NO YES NO YES NO
INFORMATION REQUEST FOR NORTH ANNA NUCLEAR POWER PLANT
COMPONENT DESIGN BASES INSPECTION
Please provide the information electronically in .pdf files, Excel, or other searchable format on
CDROM. The CDROM should be indexed and hyperlinked to facilitate ease of use. Lists
should contain enough information to be easily understood to someone who has a knowledge
of pressurized water reactor technology.
1. From your most-recent probabilistic safety analysis (PSA) excluding external events and
fires:
a. Two risk rankings of components from your site-specific probabilistic safety analysis
(PSA): one sorted by Risk Achievement Worth (RAW), and the other sorted by
Birnbaum Importance.
b. A list of the top 500 cutsets.
c. A risk ranking of all operator actions, sorted by RAW.
2. From your most-recent probabilistic safety analysis (PSA) including external events and
fires:
a. Two risk rankings of components from your site-specific probabilistic safety analysis
(PSA): one sorted by Risk Achievement Worth (RAW), and the other sorted by
Birnbaum Importance.
b. A list of the top 500 cutsets.
c. A risk ranking of all operator actions, sorted by RAW.
3. Human reliability worksheets for the operator actions included in your PSA model.
4. Any pre-existing evaluation or list of components and calculations with low design margins
(i.e., pumps closest to the design limit for flow or pressure, diesel generator close to design
required output, heat exchangers close to rated design heat removal, MOV risk-margin
rankings, etc.).
5. A list of operating experience evaluations completed within the last two years, sorted by
associated component and/or system.
6. A list of design modifications implemented within the last two years, sorted by affected
system.
7. A list of corrective-action evaluations that involved plant equipment and were completed
within the last two years, sorted by involved component or system.
8. A list of common-cause failure of components that have occurred at North Anna and have
been identified within the last five years.
Enclosure
VEPCO 2
9. A list of operability evaluations completed within the last two years, sorted by associated
component or system.
10. Contact information for a person to discuss PRA information prior to bag man trip: name,
title, phone number, and e-mail address
11. List of equipment currently on the sites Station Equipment Reliability Issues List, including
a description of the reason(s) why each component is on that list and summaries (if
available) of your plans to address those reasons.
12. List of equipment currently in GL 91-18 status.
13. List of equipment currently in MR (a)(1) status.
Enclosure