ML071100274
| ML071100274 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 04/20/2007 |
| From: | Cain L NRC/RGN-II/DRS/EB1 |
| To: | Walt T Carolina Power & Light Co |
| References | |
| IR-07-006 | |
| Download: ML071100274 (6) | |
See also: IR 05000261/2007006
Text
April 20, 2007
Carolina Power & Light Company
ATTN: Mr. T. D. Walt
Vice President
H. B. Robinson Steam Electric Plant Unit 2
3581 West Entrance Road
Hartsville, SC 29550
SUBJECT: NOTIFICATION OF H. B. ROBINSON NUCLEAR PLANT - COMPONENT
DESIGN BASES INSPECTION - NRC INSPECTION REPORT
Dear Mr. Walt:
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 H. B. Robinson Nuclear
Plant during the weeks of July 16 - 20, 2007, July 30 - August 3, 2007, and August 13 - 17,
2007. The inspection team will be led by Mr. Steven D. Rose, a Senior Reactor Inspector from
the NRC's Region II Office. 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 April 19, 2007, Mr. Rose confirmed with Mr. G. Sanders of
your staff, arrangements for an information gathering site visit and the three-week onsite
inspection. The schedule is as follows:
- Information gathering visit: Week of June 25 - 29, 2007
- Onsite weeks: July 16 - 20, 2007, July 30 - August 3, 2007, and August 13 - 17,
2007.
The purpose of the information gathering visit is to meet with members of your staff to identify
risk-significant components and operator actions. Information and documentation needed to
support the inspection will also be identified. Mr. Walt Rogers, a Region II Senior Reactor
Analyst, may accompany Mr. Rose during the information gathering visit to review probabilistic
risk assessment data and identify risk significant components which will be examined during the
inspection.
CP&L 2
The enclosure lists documents that will be needed prior to the information gathering visit.
Please contact Mr. Rose prior to preparing copies of the materials listed in the enclosure and
provide this information to the Region II office by June 18, 2007.
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
July 9 - 13, 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. Rose at (404) 562-4609 or me at
(404) 562-4876.
Sincerely,
/RA/
L.M. Cain, Acting Branch Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos.:50-261
License Nos.:DPR-23
Enclosure: Information Request for H. B. Robinson Nuclear Plant
Component Design Bases Inspection
CP&L 3
cc w/encl: David T. Conley
William G. Noll Associate General Counsel - Legal Dept.
Director, Site Operations Progress Energy Service Company, LLC
Carolina Power & Light Company Electronic Mail Distribution
H. B. Robinson Steam Electric Plant
Electronic Mail Distribution John H. O'Neill, Jr.
Shaw, Pittman, Potts & Trowbridge
Ernest J. Kapopoulos, Jr. 2300 N. Street, NW
Plant General Manager Washington, DC 20037-1128
Carolina Power & Light Company
H. B. Robinson Steam Electric Plant Chairman of the North Carolina
Electronic Mail Distribution Utilities Commission
c/o Sam Watson, Staff Attorney
Paul Fulford, Manager Electronic Mail Distribution
Performance Evaluation and
Regulatory Affairs PEB 5 Robert P. Gruber
Electronic Mail Distribution Executive Director
Public Staff - NCUC
C. T. Baucom, Supervisor 4326 Mail Service Center
Licensing/Regulatory Programs Raleigh, NC 27699-4326
Carolina Power & Light Company
H. B. Robinson Steam Electric Plant Public Service Commission
Electronic Mail Distribution State of South Carolina
P. O. Box 11649
J. F. Lucas, Manager Columbia, SC 29211
Support Services - Nuclear
Carolina Power & Light Company
H. B. Robinson Steam Electric Plant
Electronic Mail Distribution
Henry J. Porter, Director
Div. of Radioactive Waste Mgmt.
Dept. of Health and Environmental
Control
Electronic Mail Distribution
R. Mike Gandy
Division of Radioactive Waste Mgmt.
S. C. Department of Health and
Environmental Control
Electronic Mail Distribution
Beverly Hall, Chief Radiation
Protection Section
N. C. Department of Environment,
Health and Natural Resources
Electronic Mail Distribution
____________________________
OFFICE RII:DRS RII:DRS RII:DRP
SIGNATURE /RA/ /RA/ /RA/
NAME WRogers SRose RMusser
DATE 4/19/2007 4/19/2007 4/19/2007
E-MAIL COPY? NO NO NO YES NO YES NO YES NO YES NO
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.
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..
3. Risk ranking of operator actions from your site specific PSA sorted by RAW. Provide
copies of your human reliability worksheets for these items..
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 station applicability evaluations/reviews performed and documented in the station
corrective action program in the past two years for industry events, critical equipment
failures, and safety related equipment vulnerabilities [as communicated by NRC generic
communications, industry communications, 10 CFR part 21 notifications, etc.]
6. A list of safety related SSC design modifications implemented within the last two years,
sorted by affected system.
7. This item deleted. Corrective action lists will be requested after the component sample is
determined.
8. A list of common-cause failure of components that have occurred at H. B. Robinson and
have been identified within the last five years.
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 the information
gathering trip: name, title, phone number, and e-mail address
Enclosure
2
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 RIS 05-020 (formerly GL 91-18) status.
13. List of equipment currently in MR (a)(1) status.
Enclosure