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, 2007Carolina Power & Light CompanyATTN:Mr. T. D. WaltVice PresidentH. B. Robinson Steam Electric Plant Unit 2
3581 West Entrance Road
Hartsville, SC 29550SUBJECT:NOTIFICATION OF H. B. ROBINSON NUCLEAR PLANT - COMPONENTDESIGN BASES INSPECTION - NRC INSPECTION REPORT
05000261/2007006Dear 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 functionas 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 ofyour 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 identifyrisk-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 2The 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 onlythose documents required for the inspection preparation. During the information gathering visit, the team leader will also discuss the following inspectionsupport 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 itsenclosure will be available electronically for public inspection in the NRC Public DocumentRoom 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 theinformation 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 ChiefEngineering Branch 1
Division of Reactor SafetyDocket Nos.:50-261License Nos.:DPR-23Enclosure: Information Request for H. B. Robinson Nuclear Plant Component Design Bases Inspection
CP&L 3cc w/encl:William G. Noll
Director, Site Operations
Carolina Power & Light Company
H. B. Robinson Steam Electric Plant
Electronic Mail DistributionErnest J. Kapopoulos, Jr.Plant General Manager
Carolina Power & Light Company
H. B. Robinson Steam Electric Plant
Electronic Mail DistributionPaul Fulford, ManagerPerformance Evaluation and
Regulatory Affairs PEB 5
Electronic Mail DistributionC. T. Baucom, SupervisorLicensing/Regulatory Programs
Carolina Power & Light Company
H. B. Robinson Steam Electric Plant
Electronic Mail DistributionJ. F. Lucas, ManagerSupport Services - Nuclear
Carolina Power & Light Company
H. B. Robinson Steam Electric Plant
Electronic Mail DistributionHenry J. Porter, DirectorDiv. of Radioactive Waste Mgmt.
Dept. of Health and Environmental
Control
Electronic Mail DistributionR. Mike GandyDivision of Radioactive Waste Mgmt.
S. C. Department of Health and
Environmental Control
Electronic Mail DistributionBeverly Hall, Chief RadiationProtection Section
N. C. Department of Environment,
Health and Natural Resources
Electronic Mail DistributionDavid T. ConleyAssociate General Counsel - Legal Dept.
Progress Energy Service Company, LLC
Electronic Mail DistributionJohn H. O'Neill, Jr.Shaw, Pittman, Potts & Trowbridge
2300 N. Street, NW
Washington, DC 20037-1128Chairman of the North Carolina Utilities Commission
c/o Sam Watson, Staff Attorney
Electronic Mail DistributionRobert P. GruberExecutive Director
Public Staff - NCUC
4326 Mail Service Center
Raleigh, NC 27699-4326Public Service CommissionState of South Carolina
P. O. Box 11649
Columbia, SC 29211
____________________________OFFICERII:DRSRII:DRSRII:DRPSIGNATURE/RA//RA//RA/NAMEWRogersSRoseRMusserDATE4/19/20074/19/20074/19/2007
E-MAIL COPY? NO NO NO YESNO YESNO YESNO YESNO
EnclosurePlease provide the information electronically in ".pdf" files, Excel, or other searchable format onCDROM. 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 andfires:
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 andfires:
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. Providecopies 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 stationcorrective 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 isdetermined
.8.A list of common-cause failure of components that have occurred at H. B. Robinson andhave been identified within the last five years. 9.A list of operability evaluations completed within the last two years, sorted by associatedcomponent or system.10.Contact information for a person to discuss PRA information prior to the informationgathering trip: name, title, phone number, and e-mail address
2Enclosure11.List of equipment currently on the site's Station Equipment Reliability Issues List, includinga 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.