ML072260118
| ML072260118 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 08/27/2007 |
| From: | Maurice Heath NRC/NRR/ADRO/DLR/RLRA |
| To: | Duncan R Carolina Power & Light Co |
| Heath, M, NRR/DLR/RLRA, 415-3137 | |
| References | |
| Download: ML072260118 (10) | |
Text
August 27, 2007 Mr. Robert J. Duncan II Vice President Carolina Power & Light Company P.O. Box 165, Mail Zone 1 New Hill, NC 27562
SUBJECT:
REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1, LICENSE RENEWAL APPLICATION
Dear Mr. Duncan:
By letter dated November 14, 2006, Carolina Power & Light Company submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54, to renew the operating license for Shearon Harris Nuclear Power Plant, Unit 1, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review.
These requests for additional information were discussed with Roger Stewart, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-3137 or via e-mail MLH5@nrc.gov.
Sincerely,
/RA/
Maurice Heath, Project Manager License Renewal Branch A Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-400
Enclosure:
Requests for Additional Information cc w/encl: See next page
ML072260118 OFFICE LA:DLR PM:RLRA:DLR BC:RLRA:DLR NAME IKing MHeath LLund DATE 08/13/07 08/24/07 08/27/07
Enclosure SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 LICENSE RENEWAL APPLICATION REQUESTS FOR ADDITIONAL INFORMATION (RAIs)
RAI 2.3.3-1 The top of license renewal application (LRA) page 3.3-440 reads: Notes for Tables 3.3.2-1 through 3.3.2-68: It appears that these Notes are also applicable to Tables 3.3.2-69 through 3.3.2-71. Also, the top of page 3.5-198 reads: Notes for Tables 3.5.2-1 through 3.5.2-26. It appears that these Notes are also applicable to Tables 3.5.2-27 through 3.5.2-29. Please confirm.
RAI 2.3.3-2 Plant Specific Note No. 716 for Tables 3.3.2-1 through 3.3.2-68 (LRA Page 3.3-447) reads Alignments for piping and ducting may be considered equivalent components. This is supported by equivalencies in NUREG-1801, such as found in NUREG-1801,Section V.A-1.
NUREG-1801 Section VA Engineered Safety Features - Containment Spray System (PWR) has an Item V.A-1 for Steel Ducting, piping and components external surfaces in Air - Indoor uncontrolled (External) environment with the effect being loss of material/general corrosion and identifies the applicable aging management program as NUREG-1801 Chapter XI.M36, "External Surfaces Monitoring. Is this the Section V.A-1 being referred to? What is the definition of alignments? Are alignments for piping and ducting referring to supports, fittings / components, assemblies or something else? In what sense or with what are they considered equivalent components and exactly how does NUREG-1801 Section VA Item V.A-1 support this equivalency determination?
RAI 2.3.3-3 Drawing 8-G-0517-LR has a box shaded green titled DISCHARGE FROM CRDM COOLING FANS at grid location G-9. Is this depicting a common discharge ductwork plenum - or just a containment volume where mixing occurs? If the latter, why is it highlighted green?
RAI 2.3.3-4 Drawing 8-G-0517-SO3-LR Grid B-2 shows fan P-5 1B housing as being partially highlighted while fan P-5 1A housing is entirely highlighted. Is fan P-5 1B housing entirely in scope?
RAI 2.3.3-5 Drawing 8-G-0548-LR Grid B-8 shows a Screen that is partially highlighted. Is the Screen, the bird screen and is it entirely in scope? At Grid J-4 two damper bodies/enclosures, DG-GD3 (SA-1) and DG-GD4 (SA-1) appear to be partially highlighted. Are they entirely in scope?
RAI 2.3.3-6 In Section 2.1.1.1, the requirements of Title 10 of the Code of Federal Regulations (10 CFR) 54.4(a)(1) pertaining to safety-related systems, structures, and components (SSCs) within the scope of the license renewal were compared to those of PassPort Equipment Data Base (EDB)
Quality Class A designation. It was stated that the definition of PassPort EDB Quality Class A is determined to be consistent with the scoping criteria of 10 CFR 54.4(a)(1), such that this designation is sufficient to facilitate scoping of the Shearon Harris Nuclear Power Plant (HNP)
SSCs under 10 CFR 54.4(a)(1). However, it was stated in Section 2.1.1.2 (2nd paragraph in page 2.1-11) that an evaluation of components located in Turbine Building and classified as safety-related has determined that these components do not meet the license renewal definition of safety-related. Please explain the differences in the safety-related classifications between HNP Passport EDB and license renewal and how a component that is classified as safety-related in PassPort EDB may not meet the license renewal safety-related classification?
RAI 2.3.3-7 In Section 2.3 Scoping and Screening Results, the following statements were made for many systems (e.g. Sections 2.3.2.1, 2.3.3.56, 2.3.3.57):
The system contains nonsafety-related components that have the potential to cause an adverse physical interaction with safety related equipment and/or nonsafety-related piping components connected to and providing support for the safety-related functional boundary of the system. These components have been included in scope of license renewal as a result of the 10 CFR 54.4(a)(2) review. Also, the system contains components that are conservatively assumed to meet the criteria of 10 CFR 54.4(a)(2) based on their quality class and are, therefore, included in scope of license renewal.
a) What are the intended functions of the non-safety related components? Are they reflected in Table 2.0-1 Intended Function Abbreviations and Definitions, Table 3.2.1 Summary of Aging Management Evaluations in Chapter V of NUREG-1801 for Engineered Safety Features, Table 3.2.2 Engineered Safety Features - Summary of Aging Management Evaluation, and Table 3.3.2 Auxiliary Systems - Summary of Aging Management Evaluation?
b) What components are included in scope of License Renewal due to the conservative assumption that they meet the criteria of 10 CFR 54.4(a)(2)? Are they reflected in the appropriate tables mentioned in the question above? Take any one system as an example and clarify how this information can be traced in the LRA.
Letter to R. Duncan, from M. Heath, dated August 27, 2007
SUBJECT:
REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1, LICENSE RENEWAL APPLICATION DISTRIBUTION:
HARD COPY:
DLR R/F E-MAIL:
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Shearon Harris Nuclear Power Plant, Unit 1 cc:
David T. Conley Associate General Counsel II -
Legal Department Progress Energy Service Company, LLC Post Office Box 1551 Raleigh, NC 27602-1551 Resident Inspector / Harris NPS c/o U. S. Nuclear Regulatory Commission 5421 Shearon Harris Road New Hill, NC 27562-9998 Ms. Margaret A. Force Assistant Attorney General State of North Carolina Post Office Box 629 Raleigh, NC 27602 Public Service Commission State of South Carolina Post Office Drawer 11649 Columbia, SC 29211 Ms. Beverly Hall, Section Chief Division of Radiation Protection N.C. Department of Environment and Natural Resources 3825 Barrett Drive Raleigh, NC 27609-7721 Mr. J. Paul Fulford, Manager Performance Evaluation and Regulatory Affairs PEB 5 Carolina Power & Light Company Post Office Box 1551 Raleigh, NC 27602-1551 Mr. Eric McCartney Plant General Manager Shearon Harris Nuclear Power Plant Carolina Power & Light Company P. O. Box 165, Mail Zone 3 New Hill, NC 27562-0165 Mr. Chris L. Burton Director of Site Operations Carolina Power & Light Company Shearon Harris Nuclear Power Plant Post Office Box 165, Mail Zone 1 New Hill, NC 27562-0165 Mr. Robert P. Gruber Executive Director Public Staff NCUC 4326 Mail Service Center Raleigh, NC 27699-4326 Chairman of the North Carolina Utilities Commission P. O. Box 29510 Raleigh, NC 27626-0510 Mr. Herb Council, Chair Board of County Commissioners of Wake County P. O. Box 550 Raleigh, NC 27602 Mr. Tommy Emerson, Chair Board of County Commissioners of Chatham County P. O. Box 87 Pittsboro, NC 27312 Mr. Thomas J. Natale, Manager Support Services Carolina Power & Light Company Shearon Harris Nuclear Power Plant P. O. Box 165, Mail Zone 1 New Hill, NC 27562-0165 Mr. David H. Corlett, Supervisor Licensing/Regulatory Programs Shearon Harris Nuclear Power Plant Carolina Power & Light Company P. O. Box 165, Mail Zone 1 New Hill, NC 27562-0165
Shearon Harris Nuclear Power Plant, Unit 1 cc: Mr. John H. ONeill, Jr.
Shaw, Pittman, Potts & Trowbridge 2300 N Street, NW Washington, DC 20037-1128 Ms. Julie Keys Nuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC 20006-2708