ML18016A379
| ML18016A379 | |
| Person / Time | |
|---|---|
| Site: | Harris |
| Issue date: | 04/13/1998 |
| From: | Scott Flanders NRC (Affiliation Not Assigned) |
| To: | Robinson W CAROLINA POWER & LIGHT CO. |
| References | |
| TAC-MA0433, TAC-MA433, NUDOCS 9804160173 | |
| Download: ML18016A379 (6) | |
Text
April 13, 1998 Mr. W. R. Robinson, Vice President Shearon Harris Nuclear Power Plant Carolina Power 8 Light Company Post Office Box 165 - Mail Code: Zone 1 New Hill, North Carolina 27562-0165
SUBJECT:
SHEARON HARRIS UNIT 1 - REQUEST FOR ADDITIONALINFORMATION (RAI) REGARDING INSERVICE INSPECTION PROGRAM RELIEF REQUEST, REACTOR PRESSURE VESSEL WELDS (TAC NO. MA0433)
Dear Mr. Robinson:
By letter dated December 16, 1997, Carolina Power 8 Light Company (CP8L) submitted a request for relief from the criteria of 10 CFR 50.55a(g)(6)(ii)(A)(2), which specifies the requirements for augmented examinations of reactor pressure vessel welds. The staff has initiated its review of the submittal and determined that additional information is needed.
The Enclosure provides the details of the requested information.
To ensure a timely review of this submittal, the staff requests a response to the enclosed questions within 60 days of receipt of this letter. Ifthis is not achievable, CP8L should notify the staff and propose a date for submittal of a response to the RAI. Should you have any questions related to this letter or the enclosed RAI, please contact me at (301) 415-1172.
Sincerely, (Original Signed By)
Scott C. Flanders, Project Manager Project Directorate II-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-400
Enclosure:
As stated cc w/enclosure:
See next page
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-Mr. W. R. Robinson Carolina Power & Light Company Shearon Harris Nuclear Power Plant Unit 1 CC:
Mr. William D. Johnson Vice President and Senior Counsel Carolina Power 8 Light Company Post Office Box 1551 Raleigh, North Carolina 27602 Resident Inspector/Harris NPS c/o U.S. Nuclear Regulatory Commission 5421 Shearon Harris Road New Hill, North Carolina 27562-9998
- Ms;Karen E; Long-Assistant Attorney General State of North Carolina Post Office Box 629 Raleigh, North Carolina 27602 Public Service Commission State of South Carolina Post Office Drawer Columbia, South Carolina 29211 Regional Administrator, Region II U.S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303 Mr. Mel Fry, Acting Director Division of Radiation Protection N.C. Department of Environment, 3825 Barrett Dr.
Raleigh, North Carolina 27609-7721 Ms. D. B. Alexander Manager Performance Evaluation and Regulatory Affairs Carolina Power 8 Light Company 412 S. Wilmington Street Raleigh, North Carolina 27601 Mr. Bo Clark Plant General Manager-Harris Plant Carolina Power 8 Light Company.
Shearon Harris Nuclear Power Plant P.O. Box 165 New Hill, North Carolina 27562-0165 Mr. J. W. Donahue Director of Site Operations Carolina Power 8 Light Company Shearon Harris Nuclear Power Plant Post Office Box 165, MC: Zone 1
New Hill, North Carolina 27562-0165 Mr. Robert P. Gruber Executive Director Public Staff NCUC Post Office Box 29520
- - Raleigh; North'Carolina 27626 Chairman 'of the North Carolina Utilities Commission Post Office Box 29510 Raleigh, North Carolina 27626-0510 Mr. Milton Shymlock U.S Nuclear Regulatory Comm..
Atlanta Federal Center 61 Forsyth Street, SW, Suite 23185 Atlanta, Georgia 30303 Mr. Stewart Adcock, Chairman Board of County Commissioners of Wake County
~ P. O. Box 550 Raleigh, North Carolina 27602 Health and Natural Resources Margaret Bryant Pollard, Chairman Board of County Commissioners of Chatham County P. O. Box 87 Pittsboro, North Carolina 27312 Mr. Chris A. VanDenburgh, Manager Regulatory Affairs Carolina Power 8 Light Company Shearon Harris Nuclear Power Plant P.O. Box165, Mail Zone 1
New Hill, NC 27562-0165 Mr. Johnny H. Eads, Supervisor Licensing/Regulatory Programs Carolina Power 8 Light Company Shearon Harris Nuclear Power Plant P. O. Box 165, Mail Zone 1
New Hill, NC 27562-0165
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In accordance with 10 CFR 50.55a(g)(6)(ii)(A), all licensees must implement once, as part of the inservice inspection (ISI) interval in effect on September 8, 1992, an augmented volumetric examination of the reactor pressure vessel (RPV) welds specified in Item B1.10 of Examination Category B-Aof the 1989 Edition of the American Society of Mechanical Engineers (ASME) Code,Section XI. Examination Category B-A, Items B1.11 and B1.12, require volumetric examination of essentially 100% of the RPV circumferential and longitudinal shell welds, as defined by Figures IWB-2500-1 and -2, respectively.
Essentially 100%, as defined by 10 CFR 50.55a(g)(6)(ii)(A)(2), is greater than 90% of the examination volume of each weld. Licensees unable to satisfy the requirements of 10 CFR 50.55a(g)(6)(ii)(A) must propose an alternative to the examination requirements that provides an acceptable level of quality and safety; the alternative may be used when authorized by the Director of the Office of Nuclear Reactor,,Regulation.
For licensees with fewer than 40 months remaining in the interval on the effective date, deferral ofthe augmented examination is permissible with the conditions stated in the regulations.
In addition, all previously granted relief for Item B1.10, Examination Category B-A, for the interval in effect on September 8, 1992, is revoked by the new regulation.
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The staff has reviewed the available information provided by the licensee in the December 16, 1997, submittal. The applicable edition of the Code for the Shearon Harris Nuclear Power Plant first 10-year ISI interval is the 1983 Edition through Summer 1983 Addenda ofASME Section XI.
The licensee stated in the December 16, 1997, letter that "in accordance with 10CFR50.55a(a)(3),
Carolina Power 8 Light Company (CPSL) hereby requests relief from the criteria of 10CFR50.55a(g)(6)(ii)(A)(2) for augmented examinations of reactor pressure vessel (RPV) welds at the Harris Nuclear Plant (HNP)." It appears that the licensee has included components in this request for relief that are not subject to the augmented examination but are subject to ASME Code requirements.
Because the augmented reactor vessel examination is a Code of Federal Regulations requirement, the information submitted regarding that examination should be separate from relief requests regarding ASME Code requirements.
Provide a proposed alternative to the regulatory requirements (augmented reactor pressure vessel examination) for Items B1.11'and B1.12 that provides an acceptable level of quality and safety.
Provide a separate request for relief citing the applicable paragraph(s)
(i.e. 10CFR50.55a(a)(3)(l),
10CFR50.55a(a)(3)(ii), or 10CFR50.55a(6)(l)) for the remaining subject welds not meeting the requirements ofASME Section XI.
Enclosure
21 The licensee performed the RPV examinations in accordance with ASME Section XI, 1983 Edition with Addenda through Summer 1983. As required by 10CFR50.55a(g)(6)(ii)(A)(2), the augmented examination requirements for the reactor vessel shell welds are those specified in Table IWB-2500-1, Item B1.10 of Examination Category B-A, "Pressure Retaining Welds in Reactor Vessel," of the 1989 Edition of ASME Section XI. Verifythat these augmented requirements have been met except for the welds receiving limited examination coverage listed in the request for relief.
3.
It appears from the request for relief that the limitations associated with the subject welds are primarily due to physical obstructions and nonconducive geometry of the component surfaces.
The licensee stated that these conditions prevent 100 percent examination coverage.
The limitations listed in Tables 1 and 2 of the request for relief
- are not detailed.-.ln some cases;.identical limitations are listed for welds that have-received 100% coverage (e.g., integral extension limitation on RVNOZBO-N-O-IRS).
Provide more detail regarding the limitations associated with the subject welds. If available, include drawings of nonconducive geometries and physical obstructions associated with the components as well as other items that may help describe the limitations.
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