ML20248K377
| ML20248K377 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 06/05/1998 |
| From: | Rinaldi F NRC (Affiliation Not Assigned) |
| To: | Barron H DUKE POWER CO. |
| References | |
| TAC-MA0707, TAC-MA707, NUDOCS 9806100095 | |
| Download: ML20248K377 (5) | |
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Mr. H. B. Barron June 5, 1998 Vice President, McGuire Sita Nucle:r Generation Department Duke Energy Corporation -
12700 Hagers Ferry Road Huntersville, North Carolina 28078-8985
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING THE MCGUIRE NUCLEAR STATION, UNIT 1, FIRST INSERVICE INSPECTION PROGRAM PLAN REQUEST FOR RELIEF NO.97-004 (TAC NO. MA0707)
Dear Mr. Barron:
The NRC staff is reviewing your submittal of January 15,1998, requesting relief from the applicable ASME Code Section XI requirements. During its review, the staff determined that the enclosed additional information is needed in order to complete its review of your request.
Please provide your response within 30 days from the date of this letter. In addition, to expedite the review process, please send a copy of your response to the NRC's contractor, the Idaho National Engineering and Environmental Laboratory (INEEL), at the following address:
MichaelT. Anderson INEEL Research Center 2151 North Boulevard P.O. Box 1625 Idaho Falls, Idaho 83415-2209 If you have any questions regarding this request, please contact me at 301-415-1447.
Sincerely, ORILINAL SIGNED BY:
Frank kinaldi, Project Manager Project Directorate ll-2 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation i
Docket No. 50-369
Enclosure:
As stated cc w/ encl: See next page
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McGuire Nuclear Statien cc:
Mr. Paul R. Newton Ms. Karen E. Long Legal Department (PBO5E)
Assistant Attorney General Duke Energy Corporation North Carolina Department of 422 South Church Street.
Justice Charlotte, North Carolina 28242 P. O. Box 629 Raleigh, North Carolina 27602 County Manager of Mecklenburg County L. A. Keller 720 East Fourth Street Manager-Nuclear Regulatory-Charlotte, North Carolina 28202 Licensing Duke Energy Corporation Michael T. Cash 526 South Church Street Regulatory Compliance Manager Charlotte, North Carolina 28242 Duke Energy Corporation McGuire Nuclear Site Regional Administrator, Region 11 12700 Hagers Ferry Road U.S. Nuclear Regulatory Commission Huntersville, North Carolina 28078 Atlanta Federal Center 61 Forsyth Street, S.W., Suite 23T85 J. Michael McGarry, Ill, Esquire Atlanta, Georgia 30303 Winston and Strawn 1400 L Street, NW.
Elaine Wathen, Lead REP Planner Washington, DC 20005 Division of Emergency Management 116 West Jones Street Senior Resident inspector Raleigh, North Carolina 27603-1335 i
clo U.S. Nuclear Regulatory Commission Mr. Richard M. Fry, Director 12700 Hagers Ferry Road Division of Radiation Protection Huntersville, North Carolina 28078 North Carolina Department of Environment, Health and Natural Mr. Peter R. Harden, IV Resources Account Sales Manager 3825 Barrett Drive Westinghouse Electric Corporation Raleigh, North Carolina 27609-7721 Power Systems Field Sales P. O. Box 7288 Mr. T. Richard Puryear Charlotte, North Carolina 28241 Owners Group (NCEMC)
Duke Energy Corporation Dr. John M. Barry 4800 Concord Road Mecklenberg County York, South Carolina 29745 Department of Environmental Protection 700 N. Tryon Street Charlotte, North Carolina 28202 r
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Request for Additional Information (RAl) on the First 10-Year interval inservice Insoection (ISI)
Request for Rehef 97-004 A.
Scope / Status of Review Throughout the sehe life of a water-cooled nuclear power facility, Title 10 of the Code of Federal Regulations (10 CFR) Section 50.55a(g)(4) requires that components (including supports) that are classified as American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code) Class 1, Class 2, and Class 3 meet the requirements, except design and access provisions and preservice examination requirements, set forth in the ASME Code,Section XI, " Rules for Inservice Inspection of Nuclear Power Plant Components,"
to the extent practical within the limitations of design, geometry, and materials of construction of the components. This section of the regulations also requires that inservice examinations of components and system pressure tests conducted during successive 120-month inspection intervals comply with the requirements in the latest edition and addenda of the Code incorporated by reference in 10 CFR 50.55a(b) on the date 12 months prior to the start of the interval, subject to the limitations and modifications listed therein. The components (including supports) may meet examination requirements set forth in subsequent editions and addenda of the Code that are incorporated by reference in 10 CFR 50.55a(b) subject to the limitations and modifications listed therein and subject to NRC approval.
The staff has reviewed the information provided by Duke Energy Corporation (the licensee) in its January 15,1998, submittal. The applicable edition of the Code for the McGuire Nuclear Station, Unit 1, first 10-year ISI interval is the 1983 Edition through Summer 1983 Addenda of ASME Code Section XIB.
B.
Additional Information Required Request for Relief 97-004 contains two parts. Part 1 pertains to reactor pressure vessel (RPV) shell welds and Part 2 pertains to reactor vessel nozzle welds.
Provide the date (month / year) that the RPV weld examinations in Part 1 of the request for relief were performed. Also, seven of the nine welds listed in Part 1 are Category B-A, item B1.10 welds and are subject to the augmented RPV examination requirements. Section 50.55a (g)(6)(ii)(A)(2) states, in part, that "All licensees shall augment their reactor vessel examination by implementing once, as part of the inservice inspection interval in effect on September 8, 1992, the examination requirements for reactor vessel shell welds specified in item B1.10 of Examination Category B-A." Licensees with fewer than 40 months remaining in the inservice inspection interval in effect on September 8,1992, may under specified conditions defer the augmented RFV examination to the first period of the next inspection interval. Because this request for relief is for the first 10-year interval that ended November 30,1992, the status of the augmented examinations required by 10 CFR 50.55a must be known before the request for relief can be evaluated. Provide the staff with the status of the augmented reactor pressure
. vessel examinations required by 10 CFR 50.55a(g)(6)(ii)(A). Discuss the Enclosure l
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l implementation schedule for the augmented RPV examinations as well as the augmented examination coverages obtained for each item B1.10 weld at the McGuire Nuclear Power Station, Unit 1.
The augmented reactor vessel examination may, under specified conditions, be used to take credit for the RPV examination required by ASME Code Section XI. However, the augmented examination is not required by the Code, but is a separate requirement imposed by the Code of Federal Regulations if the licensee determined that it was unable to completely satisfy the requirements for the augmented reactor vessel examinations,10 CFR 50.55a(g)(6)(ii)(A)(5) states that the licer,see "shall submit information to the Commission to support the determination and shall propose an altemative to the examination requirements that would provide an acceptable level of quality and safety." Explain the intent of the licensee concoming the proposed altemative as required by 10 CFR 50.55a(g)(6)(ii)(A)(5) for those welds with incomplete examination coverage associated with the augmented examinations. To ensure appropriate evaluation of the proposed attematives to the augmented reactor pressure vessel examinations, reference to the correct paragraph [i.e.10 CFR 50.55a(g)(6)(ii)(A)(5)] pertaining to the Augmented Reactor Vessel Examination requirement is required in the proposed altamative.
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June 5, 1998 Mr. H. B. Barron Vice President, McGuire Site Nuclear Generation Department Duke Energy Corporation 127m Hagers Ferry Road Huntersville, North Carolina 28078-8985
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING THE MCGUIRE NUCLEAR STATION, UNIT 1, FIRST INSERVICE INSPECTION PROGRAM PLAN REQUEST FOR RELIEF NO.97-004 (TAC NO. MA0707)
Dear Mr. Barron:
The NRC staff is reviewing your submittal of January 15,1998, requesting relief from the applicable ASME Code Section XI requirements. During its review, the staff has determined that the enclosed additional information is needed in order to complete its review of your request. Please provide your response within 30 days from the date of this letter, in addition, to expedite the review process, please send a copy of your response to the NRC's contractor, the Idaho National Engineering and Environmental Laboratory (INEEL), at the following address:
MichaelT. Anderson INEEL Research Center 2151 North Boulevard P.O. Box 1625 Idaho Falls, Idaho 83415-2209 If you have any questions regarding this request, please contact me at 301-415-1447.
Sincerely, fTAd. /fdO*
Frank Rinaldi, Pfoject Manager Project Directorate 11-2 Division of Reactor Proiects - 1/11 Office of Nuclear Reactor Regulation Docket No. 50-369
Enclosure:
As stated cc w/ encl: See next page j