ML20133E765

Forwards RAI Re Util First 10-yr Interval Inservice Insp Program Plan Associated Request for Relief 96-003

ML20133E765
Person / Time
Site:	Mcguire
Issue date:	01/09/1997
From:	Nerses V NRC (Affiliation Not Assigned)
To:	Barron H DUKE POWER CO.
References
TAC-M95773, NUDOCS 9701130144
Download: ML20133E765 (5)

Text

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Mr. H. B. Barron January 9, 1997 Site Vice President McGuire Nuclear Station Duke Power Company 12700 Hagers Ferry Road Huntersville, NC 28078

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING MCGUIRE-NUCLEAR STATION, UNIT 2 FIRST 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN ASSOCIATED REQUEST FOR RELIEF NO.96-003 (TAC NO. M95773)

Dear Mr. Barron:

The Nuclear Regulatory Commission (NRC) staff, with assistance from its contractor, Idaho National Engineering Laboratory (INEL), is reviewing and evaluating the first 10-year interval inservice inspection program plan associated Request for Relief No.96-003 from the ASME Boiler and Pressure 1 Vessel Code,Section XI, requirements for McGuire Nuclear Station, Unit 2. '

Additional information (see enclosure) is required from Duke Power Company in order for the staf f to complete its review.

The staff would appreciate that a response be provided within 60 days to meet its inservice inspection program plan review schedule. In addition, to expedite the review process, please send a copy of your response to NRC's contractor, INEL, at the following address: .

Michael T. Anderson I INEL=Research Center I

~ 2151' North Boulevard ,

l P.O.' Box 1625 1

Idaho Falls, Idaho 83415-2209 1 -

l If you have any questions, please con, tact .,

me at' (301) 415-1484.

n Sincerely ~,  !

, , Original s'gned i by:

i

. ' Victor,Nerses, Senior Project Manager j Project DirectoratejII-2 4

, Division of Reactor. Projects - I/II i

, - Office, of Nuclear Reactor Regulation Docket No. 50-370 't

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Enclosure:

As stated t

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NAME VNIrsebri LBerry h HBerko h Y DATE 1/9/97 1/S/97 1/ b /97 1//k / '

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j UNITED STATES NUCLEAR REGULATORY COMMISSION l t WASHINGTON, D.C. 2066H001 1

,,,,, / January 9, 1997 l Mr. H. B. Barron Site Vice President i McGuire Nuclear Station Duke Power Company 12700 Hagers Ferry Road Huntersville, NC 28078

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING MCGUIRE NUCLEAR STATION, UNIT 2 FIRST 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN ASSOCIATED REQUEST FOR RELIEF N0.96-003 (TAC NO. M95773)

Dear Mr. Barron:

The Nuclear Regulatory Commission (NRC) staff, with assistance from its contractor, Idaho National Engineering Laboratory (INEL), is reviewing and evaluating the first 10-year interval inservice inspection program plan associated Request for Relief No.96-003 from the ASME Boiler and Pressure Vessel Code,Section XI, requirements for McGuire Nuclear Station, Unit 2.

Additional information (see enclosure) is required from Duke Power Company in order for the staff to complete its review.

The staff would appreciate that a response be provided within 60 days to meet its inservice inspection program plan review schedule. In addition, to expedite the review process, please send a copy of your response to NRC's contractor, INEL, at the following address:

Michael T. Anderson INEL Research Center 2151 North Boulevard P.O. Box 1625 Idaho Falls, Idaho 83415-2209 If you have any questions, please contact me at (301) 415-1484.

Sincerely, W

Victor Nerses, Senior Project Manager Project Directorate II-2 Division of Reactor Projects - I/II j Docket No. 50-370 l

Enclosure:

As stated cc w/ enc 1: See next page f

l

Mr. T. C. McMeekin Duke Power Company McGuire Nuclear Station cc:

Mr. Paul R. Newton Ms. Karen E. Long Legal Department, (PB05E) Assistant Attorney General Duke Power Company North Carolina Department of 422 South Church Street Justice Charlotte, North Carolina 28242-0001 P. O. Box 629 l

Raleigh, North Carolina 27602 l County Manager of Mecklenburg County 720 East Fourth Street Mr. G. A. Copp Charlotte, North Carolina 28202 Licensing - EC050 l Duke Power Company Mr. J. E. Snyder 526 South Church Street l

Regulatory Compliance Manager Charlotte, North Carolina 28242 Duke Power Company McGuire Nuclhar Site  !

12700 Hagers Ferry Road Regional Administrator, Reginn II '

U.S. Nuclear Regulatory Commission Huntersville, North Carolina 28078 101 Marietta Street, NW. Suite 2900 Atlanta, Georgia 30323 J. Michael McGarry, III, Esquire  !

Winston and Strawn Elaine Wathen, Lead REP Planner 1400 L Street, NW. l Division of Emergency Management Washington, DC 20005 116 West Jones Street l

Raleigh, North Carolina 27603-1335 Senior Resident Inspector c/o U. S. Nuclear Regulatory Mr. Dayne H. Brown, Director Commission 12700 Hagers Ferry Road Division of Radiation Protection North Carolina Department of Huntersville, North Carolina 28078 Environmental Health and Natural Resources Mr. Peter R. Harden, IV P. O. Box 27687 Account Sales Manager Raleigh, North Carolina 27611-7687 Westinghouse Electric Corporation Power Systems Field Sales l P. O. Box 7288 Charlotte, North Carolina 28241 Dr. John M. Barry Mecklenberg County Department of Environmental Protection 700 N. Tryon Street Charlotte, North Carolina 28202 Mr. T. Richard Puryear Owners Group (NCEMC)

Duke Power Company 4800 Concord Road j York, South Carolina 29745 f

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Request for Additional Inforcation First 10-Year Interval Inservice Inspection (ISI)

Request for Relief 96-003 Duke Power Company McGuire Nuclear Station, Unit 2 Docket No. 50-370

1. Scone / Status of Review Throughout the service life of a water-cooled nuclear power facility, 10 CFR 50.55a(g)(4) requires that comaonents (including supports) that are classif t::d as American Society of Mec1anical Engineers (ASME) Boiler and Pressure Vessel 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 ,

l Nuclear Power Plant Components, to the extent practical within the limitations

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! of design, geometry, and materials of construct 15n~of the components. This i section of the regulations also requires that inservice examinations of components and system pressure tests conducted during a 120-month inspection interval 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 120-month interval, subject to the limitations and l modifications listed therein. The components (including supports) may meet ,

requirements set forth in subsequent editions and addenda of the Code that are i incorporated by reference in 10 CFR 50.55a(b) subject to the limitations and modifications listed therein and subject to Nuclear Regulatory Commission (NRC) approval. l The staff has reviewed the available information provided by the licensee in the June 6, 1996, submittal. The applicable edition of the Code for the McGuire Nuclear Station, Unit 2, first 10-year ISI interval is the 1980 Edition, through Winter 1980 Addenda of ASME Section XI.

2. Additional Information Reauired Based on the above review, the staff has concluded that the following information and/or clarification is required to complete the review of Request for Relief 96-003.

A. The Code of Federal Regulations (CFR) provides that a licensee may propose an alternative to CFR or Code requirements in accordance with 10 CFR 50.55a(a)(3)(i) or 10 CFR 50.55a(a)(3)(ii). Under 10 CFR 50.55a(a)(3)(i),

the proposed alternative must be shown to provide an acceptable level of quality and safety, i.e., essentially be equivalent to the original requirement in terms of quality and safety. Under 10 CFR 50.55a

(a)(3)(ii), the licensee must show that compliance with the original l requirement results in a hardship or unusual difficulty without a compensating increase in the level of quality and safety. Examples of l hardship and/or unusual difficulty include, but are not limited to, i excessive radiation exposure, disassembly of components solely to provide access for examination, and development of sophisticated tooling that would result in only minimal increases in examination coverage.

l Enclosure

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1-1 i

l A licensee may also submit a request for relief from ASME requirements. l In accordance with 10 CFR 50.55a(g)(5)(iii), if a licensee determines that conformance with certain Code requirements is impractical for its facility, the licensee shall notify the Commission and submit, as specified in 550.4, information to support that determination. When a licensee determines that an inservice inspection requirement is impractical, e.g., component design or configuration limits the examination and the system would have to be redesigned or a component replaced to enable inspection, the licen.see should cite 10 CFR 50.55a(g)(5)(iii). The NRC may, giving due consideration to the burden placed on the licensee, impose an alternative examination requirement.

Request for Relief 96-003 was submitted in accordance with 10 CFR 50.55a(a)(3)(ii) for welds that were examined to the " extent practical" due to component configuration. However, there is no ,

discussion describing how compliance would result in a hardship or unusual 1 difficulty. Revjewthisrequestandprovidetheappropriatereferenceto the Code of Federal Regulations along with the documentation necessary to support the regu'atory basis, as discussed above.

B. In a letter u ted February 14, 1995, the licensee stated that the augmented reactor pressure vessel (RPV) exams were performed in the last outage of the first interval and that for wolds not meeting the >90%

requirement an alternative would be submitted in accordance with 10 CFR 50.55a(g)(6)(ii)(A)(5). Furthermore, the licensee confirmed in a telecon that the relief requested in the June 6,1996, submittal is intended to satisfy the ASME Section XI requirements for the first 10-year interval. However, relief from the Section XI requirements cannot be granted until the augmented requirement is satisfied. Provide the status of the augmented RPV examination with references to any applicable correspondence.

The schedule for timely completion of this review requires that the licensee provide, by the requested date, the above requested information and/or clarifications regarding the McGuire Nuclear Station, Unit 2, first 10-year ISI Request for Relief 96-003. l l

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