ML20210R130
| ML20210R130 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, Catawba, McGuire  |
| Issue date: | 08/22/1997 |
| From: | Berkow H NRC (Affiliation Not Assigned) |
| To: | Tuckman M DUKE POWER CO. |
| References | |
| TAC-M92619, TAC-M92620, TAC-M92625, TAC-M92626, NUDOCS 9709020317 | |
| Download: ML20210R130 (5) | |
Text
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NUCLEAR REGULATORY COMMISSION WASHINGTON. o.C. 30e66-4001 o.m.
August 22, 1997 Mr. M. S. Tuckman Senior Vice President Nuclear Generation Duke Power Company P. O. Box 1006 Charlotte, NC 28201
SUBJECT:
CATAWBA AND MCGUIRE NUCLEAR STATIONS - RESPONSE TO REQUEST FOR RELIEF FROM THE ASME CODE, SECTION lli REQUIREMENTS (TAC NOS. M92619, M92620, M92625 AND M92626)
Dear Mr. Tuckman:
By letters dated June 15,1995, and September 26,1996, Duke Power Company (DPC) identified an issue that certain valves in its Catawba and McGuire nuclear stations do not meet the design provisions stated in paragraphs NC-7153 and ND-7153 of Section lli cf the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code) (1971 Edition including the Winter 1971 Addenda for McGuire and 1974 Edition including the Summer 1974 Addenda for Catawba). DPC requested that it be allowed to permanently retain the installed configuration of a number of manual and motor-operated stop (block) valvss located in series with overpressure protection relief devices in the Chemical and Volume Control System, Boron Recycle System, Safety injection System, Residual Heat Removal System, Containment Spray System, Waste Gas System. Auxiliary Feedwater System, and Component Cooling System and use specific administrative controls to verify their positions.
In its submittals, DPC rsquested that the staff authorize relief from the ASME Code, Section til design requirements stated in paragraphs NC/ND-7153 pursuant to Title 10 of the Qgdp of Federal Reoulations (10 CFR) Section 50.55a(a)(3) for the installed block valve configuration. DPC stated that the block valve and relief valve configurations are part of the original plant designs and either facilitate maintenance of the affected components or close for containment isolation,
.d The staff has reviewed DPC's request for an attemative pursuant to 10 CFR 50.55a(a)(3).
The staff finds that ASME Code, Section lli requirements for Quality Group B and C components (ASME Code Class 2 and 3 components) as stated in 10 CFR 50.55a(d) and
./
0 (e), respectively, apply to nuclear power plants whose applications for construction permits (cps) were docketed after May 14,1984. The cps for McGuire, Units 1 and 2, and Catawba, Units 1 and 2, were docketed before May 14,1984. Therefore, the regulations in 10 CFR 50.55a(d) and (e) conceming ASME Code, Section ill design requirements do not apply to McGuire and Catawba. Accordingly, authorization of an attemative to ASME Code, Section ill design requirements pursuant to 10 CFR 50.55a(a)(3) is unnecessary and inappropriate for these nuclear plants.
9709020317 970822
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PDR ADOCK 05000369
Mr. M. S. Tuckman August 22, 1997 4
i in its Final Safety Analysis Reports (FSAR), DPC committed to design and construct its McGuire and Catawba plants in accordance with ASME Code, Section 111 design provisions.
In its June 15,1995, and September 26,1996, letters, DPC identified a number of ASME Code Class 2 and 3 block valves installed in the McGuire and Catawba plants that did not meet the design requirements of ASME Code, Section lil, paragraphs NC/ND 7153. The NRC staff views DPC's discovered condition of noncompliance with 'he ASME Code, Section ill design provisions as a deviation from plant licensing commitments. Accordingly, DPC may desire to revise its licensing basis to accept the deviation as-is, and to either perform an evaluation of the discovered condition pursuant to 10 CFR 50.59, or submit a proposed license
- amendment to authorize a change in the licensing basis.
On the basis of the above evaluation, the staff concludes that authorization of an attemative or relief from ASME Code, Section lli design provisions for ASME Code Class 2 and 3 components is unnecessary and inappropriate for the Catawba and McGuire nuclear stations.
DPC may desire to accept the discovered deviation from its licensing commitments as a
" change" to its facility and evaluate it in accordance with 10 CFR 50i9, or otherwise submit a proposed license amendment to authorize a change in the licensing basis.
l Sincerely, ORIGINAL SIGNED BY L. WHEELER FOR:
Herbert N. Berkow, Director Project Directorate ll-2 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation Docket Nos. 50-369, 50-370, 50-413, and 50-414 cc: See next page DISTRIBUTION Docket File B.Boger M.Tschiltz, EDO PUBLIC G. Hammer, 0-7 E23 GHill (8)
OGC ACRS JJohnson, Ril PDil-2 Rdg
. SShaeffer, Ril DOCUMENT NAME: G:\\ CATAWBA \\ CAT 92625.LTR To receive a copy of this document, Indicate in the box: "C" = Copy without.
attachment / enclosure "E" = Copy with attachment /enclosuree "N" = No copy OFFICE PM:PDil-2,. E, LA:PDll-2 0 PM:Ppp-@
D:PDhg2,P C NAME P. Tam:cn((y( L. Berry y[(l VAdrseW ' ; F,i. Berkow DATE g/1L/97
] kJ/97 ' \\ $ // 97
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i OFFICIAL RECORD COPY i
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Mr. M. S. Tuckman 2-In its Final Safety Analysis Reports (FSAR), DPC committed to design and construct its McGuire and Catawba plants in accordance with ASME Code, Section lli design provisions.
in its June 15,1995, and September 26,1996, letters, DPC identified a number'of ASME Code Class 2 and 3 block valves installed in the McGuire and Catawba plants that did not
- meet the design requirements of ASME Code, Section lil, paragraphs NC/ND-7153. The
- NRC ' staff views DPC's discovered condition of noncompliance with the ASME Code, Section lil design provisions as a deviation from plant licensing commitments, Accordingly, DPC may desire to revise its licensing basis to accept the deviation as-is, and to either perform an evaluation of the discovered condition pursuant to 10 CFR 50.59, or submit a proposed license amendment to authorize a change in the licensing basis.
On the basis of the above evaluation, the staff concludes that authorization of an attemative l'
or relief from ASME Code, Section lli design provisions for ASME Code Class 2 and 3 i
components is unnecessary and inappropriate for the Catawba and McGuire nuclear stations.-
DPC may desire to' accept the discovered deviation from its licensing commitments as a
" change" to its facility and evaluate it in accordance with 10 CFR 50.59, or otherwise submit a proposed license amendment to authorize a change in the licensing basis.
Sincerely,
//
erbert N. Berkow, Director Project Directorate ll-2 ~
Division of Reactor Projects - 1/ll
. Office of Nuclear Reactor Regulation Docket Nos. 50-369, 50-370, 50-413, and 50414 cc: See next page
McGuire Nuclehr St: tion --
Cat;wba Nuclear St: tion cc:
Mr. Paul R. Newton -
Mr. Richard M. Fry, Director Legal Department (PB05E)
Division of Radiation Protection Duke Power Company _
North Carolina Department of 422 South Church Street
' Environment, Health, and Charlotte, North Carolina 28242-0001 Natural Resources 3825 Barrett Drive County Manager of Mecklenburg County Raleigh, North Carolina 2760g 7721 720 East Fourth Street Charlotte, North Carolina 28202 Ms. Karen E. Long Assistant Attomey General Mr. Michael T. Cash -
North Carolina Department of Regulatory Compliance Manager ~
Justice Duke Power Company P. O. Box 62g McGuire Nuclear Site Raleigh, North Carolina 27602 12700 Hagers Ferry Road-Huntersville, North Carolina 28078 Mr. G. A.- Copp Licensing - EC050 J. Michael McGarry, lli, Esquire Duke Power Company l
Winston and Strawn 526 South Church Street 1400 L Street, NW, Charlotte, North Carolina 28242-0001 Washington, DC 20005 Regional Administrator, Region ll Senior Resident inspector U.S. Nuclear Regulatory Commission -
t clo U. S. Nuclear Regulatory Atlanta Federal Center Commission 61 Forsyth Street, S.W., Suite 23T85 12700 Hagers Ferry Road Atlanta, Georgia 30303 Huntersville, North Carolina 28078 Elaine Wathen Mr, Peter R. Harden, IV Account Sales Manager Lead REP Planner -
Division of Emergency Management
-Westinghouse Electric Corporation
_116 West Jones Street Power Systems Field Sales Raleigh, North Carolina 27603-1335 P. O. Box 7288 Charlotte, North Carolina 28241-Mr. T. Richard Puryear Owners Group (NCEMC)
Dr. John M. Barry Duke Power Company Mecklenburg County 4800 Concord Road
. Department of Environmental York, South Carolins 2g745 Protection 700 N. Tryon Street
' Charlotte, North Carolina 28202
-_.--%~
- McGuire Nucle:r St: tion -
_ Cat:wba Nucle:r St: tion cc:
Mr M. S. Kitlan North Carolina Electric Membership L-Regulatory Compliance Manager Corporation Duke Power Company P. O. Box 27306 4800 Concord Road -
Raleigh,- North Carolina 27611 York, South Carolina 29745 Senior Resident inspector North, Carolina Municipal Power 4830 Concord Road Agency Number 1 York, South Carolina 29745 1427 Meadowwood Boulevard P. O, Box 29513 Mr. G. R. Peterson Raleigh, North Carolina 27626-0513 Site Vice President Catawba Nuclear Station County Manager of York County Duke Power Company
- York County Courthouse 4800 Concord Road York, South Carolina 20745 York, South Carolina 2g745 Richard P. Wilson, Esquire Mr. H. B. Barron Assistant Attorney General _
Vice President, McGuire Site
- South Carolina Attomey General's Duke Power Company Office 12700 Hagers Ferry Road P, O. Box 11549 Huntersville, North Carolina 28078 Columbia, South Carolina 29211 Piedmont Municipal Power Agency 121 Village Drive Greer, South Carolina 29651 Saluda River Electric P. O. Box 929 Laurens, South Carolina 29360-Max Batavia, Chief Bureau of Radiological Health South Carolina Department of Health and Environmental Control
!2600 Bull Street Columbia, South Carolina 29201 i
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