ML20045B913
| ML20045B913 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 06/17/1993 |
| From: | Nerses V Office of Nuclear Reactor Regulation |
| To: | Mcmeekin T DUKE POWER CO. |
| References | |
| TAC-M84919, NUDOCS 9306210257 | |
| Download: ML20045B913 (3) | |
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June 17, 1993 Docket No. 50-369 DISTRIBUTION Docket File-OGC NRC/ Local PDRs ACRS (10)
S.Varga L. Berry Mr. T. C. McMeekin G.Lainas E.Merschoff,RII Vice President, McGuire Site D.Matthews Duke Power Company V.Nerses 12700 Hagers Ferry Road Huntersville, North Carolina 28078-8985
Dear Mr. McMeekin:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON THE SECOND 10-YEAR INTERVAL INSERVICE INSPECTION (ISI) PROGRAM PLAN FOR THE MCGUIRE NUCLEAR STATION, UNIT NO. 1 (TAC NO. M84919)
The staff has reviewed the available information in the McGuire Nuclear Station, Unit No.1 Second 10-Year Interval ISI Program Plan, Revision 0, submitted October 12, 1992, and the requests for relief from the ASME Code Section XI requirements that Duke Power Company has determined to be impractical.
Based on the above mentioned review, the NRC staff has concluded that the enclosed request for additional information and/or clarification is needed in order to complete the review of the ISI Program Plan.
The staff requests that the additional information and/or clarification be provided within 60 days from the date of this letter in order to maintain the staff's review schedule.
This requirement affects fewer than ten respondents, and therefore, it is not subject to Office of Management and Budget review under P.L.96-511.
Sincerely, ORIGINAL SIGNED BY:
Victor Nerses, Project Manager Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
Request for Additional Information cc w/ enclosure:
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I a, Mr. T. C. McHeekin 1
Duke Power Company McGuire Nuclear Station cc Mr. A. V. Carr, Esquire Mr. Dayne H. Brown, Director Duke Power Company Department of Environmental, 422 South Church Street Health and Natural Resources Charlotte, North Carolina 28242-0001 Division of Radiation Protection 1
P. O. Box 27687 County Manager of Mecklenberg County Raleigh, North Carolina 27611-7687 720 East Fourth Street Charlotte, North Carolina 28202 Mr. Alan R. Herdt, Chief Project Branch #3 Mr. R. O. Sharpe V. S. Nuclear Regulatory Commission Compliance 101 Marietta Street, NW. Suite 2900 Duke Power Company Atlanta, Georgia 30323 McGuire Nuclear Site 12700 Hagers Ferry Road Ms. Karen E. Long Huntersville, NC 28078-8985 Assistant Attorney General North Carolina Department of J. Michael McGarry, III, Esquire Justice Winston and Strawn P. O. Box 629 1400*L Street, NW.
Raleigh, North Carolina 27602 Washington, DC",20005^
Mr. G. A. Copp Senior Resident Inspector Licensing - ECOS0 c/o V. S. Nuclear Regulatory Duke Power Company Commission P. O. Box 1006 12700 Hagers Ferry Road Huntersville, North Carolina 28078.
Charlotte, North Carolina 28201-1006 Regional Administrator, Region II Mr. T. Richard Puryear U.S. Nuclear Regulatory Commission Nuclear Technical Services Manager 101'Marietta Street, NW. Suite 2900 Carolinas District Atlanta, Georgia 30323 Westinghouse Electric Corporation P. O. Box 32817 Charlotte, North Carolina 28232 Dr. John M. Barry.
Mecklenberg County ;
Department of Environmental Protection 700 N. Tryon Street.
Charlotte, North Carolina 28202 v
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Enclosure REQUEST FOR ADDITIONAL INFORMATION SECOND 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN DUKE POWER COMPANY MCGUIRE NUCLEAR STATION, UNIT 1 DOCKET NO. 50-369 1.
Paragraph 10 CFR 50.55a(b)(2)(iv) states that ASME Code Class 2 piping welds in the Residual Heat Removal (RHR), Emergency Core Cooling (ECC), and Containment Heat Removal (CHR) systems shall be examined. These systems should not be completely excluded from inservice volumetric examination based on wall thickness.
The staff has previously determined that a 7.5% augmented volumetric sample constitutes an acceptable resolution at similar plants.
Confirm that these systems, or portions of these systems, are not being excluded from volumetric examination. Also, please provide a summary table containing the total number of welds and the type of Code-required examinations being performed in the RHR, ECC, and CHR systems.
The requested table will permit the staff to determine if the extent of ISI examinations meet the applicable requirements.
2.
Verify that there are no additional relief requests, other than those submitted with the October 12, 1992,. letter.
If additional relief requests are required, the licensee should submit them at this time for staff review.
3.
Augmented examinations have been established by the NRC when added assurance of structural reliability is deemed necessary.
Please provide clarification regarding the following augmented examinations:
a)
Plans for inservice examination of the Reactor Pressure Vessel welds should address the degree of compliance with Regulatory Guide (RG) 1.150, " Ultrasonic Testing of Reactor Vessel Welds During Preservice and Inservice Examinations."
Paragraph 1.1.3 of the ISI Program discusses using RG 1.150, "... to the extent committed by Duke Power Company."
Please discuss the previous commitments Duke Power has made regarding RG 1.150 and any exceptions Duke Power may be taking, b)
Paragraph 1.1.4 states that " augmented inspections on certain systems or components will be performed in accordance with other editions or addenda of ASME Section XI as identified in the governing commitment." Specifically, what augmented inspections require the use of other editions or addenda of Section XI, and why the inspections cannot be updated to be in accordance with the Code,.
Edition being used for the ISI Program?
c) Address the degree of compliance with Branch Technical Position MEB 3-1, "High Energy Fluid Systems, Protection Against Postulated Piping Failures in Fluid Systems Outside Containment."
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