ML20044B779
| ML20044B779 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 02/01/1993 |
| From: | Dromerick A Office of Nuclear Reactor Regulation |
| To: | J. J. Barton GENERAL PUBLIC UTILITIES CORP. |
| References | |
| TAC-M83210, NUDOCS 9303040206 | |
| Download: ML20044B779 (5) | |
Text
.
I March 1, 1993 I
Docket No. 50-219 Distribution:
- Docket File-TMcLellan NRC & Local PDRs JFRogge, RI Mr. John J. Barton PD I-4 Plant Vice President and Director SVarga GPU Nuclear Corporation JCalvo i
Oyster Creek Nuclear Generating Station SNorris Post Office Box 388 ADromerick forked River, New Jersey 08731 OGC ACRS (10)
Dear Mr. Opeka:
i
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - OYSTER CREEK NUCLEAR GENERATING STATION, THIRD 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN (TAC NO. M83210)
The staff, with assistance from its contractor, Idaho National Engineering Laboratory, is reviewing and evaluating the Third 10-Year Interval Inservice Inspection Program Plan and requests for relief from the ASME Boiler and Pressure Vessel Code,Section XI requirements for Oyster Creek. Additional information is required from GPU Nuclear Corporation in order for the staff to complete its review. The staff requests that you respond to the enclosed request for additional information within 60 days of receipt of this letter.
This requirement affects one respondent and, therefore, is not subject to Office of Management and Budget review under P.L.96-511.
Sincerely, i
Original signed by Alexander W. Dromerick, Sr. Project Manager Project Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
Request for Additional Information cc w/ enclosure:
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GPU Nuclear Corporation Generating Station CC:
Ernest L. Blake, Jr., Esquire Resident Inspector Shaw, Pittman, Potts & Trowbridge c/o U.S. Nuclear Regulatory Commission 2300 N Street, NW.
Post Office Box 445 Washington, DC 20037 Forked River, New Jersey 08731 Regional Administrator, Region I Kent Tosch, Chief U.S. Nuclear Regulatory Commission New Jersey Department of 475 Allendale Road Environmental Protection King of Prussia, Pennsylvania 19406 Bureau of Nuclear Engineering CN 415 BWR Licensing Manager Trenton, New Jersey 08625 GPU Nuclear Corporation 1 Upper Pond Road Parsippany, New Jersey 07054 i
Mayor Lacey Township 818 West Lacey Road Forked River, New Jersey 08731 i
Licensing Manager Oyster Creek Nuclear Generating Station l
Mail Stop:
Site Emergency Bldg.
Post Office Box 388 Forked River, New Jersey 08731 4
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L-GPU NUCLEAR CORPORATION OYSTER CREEK NUCLEAR GENERATING STATION DOCKET NO. 50-219 RE0 VEST FOR ADDITIONAL INFORMATION - THIRD 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN 1.
Scope / Status of Review Throughout the service life of a water-cooled nuclear power facility,10 CFR 50.55a(g)(4) requires that components (including supports) that are classified as American Society of Mechanical 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 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 the successive 120-month inspection interval shall 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 a successive 120-month interval, subject to the limitations and modifications listed therein.
The components (including supports) may meet 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.
The licensee, GPU Nuclear Corporation (GPUN), has prepared the Oyster Creek Nuclear Generating Station, Third 10-Year Inservice Inspection (ISI) Program Plan to meet the requirements of the 1985 Edition of Section XI of the ASME Code.
As required by 10 CFR 50.55(g)(5), if the licensee determines that certain Code examination requirements are impractical and requests relief, the licensee shall submit information to the Nuclear Regulatory Commission (NRC) to support that determination.
The staff has reviewed the available information in the Oyster Creek Nuclear Generating Station Third 10-Year Interval ISI Program Update, submitted April 16, 1992, and the requests for relief from the ASME Code Section XI requirements that the Licensee has determined to be impractical.
2.
Additional Information Recuired Based on the above review, the staff has concluded that the following information and/or clarification is required in order to complete the review of the ISI Program Plan:
, A.
Please provide isometric and/or component drawings showing the Code Class 1 and 2 piping welds, components, and supports that Section XI of the ASME Code requires be examined during the third 10-year inspection interval.
B.
Sections 4.1, 5.1, and 6.1 of the Oyster Creek Third Interval ISI Program Update reference an Oyster Creek 10-Year Schedule that appears to contain an itemized listing of the components subject to examination during the third 10-year interval.
Please provide the staff with a copy of this listing.
The requested listing, along with the requested isometric / component drawings, will permit the staff to determine if the extent of ISI examinations meets the applicable Code requirements.
C.
Chapter 5, page 5-12, of the Program Update states that welds in the Core Spray System that are excluded from examination by Section XI criteria (piping < 3/8-inch nominal wall thickness and > 4-inch NPS) shall be examined under an augmented schedule.
Please provide the staff with a copy of the Augmented Schedule containing a listing of the affected welds if it is not already incorporated into the Oyster Creek 10-Year Schedule mentioned in Section B above.
D.
Provide a list of the ultrasonic calit, ration standards being used during the third 10-year interval ISI at Oyster Creek Nuclear Generating Station.
The list should include the calibration standard identifications, sizes, and material specifications.
E.
Augmented examinations have been established by the NRC when added assurance of structural reliability is deemed necessary.
Examples of documents that address augmented examinations are:
(1) Branch Technical Position MEB 3-1, "High Energy Fluid Systems, Protection Against Postulated Piping Failures in Fluid Systems Outside Containment;"
(2)
Regulatory Guide 1.150, Ultrasonic Testing of Reactor Vessel Welds During Preservice and Inservice Examinations; (3) NUREG-0619, BWR Feedwater Nozzle and CRD Return Line Nozzle Cracking; (4) NUREG-0803, Integrity of BWR Scram System Piping; and (5) Generic Letter 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping (ref. NUREG-0313).
Several of these documents are mentioned as Regulatory Documents in the Program Update, but the extent of the associated augmented examinations is not clear.
Please address the degree of compliance with these and any other augmen9d examinations that may have been incorporated in the Oyster Creek i
Nuclear Generating Station Third 10-Year Interval Inservice Inspection Program Plan.
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~i i i F.
Reauest for Relief RI:
Relief is requested from performing the Code-required volumetric examinations for the meridional and circumferential lower head welds.
Please provide drawings and a more detailed technical discussion regarding the limitations preventing examination of these welds.
i G.
Reauest for Relief R2:
Relief is requested from the Code-required surface and/or volumetric examinations of 11 containment penetration welds.
Please provide the specific Code Item Number associated with each of the welds contained in this request. Other plants have performed examinations on an adjacent, accessible weld in lieu of each inaccessible containment penetration weld.
Please provide a discussion regarding this option.
H.
Reauest for Relief R7:
Relief is requested from the surface and volumetric examination requirements of the Code for several sections of the Shutdown Cooling System. As stated in the licensee's Basis and paragraph IWA-1320(e) of the Code, systems that are non-nuclear safety class, and optionally classified as Class 2 or 3 by the owner, need not meet the examination requirements of IWC-2000.
If the welds included in this request meet this criteria, why is relief being requested? Please provide a clarification regarding this request.
I.
Reauest for Relief R8:
Relief is requested from performing th Code-required volumetric examinations of the valve body welds for five Electromagnetic Relief Valves.
It is not clear why the Code requirements cannot be met by the performance of a one-sided volumetric examination.
Please provide drawings and a technical discussion describing the limitations in more detail.
J.
Reauest for Relief R9:
Relief is requested from the examination volume required by figure IWB-2500-8 of the Code for welds with overlay repairs.
The licensee considers the weld overlay repair examinations as valid examinations for satisfying the requirements of Examination Category B-J.
Please provide a listing of the welds with overlay repairs that are included in this request, and the percentage of the Examination Category B-J weld population represented by that list.
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