ML20237E446
| ML20237E446 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 08/27/1998 |
| From: | Richard Ennis NRC (Affiliation Not Assigned) |
| To: | Keiser H Public Service Enterprise Group |
| References | |
| TAC-MA1231, NUDOCS 9808310284 | |
| Download: ML20237E446 (5) | |
Text
Mr. Hirold W. K".isir August 27, 1998 Chilf Nuclicr Officer & Presid:nt-ll Nucl2cr Busin:ss Unit Public Service Electric & Gas Company Post Office Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING FIRST 10-YEAR INSERVICE INSPECTION (ISI) INTERVAL RELIEF REQUESTS FOR HOPE CREEK GENERATING STATION (TAC NO. MA1231)
Dear Mr. Keiser.
In a letter dated March 3,1998, Public Service Electric and Gas Company (PSE&G) requested approval of relief requests associated with examinations determined to be impractical during the first 10-year ISI interval.-
The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure, in order to expedite the review process, please send a copy of your response to the
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NRC's contractor, INEEL, at the following address:
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MichaelT. Anderson INEEL Research Center 2151 North Boulevard P.O. Box 1625 Idaho Falls, ID 83415-2209 We request that the additionalinformation be provided within 60 days of receipt of this letter.
The 60-day response timeframe was discussed with Mr. James Mest of your staff on August 10,1998. If circumstances result in the need to revise your response date, or if you have any questions, please contact me at (301) 415-1420.
Sincerely,
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Ric ard B. Ennis, Project Manager
- Project Directorate 1-2 Division of Reactor Projects - 1/II
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Office of Nuclear Reactor Regulation l
Docket No. 50-354
Enclosure:
Request for Additionalinformation cc w/ encl: See next page DISTRIBUTION.
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j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30666-0001 August 27, 1998.
Mr. Harold W. Keiser Chief Nuclear ONicer & President-Nuclear Business Unit Public Service Electric & Gas Company Post ONice Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING FIRST 10-YEAR INSERVICE INSPECTION (ISI) INTERVAL RELIEF REQUESTS FOR HOPE CREEK GENERATING STATION (TAC NO. MA1231)
Dear Mr. Keiser:
In a letter dated March 3,1998, Public Service Electric and Gas Company (PSE&G) requested approval of relief requests associated with examinations determined to be impractical during the first 10-year ISI interval.
The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure. !n order to expedite the review process, please send a copy of your response to the NRC's contractor, INEEL, at the following address:
MichaelT. Anderson
. lNEEL Research Center 2151 North Boulevard P.O. Box 1625 Idaho Falls, ID 83415-2209 We request that the additionalinformation be provided within 60 days of receipt of this letter.
The 60-day response timeframe was discussed with Mr. James Priest of your staff on August 10,1998. If circumstances result in the need to revise your response date, or if you have any questions, please contact me at (301) 415-1420.
Sincerely, l
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Richard B. Ennis, Project Manager Project Directorate 12
^
Division of Reactor Projects - 1/11
)
Office of Nuclear Reactor Regulation Docket No. 50-354
Enclosure:
Request for Additional Information cc w/ encl: See next page i
v Mr. Harold W. Keiser Hope Creek Generating Station Public Service Electric & Gas Company l
cc:
Jeffrie J. Keenan, Esquire Manager-Joint Generation Nuclear Business Unit-N21 Atlantic Energy P.O. Box 236 6801 Black Horse Pike Hancocks Bridge, NJ 08038 Egg Harbor Twp., NJ 08234-4130 Hope Creek Resident inspector.
Richard Hartung U.S. Nuclear Regulatory Commission Electric Service Evaluation Drawer 050g Board of Regulatory Commissioners Hancocks Bridge, NJ 08038 2 Gateway Center, Tenth Floor Newark, NJ 07102 Mr. Louis Storz.
Sr. Vice President - Nuclear Operations Lower Alloways Creek Township Nuclear Department c/o Mary O. Henderson, Clerk f
P.O. Box 236 Municipal Building, P.O. Box 157 l
Hancocks Bridge, NJ 08038 Hancocks Bridge, NJ 08038 l
l General Manager-Hope Creek Operaticns Mr. Elbert Simpson Hope Creek Generating Station Senior Vice President-P.O. Box 236 Nuclear Engineering Hancocks Bridge, NJ- 08038 Nuclear Department P.O. Box 236 Manager-Licensing and Regulation Hancocks Bridge, NJ 08038 Nuclear Business Unit - N21 P.O. Box 236 l
Hancocks Bridge, NJ 08038 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road
. King of Prussia, PA 19406 Dr. Jill Upoti, Asst. Director l
Radiation Protection Programs NJ Departmord r4 Environmental Protection and Energy CN 415 Trenton, NJ 08625 0415 l
-l REQUEST FOR ADDITIONAL INFORMATION FIRST 10-YEAR ISI INTERVAL REllEF REQUESTS FOR HOPE CREEK GENERATING STATION (TAC NO. MA1231) 1.
Scoce/ 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 successive 120-month inspection intervals comply with the requirements in the latest edition and adoenda 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 list?d 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 Nuclear Regulatory Commission (NRC) approval. The licensee, Public Service Electric and Gas Company (PSE&G), prepared the ISI Program to the requirements of the 1983 Edition through the Summer 1983 Addenda of the ASME Code Section XI.
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 NRC to support that determination.
On March 3,1998, PSE&G submitted requests for relief in letter No. LR N980085, from E. C. Simpson, "First Ten Year ISI interval Requests for Relief - 10CFR50.55a(g)(5)" to the U.S. Nuclear Regulatory Commission. The staff has reviewed the available information in requests for relief RR-B1, RR-C1, RR-01, and RR-B3. Based on this review, the staff has concluded that the information and/or clarification described in the r
next sectioilis required to complete the review of the requests.
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ENCLOSURE i
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2.
Additional Information Reauired I
The licensee's submittal does not identify the start and end dates for the Hope a.
Creek Generating Station First 10-Year ISI interval. Please include this information in your response.
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b.
The licensee's submittal includes acronyms or abbreviations that refer to non-standard, or specialized, nondestructive evaluation (NDE) techniques that they l
intend to employ during weld examinations. These abbreviations are not introduced prior to their usage. For example, Attachment 2, Class 1 Exam Limitations, page 1 of 9, of the licensee's submittal, includes a reference to "M-UT", in the " Code Req.
NDE" column. This abbreviation is not defined. Please define all non-standard acronyms in the submittal.
Each relief request must identify the welds that are covered, the applicable ASME c.
Code requirement from which relief is requested, the basis for requesting relief, and the proposed altemative. The licensee's proposal does not provide adequate information to support the determination that the Code requirements are impractical and that other methods might not reasonably increase the examination coverage, volumetric and/or surface as applicable, of the subject welds. For example, on page 2 of 9 in Attachment 2 of the licensee's submittal, the limitation discussion for meridional seam weld, RPV1-W16-2, states that the reduced volumetric coverage is "due to the location of the vessel support skirt." This discussion does not provide an adequate description of the physical limitation or indicate whether other techniques such as different interrogation angles, could have practically increased the coverage. Similar issues exist with other welds identified in Attachments 2,3, and 4 for RR-B1, RR-C1, and RR D1. Provide a technical basis for each weld, detailing the examination limitation, and discuss whether other examinations may be used to increase or supplement the limited examinations.
d.
In RR-B3, the licensee is requesting relief on the disassembly of pumps and valves for the sole purpose of inspecting the intemal surfaces. Later Codes have changed
.this requirement to "only when disassembled", and generally, the staff concurs with this later clarification. However, the licensee is requesting relief under 10 CFR 50.55a(g)(5)(iv), which is the reference for impracticality. Disassembly of components is not considered an impracticality. The licensee should reconsider which portion of CFR is used for this request and provide an appropriate basis for relief.
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