LR-N980085, Requests Approval for Relief Requests Associated W/Examinations Determined to Be Impractical During First Ten Year ISI Interval,Per 10CFR50.55a(g)(5)
| ML20217N882 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 03/03/1998 |
| From: | Eric Simpson Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LR-N980085, NUDOCS 9803090312 | |
| Download: ML20217N882 (24) | |
Text
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Pubhc Service Electnc ard Gas Company E. C. simpson Pubhc Service Electric and Gas Company PO. Box 236. Hancocks Bnoge. NJ 08038 609-339-1700 sew v<e President hxiw Eng,ne.ng IIAR 0 31998 LR-N980085 United States Nuclear Regulatory Commission Document Control Desk l Washington, DC 20555 l FIRST TEN YEAR ISI INTERVAL REQUESTS FOR RELIEF - 10CFR50.55a(g)(5)
HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 l l
Gentlemen:
Pursuant to 10CFR50.55a(g)(5), Public Service Electric and Gas Company (PSE&G) requests approval of the attached relief requests associated with examinations 4 determined to be impractical during the first ten year interval. Three of the requests involve relief from performing examinations on ams that are inaccessible due to geometrical configurations or permanent obstructions while the fourth request involves relief from disassembling Class 1 pumps and valves for the sole purpose of performing l internal surfaces (VT-3) examinations. Details concerning each of these requests are ,
included in the attachments to this letter.
Should you have any questions regarding this request, we will be pleased to discuss them with you.
Sincerely, -
f /77 I
/
Attachment (4) //
9003090312 980303 DR ADOCK 050003 11111l11ll48)l11 e=a_
114R 0 31998 Document Control Desk LR-N980085 C Mr. H. Miller, Administrator - Region i U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Ms. B. Mozafari, Licensing Project Manager - HC U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 j Mr. S. Morris (X24)
USNRC Resident inspector - HC Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering P. O. Box 415 i Trenton, NJ 08625 Mr. D. Jaffe U. S. Nuclear Regulatory Commission One White Flint North l 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 l
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MAR 0 31998 Document Control Desk LR-N980085 CEM BC Senior Vice President - Nuclear Operations (X04)
General Manager - Hope Creek Operations (H07)
Director - QA/NT/EP (X01)
Director - System Engineering (H16)
Director - Design Engineering (N23)
Director - Licensing / Regulation and Fuels (N21)
Director - Nuclear Business Support (N10)
General Manager - NBU Maintenance (X10)
Manager s Hope Creek Operations (H01)
Manager - Plant Maintenance - Maintenance Programs and Services (X07)
Manager - System Engineering - Hope Creek (H18)
Program Manager- NRB (N38)
Manager - Hope Creek Licensing (N21)
Station Licensing Engineer - Hope Creek (N21)
J. Keenan, Esq. (N21)
Records Management (N21)
Microfilm Copy Files Nos.1.2.1 (Hope Creek),5.85 l
)
1 4
ATTACHMENT 1 ,
HOPE CREEK GENERATING STATION
' FACILITY OPERATING LICEN'iE NPF-57 DOCKET NO. 50-354 BACKGROUND The provisions of 10CFR50.55a(g)(5) specify requirements related to examinations required by the ASME Code that are determined to be impractical during implementation of a plant's Inservice inspection (ISI) Program. Specifically, the provisions require that the basis for determining that an examination is impractical be demonstrated to the satisfaction of the NRC not later than twelve months following i expiration of the ISI ten year interval in which the impracticability is identified and following each subsequent ten year interval in which the examination is determined to be impractical. Pursuant to 10CFP50.55a(g)(5), Public Service Electric and Gas ,
Company (PSE&G) requests approval of the following ASME Code relief associated I with examinations determined to be impractical during the first ten yer.r interval: i RELJEF REQUEST RR-B1 I C_OMPONENT DESCRIPTION:
Class 1 Components (Limitations) l ASME CODE CLASS: l ASME Section XI Class 1 '
ASME SECTION XI EXAMINATION REQUIREMENTS:
4 For the Hope Creek Generating Station, surface and volumetric examinations shall be !
conducted in accordance with ASME B&PV Code,1983 Edition through 1983 Summer Addenda, Article IWB-2500.
BASIS FOR RELIEF:
Pursuant to 10CFR50.55a(g)(5)(iv), relief is requested from performing the inservice examination for the inaccessible portions of the examination areas identified in Attachment 2.
For each of the subject examination areas, geometric configuration and permanent obstructions affect the ability to obtain complete Code coverage. The prevailing ,
limitations and the specific reliefs for each weld are noted in Attachment 2 along with Page 1 of 5 l
' ' Attachment 1 LR-N980085 i First ISI intervcl R:ll:f R:qu: cts l
th,e indiv.idual weld numbers, the estimated areas of coverage, and the bases for limitation.
The subject welds received volumetric examination by radiography and/or surface examinations during fabrication in accordance with ASME Section Ill requirements. I These examinations provided adequate assurance of the structuralintegrity of the welds prior to plant operation. {
i ALTERNATIVE EXAMINATION:
Alternate examinations were considered for each exam area where a limitation exists; ;
however, no alternate examinations were considered to be appropriate.
The system pressure test conducted on the Class 1 pressure boundaries provides an acceptable level of assurance of system integrity and plant safety. l RELIEF REQUEST RR-C1 1
COMPONENT DESCRIPTION:
Class 2 Components (Limitations)
ASME CODE CLASS; ASME Section XI Class 2 ASME SECTION XI EXAMINATION REQUldEMENTS:
For Hope Creek Generating L'tation, surface and volumetric examinations shall be conducted in accordance with ASME B&PV Code,1983 Edition through 1983 Summer Addenda, Article IWC-2500.
BASIS FOR RELIEF:
Pursuant to 10CFR50.55a(g)(5)(iv), relief is requested from performing the inservice examination for the inaccessible portions of the examination areas identified in s Attachment 3.
For each of the subject examination areas, geometric configuration and permanent obstructions affect the ability to obtain complete Code coverage. The prevailing limitations and the specific reliefs for each weld are noted in Attachment 3 along with Page 2 of 5
' Attachment 1 LR-N980085 FirstISIinterv:1 R:ll f Requests th,e individual weid numbers, the estimated areas of coverage, and the bases for limitation.
The subject welds received volumetric exarr.ination by radiography and/or surface examinations during fabrication in accordance with ASME Section 111 requirements.
These examinations provided adequate assurance of the structural integrity of the welds prior to plant operation.
ALTERNATIVE EXAMINATION:
Alternate examinations were conside., -1 for each exam area where a limitation exists; however, no alternate examinations ware considered to be appropriate.
The system pressure test conducted on the Class 2 pressure boundaries provides an acceptable level of assurance of system integrity and plant safety.
RELIEF REQUEST RR-D1 COMPONENT DESCRIPTION:
Class 3 Components (Limitations)
ASME CODE CLASS:
ASME Section XI Class 3 ASME SECTION XI EXAMINATION REQUIREMENTS:
For Hope Creek Generating Station, visual examinations shall be conducted in accordance with ASME B&PV Code,1983 Edition through 1983 Summer Addenda, Article IWD-2500 and IWF-2500.
BASIS FOR RELIEF:
Pursuant to 10CFR50.55a(g)(5)(iv), relief is requested from performing the inservice examination for the inaccessible portions of the examination areas / component supports ;
identified in Attachment 4. i For each of the subject examination areas / component supports, permanent obstructions affect the ability to obtain complete Code coverage. The prevailing limitations and the specific reliefs for each weld are noted in Attachment 4 along with Page 3 of 5 I
- '
- Atta hm:nt1 LR-N980085 FirstISIinterv 1R:ll:f Requrcts the individual weld numbers / component support identification, the estimated areas of coverage, and the bases for limitation.
ALTERNATIVE EXAMINATION:
Alternate examinations were considered for each exam area where a limitation exists; however, no alternate examinations were considered to be appropriate.
RELIEF REQUEST RR-B3 COMPONENT DESCRIPTION:
Class 1 Pressure Retaining Pumps and Valves ASME CODE CLASS:
ASME Section XI Class 1 ASME SECTION XI EXAMINATION REQUIREMENTS:
Table IWB-2500-1, Categories B-L-2 and B-M-2, items Nos. B12.20 and B12.50 in accordance with ASME B&PV Code,1983 Edition through 1983 Summer Addenda, require a VT-3 examination of internal surfaces of pumps and valves.
BASIS FOR RELIEF:
Pursuant to 10CFR50.55a(g)(5)(iv), relief is requested on the basic that compliance with the code requirement is impractical and an unusual hardship.
The requirement to disassemble primary system pumps and valves for the sole purpose of performing a visual examination of the internal pressure boundary surfaces has only a very small potential of increasing plant safety margins and a very disproportionate impact on expenditures of p' ant man power, resources, and radiation exposure.
The performance of both carbon and stainless steel cast pump casings and valve bodies has been excellent in BWR applications. Based on this experience in the industry and regulatory acceptance of these alloys, continued excellent service performance is anticipated.
A more practical approach, that would provide an equivalent sampling program and significantly reduced radiation exposure to plant personnel, is to examine the internal Page 4 of 5 l
i
- ~ Attachment 1 LR-N980085 First ISIintervnl R;li;f Requ: cts pressura boundary of only those pumps and valves that require disassembly for meintenance purposes. This would continue to provide a reasonable sampling of the primary system pumps and valves and give adequate assurance that the integrity of these components is being maintained. This approach is supported by ASME Section j XI,1989 Edition, which is approved for use in 10CFR50.55a. '
ALTERNATIVE EXAMINATION:
The Hope Creek ISI Program requires that visual examination (VT-3) of the internal pressure boundary surfaces be performed concistent with the requirements of ASME Section XI,1989 Edition.
1 I
1 Page 5 of 5
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