ML20205C444
| ML20205C444 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 03/26/1999 |
| From: | Feigenbaum T NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| AR-99004028, NYN-99038, NUDOCS 9904010211 | |
| Download: ML20205C444 (4) | |
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North Atlantic Energy Service Corporation
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)y. Atlantic Seabrook, Nil 03874 moarmai The Northeast Utilities System March 26,1999 Docket No. 50-443 NYN-99038 AR 99004028 United States 14uclear Regulatory Commission i
Attention: Document Control Desk Washington, DC 20555 1
Seabrook Station Reactor Vessel Inspection Telephone Conference On March 15, 1999, a telephone conference was held between members of North Atlantic Energy Service Corporation (North Atlantic) and NRC Staff to discuss aspects of North Atlantic's plan for the inservice inspection (ISI) of the Seabrook Station Unit I reactor vessel /
during the upcomirc refueling outage (OR06). The purpose of this letter is to summarize our inspection plans for your information.
The reactor vessel ISI will be performed in accordance with the requirements of 10 CFR 50.55a.
North Atlantic is currently committed to perform ISI of the reactor vessel in accordanc requirements of Section XI of the 1983 Edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (includir:g addenda through the Summer of 1983). Additionally, as a result of the augmented examination requirements for reactor vessels specified in 10 CFR 50.55a(g)(6)(ii)(A)(2), the examinations of reactor vescel shell welds specified in Item B.1.10 " Pressure Retaining Welds in Reactor Vr.;sel," of Table IWB-2500-1 of subsection IWB, are required to be performed in accordance with the 1989 Edition of Section XI subject to the conditions specified in subsections 50.55a(g)(6)(ii)(A)(3) and (4). North Atlantic indicated during the telephone conference that it planned to satisfy both the ASME Code and augmented examination requirements during the OR06 inspection.
The =ASME. Code and the augmented examination requirements identified in 10 CFR 50.55a(g)(6)(ii)(A)(4) require that the examination coverage of the welds include essentially
- 100% of the weld length.' The " essentially 100%" examination requirement is defined in 10 CFR 50.55a(g)(6)(ii)(A)(2) as more than 90 percent of the examination volume of each weld. North Atlantic identified based upon a pre-inspection estimate of the reactor vessel welds that it is impractical to achieve the " essentially 100%" coverage requirement for certain nozzle and shell welds.
t 9904010211 990326 U PDR ADOCK 05000443 Q
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E U.S. Nuclear Regulatory Commission
- NYN-99038 / Page 2 4
8 North Atlantic will submit ASME Code relief request (s) pursuant to the requirements of 10 CFR 50.55a(g)(5)(iii) and (iv) for all reactor vessel welds for which it determined were impractical to meet the " essentially 100%" coverage requirements of Section XI of the 1983 Edition of the ASME Boiler and Pressure Vessel Code (including addenda through the Summer of 1983) after the completion of the examination.
Additionally, for reactor vessel shell welds inspected to the augmented examination requirements i
of 10 CFR 50.55a(g)(6)(ii)(A)(2) for which North Atlantic determines that the " essentially 100%" coverage requirements were not met, a request to propose an alternative to the augmented examination requirements will be submitted after the completion of the examination pursuant to 10 CFR 50.35a(g)(6)(ii)(A)(5).
Should you require further information regarding this matter, please contact Mr. James M.
Peschel, Regulatory Compliance Manager at (603) 773-7194.
Very truly yours, j
NORTH ATLANTIC ENERGY SERVICE CORP.
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Ted C. Feigegnm Executive Vice President and Chief Nuclear Officer cc:
H. J. Miller, NRC Regional Administrator J. T. Harrison, NRC Project Manager, Project Directorate 1-2 R. K. Lorson, NRC Senior Resident Inspector
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ENCLOSURE 1 TO NYN-99038 1
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North Atlantic Commitments Contained in NYN-99038 l
Description of Commitment AR#99004028-02 North Atlantic will submit ASME Code relief request (s) pursuant to the requirements of 10 CFR 50.55a(g)(5)(iii) and (iv) to the NRC for all reactor vessel welds for which it determined were impractical to meet the " essentially 100%" coverage requirements of Section XI of the 1983 Edition of the ASME Boiler and Pressure Vessel Code (including add:nda through the Summer of 1983) after the completion of the examination.
AR#99004028-03 For reactor vessel shell welds inspected to the augmented examination
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requirements of 10 CFR 50.55a(g)(6)(ii)(A)(2) for which North Atlantic determines that the " essentially 100%" coverage requirements were not met, North Atlantic will submit a request to propose an altemative to the augmented examination requirements after the completion of the examination pursuant to 10 CFR 3
50.55a(g)(6)(ii)(A)(5).
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