ML17158B975
| ML17158B975 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 03/07/1997 |
| From: | Stolz J NRC (Affiliation Not Assigned) |
| To: | Byram R PENNSYLVANIA POWER & LIGHT CO. |
| Shared Package | |
| ML17158B976 | List: |
| References | |
| TAC-M94505, TAC-M94506, NUDOCS 9703130166 | |
| Download: ML17158B975 (4) | |
Text
Robert G.
Byram Senior Vice President-Nuclear Pennsylvania Power and Light Company.
2 North Ninth Street Allentown, PA 18101 Harch 7,
1997
SUBJECT:
EVALUATION OF THE FIRST 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAH PLAN, REQUESTS FOR RELIEF 1RR-24 AND 2RR-21 FOR SUSQUEHANNA STEAN ELECTRIC STATION, UNITS 1
AND 2 (TAC NOS.
H94505 AND H94506)
Dear Hr. Byram:
The staff with technical assistance from its contractor, the Idaho National Engineering Laboratory (INEL) has reviewed and evaluated the informati,on provided by Pennsylvania Power and Light Company (PP&L) in a letter dated January 9,
1996.
In the letter were included relief requests 1RR-24 and 2RR-21 for units 1
and 2 respectively regarding the augmented examination of the reactor pressure vessel required by 10 CFR 50.55a(g)(6)(ii)(A).
The request was for relief from examining essentially 100% of the reactor pressure vessel (RPV) circumferential and longitudinal shell welds, AD, BK, and BH.
An alternative was proposed to examine in excess of 80% but less than 90% of the length of these welds.
As indicated in the attached safety evaluation, the staff concludes that PP&L has made a reasonable effort to maximize examination coverage "of the RPV shell welds through the use of improved inspection equipment and has examined 96% of the total weld length of all vessel shell welds.
This provides reasonable assurance that the structural integrity of the. reactor, vessel welds will be maintained in service.
Imposing the augmented vessel'e'xamination coverage requirements of 10 CFR 50.55a(g)(6)(ii)(A) would result in. a burden. without a compensating increase in quality and safety.
Therefore, the proposed alternative is authorized pursuant to 10 CFR, 50.55a(a)(3)(ii).
I '
1 Sincerely,
, Original 'si.gned'by
,John F. Stol,z, Director Project Directorate I-2 Division of Reactoij Projects -'/II Office of Nuclear Reactor Regulation Docket Nos.
50-387/388 1
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTO N y D C 2055&0001 March 7, 1997 Mr. Robert G.
Byram Senior Vice President-Nuclear Pennsylvania Power and Light Company 2 North Ninth Street Allentown, PA 18101
SUBJECT:
EVALUATION OF THE FIRST 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN, RE(UESTS FOR RELIEF 1RR-24 AND 2RR-21 FOR SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1
AND 2 (TAC NOS.
M94505 AND M94506)
Dear Mr. Byram:
The staff with technical assistance from its contractor, the Idaho National Engineering Laboratory (INEL) has reviewed and evaluated the information provided by Pennsylvania Power and Light Company (PP&L) in a letter dated January 9,
1996.
In the letter were included relief requests 1RR-24 and 2RR-21 for units 1 and 2 respectively regarding the augmented examination of the reactor pressure vessel required by 10 CFR 50.55a(g)(6)(ii)(A).
The request was for relief from examining essentially 100% of the reactor pressure vessel (RPV) circumferential and longitudinal shell welds, AD, BK, and BM.
An alternative was proposed to examine in excess of 80M but less than 90N of the length of these welds.
As indicated in the attached safety evaluation, the staff concludes that PP8L has made a reasonable effort to maximize examination coverage of the RPV shell welds through the use of improved inspection equipment and has examined 96N of the total weld length of all vessel shell welds.
This provides reasonable assurance that the structural integrity of the reactor vessel welds will be maintained in service.
Imposing the augmented vessel examination coverage requirements of 10 CFR 50.55a(g)(6)(ii)(A) would result in a burden without a compensating increase in quality and safety.
Therefore, the proposed alternative is authorized pursuant to 10 CFR 50.55a(a)(3)(ii).
Sincerely, Docket Nos. 50-387/388
Enclosure:
Safety Evaluation cc w/encl:
See next page o
n F. Stolz, Director P oject Directorate I-ivision of Reactor Projects I/II Office of Nuclear Reactor Regulation
Mr. Robert G.
Byram Pennsylvania Power
& Light Company Susquehanna Steam Electric Station, Unit's 1
& 2 CC:
Jay Silberg, Esq.
- Shaw, Pittman, Potts
& Trowbridge 2300 N Street N.W.
Washington, D.C.
20037 Bryan A. Snapp, Esq.
Assistant Corporate Counsel Pennsylvania Power
& Light Company 2 North Ninth.Street Allentown, Pennsylvania 18101 Mr. J.
M. Kenny Licensing Group Supervisor Pennsylvania Power
& Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. K. Jeni son Senior Resident Inspector U. S. Nuclear Regulatory Commission P.O.
Box 35 Berwick, Pennsylvania 18603-0035 Mr. William P. Dornsife, Director Bureau of Radiation Protection Pennsylvania Department of Environmental Resources P. 0.
Box 8469 Harrisburg, Pennsylvania 17105-8469 Mr. Jesse C. Tilton, III Allegheny Elec. Cooperative, Inc.
212 Locust Street P.O.
Box 1266 Harrisburg, Pennsylvania 17108-1266 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Mr. George Kuczynski Plant Manager Susquehanna Steam Electric Station Pennsylvania Power and Light Company Box 467 Berwick, Pennsylvania 18603 Mr. Herbert D. Woodeshick Special Office of the President Pennsylvania Power and Light Company Rural Route 1,
Box 1797 Berwick, Pennsylvania 18603 George T. Jones Vice President-Nuclear Operations Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Dr. Judith Johnsrud National Energy Committee Sierra Club 433 Orlando Avenue State College, PA 16803 Chairman Board of Supervisors 738 East Third Street
- Berwick, PA 18603