ML17158A305
| ML17158A305 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 05/23/1994 |
| From: | Chris Miller Office of Nuclear Reactor Regulation |
| To: | Byram R PENNSYLVANIA POWER & LIGHT CO. |
| Shared Package | |
| ML17158A306 | List: |
| References | |
| IEB-93-003, IEB-93-3, TAC-M87908, TAC-M87909, NUDOCS 9406030054 | |
| Download: ML17158A305 (4) | |
Text
May 23, 1994
.Docket Nos.
50-387 and 50-388
("
(
Nr. Robert G.
Byram Senior Vice President-Nucle'ar Pennsylvania Power and Light.
Company 2 North Ninth Street Allentown, Pennsylvania'8101
Dear Mr." Byram:
SUBJECT:
SAFETY EVALUATION OF THE INSERVICE,TESTING PROGRAM RELIEF REQUESTS FOR PUMPS AND 'VALVES, SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1
AND "2 (TAC'OS.
H87908 AND 87909)
The NRC staff'as completed their review of the information concerning the inservice testi'ng (IST)"program that was s'ubmitted by Pennsylvania Power 8
Light Company (PP8L) in a'etter'da'te'd Oct'ober 12, 1993.
This letter contained Rev'ision 9 for Susquehanna Unit 1
and Revision 6 for Unit 2.
These revisions corrected the numbering of valves in the control rod drive system and added the,valvesassociated with the reactor water level backfill modifications 'w'hich were mandated by NRC Bulletin 93-03, "Resolution of Issues Related to Rea'ctor Vessel Water Level Instrumentation in BWRs."
In addition, PP8L requested relief to extend the testing frequency for these valves.
The results of the staff review are contained in the enclosed Safety Evaluation.
The evaluation indicates that PP8L has adequately responded to NRC Bulletin 93-03.
In addition the staff has concluded that the alternate testing described in the submittal will provide reasonable assurance of the operational readiness of the valves referenced above to perform their safety-related functions The staff has further determined that approving the alternative, pursuant to 10 CFR 50.55a(a)(3),
is not required because the check valves are not ASHE Code Class 1, 2, or 3, notwithstanding that the testing is considered augmented to the scope of 10 CFR 50.55a.
Sincerely, Original s@ned by Charles L Miller Charles 1.. Hiller, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
Safety Evaluation cc w/enclosure:
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Docket Nos. 50-387 and 50-388 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055$ 4001 May 23, 1994 Hr. Robert G:
Byram
,Senior Vice President-Nuclear Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101
Dear Mr. Byram:
SUBJECT:
SAFETY EVALUATION OF THE INSERVICE TESTING PROGRAM RELIEF REQUESTS FOR PUMPS AND VALVES, SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1
AND 2 (TAC NOS.
M87908 AND 87909)
The NRC staff has completed their review of the information concerning the inservice testing '(IST) program that was submitted by Pennsylvania Power Light Company (PP&L) in a letter dated October 12, 1993.
This letter contained Revision 9 for Susquehanna Unit 1
and Revision 6 for Unit 2.
These revisions corrected the numbering of valves in the control rod drive system and added the valves associated with the reactor water level backfill modifications which were mandated by NRC Bulletin 93-03, "Resolution of Issues Related to Reactor Vessel Water Level Instrumentation in BWRs."
In addition, PP&L requested relief to extend the testing frequency for these valves.
The results of the staff review are contained in the enclosed Safety Evaluation.
The evaluation indicates that PP&L has adequately responded to NRC Bulletin 93-03.
In addition the staff has concluded that the alternate testing described in the submittal will provide reasonable assurance of the operational readiness of the valves referenced above to perform their safety-related function.
The staff has further determined that approving the alternative, pursuant to 10 CFR 50.55a(a)(3),
is not required because the check valves are not ASME Code Class 1, 2, or 3, notwithstanding that the testing is considered augmented to the scope of 10 CFR 50.55a.
Sincerely,
Enclosure:
Safety Evaluation
~
cc w/enclosure:
See next page Charles L. Miller, Director Project Directorate I-2 Division of. Reactor Projects I/II Office of Nuclear Reactor Regulation
Mr. Robert G.
Byram Pennsylvania Power
& Light Company Susquehanna Steam Electric Station, Units 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. Scott Barber 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. Harold G. Stanley Vice President-Nuclear Operations 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 Engineering Pennsylvania Power and Light Company 2 North Ninth.Street Allentown, Pennsylvania 18101