ML17158C161
| ML17158C161 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 05/15/1997 |
| From: | Poslusny C NRC (Affiliation Not Assigned) |
| To: | Byram R PENNSYLVANIA POWER & LIGHT CO. |
| References | |
| TAC-M90541, TAC-M90542, NUDOCS 9705210271 | |
| Download: ML17158C161 (6) | |
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~o->v 385-UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON> D.C. 205~001 May 15, 1997 Mr. Robert G.
Byram Senior Vice President-Nuclear Pennsylvania Power and Light Company 2 North Ninth Street Allentown, PA 18101
SUBJECT:
NRC VISIT TO PENNSYLVANIA POWER AND LIGHT COMPANY OFFICE CONCERNING OUTSTANDING ISSUE ON CLASS lE/NON 1E ISOLATION AT SUSQUEHANNA STEAM ELECTRIC STATION (SSES),
UNITS 1
AND 2 (TAC NOS.
M90541 AND M90542)
Dear Mr. Byram:
On April 29,
- 1997, I visited your office in Allentown, PA, with staff members from the Instrumentation and Controls Branch to audit information supporting your two submittals dated November 26, 1996 and February 3, 1997.
These submittals provided analyses results to support the fact that isolators had not been installed in approximately 250 circuits in the SSES units.
Each of the circuits included in the submittals reflect interface between Class lE and non-Class 1E components.
The purpose of the visit was to obtain a better understanding of the analyses assumptions, methods and conclusions and to determine the nature of the circuits that had been included.
During the discussions, the following facts were highlighted by your staff that could possibly lead to the resolution of the isolation issue for the SSES units:
(1) approximately 150 of the analyzed circuits exclusively provide indication and do not interface with any protection
- system, and therefore, would not be subject to isolation specifications of IEEE-279-1971; (2) approximately 8 of the total circuits analyzed are those which have Class 1E and non-Class lE interface and a fault or failure in the non-Class 1E device would cause the associated Class lE component to fail safe, consistent with IEEE-279-1971; and (3) the remaining approximately 100 circuits have dual-element thermocouples that provide backup protection and are not credited in the plant safety analysis, therefore would not need isolation devices to meet IEEE-279-1971 requirements.
Based on the above clarification of the nature of the circuits that your staff has analyzed, the NRR technical staff suggested that PP8L provide to the Commission a document that would summarize the effort that was reflected in the two submittals and provide more details on items (l)-(3) above for staff review.
The staff will then evaluate that information relative to plant compliance with IEEE-279-1971, as required by 10 CFR 50.55(a),
and will develop a finding to be documented in a safety evaluation.
Your staff indicated that it couid provide 'such a submittal by the end of Nay 1997.
HIIC RI.E CEHYBI COPE I
97052i027% 9705i5 PDR ADQCK 05000387 P
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Byram Nay 15, 1997 It would be appreciated if you could accelerate this submittal and ensure that it contains sufficient technical detail to facilitate a staff safety finding on this issue, which remains one of the oldest outstanding licensing issues with the Commission.
Sincerely, Docket Nos. 50-387/388 cc:
See next page Chester
- Poslusny, S nior Project Manager Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
R.
Byram May 15, 1997 It would be appreciated if you could accelerate this submittal and ensure that it contains sufficient technical detail to facilitate a staff safety finding on this issue, which remains one of the oldest outstanding licensing issues with the Commission.
Sincerely, Docket Nos.
50-387/388 cc:
See next page DISTRIBUTION
+Docket File PUBLIC PDI-2 Reading SVarga JStolz CPoslusny MO'rien OGC ACRS
- MModes, RGN-I
/s/
Chester
- Poslusny, Senior Project Manager Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation OFFICE NAME DATE PDI-2 PM CPoslusny:rb 5 A/97 PD-IkDI-2 D
JStolz 97 OFFICIAL RECORD COPY DOCUMENT NAME:
SU90541.GEN
pl SAI
Hr. Robert G.
Byram Pennsylvania Power
& Light Company t
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 Hr. J.
H. Kenny Licensing Group Supervisor Pennsylvania Power
& Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Hr. K. Jenison Senior Resident Inspector U. S. Nuclear Regulatory Commission
,P.O.
Box 35 Berwick, Pennsylvania 18603-0035 Hr.; William P. Dornsife, Director Bureau of Radiation Protection Pennsylvania Department of Environmental Resources P. 0.
Box 8469 Harrisburg, Pennsylvania 17105-8469 Hr. 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 Hr. George Kuczynski Plant Hanager Susquehanna Steam Electric Station Pennsylvania Power and Light Company Box 467 Berwick, Pennsylvania 18603 Hr. 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