ML17158B919

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Forwards Request for Addl Info Re Electrical Isolation for Licensee Facility
ML17158B919
Person / Time
Site: Susquehanna  Talen Energy icon.png
Issue date: 01/15/1997
From: Poslusny C
NRC (Affiliation Not Assigned)
To: Byram R
PENNSYLVANIA POWER & LIGHT CO.
References
TAC-M90541, TAC-M90542, NUDOCS 9701230269
Download: ML17158B919 (5)


Text

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Mr. Robert G.

Byram Senior Vice President-Nuclear Pennsylvania Power and Light Company 2 North Ninth Street Allentown, PA 18101

~January 15, 1

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SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION (RAI) CONCERNING ELECTRICAL ISOLATION FOR SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1

AND 2 (TAC NOS.

M90541 AND M90542)

Dear Mr. Byram:

The staff has completed a preliminary review of Pennsylvania Power

& Light Company's (PP8L) submittal dated November 27, 1996 and has developed a set of questions as listed in the enclosed RAI.

Please provide the requested information not later than February 5,

1997.

If you have any questions concerning this RAI, please contact me at 301-415-1402.

Sincerely,

/s/

Chester

Poslusny, Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket Nos.

50-387/388

Enclosure:

cc w/encl:

RAI

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& 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 8 Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. K. Jenison 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

ON

'S SUB ITT L DATED OVE BE 27 1996 1.0 Appendix L includes cables that connect:

g device to g device with isolation, g device to blank device with isolation, 9 device to N/A device with contact to coil isolation, and g device to non-IE device with N/A isolation Please explain these interfaces and their isolation function.

2.0 Is there any single random failure in this analysis which should meet the "second random failure" requirement of paragraph 4.7.3, "Single Random Failure" of IEEE 279?

3.0 endices A and E

4.0 How can the closure of residual heat removal system (RHR) valves, reactor water cleanup system (RWCU) valve and reactor core isolation cooling (RCIC) valve be categorized as "fail in the safe direction?"

endix 8

5.0 Non-IE pressure and speed indication of high pressure core injection system (HPCI) is used in station blackout Emergency Operating Procedure.

Justify its categorization as "no failure mode for station blackout."

endix D

Indicating instrument is CISH-Ell-1R001A.

What does TRS-Ell-1R601 indicate?

6.0 endix E

Pages 134a and 134b - Non-class IE fuse in the Non-IE recorder can not be credited to open before the class IE circuit breaker and also this fuse can not be relied upon to protect other connected IE or g loads from a fault in the non-IE recorder.

7.0 endices F

G and H

a)

Will the closure of RWCU system primary containment isolation (PCI) valves (number of valves were not identified) indirectly cause a

reactor trip, initiate actuation of safety systems, or affect plant operation?

How can the closure of these valves be categorized as "fail in safe direction?"

b)

Ooes the neutron flux scram for loss of intermediate range monitor (IRM) selector switch and average power range monitor (APRN) trip cause half scram or a full scram?

Justify the "single failure" and "fail in safe direction" categorization.

8.0 Appendices J and K contents stated on page 8 (4th paragraph of section B) are different from those included in the submittal.

Correct appendices should be provided.

ENCLOSURE

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