ML18086A279

Forwards Request for Addl Info Re Control Sys Failures.Util Must Provide Assurance That DBE Analyses Adequately Found More Fundamental Failures

ML18086A279
Person / Time
Site:	Salem
Issue date:	04/16/1981
From:	Tedesco R Office of Nuclear Reactor Regulation
To:	Mittl R Public Service Enterprise Group
References
NUDOCS 8104230913
Download: ML18086A279 (5)

Text

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APR 1 6 1981 Docket No.:

50-311 Mr. R. L. Mittl, General Manager Licensing & Environment Engineering & Construction Department Public Service Electric & Gas Company 80 Park Plaza Newark, New Jersey 07101

SUBJECT:

• • CONTROL SYSTEM FAILURES - SALEM NUCLEAR GENERATING*ST~TION, UNIT 2 The analyses reported in Chapter 15 of the FSAR are intended to demonstrate the adequacy of safety systems in mitigating anticipated operational occurrerces and accidents.

Based on the conservative assumptions made in defining these "design bases" events and the detailed review of the analyses by the staff, it is likely that they adequately bound the consequences of single control system failures.

To provide assurance that the design basis event analyses adequately bound other more fundamental credible failures, you are requested to provide the information delineated in the enclosure within 30 days of receipt of this letter. Should you have any questions, contact our Licensing Project Manager, Gary Me.y.e'.r.

Enclosure:

As stated cc: See next page.

DISTRIBUTION:

SEE NEXT PAGE.

Robert L. Tedesco, Assistant Director

. *for Licensing Division of Licensing c;;~R£,FORM 3 lBlle>/SOlNRCMe> 24 o OFFIC-iAL. RECORD COPY QUSGP0:1980-329-824

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, 0. C, 20555 *

• Docket No. : 50-311 Mr. R. L. Mittl, General Manager

. Licensing & Envi ronmenf APR '- 6 1_9 8\\

Engineering & Construction Department

• Public Service Electric & Gas Company 80 Park Plaza Newark, New Jersey 07101

SUBJECT:

CONTROL.SYSTEM. FAILURES - SALEM NUCLEAR GENERATING STATION, UNIT 2 The analyses reported in Chapter 15 of the FSAR are intended to demonstrate the adequacy of safety systems in mitigating anticipated operational occurrences and accidents.

Based on the conservative assumptions made in defining these "design bases...

events and the detailed review of the analyses by the staff, it is likely that they adequately bound the consequences of single control system failures.

To provide assurance that the design basis event analyses adequately bound

other more fundamental credible failures, you are requested to provide the information delineated in the enclosure within 30 days of receipt of this letter. Should you have any questions, contact our Licensing Project Manager,*

Gary Meyer.

Enclosure:

As stated cc:: See next page.,

Sincerely, Robert L. Tedesco, Assistant Director for Licensing Division of Licensing I

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A Mf~ R. L. Mittl, General Manager licensing & Environment.

Engineering &.Construction Department Public Service Electric & Gas Company BO Park Plaza Newark, New Jersey 07101 cc:

Richard Fryling, Jr., Esq.

Assistant General Counsel Public Service Electric & Gas Company 80 Park Plaza Newark, New Jersey 07101 Nark Wetterhahn, Esq.

Conner, Moore & Caber

. Suite l 050 1747 Pennsylvania Avenue, N. w.

Washington, o. c.

20006 Mr. Leif J. Norrholm c/o u. s. Nuclear Regulatory Commission Drawer I Hancocks Bridge, New Jersey 08038

• --------"----"'--------*~--...--**~~------~--~-

ENCLOSURE REQUEST FOR ADDITIONAL *INFORMATION (1)

Identify those control systems whose *failure or malfunction could

• seriously impact plant safety.

(2)

• Indicate which, if any, of the. control systems identified in (l) receive power from common power sources.* The power sources considered should include all power sources whose failure or malfunction could lead to failure or malfunction of more than one control system* af!d should extend to the effects of cascading power losses due to the failure of higher level d.istribution panels and load centers.

(3)

Indicate which; if any, of the control systems identified in (1) receive input signals from common sensors.

The sensors considered should include, but should not necessarily be limited to, common hydraulic headers or impulse lines feeding pressure, temperature, level or other signals to two or more control systems.

(4)

• Provide justification that any simultaneous malfunctions of the control

• systems identified in (2) and (3) resulting from failures or mal-functions of the applicable common power source or sensor are bounded by the. analyses in Chapter 15. and wou}d not require *action or response beyond the capability Qf operators or safety systems.

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