ML20094N764

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Forwards Draft FSAR Pages in Response to NRC 820825 Request for Addl Info Re Instrument Setpoint Methodology for Reactor Protection Sys & ESF Instrumentation Setpoints.Info Should Close SER Confirmatory Issue 26
ML20094N764
Person / Time
Site: Limerick  
Issue date: 08/10/1984
From: Kemper J
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To: Schwencer A
Office of Nuclear Reactor Regulation
References
OL, NUDOCS 8408160379
Download: ML20094N764 (3)


Text

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PHILADELPHIA ELECTRIC COMPANY '

2301 MARKET STREET P.O. BOX 8699 PHILADELPHI A. PA.19101 JOHN S. KEMPER

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AUG 101984 Mr. A. Schwencer, Chief Docket Nos.:

50-352 Licensing Branch No. 2 50-353 U. S. Nuclear Regulatory Conmission Washington, D.C. 20555

Subject:

Limerick Generating Station, Units 1 and 2 Request for Additional Information Instrurentation Setpoint Methodology

Reference:

1)

A. Schwencer to E. G. Bauer, Jr., dated August 25, 1982.

File:

GOVT 1-1 (NRC)

Dear Mr. Schwencer:

The reference 1 letter requested additional information on the methodology used to establish Limerick's Reactor Protection System (RPS) and Engineered Safety Feature (ESF) instrumentation setpoints.

This information is provided in the attached draft FSAR pages that will be incorporated into the FSAR via revision 36 which will be submitted in Septenber 1984.

We believe that this information closes SER confinnatory issue #26.

Sincerely,

& Of G Y'

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DFC/gra/08068405 cc: See Attached Service List hM[

8408160379 840810 PDR ADOCK 05000352 E

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cc: Judge Lawrence Brenner' (w/ enclosure)

Judge Richard F. Cole (w/ enclosure)

Troy _B.

Conner, Jr., Esq..

(w/ enclosure)

LAnn P.- Hodgdon, Esq..

- (w/ enclosure)

-Mr. Frank'R. Romano.

(w/ enclosure).

Mr. Robert L. Anthony (w/ enclosure)...

-Charles W. Elliot, Esq.--

l(w/ enclosure)'

Zori G. Ferkin, Esq.

(w/ enclosure).

Mr. Thomas Gerusky-(w/ enclosure)

Director, Penna. Emergency.

'(w/ enclosure)

Management Agency Angus R. Love, Esq.

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David Wersan, Esq.

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Robert J. Sugarman,~Esq.

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. Spence W.' Perry, Esq.

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Jay M. Gutierrez, Esq.

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Atomic Safety & Licensing (w/enclo are)

Appeal Board.

Atomic Safety & Licensing (w/ enclosure)

Board Panel Docket & Service Section (w/ enclosure)

' Martha W. Bush, Esq.

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Judge Peter A. Morris (w/ enclosure).

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DRAET QUESTION 421.32 (7.1, 7.3)

Provide a detailed discussion _on the methodology used to establish the trip setpoint and allowable value for each Reactor Protection System-(RPS) and Engineered Safety Feature (ESF) channel.

Include the following Information:

a)

The trip value asstmed in the FSAR Chapter 15 analyses.

b)

The margin between the contined channel error allowance and the total channel error allowance asstsned in accident

analysis, c)-

The values assigned to each component of the combined channel error allowance (e.g., process measurement accuracy, suiisor calibration accuracy, sensor drift, sensor environmental allowances, _ instrtsnent rack drift) the basis for these values, and the methodology used to stm these errors.

d)

The degree of conformance to the guidance provided in Regulatory Guide 1.105 Positions C.1 thru C.6.

DRAET

RESPONSE

These Setpoint Methodology concerns will be addressed by the Action Plan submitted in the reference 421.32-1 letter.

Limerick endorses the work scope and schedule proposed by the Actton Plan, which was accepted by the NRC staff in the reference 421.32-2 letter.

References 421.32-1 Letter, J. F. Carolan (Chairman, LRG Instrtmentation Setpoint Methodology Group) to T. M. tbvak (Assistant Director for Licensing, Division of Licensing), " Action Plan to Answer the NRC Staff concerns on Setpoint Methodology for General Electric Supplied Protection System Instrtsnentation,"

June 29, 1984.

421.32-2 Letter, B. J. Youngblood (Chief, Licensing Branch No. 1, Division of Licensing) to J. F. Carolan, " Acceptance of Action Plan to Answer NRC Staff Concerns on Setpoint Methodology for General Electric Supplied Protection System Instrtsnentation," July 23, 1984.

DFC/gra/08068407 i

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