ML20151V912

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Submits Supplemental Info Re Safety Considerations for Util 880708 Proposed Changes to Tech Specs Involving Veritrak/Tobar Transmitter Replacement
ML20151V912
Person / Time
Site: Seabrook 
Issue date: 08/08/1988
From: George Thomas
PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NYN-88109, NUDOCS 8808230058
Download: ML20151V912 (2)


Text

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Q George S. Thomas "

t v ce PreddenLNuclear Production i

NYN-881091 Put2C Service of New Hampshire E

N:w Hampshire Yanks Division United Status Nuclear Regulatory Commission

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Washington, DC 205 s Attention:

Document Control Desk

References:

a) Facility Operating License NPF-56, Docket No. 50-443 b) PSNH letter NYN-88091 dated July 8, 1988, "Request for License Amendment,";G. S. Thomas to USNRC c)

PSNH letter NYN-88075 dated May 27, 1988

'Veritrak/Tobar Transmitter Replacement.' G. S. Thomas to USNRC

Subject:

Request for License Amendment (Roremount Transmitters).

Supplemental Information Gentlemen Reference (b) submitted proposed changen to the Seabrook Station Technical Specifications resulting froc: the replacement of Veritrak/Tobar transmitters with Rosemount transmitters as described in Reference (c).

In order to clarify tne initial submittal [ Reference (b)). New Hampshire Yankee (NHY) provides the following supplemental information regarding safety considerations for the proposed changes:

New Hampshire Yankee has reviewed th iroposed change utilizing the criteria specified in 10CFR50.92 and nas determined that the proposed changes will not 1.

Involve a significant increase in the probability or consequences of an accident previously evaluated.

The Rosemount transmitters are environmentally and seisetically qualified for their locations inside the Containment.

The replete'nent Rosemount transmitters have been used in operating plents and have.an excellent history of performing within stated accuracy limits.

The protection system setpoints were developed by calculating the instrument charinel' statistical allowance using the Westinghouse o'

methodology, and applying this to the FfAR Chapter 15 accident analy/.s limit. This information has previously been submitted to d

the NRC Staff via Reference (c).

boo EGO 8230058 880808 4 1 PDR Al)DCN 05000443 P

PDC 1 0 I

,y P.O. Box 300. Seabrook. NH 03874. Telephone (G03) 474 9574 ;

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V dbitcdStctcsNuclGarR:gulctoryCommission August 8, 1988 Attention:

Document Control Desk Page 2 2.

Create the possibility of a new or different kind of accident from any accident previously evaluated.

The replacement Rosemount transmitters are identical in type to the Veritrak transmitters except for the pressuriser pressure transmitter.

In this application, the Rosemount tranrraitter is a gauge type preasure transmitter while the Veritrak j

transmitter is an absolute type.

The effect of normal variations in atmospheric pressure have been considered in the instrument setpoint calculation.

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Involve a nignificant reduction in a margin of safety.

When compared to the calculated values, the steam generator low-low level setpoint is conservative. The margin between the total allowance and the channel ntatistical allowance is increased for the Rosemount transmitter.

The effect of the Rosemount transmitters on the overtemperature delta T trip was evaluated and determined to be acceptable since it resulted in an increase of 0.6 percent of span in the margin between the total allowance and the channel statistical allevance.

When compared to the calculated values, the low pressu.rizer pressure reactor trip setpoint, low pressurizer pressure aafety injection setpoint, and the high pressurizer pressure reactor trip aetpoint are conservative.

The margin between the total allowance and the channel

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statistical allowance is approximately (within 0.04 percept of span) the same for the Rosemount and Veritrak transmitters.

Based on the considerations contained herein, it in concluded that there is reasonable assurance that operation of Seabrook Station, consistent with the proposed Technical Specifications, will not endanger the health and st.fety of the public.

Should you have any questions regarding this supplemental information, l

please contact Mr. Richard R. Belanger at (603) 474-9574, extension 4048.

Very truly yours,

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-2 Geor S. Thomas cca Mr. Wfiliam T. Enssell Regional Adrainistrator Region I United States Nuclear Regelatory Commission 425 Allendale Avenue King of Prussia., PA 19406 Mr. Victor Nerses. Project Manager Project Directoratti I-3 Division of Reactor Trojects United States Nuclear Regulatory Cocaission i

Vashington, DC 29555 Mr. Antone C. Cerne NRC Senior Reuident Inspector B

Seabrook Statl.on Seabrook, NH 03874 w

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