ML18079A517
| ML18079A517 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/01/1979 |
| From: | Parr O Office of Nuclear Reactor Regulation |
| To: | Mittl R Public Service Enterprise Group |
| References | |
| NUDOCS 7907110281 | |
| Download: ML18079A517 (2) | |
Text
Distribution:
Boyd
- s. Hanauer OELD D. Ross J. Knight IE (3)
D. Vassallo R. Tedesco Docket Fil NRC PDR Local PDR L\\~R #3 Fi 1 e F.
t~i 11 i ams R. DeYourig BCC: JBuchanan Docket Ho. 50-311
- 0. Parr
- v. Moore TAbernathy A. Dromerick
. M. Rushbrook
. R. Mattson Mro R. L. Mittl, General Manager Licensing and Environment l~.
M.
R.
Engineering and. Construction Department
- Public Service Electric and Gas Company 80 Park.Place
.!.. lewark 9 Ne\\'J Jersey 07101
Dear Mr. Mittl:
Kreger ACRS ( 16)
Ernst Denise JUN 011911
SUBJECT:
REQUEST FOR ADOITION.l\\L INFORMATION - INSTRUMENTATION QUALIFICATION (Sl}LEM NUCLEAR GENERATING STATION, UNIT NO. 2),
l4e have completed our review of the ~*Jestinghouse Electric Corporation's report entitled, "Qualification Testing of Barton Pressure and Differential Pressure Transmitters 11 (Proprietary).\\'Jhich addresses the Barton transmitters used in your application and find that additional fnformation is required.,The results of the qualification tests.~ as delineated in the above cited report, s.hol/; that the Barton transmitters, with the exception of the Barton 763 narrow range pressure transmitter, met specifications for the initiation of the protection system actions.
flo~~ever, they did not meet specified accuracies for manual cpntrol during post-accident cooling. Therefore, v1e require that you s'pecify the schedule for submittal of additional j~stification to demonstrate that these transmitters \\'iill meet all of their perforrnance requirements including furictions*
needed d.uring a hypothesized post-accident cooling period.
In the interim i'le require that you describe prior to licensing (1) the alternate qualified instruments and procedures for manually controlling reactor conditions during long-term post-accident cooling, and (2) the bases for acceptability of the measured error in the Barton 763 narrovJ range pressure transmitter for initiating short term protection system actions. Moreover, if the calculated containment environment tempel'.'atures exceed those values specified for sequential tests, '<<le require tbat you shovJ that the protective enclosures around transmitters i<1ould prevent transmitter temperatures from exceeding values measured in the tests.
Please provide a schedule tt1ithin 14 days for the submittal of this information.
Ol'FICS~
cc:
RIRMAMll~
DATI:..
'7 9 07 1102 ~(
Sincerely,
, OrJ:gi~J Slgn£:Q b}!
. o.. O.. P.arc...,,,:.""......
- Olan D.
Parr~ Chief Light l~ater Reactors Branch. No. 3 iv1s on 0( 11roJe.c
- 7anagement
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- U.S. QOVl!:R~t.t!;NT PRINTING Ofl'prlCIM I 071.. 201.. 7fSI
Mr. R. L. Mittl, General Manager cc:
Richard Fryling, Jr., Esq.
Assistant General Counsel Public Service Electric & Gas Company 80 Park Pl ace Newark, New Jersey 07100 Mark Wetterhahn, Esq.
Conner, Moore & Cob~r 1747 Pennsylvania Avenue, N.W.
Suite 1050 Washington, D.C.
20006 Mr. Leif J. r*:orrho l m.
U. S. Nuclear Regulatory Commission Region I Dra\\'1er I Hancocks Bridge, New Jersey 08038 JUN 0 1 1979