ML18092A190
| ML18092A190 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/24/1984 |
| From: | Liden E Public Service Enterprise Group |
| To: | Varga S Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18092A191 | List: |
| References | |
| TASK-2.F.2, TASK-TM NUDOCS 8406010281 | |
| Download: ML18092A190 (3) | |
Text
PS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department May 24, 1984
- u. s. Nuclear Regulatory Commission Off ice of Nuclear Reactor Regulation Division of Licensing Washington, D. C.
20555 Attention:
Mr. Steven A. Varga, Chief Operating Reactors Branch, No. 1
Dear Mr. Varga:
INADEQUATE CORE COOLING INSTRUMENTATION TMI ITEM II.F.2 SALEM GENERATING STATION UNITS NO. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 The following information is provided as supplement to our letter dated April 4, 1984.
This information involves commitments made by PSE&G in telephone conversations with the NRC reviewers:
Messers. T. Huang, L. Philips, and H. Lee of ONRR, on May 4 and 11, 1984.
- a.
Validation of Emergency Operating Procedures (EOPs) incorporating RVLTS -
The EOP Critical Function Status Trees (CFST) that include RVLIS are written but can not be validated on the Salem Simulator because RVLIS is not yet incorporated in the simulator.
A walk-through on the CFSTs referencing RVLIS will be completed by June 8, 1984 as re-quired by the NRC.
However, due to the training and final review/approval process involved, implementation will not take place until the period between November, 1984 and March, 1985.
1--0406oio2a 1 *040:;24 _________ 1 PDR ADOCK 05000272
. 1
- p PDR The Energy People IV
~oO
,\\,
95-2168 (75M) 12-83...J
Mr. Steven 5/24/84
- b.
Technical Specification incorporating RVLIS -
As explained in PSE&G letter dated April 4, 1984, the Technical Specification dealing with ICCI is being prepared with other NUREG 0737 Technical Specifications.
The schedule for submittal of NUREG 0737 Technical Specifications, as negotiated with the NRC Project Manager, is currently June/July 1984.
As requested by the NRC ICCI reviewers, PSE&G will expedite the Technical Specification preparation to submit the proposed RVLIS Technical Specification by mid-June, 1984, for NRC review.
The Technical Specification, as negotiated with the NRC, will then be submitted for license change.
- c.
Qualified Core Exit Thermocouple (CET) System -
PSE&G will either replace the existing reference junction box (RJB) with a qualified component or investigate the possibility of replacing CET in-containment cable with MI cable.
The latter scheme will require the removal of the RJB to out-side containment.
In either case, due to the long lead time of purchase items involved, the earliest installation date will be the next (1986) refueling outage for Unit 1 and the 1986 refueling outage for Unit 2.
A further description of the CET upgrade and the schedule will be provided in early June, 1984.
- d.
Qualified Backup Display -
PSE&G is presently contacting the manufacturers to develop a qualified backup display package.
Due to long lead time involved, the earliest implementation date will be as indicated in paragraph c above.
- e.
Test and calibration results of Unit 2 RVLIS are attached for your review and use.
- f.
Status of Installation of Kits No. 2 and 3 of RVLIS -
Kit No. 2 was received from Westinghouse.
Kit No. 3, according to Westinghouse, will be sent to PSE&G in June.
The present schedule calls for installation of these kits in Unit No. 1 during the current refueling outage and Unit No. 2 during the 1985 refueling outage.
't Mr. Steven 5/24/84
- g.
Request for NRC approval of plant specific installation will follow the completion of the above items.
Attachments Sincerely, E. A. Liden Manager -
Nuclear Licensing and Regulation C
Mr. Donald c. Fischer Licensing Project Manager Mr. James Linville Senior Resident Inspector l