ML20198F086
| ML20198F086 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 11/08/1985 |
| From: | Mittl R Public Service Enterprise Group |
| To: | Butler W Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8511140264 | |
| Download: ML20198F086 (2) | |
Text
-
E Pubkc Sertice Electnc and Gas Company 80 Park Plaza, Newark, NJ 07101/ 201430-8217 MAILING ADDRESS / P.O. Box 570, Newark, NJ 07101 Robert L. Mitti General Manager Nuclear Assurance and Regulation November 8, 1985 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20814 Attention:
Mr. Walter Butler, Chief Licensing Branch 2 Division of Licensing Gentlemen:
HOPE CREEK SER SECTION 7.6.2.1 " ISOLATION OF LOW-PRESSURE SYSTEM FROM THE HIGH-PRESSURE REACTOR COOLANT SYSTEM" HOPE CREEK GENERATING STATION DOCKET NO. 50-354 The purpose of this correspondence is to formalize the results of the discussion of November 6, 1985 between Mr.
B.A.
Preston of Public Service Electric & Gas Company (PSE&G) and Mr.
D.H.
Wagner of the NRC concerning the subject topic.
In this regard, the staff has indicated that it finds the design of the high pressure / low-pressure boundary device associated with the alternate remote shutdown system (Residual Heat Removal Valve Ell-HV-F015A) acceptable, but is concerned that an inadvertent manual actuation could occur and cause a breach of the high pressure / low-pressure boundary.
With respect to the above, PSE&G shall implement the following actions in order to address the staff's concerns.
1.
The labeling for the alternate remote shutdown system RHR valve Ell-HV-FOl5A will be appropriately changed to reflect a warning that inadvertent actuation could cause overpressurization of the RHR piping.
This labeling will be designed, fabricated, and located in accordance with good human factors engineering principles.
\\
2)%
8511140264 851100 I 6 PDR ADOCK 05000354 E
PDR l
The Energy People 954312 (3Y! 4 84
~
y-a.
j,.
Director of Nuclear-2 11/8/85 Reactor Regulation" l2i Prior to full' power operation, PSE&G will install a clow pressure' permissive indication (e.g., blue light),
so the operator at the MCC panel'will know when RHR valve F015A can be opened without causing a breach of the reactor pressure boundary because of overpressuri-zation of the RHR piping.
In the' event there are any questions in this regard, do not hesitate to contact us.
Very truly yours,
.b.
[j c-
-s
.C D.H. Wagner USNRC Licensing Project Manager A.R.
Blough USNRC Senior Resident Inspector L