ML18086B477
| ML18086B477 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 04/20/1982 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Uderitz R Public Service Enterprise Group |
| References | |
| IEB-80-04, IEB-80-4, NUDOCS 8205110668 | |
| Download: ML18086B477 (4) | |
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Docket Nos. 50-272 50-311 Mr. Richard A. Uderitz Vice President - Nuclear Public Service Electric and Mail Code Tl 5A P. 0. Box 570 Newark, New Jersey 07101
Dear Mr. Uderitz:
- >.* e Gas Co.
We are currently reviewing your response to IE Bulletin 80-04 as provided in your letter dated Apri1 17, 1980.
In order for us to complete this review we request that you provide additional information, as described in the enclosure to this letter,within thirty days of receipt of this letter.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore OMB clearance is not required under P.L.96-511.
Enclosure:
As stated cc w/encl:
See next page Sincerely, l5l Steven A. Varga, Chief Operating Reactors Branch #1 Division of Licensing s2os11066a-s2o42o ___ -- *-----
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NRC FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY USGPO: 1981-335-960
Mr. R. A. Uderitz Public Service Electric and Gas Company cc:
Mark J. Wetterhahn, Esquire Conner and Wetterhahn Suite 1050 1747 Pennsylvania Avenue, NW Washington, D. C.
20006 Richard Fryling, Jr., Esquire Assistant General Solicitor Public Service Electric and Gas Company Mail Code TSE - P.O. Box 570 Newark, New Jersey 07101 Gene Fisher, Bureau of Chief Bureau of Radiation Protection 380 Scotch Road Trenton, New Jersey 08628 Mr. R. L. Mittl, General Manager Corporate Quality Assurance Public Service Electric and Gas Company Mail Code T16D - P.O. Box 570 Newark, New Jersey 07101 Mr. Henry J. Midura, Manager Salem Operations Public Service Electric and Gas Company P. o. Box 168 Hancocks Bridge, New Jersey 08038 Salem Free Library 112 West Broadway "
Salem, New Jersey 08079 Leif J. Norrholm, Resident Inspector Salem Nuclear Generating Station
- u. S. Nuclear Regulatory Commission Drawer I Hancocks Bridge, New Jersey 08038 Mr. Edwin A. Liden, Manager -
Nuclear Licensing Public Service Electric and Gas Company Mail Code Tl6D - P.O. Box 570 Newark, New Jersey 07101 Ronald c. Haynes Regional Administrator - Region I U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406
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REQUEST FOR ADDITIONAL INFORMATION RELATED TO fE BULLETIN 80-04 ENCLOSURE e
Evaluation of the information contained in the April 17, 1980 [l) from the Public Service Electric and Gas Company (PSBiiG) to the Nuclear Regulatory Ccmmission (N.RC) relating to IE Bulletin 80-04, *Analyais of a PWR Main Steam Line Break with Continued Peedwater Addition,* revealed an item of concern.
Additional information relating to this cor.cern im ~ed before ~ final evalu-ation can be made regarding the potential for exceeding containment design pressure.
This concern and the additional inforaation needed to resolve this concern are identified in this Request for.Additional Information.
- IE Bulletin 80-04 directs the Licensee to review containment pressure response to a main steam line break (MSLB) accident to determine the impact of runout flow from the auxiliary feedwater (AFW) system and other energy sources.
PSEiiG's response concerning the MSLB analysis for Salem Nuclear Generating Station Units 1 and 2 atated in PSAR Question 5.106 [2] that the APW system is
~manually realigned by the operator after 10 minutes.
PSE&G's response is not sufficient to enable F.RC to complete the evaluation of the potential for exceeding containment design pressure. The analysis takes credit for operator action to identify the affected steam generator and isolate Al"W flow to that generator within 10 minutes after the start of the accident.
In light of atudies performed on operator response.. to stressful situations,, this time may be unrealistic.
A review of !'SAR Question 5.89 (2) reveals that, in the majority of the MSLB scenarios analyzed, the peak containment pressure occurs after the A!'W system is isolated at the lD-llinute point.
...,,.. *~--
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,I If operator action is delayed or is incorrect,..Sditional feedvater will
, r be added to the affected steam generator mo that the containment.. y exceed its design pressure.
BEQUEST The following information concerning your analy*is of containment pressure response to a MSLB with continued feedwater addition i* required:
- 1. Provide the actions required to be performed by the operator to prevent exceeding containment design pressure.
Provide justification for the time at which credit is taken for operator action.
- 2. Provide the time after the start of a llSLB when containment design pressure will be exceeded if no operator action is taken to terminate the accident.
Provide the magnitude of the peak pressure and the time at which the peak occurs.
- 1.
PSE&G Lette~ to HBC
Subject:
.Response to IE Bulletin 80-04 April 17, 1980
- 2. Salem Nuclear Generating Station Units 1 and 2 Final Safety Analysis Report Questions 5.89 and 5.106