ML18092A267
| ML18092A267 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/07/1984 |
| From: | Liden E Public Service Enterprise Group |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8409110004 | |
| Download: ML18092A267 (3) | |
Text
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Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department September 7, 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:
ADDITIONAL INFORMATION ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRICAL EQUIPMENT SALEM GENERATING STATION UNITS l AND 2 DOCKET NOS. 50-272 AND 50-311 In its letter, dated August 13, 1984, the NRC requested additional information to complete its review of the environmental qualification of safety-related electrical equipment.
PSE&G's response to those items follows:
- 1.
Submit all justifications for continued operation (JCO's) currently being relied on.
For Salem Unit 1, all electrical equipment previously relying on JCO's has been replaced with qualified equipment.
On Unit 2, all qualified equipment has been installed, with the exception of Limitorque motorized valve actuators.
These actuators will either be replaced or qualified by the second refueling outage, scheduled for January 1985.
The Energy People 95-2168 (25M) 6-84
- -~
Mr. Steven 9/7/84 A JCO for Limitorque motorized valve actuators was submitted by a letter dated November 26, 1980, and revised by a letter dated February 3, 1983.
This JCO is still applicable for Unit 2.
No significant degradation of any safety function or misleading information to the operator as a result of failure of the equipment under the accident environment resulting from a design basis event will qccur.
- 2.
Confirm the methodology used to identify equipment within the scope of 10CFR50.49 (b) (2).
The methodology used to identify the equipment within the scope of 10CFR50.49 (b) (2) was confirmed to be in accordance with the NRC requirements.
These results have previously been submitted to the NRC as Enclosure 3 to our letter of June 8, 1984.
- 3.
Confirm that all design basis events that could potentially result in a harsh environment were addressed in identifying equipment within the scope of 10CFR50.49 (b) (1).
The environmental effects resulting from all postulated design-basis accidents documents in Chapter 15 of the Salem Generating Station Updated Final Safety Analysis Report (UFSAR), including the Loss-of Coolant Accident (LOCA) and the Steam Line Break Accident (SLBA) inside containment, were considered in the identification of safety-related electrical equipment which was to be environmentally qualified.
Therefore, all design-basis events were considered in the identification of electrical equipment within the scope of Paragraph ( b) ( 1) of 10CFR50.4 9.
These results have previously been submitted to the NRC in our letter of June 8, 1984.
- 4.
Confirm that the electrical equipment within the scope of 10CFR50.49 (b) (3) is all Regulatory Guide 1.97 category 1 and 2 equipment or that justification has been provided for any such equipment not included in the environmental qualification program.
Mr. Steven 9/7/84 The electrical equipment within the scope of 10CFRS0.49 (b)
(3) that is Regulatory Guide 1.97 category 1 and 2 equipment has been identified and submitted to the NRC in our letters dated September 21, 1983 and August 9, 1984.
For the equipment within the scope of 10CFRS0.49 (b) (3) that has not been qualified as required by Regulatory Guide 1.97, justifications were submitted to the NRC in those letters.
Should you have any questions, please contact us.
C Mr. Donald c. Fischer Licensing Project Manager Mr. James Linville Senior Resident Inspector E. A. Liden Manager -
Nuclear Licensing and Regulation