ML18079A880
| ML18079A880 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/28/1979 |
| From: | Mittl R Public Service Enterprise Group |
| To: | Parr O Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7908300520 | |
| Download: ML18079A880 (3) | |
Text
. 0 PS~G*
Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201/430-7000 August 28, 1979 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Attention:
Mr. Olan D. Parr, Chief Light Water Reactors Branch 3 Division of Project Management Gentlemen:
RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION NO. 2 UNIT SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-311 Public Service Electric and Gas Company hereby transmits 60 copies of its response to your request for additional in-formation numbered 3.13, concerning fuel assembly grid strap damage.
The information contained herein will be incorpo-rated into the Salem FSAR in an amendment to our application.
Should you have any questions, please do not hesitate to contact us.
Encl.
CF08 The Energy People Very truly yours, f { lllt&f,4, R. L. Mittl General Manager -
Licensing and Environment Engineering and Construction 95-0942
QUES'l'ION 3.13 During a recent refueling outage at a W plant (Salem Unit 1),
strap damage was observed ori a number of fuel spacer grids.
It is not known whether the damage occurred during the initial core loading or during the refueling withdrawal.
What assurances can you provide that the same type of grid damage will not be experienced at Salem Unit 2?
ANSWER PSE&G has reviewed Salem Unit 2 initial fuel loading operations in light of Salem Unit 1 refueling experience.
There are some significant differences between initial fuel loadi~g and refueling operations that preclude the occurrence of grid strap damage that has been experienced on Salem Unit 1:
- 1.
During initial fuel loading, only the* reactor vessel is filled with water.
The fuel handling operation is performed
- in an essentially 11 dry 11 condition rather than working in 30 to 40 feet of water during refueling~
- 2.
Fuel for the initial core is unirradiated; therefore, the fuel is 11 straight 11
- Assembly interface interactions are minimal.
- 3.
For the initial core, the fuel is slab loaded versus a one-to-one interchange; therefore, the numbcir of fuel move-ments and any potential interferences are minimal in comparison.
- 4.
The Salem refueling team has gained considerable experience as a result of Salem Unit 1 refueling.
SNGS-FSAR Units 1 & 2 Q3.13-l Amendment 45
l_
Westinghouse has reviewed the Salem refueling experience and issued an interim set of guidelines to its customers.
Salem personnel are familiar with these recommendations, which were derived, in part, from Salem experience.
Initial fuel loading procedures have been revised to incorporate close observance of the Toad.c.ell readout and stopping crane motion on predetermined load differentials during fuel assembly movement in the coreo SNGS-FSAR Units 1 & 2 Q3.13-2 Amendment 45