ML18087A928
| ML18087A928 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/16/1983 |
| From: | Liden E Public Service Enterprise Group |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| NFG-83-082, NFG-83-82, NUDOCS 8305230094 | |
| Download: ML18087A928 (3) | |
Text
NFG 83-082 Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department Ref.
License Amendment No. 19 License Amendment No. 20 May 16, 1983 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20014 Attention:
Mr. Steven A. Varga, Chief Operating Reactors Branch #1 Division of Licensing
Dear Mr. Varga:
REVISION TO CYCLE 2 RELOAD ANALYSIS SALEM GENERATING STATION, UNIT NO. 2 DOCKET NO. 50-311 Salem Unit No. 2 has concluded its first.cycle of operation and commenced a refueling outage on January 21, 1983.
The results of the Cycle 2 Reload Analysis were transmitted to you on Janu-ary 31, 1983.
Subsequent to that submittal, the Cycle 2 core loading pattern has been revised due to fuel grid strap damage that occurred during the refueling operation in February.
The purpose of this letter is to inform you of these revisions and their effect on the Reload Safety Evaluation and the approved amendments to the Unit No. 2 Technical Specifications.
During the refueling operation, assembly N-18 was damaged, pre-'
venting its reinsertion for use in Cycle 2.
The core loading pattern was modified to replace the damaged assembly along with three of its symmetric partners with four region 2 assemblies which were not originally scheduled for Cycle 2 duty.
There were no changes to the new fuel locations.
The revised loading pattern is described in Attachment 1.
The revised Cycle 2 design has been evaluated by Westinghouse using the methodology described in WCAP-9273, "Westinghouse Reload Safety Evaluation Methodology".
The results of this evaluation confirm that the previously submitted license amend-ment requests remain conservative for the revised Cycle 2 load-ing pattern.
With the approval of Amendments No. 19 and 20, the revised Cycle 2 RSE addressed those accidents analyzed and re_Eor:t_ed._in the_ FSAR which could potentially be affected by this 8305230094 830516 PDR ADOCK 05000311 P
PDR The Energy People 95-21 68 (80 M) 11-82
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NFG 83-082 Director of Nuclear Reactor Regulation May 16, 1983 reload.
PSE&G has reviewed the results of the Westinghouse RSE.
This review concludes that the effects of the revised reload on the design basis and postulated accidents analyzed in the FSAR are accommodated within the conservatism of the assumptions used in the previous applicable safety analyses.
For purposes of verification, PSE&G has performed an internal, independent Reload Safety Evaluation for Cycle 2.
The results indicate that the quantity F6H may violate Specification 3.2.3 for low power, rodded operation at BOC.
Specifically, the possibility of violation is suspected at Beginning of Cycle, below 50% power, with the rods at the insertion limits described by Amendment No. 19.
The results of the PSE&G analyses have been discussed with Westinghouse.
Westinghouse has evaluated all ac-cidents or limits sensitive to Rod Insertion Limits, and they have determined that none of those accidents or limits would be adversely effected by the operation of Salem 2 Cycle 2 with the control rods at or above the Rod Insertion Limits described in Amendment No. 19.
However, to preclude the possibility of such a violation, a measurement of F6H near the insertion limit will be made during the low power physics tests, and the appropriate Administrative Rod Insertion Limits will be determined and implemented prior to entering Mode 1 operation.
Should administrative limits be re-quired, an appropriate request for license change will be sub-mitted to the NRC.
Attachment
- yours, Manager - Nuclear Licensing and Regulation cc:
Leif Norrholm, Senior Resident Inspector D. Fisher, Licensing Project Manager Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission
90°
-~-------. -
ATTACHMENT 1 REVISED CORE LOADING PATTERN SALEM 2, CYCLE 2 0
N M
L K
J I
H G
F E
18 0 °1 I I 4
4 4
4 4
4 4
4 4
4 2
3 2
3 2
4 20*
?n*
4 4
2 1
2 3
3 3
2 1
SS 20*
16*
4 2
2 4
3 3
2 3
3 4
16 16 4
4 1
4 3
2 3
4 3
2 3
20*
H1 16 4
2 2
3 2
3 2
3 2
3 2
4 3
3 3
3 2
4 3
4 2
3 12 12 4
2 3
2 4
3 3
1 3
3 4
16*
16 1 Ii
- 4.
3 3
3 3
2 4
3 4
2 3
12 12
- 4 2
2 3
2 3
2 3
2 3
2 SS 4
4 1
4 3
2 3
4 3
2 3
20*
16 16 I
SS 4
2 2
4 3
3 16 -
4 4
2 1
2 3
?n*
4 4
4 2
3 20*
4 4
4 Region Number Number of Burnable Poison Rods Secondary Source Rods Depleted Burnable Poison Rods 2
3 3
3 SS
, c.*
2 3
4 4
3 2
2 4
Region 1
2 3
4 4
16 1
4
?()*
4 NFG 83-082 D
c 4
4 2
4
?n*
2 2
.4 1
lli 3
2 SS 3
3 2
3 1 Ii*
3 3
3 2
4 1
16 2
2 2
4 20*
4 W/O U235 2.. 103 2.617 3.121
- 3. 410 4
B 4
4 4
?()*
2 3
2 3
2 4
20*
4 4
A 4
4 4
4 4
4 4
1 2
3 4
..,__ 5 i...- 6
..__ 7 27 oo 8
i.-.,, 9
._,,_ 10
~
11 12 13 14 15
-~
-