ML20211L249
| ML20211L249 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 12/08/1986 |
| From: | Corbin McNeil Public Service Enterprise Group |
| To: | Noonan V Office of Nuclear Reactor Regulation |
| References | |
| NFU-86-386, NUDOCS 8612150395 | |
| Download: ML20211L249 (4) | |
Text
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Pubhc Service Electric and Gas Cornpany Corbin A. McNeill, Jr.
Public Sm. ice Electric and Gas Company P.O. Box 236. Hancocks Bndge. NJ 08038 609 339-4800
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NFU 86-386 December 8, 1986 Office of Nuclear Reactor Regulation U.S. Nuclear Regulator Commission 7920 Norfolk Avenue Bethesda, MD 20014 Attention:
Mr. Vincent S. Noonan, Director PUR Project Directorate #5 Division of PUR Licensing A Gentlemen:
CYCLE 4 RELOAD ANALYSIS FACILITY OPERATING LICENSE DPR-75 UNIT NO. 2 SALEM GENERATING STATION DOCKET NO. 50-311 Salem Unit No. 2 concluded its third cycle of operation and commenced a refueling outage on October 2, 1986.
Cycle 3 achieved a cycle burnup of 15,472 MUD /MTU (402 EFPD).
The startup of Cycle 4 is scheduled for December 10, 1986.
The intent of this letter is to inf orm you of PSE&G's plans regarding the Salem No. 2, Cycle 4 reload core which is expected to achieve a burnup of 17,000 MUD /MTU (441 EFPD).
The Cycle 4 reload core will utilize 84 neu Region 6 Westinghouse 17 x 17 fuel assemblies at 3 8 w/o enrichment, and 1728 fresh burnable absorber rods.
The mechanical design of the Region 6 fuel assemblies is the same as the Region 5 assemblies, except for the use of chamfered pellets, a 49 pellet holddown spring, reduced backfill He gas pressurization, 304L stainless steel grid sleeve material and a radiused end design bottom end plug.
The Region 6 fuel pellets have a small chamfer at the outer edge of the pellet ends and a reduction in the dish diameter and depth compared to previous unchamfered pellets.
The pellet chamfer improves pellet chip resistance during manufacturing and han-dling.
The change in the grid sleeve material from 304 stainless steel to 304L stainless steel reduces the potential for stress corrosion cracking of the grid sleeves.
The fuel rod bottom end plug was changed from a chamfered end to a radiused end to improve rod loading and reduce the potential of grid damage during rod loading.
The 49 spring provides more gas plenum g h (o volume for fission gas release and reduces the potential for 3
pellet chipping.
8612150395 861208 DR ADOCK 05000 1
)
V. S. Noonan 12-8-86 Westinghouse has completed the safety evaluation of the Cycle 4 reload core design in accordance with the Westinghouse reload methodology as outlined in the Westinghouse topical report,
" Westinghouse Reload Safety Evaluation Nethodology, UCAP-9273-A (Reference 1).
The dropped RCCA event was analyzed according to the dropped rod methodology described in Reference 2.
This evaluation showed that all Cycle 4 peaking factors, rod worths and kinetic parameter values meet current limits with the exception of the normalized trip reactivity insertion rate which is slightly _different from the current limit.
The effects of this different normalized trip reactivity rate was evaluated for those accidents affected and results shou that previously accept-ed safety limits are not exceeded.
The above evaluation also demonstrated that the core vill remain subcritical on the soluble baron provided by the ECCS, follouing a hypothetical large break LOCA, assuming that the Baron Injec-tion Tank (BIT) is kept active for the first 540 NUD/NTU (14 EFPD).
PSE&G uill not implement LCR 85-07 BIT Elimination until this burnup has been exceeded.
Prior to future reloads, the RUST baron concentration uill be increased to compensate for BIT removal.
PSE&G has reviewed the Cycle 4 reload analysis.
The revieu included performing independent calculations of key safety analysis parameters using in-house computer codes.
The revieu demonstrated that the results of all the postulated events are uithin allouable limits.
The Radial Peaking Factor Limit Report for Salem Unit No. 2 Cycle 4 uas submitted previously in Reference 4.
We have determined that no unreviewed safety questions as defined by 10CFR50.59 are involved uith this reload.
Therefore, based on this revieu, application for amendment to the Salem Unit 2 operating license is not required.
The reload core design will be verified during the startup physics testing program.
This program vill include, but is not limited to, the follouing tests:
1 Control rod drive tests and drop time 2
Critical boron concentration measurements 3.
Control rod bank worth measurements 4.
Moderator temperature coefficient measurement 5
Pouer distribution measurements using the incore flux mapping system.
L
4 V. S. Noonan 12-8-86 Should you have any questions, we will be pleased to discuss them with you.
Sincerely, Attachment
References:
(1)
Bordelon, F.
M.,
et.
al.,
"Uestinghouse Reload Safety Evaluation Methodology", UCAP-9273-A, July, 1985 (2)
- Norita, T.,
et. al.,
" Dropped Rod Methodology for Negative Flux Rate Trip Plants",
UCAP-10298-A, June, 1983.
(3)
Telecon betueen NRC (D. Fischer, R. Lodell, U. Brooks and R. Karsch) and PSE&G staff on September 2, 1986,
Subject:
Post-LOCA sub-criticality concerns for Salem 2 Cycle 4 Reload Design.
(4)
Letter C. A. McNeill, Jr. (PSE&G) to T. E.
Hurley (NRC), " Cycle 4 Radial Peaking Factor Limit Report Facility Operating License DPR-75 Unit No. 2, Salem Generating Station Docket No. 50-311", September 30, 1986.
C Nr. D. C. Fischer Licensing Project Manager Nr. T.
J. Kenny Senior Resident Inspector i
l I
ATTACHMENT CORE LOADING PATTERN SALEM UNIT 2 CYCLE 4 R
P N
M' L
K J
H G
F E
D C
B A
I I
SA 6
4 6
4 6
5A 1
.8 8
8 4
SA 6
5A 6
5A 6
5A 6
SA 4
2 20 24 24 20 4
SA 6
- A 6
SA 3
5A 6
SA 6
SA 4
3 16 20 SS 20 16 5A 6
5A 6
4 6
SA 6
4 6
5A 6
5A 4
16 24 24
~24 24 16 SA 6
SA 6
SA 6
4 6
4 6
5A 6
5A 6
-5 20 24 8
24 24 24 8
24 20 6
5A 6
4 6
4 6
4 6
4 6
4 6
5A 6
-6 8
20 24 24 24 24 20 8
4 6
5A 6
4, 6
4 6
5B 6
4 6
5A 6
4
-7
- 24 24 24 24 24 24 24 6
5A SA 5A 6
4*
6 4
6 4
8 8
24 24, 24 24 8
'4..
6-SA 6
4 6
5B 6
5B 6
4 6
SA 6
4 9
24 24 24 24 24 24 2'4 6
SA *
- 6. -
4-6 4
6 4
6 4
6 4
6 SA 6
-lo 8
20 24 24 24 24 20 8
-l SA 6
5A 8
5A 6
4 6
4 6
SA 6
5A 6
-11 20 24 8
24 24 24 8
24 20 5A 6
SA 6
4 6
5A 6
4 6
SA 6
5A 12 16 24 24 24 24 16 4
5A 6
5A 6
5A 3
SA 6
SA 6
5A 4
13 16 20 SS 20 16 4
SA 6
5A 6
SA 6
5A 6
5A 4
- 4 20 24 24 20 SA 6
4 6
4 6
SA g5 8
8 8
I Region W/O U235 XX REGION NUMBER YY NUMBER OF BURNABLE ABSORBER RODS 3
3.10 4
3.80
_