ML20101C843
| ML20101C843 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 12/14/1984 |
| From: | Liden E Public Service Enterprise Group |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| NFU-84-335, NUDOCS 8412210218 | |
| Download: ML20101C843 (5) | |
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NFU 84-335
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Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Depadment December 14, 1984 Director of Nuclear Reactor Regulation U.
S. Nuclear Regulatory Commission
-Washington, D. C.
20555 Attention:
Mr.' Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing Gentlemen:
CYCLE 3 RELOAD ANALYSIS FACILITY OPERATING LICENSE DPR-75 UNIT NO. 2
~ SALEM GENERATING STATION DOCKET-NO. 50-311 Salem Unit.No. 2 concluded its second cycle of operation and commenced a refueling outage on October 4, 1984.
Cycle 2 achieved a cycle burnup of 5,664 MWD /MTU.
The startup of Cycle 3 is scheduled'for April 1, 1985.
The intent of this letter is to inform you of PSE&G's plans regarding Salem No. 2, Cycle 3 reload core which is expected to achieve a burnup of 16,700 MWD /MTU.
The Cycle 3 reload core will utilize 68 new Region 5 Westing-house 17x17 fuel assemblies and 1,664 fresh burnable poison rods.
The Region 5 feed fuel consists of 64 assemblies at 3.8 w/o enrichment and 4 assemblies at 3.4 w/o (see at-tached Figure 1).
All Region 5 assemblies are of the same mechanical, nuclear and thermal hydraulic design as the Region 4 assemblies, which were inserted in Cycle 2, with the exception of the-end plug design change.
This design change-was implemented to facilitate modified fuel rod loading techniques.
Westinghouse has completed the safety evaluation of the Cycle 3 reload core' design in accordance with the Westinghouse reload methodology as outlined in the Westinghouse topical report, " Westinghouse Reload Safety Evaluation Methodology, WCAP 9273, March 1978."
Based on this methodology, those incidents analyzed and reported in the Salem UFSAR that 1
could potentially be affected by the fuel reload were ad-dressed.
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- The: Cycle}3,. reload analysis.is predicated'on'the NRC approval' ofran amendmentito the Salem 2-Technical; Specification regard-Ding-the K(Z) curve (Reference'l) which was submitted to.
.the.NRC..on> October-15, 1984.. The reload. analysis ~showed~
~
fthat:all cycle 3, peaking: factors, rod worths and kinetic
, parameter values. meet current' limits with the exception 1
>of.the Cycle.3LSCRAM curve. 'An investigation'of the:trans -
ientsiimpact'ed'by the' change in the Cycle 3. SCRAM curve
- showed that the-previously accepted safety limits'were not.
exceeded.. Therefore,-no' reanalysis was performed.
The' dropped RCCA event was analyzed according to the new
, dropped' rod methodology: described in Reference 2.
Results show that the~DNB design basis.is met for all dropped rod events-initiated from full power so that the interim' operating restrictions (Reference 3) willibe removed for this cycle.
- PSE&G.has reviewed the Cycle 3 reload analysis.
The review eincluded performing an independent reload safety evaluation using.'in-house-. computer. codes.
.The review demonstrated Ethat the results of all the' postulated events are'within allowable-limits' assuming the approval of the K(Z) curve
-amendment.
7
,i TheJRadial Peaking Factor Limit Report;for Salem Unit No.
2, Cycle 3 is_ presently'in preparation.
It will be submitted.
to the NRC at least 60 days' prior to initial criticality of Cycle 3.
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'Th'e Salem Operations Review Committee has con 71uded that-for-the operation of Salem' Unit 2 at rated the mal' power,'O
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the cycle 3~ reload involves no unreviewed' safety question as defined tur 10CFR50.59.
Therefore, pending NRC approval.
of1the Salem Unit 2 K(Z) curve. Technical Specification amend-l 3 ment, for-which expedited NRC review and handling has been
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The reload core design will be verified during the startup physics testing program.
This program will~ include, but l,
- is not limited to, the following tests
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Control rod drive tests and drop time 2.
Critical boron concentration measurements t
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Mr. Steven A. Varga 12/14/84 1
3.
Control rod bank worth measurements
'4.sModerator temperature coefficient measurement, and 5.'
Power distribution measurements using the incore flux mapping system.
Very truly yours,
)
E. A. Liden Manager - Nuclear Licensing and Regulation
References:
1.
Letter from E. Liden (PSE&G) to NRC (Attn.
S. Varga) Request for Amendment, Facility Operating License, Unit No. 2, Salem Genera-ting Station, Docket No. 50-311, LCR 84-08, dated October 15, 1984.
2.
Letter from Cccil D. Thomas (NRC) to E.
P. Rahe, Jr.,
Subject:
Acceptance for Referencing of Licensing Topical Report WCAP-10297-A(p),
WCAP-10248-A (NS-EPR-2545) Entitled " Dropped Rod Methodology for Negative Flux Rate-Trip Plants," March 31, 1983.
3.
Letter from Steven A. Varga (NRC)'to R. A.
Uderitz (PSE&G), Docket Nos. 50-272 and 50-311, dated November 1, 1982.
t QZD:dgh Attachment L.
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^ Mr.-Steven lA..Varga
- 12/14/84 IC.
Mr. Donald C.'Fischer
-Licensing Project Manager-Mr.-James.Linville
-4 Senior. Resident-Inspector-J
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FIGURE 1 CORE LOADING PATTERN SA1.EM UNIT 2 CYCLE 3 180*
R F
N M
L K
J B
G F
E D
C B
A i
I 8
I I
f f
f g
1 4
4 4
5A 4
4 4
12 2
3 4
5A 4
5A 4
5A 4 i 5A 4
.3 24 24 24 24 3
3 4
5A 4
5A 3
3 3
'5A 4
5A 4
3 24 24 SS 24 24 i
4 4
5A 4
4 3
5A 3
5A 3
4 4
5A 4
24 24 20 20 24 24 5-4 5A 4
4 4
5A 3
5A 3
5A 4
4 4
5A 4
24 24 12 20 16 20 12 24 24 1
6-4 4
5A 3
5A 3
5A 3
5A 3
5A 3
SA 4
4 24 20 20 20 20 24 7-4 5A 3
5A 3
5A 3
5B 3
5A 3
5A 3
5A 4
24.
20 20 16 20 20 24 90 8 -
SA 4.-
3 3
SA 3
55 3
SB 3
5A 3
3 4
SA 270*
12 16 16 16 16 12 9-4 5A 3
SA 3
SA 3
5B 3
SA 3
SA 3
5A 4
24 20 20 16 20 20 24 10-4 4
5A 3
5A 3
5A 3
5A 3
5A 3
5A 4
4 24 20 20 20 20 24 11-4 5A 4
4 4
5A 3
5A 3
5A 4
4 4
5A 4
24 24 12 20 16 20 12 24 24 12 4
5A 4'
4 3
5A 3
5A 3
4 4
5A 4
24 24 20 20 24 24 13 3
4 SA 4
5A 3
3 3
5A 4
5A 4
3 24 24 SS 24 24 14 3
4 5A 4
5A 4
5A-4 5A 4
3 24 24 24 24 15 4
4 4
5A 4
4 4
12 1
0*
Region w/o U235 3
3.12 X
REGION NUMBER 4
4 Y
NUMBER OF BURNABLE ABSORBER RODS 5A 3
5B 3.40 SS SECONDARY SOURCE RODS i
....