ML18082B244
| ML18082B244 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/24/1980 |
| From: | Librizzi F Public Service Enterprise Group |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8009300503 | |
| Download: ML18082B244 (3) | |
Text
-
PS~G Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201 /430-7000 September 24, 1980 Director 0£ Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 Attention:
Mr. Steven Varga, Ch:Le£ Operating Reactors Branch.#1 Div:Lsiori of Licens:i,ng
- Gentlemen:
CYCLE 3 RELOAD ANALYSIS FACILITY OPER.ATJ;NG LICENSE DPR-70 UNIT NO. 1 SALEM GENERATING STATION DOCKET NO. 50-272 Salem Unit No. 1 has conclud,ed itis. second, cycle of operation, and commenced a refueling outage on September 19, 1980.
Cycle 2 operation was terminated with a cycle burnup of 8326 MWD/MTU.
Startup of CY'cle 3 is expected to occur in early December 1980.
This letter is to advise you of PSE&G's re~:Lew and plans re-garding Salem No. 1 cycle 3 re1oad core.
Cycle 3 is expected to achieve a burnup of 9000 MWD/MTU.
The CY'cle 3 reload core will cons:Lst of 64 new Westinghouse 17 x 17 fuel asserribl:Les.
Fifty-two {_521 assemblies w:Lll have an enrichment of 2. 80 w/o and the re!I\\a:Lning twelve (_J,2 l a,ssembl:i,es will have an enrichment 0£ 3.40 w/o Csee attached f:Lguret.
A rev:Lew was performed on Salem No. 1 Cycle 3 reloa,d core which addressed those incidents analyzed and reported in the Salem FSAR that could potentially be af£ected by the £uel reload.
This review was performed in accordance with the Westinghouse reload methodology as outlined in the March 1978 Westinghouse toJ?ical report "Westinghouse Reload Safety Evaluation Methodology" (_WCAP-9272).
All Cycle 3 assembl:i,es are 0£ the same mechan:Lcal, nuclea,r and thermal hydraulic design as the cycle 2 asserriblies.
The total peaking factor envelope is the same for both Cycle 2 and Cycle 3.
There are no changes in the kinetic parameters from Cycle 2 to Cycle 3.
The locations of the Optimized Demonstr*ation.Puel, A,ssemblies are
\\
shown in the attachment.
The asserribly in the H-5 location is
~ \\
instrumented with a thermocouple.
The assembly in the H-11
~\\ \\
>m""L]
1879 1979 95-2001 (300M) 1-79
Dir. of Nuc. Reac. Regulation 2 -
location is instrumented with a movable incore fl,ux d,etector.
The criteri.a with respect to FA and F used to determine the location of the Optimized AssemMlies age as follows:
- 1.
Demonstration assemblies are placed in the *core such that the lead power fuel rods operate at least 6% lower in FAH than the maximum allowed design value for the standard assemblies.
- 2.
Demonstration assemblies are located such that they operate with FQ values at least 0.10 lower than the design value for standard assemblies.
PSE&G has reviewed the bases of the reload analysis and the Westinghouse Reload Safety Evaluation (RSE) Report with Westing-house.
The review of all incidents demonstrated that the results of all the postulated events are within allowable limits.
The reload safety evaluation demonstrated that Technical Specifica-tion changes are not required for operation of Salem Unit 1 at rated thermal power during Cycle 3.
Salem's Station Operations Review Committee and the.Nuclear Review Board have concluded that no unreviewed safety questions as defined by 10 CFR 50.59 are involved with this reload.
Therefore, based on this review application for amendment to the Salem Unit 1 operating license is not required.
The reload core design will be verified during the startup physics testing program.
This program wi.11 include, but not be limited to, the following tests: *
- 1.
Control rod drive tests and drop ti.me
- 2.
Critical boron concentration mea,surenierits
- 3.
Control rod bank worth me~surements
- 4.
Moderator temJ:!>erature coefficient measurenierit
- 5.
Power coefficient measurement, and
- 6.
Startup power distribution measurements using the incore flux mapping system.
Very truly yours, c~~~ffr General Manager -
Electric Production
LEM l -
CYCLE 3 Region 2 - Standard l 7xl 7 (_2. 81 w/o)
Region 3 -
Standard 17x17 (3.29 w/ol Region 4 -
Standard 17x17 (2.80 w/oY Region 4A - Optimized 17xl7 (2.80 w/o)
Region SA -
Standard 17x17(2.80 w/o)
Region SB -
Standard 17x17 (3.40 w/o)
R p
SA SA 3
SB 2
3 SA SA 2
3 SB 2
~'
SA SA 2
SB 2
3 SA SA 3
SA 3
SA 3
3 4
4 4
3 4
4 4
3 3
4 3
24 3
2 4
2 3
3 4
3 SA SA m
Lill i I H
SA 2
SA 2
SA 3
3 2
20 2
3 3
c::c::
4 4
3 4
4 4
3 2
4A 2
3 3
3 4
3 4
3 3
4 2
4 2
4 2
3 4
3 4
3 4
4 2
4 2
4 2
3 4
3 4
3 3
3 2
4A 2
3 3
4 4
3 4
4 4
3 3
2 20 2
3 3
c:; c; 2
.SA 2
SA 2
SA SB SA SB SA SB 5A Region Number of Burnable Poison Rods Secondary Source Rods D
SA 3
3 4
4 4
3 4
4 4
3 3
SA Optimized Derronstration Assemblies c
B A
- 1 SA 2
SA SA 3
3 SA 4
3 SA SA
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s 3
2 SB.__ 6 2
SA SA 7
3 0
2
.SB.___
SS 8
2 SA SA -
9 3
2 SB
,___ 10 3
SA SA -
, 1 3