ML18095A243
| ML18095A243 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/30/1990 |
| From: | Labruna S Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NLR-N90109, NUDOCS 9006060052 | |
| Download: ML18095A243 (5) | |
Text
Public Service Electric and Gas.
Company Stanley LaBruna
- Public Service Electric and Gas Company P.O. Box 236. Hancocks Bridge. NJ 08038 609-339-4800
,; cs P~es.dert - :\\luciear Ooerat:ons May 30, 1990 NLR-N90109 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
CYCLE 6 RELOAD ANALYSIS FACILITY OPERATING LICENSE DPR-75 UNIT NO. 2 SALEM GENERATING STATION DOCKET NO. 50-311 Salem Unit No. 2 completed its fifth cycle of operation on March 30, 1990.
The burnup at the end of Cycle 5 was 14614 MWD/MTU.
The startup of Cycle 6 is scheduled for June 11, 1990.
The intent of this letter is to inform you of PSE&G's plans regarding Salem Unit No. 2 Cycle 6 reload core which is expected to achieve a burnup of 16600 MWD/MTU.
The cycle 6 reload core will utilize 76 new Region 8 Westinghouse 17 X 17 fuel assemblies consisting of 40 assemblies at 4.0 w/o enrichment and 36 assemblies at 3.8 w/o enrichment (see attached Figure 1).
The loading contains a total of 1632 fresh burnable absorber rodlets located in 32 of the Region 8 fuel assemblies arranged as shown in the figure.
The mechanical design of the Region 8 assemblies will incorporate.a low pressure drop Zircaloy grid.
This upgraded fuel feature is part of the Vantage 5 Hybrid (V5H) fuel design (Reference 1).
In addition, the Region 8 V5H assemblies will incorporate a Debris Filter Bottom Nozzle (DFBN) and snag-resistant grids.
The DFBN, a low profile bottom nozzle which is structurally and hydraulically equivalent to the existing nozzle, is designed to inhibit debris from entering the active fuel region of the core and thereby improves fuel performance by minimizing debris related fuel failures.
The snag-resistant grids contain outer grid straps which have modified corner geometry and guide tabs to help prevent assembly hangup from grid strap interference during assembly removal.
In addition, the Region 8 assemblies will continue to use the reconstitutable top nozzle design and standardized fuel pellets introduced in the previous cycle.
Westinghouse has completed the safety evaluation of the Cycle 6 reload core design utilizing the methodology described in Reference 2.
9006060052 900530 PDR ADOCK 05000311 P
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Document Control Desk NLR-N90109 2
Based on this methodology, those incidents analyzed and reported in.the Salem USFAR (Reference 3) that could potentially be affected by the fuel reload were addressed.
5-30-90 The dropped RCCA event was evaluated based on the methodology described in Reference 4.
For steam line break incidents at pressures below 1000 psia, the DNBR limit of 1.45 was utilized in the safety analysis (Reference 5).
The safety evaluation states that all Cycle 6 kinetics parameters, control rod worths, and core peaking factors meet current limits with the exception of 1) the Beginning of Cycle (BOC) least-negative Doppler-only power defect and 2) the normalized trip reactivity insertion rate.
A reduced BOC least-negative Doppler-only power defect was incorporated into the safety analysis.
The UFSAR Rod Withdrawal from Subcritical and Rod Ejection transients were analyzed using the reduced Doppler defect limit. This analysis demonstrated that the acceptance criteria for these transients were met.
The normalized trip reactivity insertion rate, which is slightly different from the current limit, was compared to the previous analyses and evaluated for those accidents affected.
The analyses in the Plant Safety Evaluation (Reference 1) were demonstrated to remain applicable.
Six Salem Unit No. 2 Technical Specification changes have been approved for implementation starting in Cycle 6.
These changes are: 1) V5H fuel upgrade (change in DNBR correlation, increase in RCCA drop time, deletion of Rod Bow Penalty as a function of burnup and removal of flow rate from F-DELTA-H function),
- 2) redefinition of FULLY WITHDRAWN RCCA position to between 228 and 222 steps, 3) incorporating requirements for head vents into the bases, 4) reducing RHR requirements in Mode 6 from 3000 gpm to 1000 gpm, 5) revise heatup and cooldown curves per specimen capsule test results, 6) change the RHR open permissive setpoint to 375 psig.
The Radial Peaking Factor Limit Report for Salem Unit No. 2 Cycle 6 was previously submitted in Reference 6.
PSE&G has reviewed the basis of the Cycle 6 reload analysis and the Westinghouse Reload Safety Evaluation Report with Westinghouse.
We have determined that all the postulated events are within allowable limits and that no unreviewed safety questions as defined by 10CFR50.59 are involved with this reload.
Document Control Desk NLR-N90109 3
5--30-90 The reload core design will be verified during the startup physics testing program.
The program will include, but is not limited to the following tests:
- 1)
Control rod drive test and drop time measurements
- 2)
Critical boron concentration measurements
- 3)
Control rod bank worth measurements
- 4)
Moderator temperature coefficient measurements
- 5)
Power distribution measurements using the incore flux mapping system Should you have any questions regarding this transmittal, please contact us. -
/
Attachment c
Mr. J. c. Stone Licensing Project Manager Mr. T. Johnson Senior Resident Inspector Mr. T. Martin, Administrator Region I Mr. Kent Tosch, Chief Sincerely, New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625
,l Document Control Desk NLR-N90109
References:
- 1)
Foley, J. V. and Davidson, S. L.,
"Plant Safety Evaluation for Salem Nuclear Plant Units 1 and 2 Fuel Upgrade",
November 1988.
- 2)
Davidson, S. L. (Ed.), et al.,
"Westinghouse Reload Safety Evaluation Methodology", WCAP-9237-A, July 1985.
- 3)
Salem Units 1 and 2 Updated Final Safety Analysis Report, USNRC Docket Numbers 50-272 and 50-311, July 22, 1989.
- 4)
Morita, T. et al.,
"Dropped Rod Methodology for Negative Flux Rate Trip Plants", WCAP-10298-A, June 1983.
- 5)
Letter from A. c. Thadani (NRC) tow. J. Johnson (Westinghouse), January 31, 1989,
SUBJECT:
Acceptance for Referencing of Licensing Topical Report WCAP-9226-P/WCAP-9227-NP, "Reactor Core Response to Excessive Secondary Steam Releases".
- 6)
Letter S. E. Miltenberger (PSE&G) to United States Nuclear Regulatory Commission, "Cycle 6 Radial Peaking Factor Limit Report, Salem Generating Station, Unit No. 2, Docket No. 50-311",
March 21, 1990.
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