ML18102A156
| ML18102A156 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/04/1996 |
| From: | Dawn Powell Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18102A157 | List: |
| References | |
| LR-N96159, NUDOCS 9606110102 | |
| Download: ML18102A156 (4) | |
Text
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e PStiG Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit JUN 0 4 1996 LR-N96159 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
FUEL HANDLING ACCIDENT ANALYSIS SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 In letter LR-N96147 dated May 29, 1996, Public Service Electric and Gas (PSE&G) identified that the current licensing basis Fuel Handling Accident (FHA) analysis for Salem Units 1 and 2 contained non-conservative assumptions when compared to NRC Safety Guide 25.
Item 1 of Attachment 2 to letter LR-N96155 (May 31, 1996) documented PSE&G's commitment to reanalyze the FHA to address this matter.
The reanalysis of the FHA has been completed and the Salem Units are in compliance with the current licensing basis.
PSE&G has completed its review of this matter and concluded that an Unreviewed Safety Question (USQ) does not exist.
The following amplifying information is provided to support closure of this item.
PSE&G reanalyzed the FHA to support increasing the spent fuel storage capacity at Salem Units 1 and 2 and on April 28, 1993, submitted its licensing analysis to the NRC in support of a License Amendment request.
PSE&G's request was reviewed and approved on May 4, 1994 as License Amendments 151 and 131 to the Salem Unit 1 and 2 operating licenses, respectively.
The spent fuel pool rerack projects have been completed at Salem Units 1 and 2.
The dose assessment associated with the revised FHA analysis was recently reviewed as part of an ongoing project to, reconstitute and update site specific dose assessments.
That review identified that the spent fuel pool decontamination factor (DF) and charcoal filtration efficiencies assumed in the licensing analysis were inconsistent with the assumptions c.,used in NRC Safety Guide 25.
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'Document Control Desk LR-N96159 2
JUN 0 4 1996 Reconciliation of these inconsistencies with the Salem licensing basis determined that values corresponding to an overall DF of 222 and charcoal filter efficiencies of 90% and 70% (for elemental and organic Iodines) should have been used in the licensing analysis.
After correcting for these values, a thyroid dose at the exclusion area boundary of approximately 14.6 rem results.
While this value remains well within the acceptance criteria specified in NUREG-0800 (75 rem for Thyroid dose), this dose exceeds the value calculated by the NRC in the Safety Evaluation Report (SER) for Amendments 151 and 131.
To bring the plant into conformance with the NRC SER, a new FHA analysis has been developed.
Conservative assumptions incorporated to address future changes to the plant design have been revised to reflect current license and design limits.
Revised input assumptions have been generated and compared to NRC Safety Guide 25.
Deviations from the Safety Guide have been evaluated for conformance with the Salem licensing basis.
The technical basis for each deviation has also been validated.
The final calculation continues to be conservative relative to the assumed X/Q value, assumed versus actual charcoal filter efficiencies, and takes no credit for any pool decontamination for organic iodine.
The new FHA analysis for Salem Units 1 and 2 documents a thyroid dose of 13.2 rem at the Exclusion Area Boundary.
The value reported in the NRC SER for Amendments 151 and 131 was derived by increasing the previously calculated (1974 SER) thyroid dose of 11 rem by a factor of 1.2 to account for extended burnup fuel.
This results in a final thyroid dose value of 13.2 rem.
PSE&G considers its final calculated doses to be consistent with those reported in the NRC SER and therefore in compliance with the current licensing basis for the Salem Units.
As such, a USQ does not exist.
This matter has been determined to be not reportable under 10 CFR 50.9, "Complete and Accurate Information."
This condition did not represent a significant implication to the public health and safety.
While the corrected dose was outside the current licensing basis, it remained well below the 75 rem acceptance limit established in the NRC Standard Review Plan.
'Document Control Desk LR-N96159 3
JUN 0 4 1996 A copy of the 10 CFR 50.59 Safety Evaluation incorporating the new FHA analysis into the Salem design basis is attached for your.
review.
If there are any questions regarding this matter, please feel free to contact us.
- Qc:rL D. R. Powell, Manager Licensing and Regulation
- Document Control Desk LR-N96159 4
c Mr. T. T. Martin, Administrator -
Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 JUN 0 4 1996 Mr. L. N. Olshan, Licensing Project Manager -
Salem U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Mr. C. Marschall {X24)
USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV Bureau of Nuclear Engineering 33 Arctic Parkway CN 415 Trenton, NJ 08625