ML18102A149
| ML18102A149 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/31/1996 |
| From: | Eric Simpson Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LR-N96155, NUDOCS 9606070012 | |
| Download: ML18102A149 (6) | |
Text
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Public Service 1 Electric and Gas Company E. C. Simpson Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1700 Senior Vice President - Nuclear Engineering Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 Gentlemen:
FUEL HANDLING VENTILATION SYSTEM SALEM GENERATING STATION UNIT NO. 2 DOCKET NO. 50-311 MAY 31 1996 LR-N96155 In letter LR-N96147 dated May 29, 1996, Public Service Electric &
Gas identified actions which would be taken to address several unresolved issues relating to the Fuel Handling Building Ventilation (FHV) System design and licensing basis.
For clarity, Attachment 1 has been prepared to delineate those items to be completed prior to commencing spent fuel handing activities. identifies those longer term actions required to support closure of the broader issues.
Documentation of actions completed to support spent fuel handling activities will be provided for NRC review.
PSE&G will not commence spent fuel handling activities until the NRC staff has completed their review, and are satisfied that all committed actions identified in Attachment 1 are complete.
It is PSE&G's expectation that closure can be achieved with your staff on those items identified in Attachment 1 by the close of business on June 4, 1996.
If you have any questions regarding this matter, please feel free to contact us.
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Document Control Desk LR-N96155 2
C Mr. T. T. Martin, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 MAY 31 1996 Mr. L. N. Olshan, Licensing Project Manager - Salem U. S. Nuclear Regulatory Commission One White Flint North 11555 Ro6kville 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
Document Control Desk LR-N96155 3
MAY 31 1996 ATTACHMENT 1 Actions Required to Support Spent Fuel Handling Activities
- 1)
Obtain SORC approval of revised 50.59 safety evaluation which documents safety assessment for current plant conditions.
SORC presentation occurred on 5/30/96.
The evaluation was accepted wi*th minor comments which have been addressed.
Final approval is expected by 5/31/96.
- 2)
Document fuel handling accident analysis results assuming unfiltered release and using Safety Guide 25 assumptions for current plant conditions.
- 3)
This activity is complete.
Develop a list of input assumptions used in the current licensing basis fuel handling accident calculations for comparison to fuel handling ventilation system operational conditions.
Verify conformance with analysis assumptions where appropriate.
This activity is complete.
- 4)
Revise Operations Department procedures to reflect FHV System operability guidance and actions to be taken in the event conditions are not satisfied.
Revisions are expected to be completed by 6/1/96.
Training will be integrated with pre-evolution briefings and Operations shift turnover briefings.
- 5)
Establish appropriate administrative controls to monitor and required actions for building temperatures less than 40°F or greater than 105°F.
Controls identified, procedure revisions are expected to be completed by 6/1/96.
Training will be integrated with pre-evolution and shift turnover briefings.
- 6)
Revise Operations procedures to require trip of supply fan in the event of an exhaust fan trip.
Procedure revisions in progress, expected completion is 6/1/96.
Training to be integrated with pre-evolution and shift turnover briefings.
Document Control Desk LR-N96155 4
ATTACHMENT 1 (Cont)
MAY 31 1996
- 7)
Revise appropriate Operations department procedures relating to FHV system alignment to address alignment to the Charcoal filter during spent fuel handling evolutions and to require air supply to damper actuators to be cleared and tagged.
Procedure revisions are in proqress with an expected conpletion date of 6/1/96.
Traininq will be integrated with pre-evolution and shift turnover briefinqs.
- 8)
Conduct charcoal filter bypass surveillance testing in accordance with revised procedures.
Verify all FHV surveillance test results are current.
Testing has been completed with satisfactory results.
Verification of surveillances occurs durinq the completion of procedure 2-IOP-10, which verifies that prerequisites to handlinq fuel in the fuel handlinq buildinq have been satisfied.
- 9)
Monitor 21 and 22 FHV exhaust fan vibrations and make appropriate operability recommendations to the Senior.
Nuclear Shift Supervisor.
This is an onqoinq activity. 22 FHV exhaust fan is being repaired durinq the outaqe window associated with the auto start modification installation.
- 10)
Complete installation of Unit 2 FHV auto start modifications and final surveillance testing to demonstrate operability.
Installation is underway, expected completion of final surveillance testinq is 6/3/96.
l MAY 3 1 1996 Document Control Desk LR-N96155 5
ATTACHMENT 2 Long Term Actions to Address Unresolved Items
- 1)
Complete a reanalysis of the design basis fuel handling accident using Safety Guide 25 assumptions to establish compliance with the licensing basis.
Preliminary calculations results are available indicating conq;>liance is achieved.
Acceptance review of contractor calculations is expected to complete by 6/3/96.
Input parameters to be forwarded to NRR on 5/31/96 for conq;>arison with NRC dose analysis model.
- 2)
Determine if additional review of fuel handling building equipment qualification data is required to support upper limit for building temperature of 120°F.
Expected completion is 8/15/96.
- 3)
Review fuel handling building heating and cooling load calculations to establish basis for previous removal of conservatism.
Perform a 50.59 review of revised calculations.
Additional information relating to the removal of conservatism from the calculations was provided to the NRC on 5/29/96.
Expected conq;>letion of 50.59 review for these calculations is 6/30/96.
- 4)
Complete a failure modes study of the FHV system and assess the need for modifications to improve design.
Failure mod.es analysis is complete.
Additional calculations are required* to support development of final recorrmendations.
Expected conq;>letion date for this activity is 6/30/96.
- 5)
Finalize Charcoal Heating calculations and develop required UFSAR changes.
Expected conq;>letion date for calculations is 6/7/96.
UFSAR changes and supporting 50.59 safety evaluation to be developed by 6/30/96.
- 6)
Update the UFSAR upon resolution of* all issues.
Date to be determined.
prerequisite.
Closure of all issues with NRC is a
I I
Document Control Desk LR-N96155 6
MAY 31 1996 DWD/
BC Senior Vice President - Nuclear Engineering (N19)
Senior Vice President - Nuclear Operations (X04)
General Manager - Salem Operations (S05)
Director - QA/NSR (XOl)
Manager - Nuclear Safety Review (N38)
Manager - Joint Owners/Ext. Aff. Interface (N28)
Onsite Safety Review Engineer - Salem (S12)
Station Licensing Engineer - Salem (X09)
General Solicitor, R. Fryling, Jr. (Newark, 5G)
Mark J. Wetterhahn, Esq.
Records Management (N21)
Microfilm Copy File Nos. 1.2.1