ML18100B001
| ML18100B001 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 04/07/1994 |
| From: | Labruna S Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LCR-93-02, LCR-93-2, NLR-N94059, NUDOCS 9404180143 | |
| Download: ML18100B001 (4) | |
Text
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Public Service Electric and Gas Company
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Stanley LaBruna Public Service Electric and Gas' Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1700 Vice President - Nuclear Engineering APR 0 7 1994*
NLR-N94059 LCR 93-02 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C.
20555 Gentlemen:
UPDATE TO SPENT FUEL POOL RERACK LICENSING REPORT SALEM GENERATING STATION UNIT NOS. 1 AND 2 FACILITY OPERATING LICENSE NOS. DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 In a letter dated April 28, 1993, Public Service Electric and Gas Company (PSE&G) submitted a request for amendment of Facility Operating Licenses DPR-70 and DPR-75 for Salem Generating Station, Unit Nos. 1 and 2.
The proposed changes increased the Spent Fuel Pool capacities for Unit Nos. 1 and 2 from the current 1170 to 1632 fuel assemblies, and extended the decay time for Refueling Operations from 100 to 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />.
That letter contained a Licensing Report, as Attachment D, which provided the technical justification to support the requested changes.
Licensing Report page 2-9, item (viii), indicated that the assembled crane/hoist system would be load tested with 25 tons dead load prior to use.
PSE&G has reevaluated this load test and decided not to perform the test.
This decision was based primarily on safety concerns associated with the conduct of the test.
To meet the full intent of the prior to use load test, the crane and the test load must be transported over the full length of the Spent Fuel Pool.
This creates an accident potential not previously evaluated in the Safety Analysis Report (SAR).
- Also, it would be very difficult to locate 25 tons of concrete blocks on the Fuel Handling Building refueling floor for the conduct of the load test.
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PDR ADOCK 05000272 p
Document Control Desk NLR-N94059 2
APR 0 7 1994 The following technical justification supports our decision to delete the prior to use load test:
- 1.
A load drop analysis was performed to evaluate the pool structural integrity.
The analysis results were acceptable.
- 2.
An evaluation determined that the existing crane meets all the stress limits specified in applicable specifications.
- 3.
The existing Exxon racks, which are the heaviest, were installed in 1981 using the existing crane.
- 4.
The rerack project installation procedure requires that every time a rack is lifted, it should be lifted approximately 6 inches above the floor and held for approximately 10 minutes before further movement.
- 5.
A new rack handling trolley will be used for rack movement.
This rack handling trolley will be shop load tested at 150% of the rated load, prior to its arrival onsite.
Holtec will provide a load test verification certificate for the new rack handling trolley.
- 6.
The hoist manufacturer (Ingersall-Rand) will provide a load test verification certificate for the new rack handling hoist.
Salem UFSAR Section 9.1.5 (Control of Heavy Loads) includes a verification of crane design against the guidelines of industry standards such as CMAA-70 and ANSI BJ0.2-1976.
Licensing Report Table 2.5.1 also indicates that the Salem crane meets the intent of CMMA-70 and ANSI BJ0.2-1976.
ANSI BJ0.2-1976 "Overhead and Gantry Cranes," states in Section 2-2.2.2.a that prior to initial use, all new, extensively repaired, and altered cranes should be tested and inspected by, or under the direction of, an appointed or authorized person and a written report be furnished by such person, confirming the load rating of the crane.
PSE&G believes that the shop load test satisfies the intent of this suggested item.
In summary, PSE&G has determined that conducting a prior to use load test is not mandated by ANSI B30.2-1976, and would result in an accident potential not previously evaluated in the SAR.
The new rack handling trolley and rack handling hoist shop load tests, and rack installation procedural guidance provide adequate assurance of assembled crane/hoist system performance.
- Thus, PSE&G has concluded that it is not prudent to conduct the prior to use onsite load test.
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Document Control Desk NLR-N94059 APR 0 7 1994 3
Licensing Report Section 9.0 describes a radiological evaluation that was conducted to determine the impact of a fuel handling accident.
This evaluation assumed a fuel burnup of 65,000 Mwd/mtu.
Mr. J. Stone, Salem NRR Project Manager, informed PSE&G that the NRC generic analysis only approved fuel burnups to 60,000 Mwd/mtu.
Based on this information, PSE&G requests that the NRC approve our spent fuel pool rerack submittal for 60,000 Mwd/mtu.
The radiological evaluation conducted to support 65,000 Mwd/mtu bounds a fuel burnup of 60,000 Mwd/mtu.
Should you have any questions on this transmittal, please contact us.
Sincerely, c
Mr. T. T. Martin, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. J. C. Stone, Licensing Project Manager -
Salem U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. c. Marschall (S09)
USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625
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STATE OF NEW JERSEY COUNTY OF SALEM
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REF: NLR-N94059
- s. LaBruna, being duly sworn according to law deposes and say~:
I am Vice President - Nucl.ear Engineering. of Public Service Electric and Gas Company~ *and as such, *I find :the matters set forth in the above referenced letter, concerning the Salem Generating Station, Unit Nos. 1 and 2, are true to the best of my knowledge, information and belief.
7 Jersey KIMBERl Y JO BROWN NOTARY. P~BUC OF NEW JERSEY My Commission expires on --~--'-'M~vC~o~mrn~r~ss~mn~E~xp~ir~ss~A~pr~ii~2~
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