ML20137G961

From kanterella
Jump to navigation Jump to search
Forwards Response to Request for Addl Info Re TMI-1 Criticality Accident Monitor Exemption Request
ML20137G961
Person / Time
Site: Crane 
Issue date: 03/26/1997
From: Langenbach J
GENERAL PUBLIC UTILITIES CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
6710-97-2123, NUDOCS 9704020014
Download: ML20137G961 (3)


Text

,?,,**

l GPU Nuclear, Inc.

(

Route 441 South NUCLEAR Post ffice Box 480 Middletown, PA 17057 0480 Tel 717-944 7621 March 26,1997 6710-97-2123 U. S. Nuclear Regulatory Commission Attention: Document Contml Dark Washington, DC 20555 Gentlemen:

Subject:

Three Mile Island Nuclear Station Unit 1 (TMI-1)

Operating License No. DPR-50 Docket No. 50-289 Request for AdditionalInformation - Request for Exemption from 10 CFR 70.24(a)

GPUN requested an exemption from the requirements of 10 CFR 70.24(a), " Criticality Accident Requirements," for TMI-1 by letter daux! February 7,1997. Based on NRC review of our submittal, a mquest for additional information (RAI) was received in NRC letter dated j

March 13,1997. The enclosure contains our response to the RAI.

I If you have any questions or require any additional information, please contact Adam Miller at (717) 948-8128.

Sincerely, 4%hha b James W. La! nbach Vice President and Director, TMI Enclosure AWM cc:

Region I Administrator, w/ enclosure TMI-I Senior Project Manager, w/ enclosure pI TMI Senior Resident Inspector, w/eniosure 9704020014 970326 ~

PDR ADOCK 05000289 P

PDR 010001 5ppBPPPPPP5

l Enclosure 9

Response to Request for AdditionalInformation TMI-1 Criticality Accident Monitor Exemption Request

1. Describe the procedural controls and/or physical constraints imposed for precluding inadvertent criticality of fresh fuel during fuel handling, inspection, and movement prior to i

1 storage in the fresh fuel rack.

Response

i TMI procedure 1503-1 is the controlling procedure for fuel receipt activities. New fuel is shipped in NRC approved Framatome Cogema Fuels (FCF) shipping containers, which can handle up to 5 % enriched fuel. The maximum enrichment allowed by the NRC for commercial fuel is 5 %. The shipping containers are weather-proof to prevent water ingress. Fuel assemblies are handled one at a time. In all cases where fuel has plastic wrap in place, the wrap either cannot hold water due to its design or it is rendered incapable of holding water prior to fuel storage.

2. Discuss any possible sources of water during new fuel handling operations. How are these sources contmlled during the handling of new fuel?

Response

The handling of new fuel takes place in the Tmck Bay area, the new fuel storage room, and the spent fuel pool area. The credible sources of non-borated water are fire service water in all areas, and decay heat closed cooling water (essentially demineralized water) in the new fuei storage area.

The fire service water is available in these areas via firehose, which requires intentional manual action. Firehoses are only used by the station fire brigade. The fire brigade is comprised of two maintenance personnel, two auxiliary operators, and a Maintenance Foreman as the fire brigade leader. A Shift Foreman or Control Room Operator serve as an advisor to the fire brigade leader when fighting a fire. Spraying water on new fuel during an area fire is not prohibited, since even under optimum moderation conditions k.tr is less than or equal to.953.

The decay heat closed cooling water could flow into the new fuel storage room upon overflow of one of the surge tanks, both of which are located in a room adjacent to the new fuel storage room. The door separating these moms has a water tight seal and is administratively maintained closed. Shift Supervisor approval is required prior to opening the door. As stated in the above paragraph, even under optimum moderation conditions accidental criticality is precluded.

Page 1 of 2

..~

3. Verify that, with the requested exemption, mdiation monitoring remains available to meet the requimments of 10 CFR Part 50, Appendix A, General Design Criterion 63, for fuel storage areas. - Also, include a discussion of the training provided to personnel in responding to area radiation monitor alarms.

)

Response

Radiological Controls Procedure 6G0-ADM-4410.01, Fuel Receipt and Handling, provides radiation monitoring requirements for handling new fuel prior to being placed into the spent fuel pool. Any handling of fuel in the spent fuel pools is monitored by Technical Specification required radiation monitors on the fuel handling bridges. These required radiation monitors have alarm response procedures which provide instmctions to the operators upon receipt of alarms.

All individuals who have access to radiologically controlled areas must complete initial training, j

and annual refresher training thereafter, which includes proper response to area radiation 1

monitor alarms.

4. Discuss why the exemption would remain valid for possible future fuel enrichment increases.

Response

TMI-l has already obtained approval for using the maximum allowed fuel enrichment of 5%.

This appmval includes an accidental criticality analysis which concludes that an accidental criticality is not credible. Any future request for using fuel dth a higher enrichment would require submittal and approval by the NRC of a safety evaluation which would include an accidental criticality analysis. Thus, the exemption would remain valid, i

i Page 2 of 2