ML20136G696

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Forwards RAI in Order to Continue Evaluation of Licensee 970207 Request for Exemption from Requirements of 10CFR70.24(a) for Plant
ML20136G696
Person / Time
Site: Crane Constellation icon.png
Issue date: 03/13/1997
From: Buckley B
NRC (Affiliation Not Assigned)
To: Ross M
GENERAL PUBLIC UTILITIES CORP.
References
TAC-M97961, NUDOCS 9703180153
Download: ML20136G696 (4)


Text

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March 13,1997

.Mr. Michael J. Ross Director, TMI (Acting)

' GPU Nuclear Corporation P.O. Box 480 Middletown, PA 17057.

SUBJECT:

. REQUEST FOR ADDITIONAL INFORMATION - REQUEST FOR EXEMPTION FROM 10 CFR.70.24(a) " CRITICALITY ACCIDENT REQUIREMENTS," FOR TMI-1

.(TAC NO. M97961)

Dear Mr. Ross:

By letter dated February 7,1997, GPU Nuclear Corporation ~ requested an exemption from the requirements of 10 CFR 70.24(a) for TMI-1.

Based on our review lof your submittal, we find that additional information, as delineated in the enclosure, is required in order to continue our evaluation.

Should you have any questions on this please contact me at-(301) 415-1452.

Sincerely, (Original Signed By)

  • Bart C. Buckley, Sr. Project Manager Project Directorate I-3 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation Docket.No.Iio-289>

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March 13, 1997 Mr. Michael J. Ross Director, TMI (Acting)

GPU Nuclear Corporation i

P.O. Box 480 Middletown, PA 17057 i

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION - REQUEST FOR EXEMPTION FROM 10 CFR 70.24(a) " CRITICALITY ACCIDENT REQUIREMENTS," FOR THI-1 (TAC NO. M97961)

Dear Mr. Ross:

By letter dated February 7, 1997, GPU Nuclear Corporation requested an i

exemption from the requirements of 10 CFR 70.24(a) for TMI-1.

Based on our review of your submittal, we find that additional information, as delineated in the enclosure, is required in order to continue our evaluation.

Should you have any questions on this please contact me at (301) 415-1452.

Sincerely, r

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, ack eo Bart C. Buckley, Sr. Project Manager Project Directorate 1-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-289 cc: See next page 1

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Three Mile Island Nuclear Station, Unit No.1 cc:

Michael Ross Robert B. Borsum Director, O&M, TMI B&W Nuclear Technologies j

GPU Nuclear Corporation Suite 525

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P.O. Box 480 1700 Rockville Pike Middletown, PA 17057 Rockville, MD 20852 1

John C. Fornicola William Dornsife, Acting Director Director, Planning and Bureau of Radiation Protection i

Regulatory Affairs Pennsylvania Department of GPU Nuclear Corporation Environmental Resources 100 Interpace Parkway P.O. Box 2063 Parsippany, NJ 07054 Harrisburg, PA 17120 Jack S. Wetmore Dr. Judith Johnsrud Manager, TMI Regulatory Affairs National Energy Committee l

GPU Nuclear Corporation Sierra Club l

P.O. Box 480 433 Orlando Avenue l

Middletown, PA 17057 State College, PA 16803 Ernest L. Blake, Jr., Esquire Shaw, Pittman, Potts & Trowbridge 2300 N Street, NW.

1 Washingten, DC 20037 3

i Chairman Board of County Commissioners of Dauphin County Dauphin County Courthouse Harrisburg, PA 17120 4

Chairman Board of Supervisors of Londonderry Township R.D. #1, Geyers Church Road Middletown, PA 17057 Michele G. Evans Senior Resident Inspector (TMI-1)

U.S. Nuclear Regulatory Commission P.O. Box 311 Middletown, PA 17057 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406

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l REQUEST FOR ADDITIONAL INFORMATION i

TMI-1 CRITICALITY ACCIDENT MONITOR EXEMPTION REQUEST 1

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 storage in the fresh fuel racks.

2.

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

3.

Verify that, with the requested exemption, radiation monitoring remains available to meet the requirements 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.

4.

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

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