ML20012B527
| ML20012B527 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/02/1990 |
| From: | Masnik M Office of Nuclear Reactor Regulation |
| To: | Roche M GENERAL PUBLIC UTILITIES CORP. |
| References | |
| TAC-69115, NUDOCS 9003150191 | |
| Download: ML20012B527 (4) | |
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<i March 2, 1990 tocket No. 50 320 i
Mr.11. B. Roche DISTRIBUTION Vice President and Director. THI-2 e' N Miiasnik GPU Nuclear Corporation NRC & Local PDRs OGC P.O. Box 480 Plant file EJordan Middletown, Pennsylvania 16057 SVarga ACRS(10)
BBoger SNorris
Dear Mr. Roche:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR EVALUATION OF rsitS SAFETYANALYSISREPORT(TAC 69115)
F Werence: Letter with attached safety assessment, 4410 88.L-0068/0378P from F.R. Standerfer to NRC dated August 16, 1988 re " Post Defueling Monitored Storage Proposed License Amendment and Safety Analysis Report" By letter dated August 16,1988 (reference above) you submitted your Safety Analysis Report (SAR) for long term storage of the THI-2 facility. Based on our continuing review of your SAR, we have determined that additional information or further clarification is required. We request that you respond to the enclosed questions.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than 10 respondents, therefore, OMB clearance is not required under P.L. 96 511.
Sincerely,
/s/
Nichael T. Masnik, Senior Project Manager Project Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/ enclosure:
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F Mr. M. B. Roche Three Mile Island Nuclear Station GPU Nuclear Corporation Unit No. 2 CC:
Frank Lynch, Editorial Regional Administrator, Region I The Patriot U.S. Nuclear Regulatory Commission 812 Market Street 475 Allendale Road Harrisburg, PA 17105 King of Prussia, PA 19406 Dr. Judith H. Johnsrud Robert B. Borsum Environmental Coalition on Nuclear Power Babcock & Wilcox 433 Orlando Avenue Nuclear Power Division State College, PA 16801 Suite 525 1700 Rockville Pike Rockville, MD 20852 Ernest L. Blake, Jr., Esquire Marvin I. Lewis Shaw, Pittman, Potts, and Trowbridge 7801 Roosevelt Blvd. f62 2300 N Street, N.W.
Philadelphia, PA 19152 Washington, DC 20037 Secretary Jane Lee U.S. Nuclear Regulatory Commission 183 Valley Road Washington, DC 20555 Etters, PA 17319 Sally S. Klein, Chairperson Walter W. Cohen, Consumer Dauphin County Board of Comissioners Advocate Dauphin County Courthouse Department of Justice Front and Market Streets Strawberry Square, 14th Floor Harrisburg, PA 17120 Harrisburg, FA 17127 Thomas H. Gerusky, Director Mr. Edwin Kinter Bureau of Radiation Protection Executive Vice President Department of Environmental Resources GPU Nuclear Corporation P. O. Box 2063 100 Interpace Parkway Harrisburg, PA 17120 Parsippany, NJ 07054 Ad Crable U.S. Environmental Prot. Agency Lancaster New Era Region III Office 8 West King Street Attn: EIS Coordinator Lancaster, PA 17601 841 Chestnut Street Philadelphia, PA 19107 U.S. Department of Energy P. O. Box 88 Middletown, PA 17057-David J. McGoff Francis I. Young Office of LWR Safety and Technology Senior Resident Inspector (TNI-1)
NE-23 U.S.N.R.C.
U.S. Department of Energy Post Office Box 311 Washington, DC 20545 Middletown, Pennsylvania 17057
_~ -
Ouestions for GPU 1.
Describe the actions that GPU plans to take in the event cf a fire in the TM1-2 react:r containment during PDMS when the containment is on passive ventilation and when the containment is on active ventilation.
Indicate the exhaust fan and supply and exhaust damper configurations and anticipated changes in their configuration in response to a containment fire.
2.
The PDMS SAR (p. 3.7 2) states that containment penetration No. 626 was modified and designed for a maximum of 2 psig.
Is this a valid upper limit or is the penetration able to withstand higher pressure?
j 3.
Revision 6, page 7.2-2, and 7.2-6 of the PDMS SAR describes two sample filter pa breather.pers downstream of the HEPA on the containsent atmospheric i
It also states that
- provisions have been made to allow semi-annual sample filter paper removal and assay and reinstallation or
)
replacement of the DOP-tested HEPA.*
1 Describe the purpose and the specific installation configuration of the sample filter papers and explain how GPU will assure that analysis of the sample filter paper is indicative of radionuclide releases from the containment breather.
Explain why the HEPA is to be reinstalled or replaced, how often is it to be reinstalled or replaced, and for what purpose.
4.
What quantity of fuel debris will remain in the tool storage area and the tool decontamination area of the reactor containment building during PDMS?
Describe the methods that have been or will be used to quantify the amount of fuel debris in these areas.
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