ML20056A601
| ML20056A601 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/06/1990 |
| From: | Masnik M Office of Nuclear Reactor Regulation |
| To: | Long R GENERAL PUBLIC UTILITIES CORP. |
| References | |
| TAC-69115, NUDOCS 9008080304 | |
| Download: ML20056A601 (3) | |
Text
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August 6. 1990
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Dociet No. 50-320-DISTRIBUTION aDocket<filead EJordan PDI-4 Rdg OGC NRC & L PDRs ACRS (10)
Dr, R. L. Long SVarga BDoger Director, Corporate Services / Director, SNorris Wasnik THI-2 JStolz l
GFU Nuclear Corporation l
P.O. Box 480 i
Middletown, Pennsylvania -17057 l
1 Dear Dr. Long.
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR EVALUAIION OF PDMS SAFETY ANALYSIS REPORT (TAC 69115) i l
Reference:
Letter with attached safety. ass.ssment, 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 j
Report" By letter dated August 16, 1988 (reference above) you submitted your Safety Analysis Report (SAR) for long term storage of the TMI-2 facility.
Based on our continuing review of your SAR and the information provided to the staff in amendments 1 through 7 to the PDMS Safety Analysis Report.we have' determined that additional information or further clarification is required.
We request l
that you respond to the enclosed questions.
The reporting and/or recordkeeping requiremerits contained in this letter i
affect fewer than 10 respondents therefore, OMB clearance is not required j
under P.O.96-511.
l Stacerely, j
l
/s/
l i
i Michael T. Masnik', Senior Project Manager i
Project Directorate I-4 Division of Reactor Projects - I/II i
Office of Nuclear Reactor Regulation
Enclosure:
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Three Mile Island Nuclear Station GPU. Nuclear. Corporation Unit No. 2 Cc:
Frank Lynch, Editorial g
_The Patriot l'
Regional-Administrator, Region I U.S. Nuclear Regulatory Comission 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 1
State College, PA -16801 Suite 525 1700 Rockville Pike Rockville, MD 20852 Er-est L. Blake, Jr., Esquire Marvin I. Lewis
-Shaw, Pittman, Potts, and Trowbridge 7801 Roosevelt Blvd. #62 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, PA 17127 Thomas M. Gerusky, Director Mr. Edwin Kinter Buriau 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
.785 DOE Place Idaho Falls, ID 83401-1562 David J. McGoff Francis I. Young
' Office of LWR Safety and Technology SeniorResidentInspector(TMI-1)
NE-23 U.S.N.R.C.
U.S. Department of Energy Post Office Box 311 Washington, DC 20545 Middletown, Pennsylvania 17057 i
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3-4 e ENCLOSURE 1.
Provide an estimate of the total quantity of contamination (in curies) in the Auxiliary and Fuel Handling Buildings. -Include both fixed and removable contamination.-
2.
. Will sumps and floor drains in the AFHB be capped or sealed during PDMS7 If some will not, identify which ones will not be capped or sealed and indicate the methods to be used to ensure that activity within floor drain piping and sumps does not move outside as they dry.
If no methods are to be used, provide an estimate of the number of curies located in the floor drains or sumps.
3.
If your calculation of pressure rise due to the maximum credible fire in containment,is based on Calculation Number 4710-3220-87-037 (December 11, 1987, RB Fire HEPA Filter P/ t; 1)
Indicate the similarities and difference between a postulated fire in TMI-2 and the laboratory fire data from Lawrence Livermore Laboratory and indicate why the Lawrence Livermore Laboratory system >
was thought to be a good model for the THI-2 facility.
B)
An attachment to the above calculation (Memorandum O'Connor to Buchanan,
Subject:
TMI-2 Reactor Building Fire, 3370-87-0213, December 16, 1987) indicates a 20,976,000 BTU fire in.the TMI-2 containment building would result from 138 gallons of oil.
Based on a fire of 20,976,000 BTUs in the TMI-2 containment building, a pressure inside the building of much greater than 4 in, water can be calculated.
Indicate the basis for assuming (in your response to question A.13, Supplement 3 to the SAR on PDMS) that 4 in, water is the correct maximum pressure in the passive breather line.
If your calculation of pressure rise due to the maximum credible fire was not based on Calculation Number 4710-3220-87-037, indicate the code used, the calculation methods, and the assumptions that were made in determining that a fire in the reactor building would have a 6 minute duration and an expected pressure rise of -1.2 in. water et the HEPA filter in the passive breather line.
4.
Several questions have asked abcut the design and location for the PDMS Alarm and Monitoring System (SAR page SI-8, and S1-21).
Provide the answers to the previously unanswered questions.
If final design and location'of the system has not been decided provide the status of the review and an estimate of when this information will be available.
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