ML20235R269
| ML20235R269 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/16/1989 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Roche M GENERAL PUBLIC UTILITIES CORP. |
| References | |
| TAC-71119, NUDOCS 8903030233 | |
| Download: ML20235R269 (6) | |
Text
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February 16, 1989 Docket No. 50-320 Mr. M. B. Roche
~Vice President / Director, THI-2 i
GPU Nuclear Corporation P. O. Box 480 l
Middletown, Pennsylvania 17057 1
Dear Mr. Roche:
SUBJECT:
THREE MILE ISLAND NUCLEAR STATION, UNIT 2 - PROCESSED WATER DISPOSAL SYSTEM TECHNICAL EVALUATION REPORT (TAC 71119)
Reference:
Letter with attached Technical Evaluation Report, 4410-88-L-0168/0428P, from M. B. Roche to NRC, dated l
October 7, 1988 re Processed Water Disposal System Your referenced letter provided a description of the proposed Processed Water i
Disposal System. We have completed our preliminary review of the system and need additional information to complete our technical review.
Please respond to the items in Appendix A (enclosed).
I The reporting and/or recordkeeping requirements contained in this letter affect fewer than 10 respondents, therefore C'MB clearance is not reouired under P.L.96-511.
l i
Sincerely, I
original signed by Peter Tam for John F. Stolz, Director 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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February 16, 1989 Docket No. 50-320 Mr. M. B. Roche Vice President / Director, TMI-2 GPU Nuclear Corporation P. O. Box 480 Middletown, Pennsylvania 17057 i
Dear Mr. Roche:
)
i
SUBJECT:
THREE MILE ISLAND NUCLEAR STATION, UNIT 2 - PROCESSED WATER DISPOSAL SYSTEM TECHNICAL EVALUATION REPORT (TAC 71119)
Reference:
Letter with attached Technical Evaluation Report, 4410-88-L-0168/0428P, from M. B. Roche to NRC, dated October 7, 1988 re Processed Water Disposal System Your referenced letter provided a description of the proposed Processed Water Disposal System. We have completed our preliminary review of the system and need additional information to complete our technical review. Please respond to the items in Appendix A (encicsed).
The reporting and/or recordkeeping requirements contained in this letter affect fewer than 10 respondents, therefore CMB clearance is not recuired under P.L.96-511.
Sincerely,
A John F. Stolz, Direct Project Directorate I-4 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/ enclosure:
See next page
j Mr. M. B. Roche Three Mile Island Nuclear Station I
GPU Nuclear Corporation Unit No. 2 cc:
Frank Lynch, Editorial
]
Regional Administrator, Region I The Patriot j
U.S. Nuclear Regulatory Comission 812 Market Street 475 Allendale Road Harrisburg, PA 17105 King of Prussia, PA 19406 3
i Dr. Judith H. Johnsrud Robert B. Borsum i
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. #62 2300 N Street, N.W.
Philadelphia, PA 19152 Washington, DC 20037 Secretary Jane Lee U.S. Nuclear Regulatory Comission 183 Valley Road Washington, DC 20555 Etters, PA 17319 Sally S. Klein, Chairperson Walter W. Cohen, Consumer Dauphin County Board of Commissioners Advocate Dauphin County Courthouse Department of Justice Front and Market Streets Strawberry Square, 14th Floor Harrisburg, PA 17101 Harrisburg, PA 17127 Thomas M. 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 CurtisBuilding(SixthFloor) 6th and Walnut Streets Philadelphia, PA 19106 U.S. Department of Energy P. O. Box 88 Middletown, PA 17057 David J. McGoff Francis 1. Young Office of LWR Safety and Technology Senior Resident Inspector (TMI-1)
NE-23 U.S.N.R.C.
U.S. Department of Energy Post Office Box 311 Washington, DC 20545 Middletown, Pennsylvania 17057
2 Mr. M. B. Roche Three Mile Island Nuclear Station GPU Nuclear Corporation Unit No. 2 cc:
G. Kuehn R. E. Rogan GPU Nuclear Corporation GPU Nuclear Corporation.
J. J. Byrne S. Levin GPU Nuclear Corporation GPU Nuclear. Corporation W. J. Marshall GPU Nuclear Corporation l
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i ENCLOSURE APPENDIX A ADDITIONAL REQUIRED INFORMATION Foaming and sprayin 1.
evaporator (page 7)g will be used to ensure good heat transfer in the They will also affect the decontamination factors (DF) achieved by the evaporator. Describe your process control program (PCP) and your control operating parameters (i.e., level, flow rate, spray rate) to assure acod heat transfer and the design objective DF's.
If the PCP is still under development, describe how your test data will be used to develop an acceptable PCP.
2.
Provide the maximum quantity of radionuclides and maximum volume of solution that will be present in liquid evaporator bottoms at any time during evaporation. Be sure to include solutions that might result from using the evaporator in lieu of ion exchange pre-treatment.
3.
Describe what actions have been taken to prevent premature solidification of the evaporator bottoms in the concentrate tank and associated piping and describe how you plan to redissolve prematurely solidified bottoms.
l 4.
Provide the anticipated maximum quantity and radionuclides content of a batch of solids from the blender / dryer before it is transferred to the-pelletizer.
5.
Provide the maximum individual dose and population dose that could result from a transportation accident involving the waste evaporator bottoms in.
the form in which they will be shipped.
Include a description or reference for your model and assumptions.
6.
Describe the mechanisms that would mitigate the affects of a failure of the HEPA filter on the packaging enclosure. Estimate the worker exposure for workers in the building and the environmental releases.
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7.
We note that the evaporator building atmosphere may be as much as 25 percent of the occupational MPC value (page 10). List the radionuclides that are expected to be most significant. Based on our preliminary calculations, if the building atmosphere is 25 percent of the occupational MPC for soluble Sr-90 and the building is exhausted at 2500 cfm through an unfiltered exhaust, the release rate from the building will be 3.0E-4 uCi/sec. or approximately four times the particulate release rate from the evaporator operated at 5 gpm and a DF of 1000. Describe the filtration and monitoring systems planned for the building exhaust.
8.
The packaging system will be kept under negative pressure (page 9).
indicate what negative pressure will be maintained, identify where i
l will it be measured and describe the alarm and control systems.
9.
Indicate if the ambient air sampler in the evaporator building will be a continuous air monitor with an alarm. Describe how this or another device i
will be used to control airborne radioactivity to less than 25 percent of MPC and less than 50 percent of MPC for an hour.
L_______-_-__________-__--__________-.
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. 10. We calculate that if the boric acid is uniformly cssociated with the Strontium-90,thenairthatcontains2gpercentofoccupationalMPCfor Strontium-90 will also contain 35 mg/m boric acid The ACGIH 3
occupationallimitfor"nuisantgdusts"is10mg/m and for sodium salts of tetra borates is I or 5 mg/m, depending on the hydration. Describe your program for worker protection from borates.
- 11. Page 10 indicates that if acceptable radiological conditions cannot be achieved in the evaporator building within one hour evaporator operation i
will be terminated.
Indicate if this is intended to include either closed or open cycle evaporation, operation of the vaporizer section and operation of the packaging unit. Indicate if there is there any intention to shut down building exhaust during any such conditions.
- 12. Provide the basis for the apparent assumption that building exhaust monitoring is only needed if building air concentrations exceed 25 percent of the occupational MPC.
- 13. We note on page 10 that the_ evaporator system building will be placed on a curbed pad that will be of sufficient size to contain the entire volume of liquid that could be contained in the system. Provide the estimated volume. Describe the shut-off mechanisns that will be installed to discontinue feed to the system in the event of a malfunction.
14 Isolation of source and staging tanks is discussed on page 12. Indicate if isolation will be single or dual barrier. Describe how you will assure the absence of through-valve leakage.
- 15. When the evaporator and vaporizer are coupled, describe how you will accommodate mismatches in throughput.
- 16. Describe and indicate the location of rupture disks or relief valves in the system and identify where they relieve to.
- 17. Indicate the maximum time between chemical and radiochemical sample collection (page 13) and having the results available to the operating staff.
~>
- 18. List the isotopes that you w)11 analyze for in the coupled and decoupled modes. Provide the sensitivity of these analyses.
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