ML20238D017
| ML20238D017 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/02/1987 |
| From: | Travers W Office of Nuclear Reactor Regulation |
| To: | Standerfer F GENERAL PUBLIC UTILITIES CORP. |
| References | |
| CON-NRC-TMI-87-069, CON-NRC-TMI-87-69 NUDOCS 8709100510 | |
| Download: ML20238D017 (6) | |
Text
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Central File DN 50-320 NRC PDR Local PDR TMI HQ r/f September 2,1987 TMI Site r/f NRC/TMI 87-069 BBogar l
LChandler 1
Stewis l
EJerdan Docket No. 50-320 JPartlow
.g FSchroeder WTravers
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Mr. F. R. Standerfer MMasnik 4
Vice President / Director, THI-2 JThomas I
GPU Nuclear Corporation TMoslak P. O. Box 4BD ACRS Middletowa, PA 17057 Service List
Dear Mr. Standerter:
l l
Subject:
" Post-Defueling Monitored Storage" l
Duripg our ongoing review of your Enviror, mental Evaluation for TMI-2 1
Post-Defueling Monitored Storage, forwarded in your March 11, 1987 letter, the l
NRC staff had identified the need for additional / clarifying information.
Please respond to the attached questions at your earliest convenience.
You may contact M. Masnik cf my staff with any questions related to this
)
request.
Sincerely, ORIGiggt stGNED Bh z
william D. TrmM5 1
l William D. Travers, Director THI-2 Cleanup Project Directorate
Attachment:
As steted cc:
T. F. Detanitt R. E. Rogan I
W. E. Potts l
J. E. Frew J. J. Byrne A. W. Miller Service Distribution List (seeattached) 1, 1
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Attachment Questi?ns Related to Environmmtal Evaluation for TMI-2 Post-Defueling Monitored Storage 1.
- p. 5.0 - oeregraph 5 Cotn passive and forced ventilation discharges will involve controlled, HEPA filts. red paths.
Will the HEPA filters be single stage or double j
stage?
y 2.
- p. 6.0 - paragraph 1 Please clarify the location of groundwater entry, location of ccllection, maximum anticipated quantity and prehability that contamination might be 1
carried out of the building (<s) by the samt path.
The report also refers to collected precip?tation.
What radionuclides concentrations are typical in this water?
3.
- p. 6.0 - paragraph 1 What is the maximum batch size of liquid that might be collected prior to i
processing? As in the care of the accident-generated water, release of I
an untreated batch appears to be a credible, although unlikely accident.
l Please provide data on the maximum credit;le liquid release that would result from a failure to appropriately treat and monitor collected l
I decontamination solutions.
4.
- p. 8.0 - paragraph 4 l
Please provide data on the radionuclioe inventory of the portions of the Waste Disposal liquid system that are not seismically qualified.
l 5.
- p. 10.0 - paragraph 1 The repor t has " conservatively" estimated that a maximum of 3% of the radionuclides in the concrete block might migrate to the outside.
Please provide the basis or give your plans for a monitoring and mitigation program that will assure that the spreadable contamination does not exceed the estimate.
6.
- p. 11 - paragraph 4 Your submittal states, "...the most significant radionuclides contribution to the off-site dose impact results from the transuranic listed on Table 2 and Sr-90 and will bound consideration of these other nuclides." What would the relative contribution f rom Cs-137 be.
- 4 :.
- )
7.
- p. 11 - oaragraph 4 Your submittal states, " additionally, various other radionuclides will be present in the residual contamination."' What are the other radionuclides and what percentage of residual contamination do they' represent?
8.
- p. 13 - paragraph l' j
. I What h tne basis for the assumption-of 50 discharges of-the Reactor j
4 Building atmosphere a year? Page 28 indicates that entries will be made quarterly (during the initial period of PDMS.it is expected that entries.
will be made fonthly).
Will the Reactor Building atmosphere be purged between entries as well as immediately prior to each entry?
9.
- p. 15 - 1.able 3 Will the AFHB atmosphere be purged prior.to entry? Was the concentration of airbcrne contaminants in the AFHB ' considered to be the same as in the Reactor Building? Please provide the basis for ycur' answer.
10, During the maximum credible accident (a major fire), will the filtration systems in the RB and AFHB handle'the smoke produced by the. fire? Please provide the basis for your answer.
- 11. An accidental fire might increase the airborne concentration of tritium whi<:n could pass uneffected through the HEPA filters.
Please estimate (and provide the basis for) the quantity of this radionuclides that might be released by such an accident.
12.
- p. 16 - paragraph 4 Will the operation of the ventilation system result in an exit velocity for the plume? If so, what velocity is expected?
13.
- p. 19 - Table S
]
What is the " Limiting Organ" shown in Table 5?
Is it bone (as given in Table 4)? What are the' units? What is the total inventory released on which these values are based?
14.
The values.given on page 11, 2nd paragraph, and in Table 2, are for transuranic elemen'ts only. What other radionuclides are associated with the residual fuel? What are their activities? Why were they not considered in the analysis?
15.
Please provide your best estimate of the amount of, sludge remaining in i
the RS basement after completion of sludge removal 'as-well as an estimate of the activity in the remaining sludge.
j 16.
Table 1, which is attached, illustrates our understanding of the Phase i
Ill En'Jpoint Criteria.
This table is synopsized from the AFHB and RB Status Repcets as well as from TP0/TM1-188. Our analysis of the environmental in$ acts of PCMS will be based in part on the conditions in r
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the RB and AFHB a the end of. Phase III cleanu).
Therefore, it ic important that the information in this Table' 3e reviewed to ensure that it is correct.
If.this information is incorrect, please provide the-correct information.
The following questions relate to the AFHB and the RB Decontamination
~
Status Reports:
A.
. Dces " Surface Contamination" as used iri the Status Reports refer to smearable surface contamination? if yes, please provide an estimate 1
(if available) of the amount of fixed contamination that wili be left.in'each. area.
If not, please provide estimates of smearable i
I surface contamination.
1' B.
The RB and AFHB Decontamination Status. Report estimates the surface.
area for the. floor, walls and overheads of.each specific area.
The I
surface areas of equipment, piping, etc._ located in these.. areas are i
not specified and we assume are not included in the estimates.
If I
this information is available please provide it.. If. t is not i
available, we ill assume that for most areas of. the RB the surface area will be approximately double if the' surface area of equipment, piping etc. if included.
For the AFHB the' surface area will' double or triple (depending on the amount of equipment.in an area) when the equipment and piping are considered.
If you feel these assumptions are incorrect, please provide better estimates as well as their basis.
C.
Will the Phase III eiidpoint criteria be applied to contamination found on surfaces of the equipment, piping, etc. located in ecch area? If not, please indicate the amount of-contamination (smearable and fixed) that will remain in the equipment, piping,
-)
etc. in each of the areas.
Include equipment and piping that are currently shielded (if they will have potential for airborne contamination).
D.
The AFHB Dergntamination Status Report indicates that the maximum alpha contamination at the end of Phase III cleanup will be 20 1
dpm/100 sq.cm. What is the maximum alpha contamination expected in the RB at the end of Phase III cleanup?
l E.
Does the use of "N/A" for the amount of contamination in certain areas of the AFHB (in the AFHB Decontamination Status Report) mean that the level of surface contamination is below detectable limits?
E.TP0/TMI-188 p. A-3 indicates that the domestic water system will be used in support of system flush.
If " system flush" involves any action other than flushing the sumps or the waste disposal' liquid (WDL) system, please indicate.
18.
Is the enclosed stairwell / elevator shaf t seismically qualified?
1 i
I PHASE III Endpoint Criteria General Area SurfaceContamjnation, Dose Rate, Hot Spot, dpm/100 cm i
Location R/h R/h (7 ft_
J7ft
]
actor Building Refueling Canal (0.015 0.075 (50,0.00 (100,000 Elevation 347 ft (0.03 0.150 (50,000 (100,000 and Above with Eyception of D-Hing (0.07 0.350 (50,000 (100,000 j
NW-Scal Table (0.07 0.35 (50,000 (100,000 j
i Elevation 305 ft (0.07 0.35 (50,000 (100,000
(
to 347 ft i
Basement (282 ft)
(35
?
(1E+9 (1E+9 j
Auxiliary and Fuel Handling Building Areas as given in (0.0025 (1,000 (10,000 "AFHB Status Report for February (0.05 (1,000 (10,000 1987" (Memo from PR Bengel to (0.5 (50,000 (50,000 S. Levin, March 26, 1987 (1.0 (50,000 (50,000 4252-87-0015)
I Other Buildings Turbine Sullding (0.0025 l
Chemical Cleanir.g (0.0025 fluilding l
Service Building (0.0025 Containment Drain Tank Area i
1 1
TABLE 1 l
]
TMI-2 SERVICE LIST William T. Russell Frank Lynch, Editorial Regional Administrator The Patriot i
U.S. Nuclear Regulatory Commission 812 Market Street 631 Park Avenue Harrisburg, PA 17105 King of Prussia, PA 19406 Robert B. Borsum l
Dr. Judith H. Johnsrud Babcock & Wilcox Environmental Coalition on Nuclear Power Nuclear Power Division 433 Orlando Avenue Suite 220 State College, PA 16801 7910 Woodmont Avenue l
Bethesda, MD 20814 Ernest L. Blake, Jr., Esq.
Shaw, Pittman, Potts, and Trowbridge Michael Churchhill, Esq.
j Washington, DC 20037 1315 Walnut Street 2300 N Street, N.W.
PILCOP Suite 1632 Secretary Philadelphia, PA 19107 U.S. Nuclear Regulatory Commission Washington, DC 20555 Marvin I. Lewis i
7801 Roosevelt Blvd. #62 i
Frederick S. Rice, Chairman Philadelphia, PA 19152 Dauphin County Board of Commissioners Dauphin County Courthouse Jane Lee Front and Market Streets 183 Valley Road Harrisburg, PA 17101 Etters, PA 17319 l
Thomas M. Gerusky, Director Walter W. Cohen, Consumer Bureau of Radiation Protection Advocate Department of Environmental Resources Department of Justice P. O. Box 2063 Strawberry Square, 14th Floor Harrisburg, PA 17120 Harrisburg, PA -17127 Ad Crable Mr. Edwin Kintner Lancaster New Era Executive Vice President B West King Street General Public Utilities Lancaster, PA 17601 Nuclear Corporation 100 Interpace Parkway U.S. Department of Energy Parsippany, NJ 07054 P. O. Box 88 Middletown, PA 17057 U.S. Environmental Prot. Agency Region III Office David J. McGoff Attn:
EIS Coordinator Office of LWR Safety and Technology Curtis Building (Sixth Floor)
NE-23 6th and Walnut Streets U.S. Department of Energy Philadelphia, PA 19106 Washington, DC 20545 William Lochstet 104 Davey Laboratory Pennsylvania State University University Park, PA 16802
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