ML20235J586
| ML20235J586 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/14/1989 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Roche M GENERAL PUBLIC UTILITIES CORP. |
| References | |
| TAC-66625, NUDOCS 8902240334 | |
| Download: ML20235J586 (5) | |
Text
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-:F6Fruary:14, 1989 1
1 Mr. M. B. Roche DISTRIBUTION i
Vice President / Director, TMI-2 INDocketJ11e-MMasnik j
GPU Nuclear. Corporation-NRC & Local PDRs OGC j
P. O. Box 480 Plant File EJordan
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y Middletown,-PA 17057 Glainas BGrimes l
BBoger ACRS(10)
Dear Mr. Roche:
SNorris
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SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR PREPARATION OF FINAL
. SUPPLEMENT 3 TO Th.' PEIS (TAC 66625)
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'During the revision of Supplement ~3 to the Programmatic Environmental Impact-Statement dealing with Post-Defueling Monitored Storage we have determined that we need some additional information.
We request that you respond to the enclosed questions.
l Sincerely, original signed by John F. Stolz, Director Project Directorate I-4 Divisitn of Reactor Projects I/II Office of Nuclear R2 actor P9gulation cc see next page
[ADDITIONALINF0.]
- See previous concurrence LA:PDI-4*
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. Mr... N. ' B.. Roche DISTRIBUTION 1
Vice President / Director, TMI-2 Docket, File MMasnik
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' GPU Nuclear Corporation-NRC & Local PDRr 0GC.
,.P. O.; Box 480 Plant File EJordan Middletown, PA' 17057 Glainas.
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BBoger ACRS(10)
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Dear Mr. Roche:
SNorris i
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SUBJECT:
- REQUEST FOR ADDITIONA1. INFORMATION FOR PREPARATION OF FINAL' l
SUPPLEMENT 3TOTHEPEIS(TAC 66625)
- During the revision of Supplement 3 to the. Programmatic Environmental Impact 1
Statement dealing with Post-Defueling Monitored Storage we have deterinined l
that we need some additional information.
We request that you respond to the er.::10 sed questions.
Sincerely, I
original signed by Joitn F. Stolz, Director Project Directorate I 4 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation cc see next'page k
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[ADDITIONALINF0.]
- See previous concurrence LA:PDI-4*
PN:PDI-4*
D:PDI-4*
I SNorris MMasnik:cb JStolz 02/13/89 02/13/89 02/13/89 l
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State College, PA 16801 L$uite 525" a
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,l Ernest L. Blake, Jr. Esquire.
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Jane Lee
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U.S, Nuclear Regulatory Comission 183 Valley' Road Washington, DC 20555:'
Etters, PA 17319 Sally S. Klein, Chairperson -
Walter W. Cohen, Consumer 9
Dauphin County Board of Commissioners Advocate V
Dauphin County Courthouse.
Department of Justice front and Market Streets Strawberry Square,~14th Floor-
>Harrisburg, PA' 17101 Harrisburg, PA 17127 g
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,4, Thomas M.- Gerusky, Director Hr. Edwin Kinter -
Eureau of Regietion Protection Executive Vice.Presidentz Departinut of EnvironisntO Resources
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- 200.Interpace Parkway Harrisburg, PA 17120 Parsipphy, N T7054 1
Ad Crable U.S. Environmental Prot. Agency J
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Lancaster, PA 1.601 CurtisBuilding(SixthFloor) 6th 6nd Walnut Streets Philadelphia, PA 19106-U.S. Department of Energy F. O. Box 88 Middletown, PA 17057
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David J. McGoff Richard Conte 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 Washiagton, DC 20545 Middletown, Pennsylvania 17057 p-
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c ENCLOSURE
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PONS ENVIRONMENTAL REVIEW 1.
What quantity of tritium is expected to remain in the reactor building at the start of PDMS? Provide the basis for your response.
2.
What fraction of the activation products in the reactor coolant system (including the reactor vessel and any, internals expected to be present during PDMS)-exist as particulate debris or corrosion films as opposed to activated metal? What fraction of this material could be considered smearable or easily removable? Provide the basis for your response.
3.
Page 13 of GPU's July 12, 1988 comment letter on the Draf t PEIS l
Supplement 3 (Standerfer to Masnik) indicates that the cesium-137 to strontium-90 ratio for the 3000 psi concrete slab wall is approximately(J.
2:1. Data provided in an attachment to a February 2,1988 memorandum 1
J. Byrne to W. D. Travers,
Subject:
PDMS Environmental Evaluation l
Information), indicates that the ratio for the painted 3000 psi wall is l
closer to 20:1 and for the unpainted wall 23:1. What is the appropriate cesium-137 to strontium-90 ratio in the 3000 psi concrete slab walls?
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