ML19345G456

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Responds to NRC Re Mods to Processed Water Storage Tanks to Contain Minor Leakage in Pumphouse.Door Threshold Will Be Raised & Waterproofing Will Be Applied to Floor Slab Expansion Joints
ML19345G456
Person / Time
Site: Crane Constellation icon.png
Issue date: 04/01/1981
From: Hovey G
METROPOLITAN EDISON CO.
To: Barrett L
Office of Nuclear Reactor Regulation
References
LL2-81-0075, LL2-81-75, NUDOCS 8104070279
Download: ML19345G456 (2)


Text

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Metropolitan Edison Company Post Office Box 400 ll Middletown, Pennsytvania 17057 L

Wnter's Direct Dial Number April 1, 1981

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TMI Program Office

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Attn:

Mr. Lake Barrett, Deputy Director q,3,m#j[

p U. S. Nuclear Regulatory Commission

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Y(N/l c/o Three Mile Island Nuclear Station (h'

Middletown, Pennsylvania 17057 s

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Dear Sir:

Three Mile Island Nuclear Station, Unit 2 (TMI-2)

Operating License No. DPR-73 Docket No. 50-320 Processed Water Storage Tanks (PWST)

This letter is in response to your letter NRC/TMI-81-0016, dated February 27, 1981. The initial response date for this letter was delayed as stated in our letter LL2-81-0081, dated March 19, 1981, based on the meeting with you on March 19, 1981. We believe the following modifications to the PWST pumphouse will satisfy your request that we take steps to contain minor leakage of processed water in that structure.

1.

The door threshold will be raised to form a curb approximately 2 inches high.

2.

A waterproofing sealant will be applied to all floor slab expansion joints similar to the treatment of the air intake l

tunnel cork expansion joint in the service building. This sealant wi:.1 extend to a height of approximately 2 inches at floor / wall interfaces.

The above modifications should satisfy your concerns with respect to Criterion 60 of the General Design Criteria, Appendix A to 10CFR I

Part 50 (GDC 60). However, we wish to emphasize the fact that we have installed a storage system which includes two steel, epoxy lined, insulated and heat traced tanks and associated piping built to ASME B31.1 power piping code. We consider this system to be more than adequate for storage of water which, under any other circumstances, would be dischargeable.

Additionally, as we have discussed with you, we are re-examining the t

PWST radionucif dc s limits stated in our letter, TLL 395, dated October

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Metrcacatan Edson Comcany s a Merce c me Ge e a= our c Umes S s e-

e Mr. Lake Barrett LL2-81-0075 9, 1980, to be consistent with the PEIS analysis of a PWST failure.

J/e plan to discuss these revised radionuclide limits with you in

.the near future.

Sincerely, l

/S/ G. E F.0727 C. K. Hovey Vice-President and Director, TMI-2 GKH:JJB:djb cc:

Dr. B. J. Snyder, Program Director-TMI Office 1

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