ML20033A267

Forwards Request for Addl Info for Review of 810416 Request for License Amend Re Spent Fuel Pool Expansion.Nrc Also Awaits Info Requested in 810714 & 0908 Ltrs

ML20033A267
Person / Time
Site:	Brunswick
Issue date:	11/05/1981
From:	Ippolito T Office of Nuclear Reactor Regulation
To:	Jackie Jones CAROLINA POWER & LIGHT CO.
References
NUDOCS 8111250056
Download: ML20033A267 (4)

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4-I DISTRIBUTION:

Docket File NRC PDR Lo al PDR.

Docket Nos. 50-325 -

ORB #2 Rdg.

50-324 NOV 5 19 81 D. Eisenhut J. Heltemes, AE0D 67 @

M T. Ippolito Mr. J. A; Jones S. Norris

. Senior Executive Vice President J. Van Vliet N

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• Y Carolina Power & Light' Company I-d 336 Fayetteville Street I&E(3)-

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Dear Mr. Jones:

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SUBJECT:

LICENSE AMENDMENT: REQUEST 'FOR SPENT FUEL It0L EXPANSI RE: BP.UNSWICK STEAM ELECTRIC PLANT, UHlY NOS.1 AND 2 Enclosure (1) to this letter identifies additiona1'information needed by our Effluent Treatment Systems Branch for the retiew of your April 16, 1981 license amendment request. To have a reasonable chance of meeting your requested review schedule, we w111 need this information by Novseber 18, 1981.

These questions and the need for your prompt response have previously been

. discussed with ycur staff.

Enclosure (2)summarizesotherquestions,.commentt etc. forwrded during earlier conference calls for which we are awaiting your response. In addition,-

we are also awaiting the infcfmation requested by our letters dated July 14, 1981 and September 8,1981. ther review of'your Spent Fuel Pool expansion license amendment request has procedded to the point where it cannot continue.until additional information is received.

OMB clearance is not requ) red for this request since it is being transmitted to nine or fewer addressees.

Sincerely.

ORIGINAL SIGNED BY Yhomas A. Iprolito, Chief Ooerating Reacters Branch #2 Division of Licensing cc: See next page 8111250056 811105' DRADOCK05000g

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OFFICIAL RECORD COPY.

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Mr.~ J.'A. Jonesf cc:

Richard E. Jones, Esquire Carolina Power & Light _ Company 336 Fayetteville Street Raleigh, North Carolina 27602 George F. Trowbridge, Esquire Shaw, Pittman, Potts & Trowbridge 1800 M Street., N. W.-

Washington, D. C.

20036

' Resident Inspector U. S. Nuclear Reguiatory Commission P. O. Box T057 So'uthport, North Carolina 28461 Southport Brunswick County Library 109 W. Moore Street Southport, North Carolina 28461 Mr. Charles.~R' Dietz

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Plant Manager P. O. Box 458 Southport, North Carolina 28461 t

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e SPENT FUEL POOL-EXPANSION LICENSE AMENDMENT REQUEST FOR ADDITIONAL INFORMATION

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BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 1.

What volume of solid radioactive waste is expected to be generated as a

' result of re-racking of the Brunswick, Unit Nos. I and 2, spent fuel pool?

Estimate the volume, as prepared for shipment (in drums, boxes or _ wrapped) to the disposal site.

Estimate the curie-content of this waste.

2. 2 Our records indicate that the spent fuel storage pool cleanup system contains

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two 500 gpm, 300.ft head, 60 HP pumps upstrean.of two heat exchangers.and two filter /demineralizers. At what inlet water temperature do the pumps

~~ cavitate? Please indicate if your design Lfor the proposed modifications includes any change to the automatic backwash of the filter /demineralizers or. automatic bypass to maintain a minimum total flow of -1000.gpm through the

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SFP system (Figure 8-1).

Also, indicate if the proposed expansion is expected to have any impact on the anticipated annual volume of demineralizer resin waste from this source; if so, provide your estimate of the annual volume and curie content.

e Enclosure (1)

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SPENT FUEL POOL EXPANSION LICENSE AMENDMENT s

REQUEST-FOR ADDITIONAL INFORMATION BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 w

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What is the low friction m'aterial referred to on page 2-2 of the April 6, 1.

.1981 submittal?

2.

Provide copies df references 4-2 and 4-3.

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[3. Provide a-discussion of the. additional heat to be discharged to the environ-ment as a result of the expansion.

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Provide the maximum heat lo'a'd (BTU /HR) and days cooling to 125'F per Table i

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, 3 for the analyzed refueling and core unload cases.

9 Enclosure-(2) 4 n

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