ML20212M234

Forwards Suppl to 860725 Request for Addl Info Re 860521 Application to Amend License DPR-65 to Permit Storage of Consolidated Spent Fuel in Spent Fuel Pool.Response Requested within 60 Days of Ltr Receipt

ML20212M234
Person / Time
Site:	Millstone
Issue date:	08/21/1986
From:	Jaffe D Office of Nuclear Reactor Regulation
To:	Opeka J NORTHEAST NUCLEAR ENERGY CO.
References
TAC-61658, NUDOCS 8608250420
Download: ML20212M234 (4)

Text

i N y August 21, 1986 j- k<

b Distribution Docket No. 50-336 Docket File DJaffe NRC PDR PKreutzer Local PDR ACRS(10)

PD#8 Reading BGrimes 4 Mr. John F. Opeka, Senior Vice President FMiraglia 0GC Nuclear Engineering and Operations- EJordan Northeast Nuclear Energy Company JPartlow P. O. Box 270 NThompson Hartford, Connecticut 06141-0270 Gray File 3.5a

Dear Mr. Opeka:

We are in the process of reviewing your May 21, 1986 application regarding storage of consolidated spent fuel at Millstone Unit 2. In order that we may continue our review, we request that you respond to the enclosed questions within 60 days following receipt of this letter. The enclosed questions supplement our request for additional information dated July 25, 1986.

This request for information affects fewer than 10 respondents; therefore, OMB clearance is not required under P.L.96-511.

Sincerely,

/S/

David H. Jaffe, Project Manager PWR Project Directorate #8 Division of PWR Licensing-B

Enclosure:

As stated 4

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I Mr. John F. Opeka Millstone Nuclear Power Station Northeast Nuclear Energy Company Unit No. 2 cc:

Gerald Garfield, Esq. Mr. Wayne D. Romberg Day, Berry & Howard Superintendent Counselors at Law Millstone Nuclear Power Station City Place P. O. Box 128 Hartford, Connecticut 06103-3499 Waterford, Connecticut 06385 Regional Administrator, Region I Mr. Edward J. Mroczka U.S. Nuclear Regulatory Commission Vice President, Nuclear Operations Office of Executive Director for Northeast Nuclear Energy Company Operations P. O. Box 270 631 Park Avenue Hartford, Connecticut 06141-0270 King of Prussia, Pennsylvania 19406 Mr. Charles Brinkman, Manager Washington Nuclear Operations C-E Power Systems Combustion Engineering, Inc.

7910 Woodmont Avenue Bethesda, Maryland 20814 Mr. Lawrence Bettencourt, First Selectman Town of Waterford Hall of Records - 200 Boston Post Road Waterford, Connecticut 06385 Northeast Utilities Service Company ATTN: Mr. Richard R. Laudenat, Manager Generation Facilities Licensing Post Office Box 270 Hartford, Connecticut 06141-0270 l Kevin McCarthy, Director Padiation Control Unit ,

Department of Environmental Protection State Office Building Hartford, Connecticut 06106 Mr. Theodore Rebelowski U.S. NRC P. O. Box 615 Waterford, Connecticut 06385-0615 Office of Policy & Management ATTN: Under Secretary Energy Division 80 Washington Street Hartford, Connecticut 06106

REQUEST FOR ADDITIONAL INFORMATION MILLSTONE 2-STORAGE OF CONSOLIDATED FUEL IN SPENT FUEL POOL (TAC 61658)

Your submittal dated May 21, 1986 would permit consolidation of fuel and, ultimately, filling of all 1,346 rack locations for a total of 1346 fuel locations. Please respond to the following questions related to your proposal.

1. Does the proposed spent fuel storage design include storage of spent fuel assemblies for Millstone, Unit 2 only, or will it accommodate fuel from Millstone, Units 1 and 3 or other plants?

2. Describe the method (procedure) utilized for installing the consolidated fuel assemblies into Region II of the spent fuel pool. Show that the heat load generated by stored spent congolidated fuel assemblies does not exceed the values of 15.2 and 37.8 x 10 BTU /HR for normal and abnormal maximum heat load cases.

3. Provide the results of CEP00L calculations including hypotheses (assumptions) used to develop conservative temperature conditions in spent fuel subassemblies.

4. Indicate the maximum fuel pin cladding temperature you determined together with a sample calculation used to derive this temperature. Include any hypotheses (assumptions) used.

5. Provide the dimensions of the Boroflex insert shown in Figure 4.4a of your May 21, 1986 submittalwhichappeartohavebgnomitted. Whatqualigy control measures will be used to assure the B loading of 0.03 gm/cm ?

6. Definition 1.39 on page 1.8 of this submittal describes " Storage Pattern" which is used to limit placement of consolidated fuel assemblies in Technical Specification LCO 3.9.20, as follows:

" STORAGE PATTERN" "1.39 The Region II spent fuel racks contain a cell blocking device in every 4th rack location for criticality control. This 4th' location will be referred to as the blocked location. A STORAGE PATTERN refers to a blocked location

{ and adjacent and diagonal Region II cell locations surrounding the blocked location."

In order to clarify this definition, it is recommended that the word "all" be added prior to the word " adjacent." Further, it should be noted that

, the words "all adjacent and diagonal" include cells in adjacent modules if l that is your intention. Confirm that this is the case.

9. Technical Specification 4.9.18. refers to Figure 3.9-1 for fuel enrichment and burnup in order to permit placement of a spent fuel assembly in Region II of the spent fuel pool yet it is not contained in the submittal.

Page 3/4 9.23 of the present Technical Specification contains Figure 3.9-1 which is identical to Figure 3.9-3 of the May 21, 1986 submittal. Please l make suitable corrections to correct this apparent discrepancy.

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10. Describe the means utilized to maintain control over the spent fuel subassemblies in order to assure against premature consolidation of spent fuel assemblies, and maintain a proper storage condition after consolidation has taken place.

11. In response to the staff's safety evaluation report dated November 22, 1985, you noted that an amendment request, targeted for July 1986, would be prepared to restrict plant operation in the event both spent fuel pool cooling trains are not available. Please provide the latest schedule for receipt of this amendment.

12. What is the magnitude of the difference in calculated reactivity between the 123 group KENO-IV calculations (used for benchmarking) and the 16 group DOT-2W calculations (used for consolidated fuel calculations) and how was this accounted for in the fuel rock calculations? What organization performed these calculations and what is their previous experience.

D

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