ML20209H034

Forwards Request for Addl Info in Order to Continue Review of 861222 Application Re Expiration of Facility OL & 860123 Submittal Re Pressurized Thermal Shock

ML20209H034
Person / Time
Site:	Millstone
Issue date:	04/24/1987
From:	Jaffe D Office of Nuclear Reactor Regulation
To:	Mroczka E NORTHEAST NUCLEAR ENERGY CO.
References
TAC-59964, TAC-64245, NUDOCS 8705010125
Download: ML20209H034 (3)

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April 24, 1987 y g I Docket No. 50-336 DISTRIBUTION Docket FU es ACRS(10)

NRC & LPDRs DJaffe I-4 Files OGC-Bethesda Mr. Edward J. Mroczka, Senior Vice President GPA/PA BBoger Nuclear Engineering and Operations SNorris DHagen Northeast Nuclear Energy Company SVarga E L-M P. 0. Box 270 XtWik Hartford, Connecticut 06141-0270

Dear Mr. Mroczka:

We are in the process of reviewing your January 23, 1986 submittal concerning pressurized thermal shock for Millstone Unit 2. In order that we may continue our review, we request that you provide your response to the enclosed question within 60 days following receipt of this letter. .The enclosed request for additional information also relates to your December 22, 1986 application concerning the expiration date of your facility operating license and thus supplements our April 1,1987 request for additional information.

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

Sincerely, David H. Jaffe, Project Manager Project Directorate I-4 Division of Reactor Projects I/II

Enclosure:

Request for Additional Infonnation cc: w/ enclosure:

See next page Office: LA/pD I . PD PD/PD -4 GC Surnane SN s RPe son 4Stol Date: q/43/87 / 87 y/'2f87 / 87 l

l 9705010125 870424 PDR ADOCK 05000336 p PDR .,

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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 l Hartford, Connecticut 06141-0270 I Kevin McCarthy, Director Radiation Control Unit Department of Environmental Protection State Office Building Hartford, Connecticut 06106 Mr. Theodore Rebelowski U.S. NRC P. O. Box 615 l Waterford, Connecticut 06385-0615 Office of Policy & Management ATTN: Under Secretary Energy Division 80 Washington Street Hartford, Connecticut 06106

REQUEST FOR ADDITIONAL INFORMATION MILL 5 TONE UNIT 2 PRESSURIZED THERMAL SH0CK There appears to be inadequate information to justify the proposed value of the projected neutron fluence to the end of the current operating license or for.the design plant life, i.e., 32 effective full power years.

To properly justify the proposed value of the fast neutron fluence to the pressure vessel the licensee must describe the method, codes, cross sections, approximations, input parameter values error analysis, etc. NRC staff and staff consultant experience with fluence estimates and projections indicates that as a minimum a two dimensional discrete ordinates benchmarked code must be used (such as DOT). The P and So approximations and an ENOF/B-IV based cross section set with a sufn_,cient Mumber of energy groups are required. The source term for the outer row of assemblies must be expressed for each pin or if the input is on an assembly average basis the result should be adjusted.

The projected source term should account for future loadings schemes. If

. future loadings include low leakage loadings and the use of once, twice or thrice burned assemblies in peripheral locations, the effect of the increased amount of Plutonium on the neutrons / fission and the neutron spectrum must be accounted for. If there exist dosimetry measurements from surveillance

, capsules, the results should be compared with those results. Finally, the fluence should have an error estimate.

Therefore, for the staff to complete this review, the fluence value should be justified as described above.

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