ML20209H637

Forwards Request for Addl Info Re 861205 Tech Spec Change Request Concerning Cycle 22 Reload & Hybrid Control Blades Installation

ML20209H637
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	01/30/1987
From:	Zwolinski J Office of Nuclear Reactor Regulation
To:	Berry K CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
References
NUDOCS 8702060103
Download: ML20209H637 (4)

Text

_

January 30, 1987 r

Docket No. 50-155 g )ISTRIBUTION 4 50etetm Te# NThompson NRC PDR CHinson Local PDR CJamerson Mr. Kenneth W. Berry RWD1 Reading JZwolinski Director, Nuclear Licensing RBernero ACRS (10)

Consumers Power Company BRP File OGC-BETH (Info Only) 1945 West Parnall Road EJordan UCheh Jackson, Michigan 49201 BGrimes LPhillips JPartlow MHodges

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION - TECHNICAL SPECIFICATION CHANGES PERTAINING TO CYCLE 22 RELOAD AND HYBRID CONTROL BLADES INSTALLATION Re: Big Rock Point Plant The staff has reviewed your December 5,1986 Technical Specification Change Request concerning hybrid control rods and has determined that additional information is needed to complete their evaluation. Please review the enclosed information request and provide the requested information at your earliest convenience. If you have any questions, please call your NRC Project Manager, Mr. Charles S. Hinson, at (301) 492-9419.

The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.

Sincerely, Original signed by John A. Zwolinski, Director BWR Project Directorate #1 Division of BWR Licensing

Enclosure:

Information Request cc w/ enclosure:

See next page 8702060103 870130 '

PDR P

ADOCK 05000155 PDR 4f  %

DBL:BWD1 DBL:BWD1-)- DBL:BWD1 CJamerson CHinson:jg J7wolinski i / 30/87 i/.9,/87 i/s,/87

Mr. Kenneth W. Berry Consumers Power Company Big Rock Point Plant cc:

Mr. Thomas A. McNish, Secretary Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 Judd L. Bacon, Esquire Consumers Power Company 212 West Michigan Avenue .

Jackson, Michigan 49201 '

Big Rock Point Plant ATTN: Mr. 7 avid P. Hoffman Plant Superintendent 10269 U.S. 31 North Charlevoix, Michigan 49720 Mr. Bud Heeres

' County Commissioner .

303 Sheridan Charlevoix, Michigan 49720 Office of the Governor Room 1 - Capitol Building Lansing, Michigan 48913 Regional Administrator Nuclear Regulatory Commission, Region III 799 Roosevelt Road Glen Ellyn, Illinois 60237 Nuclear Facilities and Environmental Monitoring Section Office Division of Radiological Health P. O. Box 30035 Lansing Michigan 48909 U.S. Nuclear Regulatory Commission Resident inspector Office Big Rock Point Plant 10253 U.S. 31 North Charlevoix, Michigan 49720

ENCLOSURE A

RE00EST FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATING TO CYCLE 22 RELOAD AND HYBRID CONTROL BLADES INSTALLATION CONSUMERS POWER COMPANY ,

BIG ROCK POINT PLANT

, DOCKET NO. 50-155 -

1. The Technical Specification core operating limits defined in Section 5.2.1(b), Table 1, must be at least as restrictive as the operating .-

conditions determined by the Cycle 22 safety analyses based on approved methodology. Operation under conditions which could lead to violation of a safety limit in the event of an anticipated operational occurrence must be prohibited by the Technical Specifications. The existing operating limits in Table 1 do not appear to satisfy these criteria. Unless you can provide information to demonstrate otherwise, we will require that Consumers Power Company (CPC) propose additional changes to Table 1 operating limits. Some suggested features of the modified Technical Specifications follow:

(a) Core themal power - If core operating limits are to be maintained by a pre-planned power derating program based on exposure dependent ,

calculations, a curve of the maximum thermal power versus cycle exposure should be provided. Operation at thennal power limits l

defined by this curve should assure that all related core operating l thermal limits defined in Table 1 (i.e., MCPR based on XN-2, maximum steady-state heat flux, MAPLHGR, maximum bundle poweri are satisfied for the operating conditions assumed in the safety analyses.

(b) Other thermal limits - If the limits are to be expressed in values excludino application of approved uncertainty factors (Big Rock Point

! Physics Methodology Report, Rev. 3, Oct. 11, 1982), the values of the t

uncertainty factors should be incorporated into Technical Specification Table 1. Alternatively, the limits may be expressed after application of the uncertainty factors. If the limits are to be expressed as a single value for each fuel type, the Table 1 value must bound the most limiting value at any time in the operating l

cycle. Alternatively, exposure dependent curves based on the safety analyses for the operating cycle may be provided.

c

2. In the supplemental information submitted with the January 20, 1987 letter from Ralph R. Frisch, CPC,: Table 2 of Question 5 indicated that the limiting transient and controlling operating limits are very sensitive to cycle exposure time. Describe in more detail your procedures to determine the limiting transient and associated power operating limit at any point ,

in the operating cycle. For example, the transition from a heat flux ,-

limiting factor (0.5 GWD/ST) to MCPR limiting factor (1.0 GWD/ST) would not be expected to result in stepwise relaxation of the operating power limit from 213 MWt to 233 MWt. Also, provide definition of the limiting transient and the safety limit associated with each of the limiting factors determined by your safety analysis.

3. Hafnium Hybrid Control Rods - Inclusion of the hafnium hybrid control rods will be approved for Operating Cycle 22 based on the information previously submitted. However, we will reauire your commitment to define a continuing surveillance program for future cycles based on results of the Cycle 22 inspections and to submit the program for NRC approval prior to continuing operation with these control blades after operating' cycle

22. This submittal should include further discussions on the design life time, including reactivity, of the new hafnium control blades and a description of any physical differences (i.e. dimensional differences, material differences, welding techniques) between the NUCOM and GE control blades that would account for NUCOM blades being lighter than the GE blades.

.