ML20030A453

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Forwards Request for Change to Tech Specs Re ECCS Acceptance Criteria.Proposed Changes to Be Valid Nov 1974-Mar 1975
ML20030A453
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 10/31/1974
From: Lamley R, Sewell R
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To: Muntzing L
US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 8101090540
Download: ML20030A453 (8)


Text

y Oh Jeguhitory Docket Rle 4 19 74 i "@,gw ~ */

CORSumBil M

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,)i Power C0mpany

,s General Offices: 2132 West MicNgan Avenue, Jackson, M6cNgan 49201 e Area Code 517788-0550 A'

C October 31, 197h x

3 80CKETI3 HAEC NOV 5 1974 9

B2mti:M kA!L CliC1 NT M Mr. L. Manning Muntzing Re: Docket 50-155 Director of Regulation License DPR-6 gy/ Il11 \\

US Atomic Energy Commission Big Rock Point Plant Washington, DC 20545 ECCS Acceptance Criteria

Dear Mr. Muntzing:

On August 5, 197h Consumers Power Company was granted an extension until March 31, 1975 to submit the Final Acceptance Criteria evaluation in accordance with 10 CFR 50.46 for Big Rock Point. This extension was granted with two conditions: That (1) upon receipt of the final evaluation model and analysis from the vendors, Consumers Power Company would submit this evaluation model and analysis for concurrent review by the Regulatory staff, and (2) on or before October 31, 197h Consumers Power Company would submit a preliminary evaluation of ECCS performance consistent with the requirements of Appendix K although not necessarily containing the full detail and the full documentation called for in Appendix K, along with proposed license amendment or Technical Specifications changes which would bring reactor operation into conformity with the requirements of 10 CFR 50.h6. Upon submission of the preliminary evaluation, Con-sumers Power Company would commence operation within the limits of such proposed Technical Specifications as well as all Technical Specifications previously imposed by the Commission, including the requirements of the Interim Acceptance Criteria, or our variance granted from such requirements (variance from the Interim Acceptance Criteria granted on August 5, 1974 until March 1, 1976), unless Consumers Power Company files with the Commission a request for exemption from the requirements of 10 CFR 50.h6 and such request is granted.

This letter with the attached proposed changes to the Technical Specifications and safety analysis is intended to satisfy Condition 2 above. Consumers Power Company at this time does not request an exemption from the operating requirements implied by 10 CFR 50.h6 as u understand that the variance from the Interim Acceptance Criteria is valid until conformance with the 10 CFR 50.h6 criteria is required, and conformance with the 10 CFR 50.46 criteria 11275

' Mr. L. Manning Muntzing 2

ECCS Acceptance Criteria October 31, 1974 is required at the earliest by April 1, 1975 following submittal of the evaluation model and analysis. Accordingly, we anticipate requesting an exemption from the operating requirements implied by 10 CFR 50.46 concurrent with our submittal of the final evaluation model and anal-ysis on March 31, 1975 Consumers Power Company requests General Electric Company to assist in any way possible but on a not-to-interfere basis with other FAC requirements in providing the estimate required by October 31, 197h.

General Electric agreed to provide preliminary information on clad heatup, swelling and rupture as a function of linear heat generation rate for the General Electric fuel types that have been identified as limiting in earlier IAC analysis. The General Electric information has been delayed, primarily due to slow mail delivery of seme necessary input data but also due to workload requirements of gaining FAC evaluation model approval and performing specific analysis. We expect to have the General Electric re-sults within the next week and vill transmit appropriate changes in a timely manner if these results show more restrictive limits are in order.

The attached proposed changes in the Technical Specifications are intended to be valid for the period November 1, 197h to March 31, 1975, the date the final FAC evaluation is to be sumbitted. Big Rock Point is currently operating within these proposed Technical Specifica-tions in accordance with the second condition stated in the first para-graph of this letter.

Yours very truly, 1

RBS/mel Ralph B. Sewell Nuclear Licensing Administrator CC: JGKeppler, USAEC W

a 1

CONSUMERS POWER COMPANY Docket No 50-155 4

Request for Change to the Technical Specifications License No DPR 6 For the reasons hereinafter set forth, the following changes to the Technical Specifications of License No DPR-6 issued to Consumers Power Company on May 1, 1964,-for the Big Rock Point Plant, are

- requested:

I.

Changes A.

Change the table contained in Section 5 2.1(b) to read as follows:

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2 Reload E-G and F, J-1 & J-2 Reload G Minimum Core Burnout Ratio at Overpower 1.5*

1 5""

Transient Minimum Burnout Ratio in Event of La s of Recirculation Pumps From Rated Power 1.5 1.5 Maximum Heat Flux at Overpower, Btu /h-ft 500,000 395,000 Maximum Steady-State Heat Flux, Btu /h-ft h10,000 32h,000 Maximum Average Planar Linear Heat Generation Rate, Steady State kW/ft 10.3h T.00 Stability Criterion: Maximum Measured Zero-to-Peak Flux Amplitude, Percent of Average Operating Flux 20 20 Maximum Steady-State Power Level W 2hD 2h0 t

Maximum Value of Average Core Power Density @240Mg,kW/L h6 46 Maximum Reactor Pressure During Power Operation, Psig 1,h85 1,485 Minimum Recirculation Flow Rate, Lb/h (Except During Pump Trip Tests or Natural 6

6 Circulation Tests as Outlined in Sect 8) 6 x 10 6 x 10 Maximum mwd /T of Contained-Uranium for an Individual Bundle 23,500 23,500 Rate-of-Change-of-Reactor Power During Power Operation:

Control rod withdrawal during power operation shall be such that the average rate-of-change-of-reactor power is less than 50 MWt per minute when power is less than 120 W, less than 20 Wt per minute when power is between 120 and t

200 MW, and 10 W per minute when power is between 200 and 240 MW

  • t t

t

  • Based on correlation given in " Design Basis for Critical Heat Flux Condition in Boiling Water Reactors," by J. M. Healzer, J. E. Hench, E. Janssen and S. Levy, September 1966 (APED 5286 and APED 5286, Part 2).
    • Based on Exxon Nuclear Corporation Synthesized Hench Levy.

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3 B.

Cnange Table 8-2 to read as follows:

TABLE 8.2 Centermelt EEI UO -PuO 2

2 Intermediate Advanced NFS-DA Minimum Core Burnout Ratio at Ovtrpower 1.5*

1.5*

1.5" 1.5 Transient Minimum Burnout Ratio in Evint of Loss of Recirculation From Rated Power 1.5 1.5 1.5 1.5 Maximum Heat Flux at Overpower, 2

h02,000 Btu /h-Ft 500,000 Maximumgteady-StateHeatFlux, Btu /h-Ft 410,000 500,000 500,000 329,000 Maximum Average Planar Linear Heat

'f.23 Generation Rate, Steady State kW/Ft St bility Criterion: Maximum M;asured Zero-to-Peak Flux Amplitude, Percent of Average 20 Operating Flux 20 Maximum Steady-State Power Level, MW 20 2h0 t

Maximum Value of Average Core Power 1,h85 Operation, Psig 1,h85 Minimum Recirculation Flow Rate, Lb/h (Except During Pump Trip Tests or Natural Circulation Tests ac Outlined 6 x 10 in Section 8) 6 x 10 Maximum mwd /T of Contained Uranium 23,500 for an Individual Bundle 23,500 Number of Bundles:

Pellet UO 1

3 2

Powder UO 1

2 2

Rate-of-Change-of-Reactor Power During Power. Operation:

Control rod withdrawal during power operation shall be such that the average rate-of-change-of-reactor power is less than 50 MWt per minute when power is less than 120 MW, less than 20 MWt per minute when power is between 120 and 200 MWt and t

10 MWt per minute when power is between 200 and 2h0 MW

  • t cBased upon critical heat flux correlation, APED-5286.

ocho longer used in reactor.

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4 II.

Discussion On August 5,1974 the AEC granted an extension of the deadline for submitting an ECCS evaluation of Big Rock Point in accordance with the Final Acceptance Criteria of 10 CFR 50.46 until March 31, 1975 One condition of the granting of this extension was that Consumers Power Company would submit a preliminary evaluation by October 31,197h along with proposed Technical Specifications changes which would govern reactor operation in the interim period November 1, 1974 to March 31, 197h.

Analyses have been performed on the four fuel types present in the Big Rock Point core to predict peak clad temperatures as a function of MAPMGR. These analyses have been performed by Consumers Power Company using the M0XXY/ Mod kB model previously described in Appendix A of our May 30,1974 submittal to the Directorate of Licensing. This model has been approved by the AEC for heatup analyses in accordance with the IAC.

No credit has been taken for inert rod wett'.ng during operation of the core spray.

The following table gives peak clad temperatures predicted for the DBA heatup by M0XXY/ Mod kB. The MAPLHGR corresponding to 2200 F have been obtained by linear interpolation.

Fuel Type F

Mod F G

NFS MAPMGR PCT MAPMGR PCT MAPMGR PCT MAPMGR PCT kW/Ft F

kW/Ft F

kW/Ft F

kW/Ft F

13.38 2756 13.55 2786 8.87 2779 9.31 2873 10.34 2200 10.41 2200 7.00 2200 7.23 2200 10.03 2143 10.16 2153 6.65 2092 6.98 2118 The 2200 F peak clad temperature was chosen to correspond with the 2200 F peak clad temperature criterion of the 10 CFR 50.h6 Acceptance Criteria. We feel this choice is a reasonable one on which to govern operation between now and March 31, 197h.

Conservatism is also contained in these estimates for the G and NFS fuel types in that no credit is taken for rod vetting. Consumers Power Company feels that credit for rod wetting is justified and will be allowed in applicable evaluation models when they are approved.

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5 Consumers Power Company has made every effort to meet the intent of supplying an evaluation of Big Rock Point in accordance with the 10 CFR 50.h6 Acceptance Criteria. We note that to our knowledge, there is no AEC-arproved evaluation model presently available to perform the evaluation due March 31, 1975 or the preliminary evaluation due October 31, 197h. Accordingly, the results contained herewith represent the best estimate of Big Rock Point ECCS performance.

III. Conclusion Based on the foregoing, the Big Rock Point Plant Review Com-mittee and the Safety and Audit Review Board have concluded that this change does not involve a significant hazards consideration.

CONSUMERS POWER COMPANY f

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0 W w - (y By

/A, Al R. A. Lamley, Vice PFesident Date: October 31, 1974 Sworn and subscribed to before me this 31st day of October 197h.

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Lois E. Barnes, Notary Public Jackson County, Michigan My commission expires June 20, 1976.

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AEC DISTRIBUTION FOR PART 50 DOCKET MATERML_

(TEMPORARY FORM)

CONTROL NO: 11275 FILE:

Consumers Power Company DATE OF DOC DATE REC'D LTR TWX RPT OTHER FROM: Jackson, Mich. 49201 Mr. R.B. Sewell 10-31-74 11-4-74 X

TO:

ORIG CC OTHER SENT AEC PDR m

L.H. Huntzing 3 signed SENT LOCAL PDR XXX CLASS UNCLASS PROPINFO INPUT NO CYS REC'D DOCKET NO:

XXX XXX 40 50-155 DESCRIPTION:

ENCLOSURES:

Ltr trans the following.....

Proposed changes to tech specs....re ECCS Aceptance Criteria........

ACKNOWLEDGED (40 cys encl rec'd)

PLANT NAME:

Big Rock Point DO NOT REMOVE FOR ACTION /lNFORMATION BUTLER (L )

SCHWENCER (L)e/2]EMANN (L)

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EXTERNAL DISTRIBUTION Fllll pRF

  1. - LOCAL PDR Charlevoix, Mich.

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  1. 1 TIC (ABERNATHY) (1)(2)(10)- NATIONAL LABS 1 - PDR-SAN /LA/NY

/1 - NSIC (BUCHANAN) 1 - ASLBP(E/W Bldg. Rm S29) 1 - BROOKHAVEN NAT LAB 1 - ASLB 1 - W. PENNINGTON, Rm E-201 GT 1 - G. U LRIKSON, ORN L 1 - Newton Anderson 1 - B&M SWINEBROAD, Rm E-201 GT 1 - AGMED (RUTH GUSSMAN)

/6 - ACRS IKUDOUGS Sent to 1 - CONSULTANTS Rm B-127 GT Diggs NEWMARK/BLUME/AGBABIAN 1 - R. D. MUELLER, Rm E-201 11-4-74 GT

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