ML20002C693
| ML20002C693 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 07/24/1973 |
| From: | Sewell R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Oleary J US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8101100735 | |
| Download: ML20002C693 (4) | |
Text
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Power Company General Offsces: 212 West Michigan Avenwo. Jackson, Michigan 4920:. Area Code 517708 05S0 July 24, 1973
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License No DPR-6 94 Directorate of Licensing US Atomic Energy Camission h
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Washington, DC 20545 t'
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Dear Mr. O' Leary:
By letter dated January 5,1973, Mr. Dennis L. Zieman requested additional infomation vith respect to infomation submitted by Consumers Power Company concerning the Big Rock Point " Loss-of-Coolant Accident Analysis (LOCA)." This letter is written to provide requested infoma-tion that is presently available.
At the present time, complete information is not available with respect to gama smearing, further test data with respect to rod wetting and metal / water reaction taking into account the reaction on the interior of the cladding. It is our understanding that a topical report will be submitted by General Electric Company (GE) concerning gamma smearing within the next several months. This report will show that the 4% reduction in decay heat assumed in our previous analysis will be shown to be conserva-tive. Further testing has been perfomed by GE with respect to unpowered rod wetting, and data reduction is still in progress. It is currently anticipated that the data reduction will be completed such that additional verification of the rod wetting model will be provided by the end of 1973 Inside and outside metal / water reaction has not been calculated because no models are presently available. We anticipate that this information can be provided, if appropriate, several months after a decision is reached in the ECCS rule-making hearings.
Sensitivity studies have been performed for Reload G fuel assem-blies with respect to the gama smearing allowance and number of unpowered rods in a fuel assembly. These studies are su-rized below for the design basis accident (DBA):
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2 Docrat No 50-155 License No DPR-6 July 24, 1973 Peak Clad Temperature for DBA Original Reload G Reload G-1 (1 Unpowered Zr Rod)
(4 Unpowered Zr Rods)
A.
Base Case 4% Gamma Smearing Credit Unpowered Zircaloy Rod (s) Wet (s) 2284 F 2036 F B.
Gamma Smearing Effect Same as A, Except NO Gamma Smearing Credit 2411 F 2092 F C.
Rod Wetting Effect See as A, Except No Unpowered Zircaloy Rod o
Wetting Credit 2657 F 2658 F D.
Unpowered Rod (s) Effect Same as C, Except Unpowered Zircaloy Roes Replaced With Fuel Rods W.th Local Power Factors of 1.0 (Same Bundle, Average Power) 2727 F 2785 F Attached is a copy of Special Report No 15 titled " Preliminary -
Description of Reactor Depressurization System, Big Rock Point." Although final design work is still in progress on the system described, the con-cepts are considered firm and we are moving ahead with procurement activi-ties in order to meet the deadlines established by the Interim Policy Statement. Your expeditious review and ccenments on the system design will be appreciated. We intend to submit a final design report and pro-posed technical specification changes not later than January 1974.
You will note in Special Report No 15 that three one-half capacity depressurization valves are being provided such that any single failure will not reduce the blowdown rate below the design value. In addition, the ca-pacity of the valves is such that the inadvertent failure open of any one valve will not result in the core being uncovered (refer to Figure II of Attachment A of our February 9,15r/0 letter to Dr. Peter A. Morris).
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DocknlNo 50-155 Licensa No DPR-6 i
July 24, 1973
~~Again, we will appreciate receiving any ccanents concerning the ~
- Reactor Depressurizing System as soon as possible.
Yours very truly, k.-
- RBS/ map Ralph B. Sewell Nuclear Licensing Administrator
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(TDiPORARY FORM)
CONTROL NO: 5738 FILE:
FRCH:
DATE OF DOC DATE REC'D LTR MEMO RPT OTHER C:nsumers Power Comonny Jackson, Michican 49201 Rolph B. Sewell 7-24-73 7-26-73 X
T03 ORIG CC OTTER SENT AEC PDR V
SENT LOCAL PDR Mr. O'Learv 1 sicned CLASS UNCLASS PROP INFO INPUT NO CYS REC'D DOCKET NO:
XX 40 50-iss DESCRIPTION:
ENCLOSURES:
Ltr re our 1-5-73 l tr..... fitrnishing requested REPORT: Special Renort No. 15 - Pre-info concerning " Loss-of-Collant Accident
~~lininary Description of Reactor De-Analysis (LOCA) ".......& trans the following:
pressurization System for the Big Rock Point Plant.
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( 40 cvs rec'd)
PLANT NAME:
Bin Rock Point g gy FOR ACTION /INF0PJfATION 7-N 71 AB BUTLER (L)
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CASE KNIGHT BALLARD COULBOURNE (L)
PLANS GIAMBUSSO PAWLICKI SPANGLER LEE (L)
MCDONALD BOYD SHA0 MAICRET (L)
DUBE MOORE (L)(BWR)
STELLO ENVIRO SERVICE (L) y DEYOUNG(L)(PWR)
HOUSTON MULLER SIEPPARD (E)
INFO V SKOVIIOLT (L)
NOVAK DICKER SMITH (L)
C. MILES P. COLLINS ROSS KNIGHTON TEETS (L)
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