ML20030A528
| ML20030A528 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 08/15/1974 |
| From: | Sewell R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8101090933 | |
| Download: ML20030A528 (3) | |
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CORSumCi'S Power t
j C0mpany General Offices: 212 West Mach -
Jackson Michigan 49201. Area Code S17 788 OSSO b.m August 15
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Docket 50-15 s
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Directorate of Licensing
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License DPR-6 US Atomic Energy Commission';
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Gentlemen:
Attached is one (1) original and thirty-nine (39) co-.
..med copies of the report entitled " Big Rock Point Plant Reactor Depressuri-zation System Description, Operation and Performance Analysis." This report is intended to fulfill our commitment made to you during our meeting of July 2h,1974.
As a result of design considerations, quenching media such as the spent fuel pool (discussed in our Special Report No 15) and an open quench tank were determined to be impracticable. The use of the spent fuel pool was rejected because of potential adverse effects on the stored spent fuel. The open quench tank was unacceptable because of excessive forces generated by the steam condensation phenomenon.
The reactor depressurization system (RDS) now being designed will dis-charge the steam into the steam drum enclosure where it condenses.
Various methods of assuring personnel safety following an inadvertent release of steam into the containment are being evaluated.
These methods include the use of shelters that will allow personnel to wait out the transient or provide a place to don protective clothing so as to permit exit from contaminant in the steam atmosphere.
It should be noted that Section 8.2, Periodic Testing,'is not included in this submittal. The testing requirements for the RDS presented in this section establish the test and surveillance inter-vals that are to be specified in a proposed change to the Technical Specifications. Under requirements of internal procedures, suggested Technical Specifications changes to be submitted with a request to amend our operating license must receive the review and approval of the Plant Review Committee and the Safety Audit and Review Board.
After this review and approval, Section 8.2 and the Technical Speci-fications will be sumitted. Our present schedule calls for this sub-mittal to be made by January 2.1075.
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- Directorate of Licensing 2
Big Rock Point Plant August 15, 1974 Engineering design and procurement activities related to the RDS are in progress. Certain mechanical components (piping and valves) have been committed to fabrication. Portions of the elec-trical systems that are not at this time critical path items are not as yet released for manufacture but it is our plan to permit this release in late fall of this year.
To permit an orderly incorporation of your comments in a manner to minimize their effects on the design effort to date, we would greatly appreciate the completion of your review of the en-closed report by October 1, 1974. We vill be happy to meet with you at any time as well as provide any additional information you deem necessary.
Yours very truly,
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RBS/ce Ralph B. Sewell Nuclear Licensing Administrator CC: JGKeppler, USAEC f
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,AEC DISP I3L*~ICN FOR PART 50 DCLKET PAT 7TAL i
(TaiPORARY F0Fli)
CO'iTROL NO:__ 8518 FILE:
FROHg DATE OF DOC DATE REC'D LTR TWX RPT GTiiER Consumers-Power Company J:ckson, MI Ralph B. Sewell 8-15-74 8-19-74 X
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ORIG CC OTHER SENT AEC PDR XXX SDiT LOCAL FD2 XXX Directorate of Licensing 1 signed 39 CLASS UNCLASS PROP INFO INPUT NO CYS REC'D DOCKET I;0:
XXX 40 50-155 "DESCRIPTICN :
ENCLOSURES:
ACKNOWLED Big Rock Point Plant Reacto[TED Ltr trans the following....
Report:
Depressurization System Description, Operation & Performance Analysis....
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B. HURT CASE KNIGHT BALLARD KREUTZER (E)
GIAMBUSSO PAWLICKI SPANGLER LEE (L)
PLANS BOYD SHA0 MAIGRET (L)
MCDONALD MOORE (L)(LWR-2)
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CHAPMAN DEYOUNG (L)(LWR-1)
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