ML20002D887
| ML20002D887 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 03/02/1971 |
| From: | Walke G CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Morris P, Skovholt D US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8101230301 | |
| Download: ML20002D887 (4) | |
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CONSUMERS 1-0WER COMPANY g
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JACKSON, MICHIGAN 5
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TWX 517-787-1987 6[
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1971 M/R 2 PM i 32 3-2-7'1 1-10'PM
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MAR 2 197y ;
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DR P A MORRIS, DIRECTOR a>
m DIVISION OF REACTOR LICENSING UNITED STATES ATOMIC ENERGY COMMISSION e
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NAR 2 1971
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WITH REGARD TO YOUR STAFF"5 QUESTION CONCERNING THE CONSEQUENCES OF
'IHE LACKUP CORE SPRAY N022LE PARTING AND FALLING TO THE TOP OF THE CORE AREA IN THE BIG ROCK POINT REACTOR VESSEL THE FOLLOWING INFORMA-TION IS SUBMITTED-A-
IN TFE UNLIKELY EVENT THAT THE NO22LE WAS TO BREAK AND FALL TO THE CORE REGION, IT WOULD PROBABLY LODGE ITSELF SUCH THAT
' THE LOWER TIP WAS RESTING BETWEEN A FUEL BUNDLE HANDL!. AND GRID BAR WITH THE UPPER PORTION AGAINST THE BAFFLF PLATES.
THIS WOULD NOT SIGNIFICANTLY ALTER FLOW THROUGH Ali PORTION OF FUEL BUNDLE BECAUSE OF THE SI2E OF THE NO22LE TIP AND ITS INABILITY TO SEAT AGAINST THE UPPER TIE PLATE DUE TO PROTRU-h SIONS ABOVE THE TIE PLATE. IN THIS CASE ONLY ONE BUNDLE WOULD q
BE AFFECTED.
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B-A VERT SMALL CHANCE EXISTS THAT THE BROKEN N022LE WOULD CLEAR
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y THE BAFFLE PLATES AND FALL SUCH THAT IT WOULD LIE ACROSS THE TOP OF THE GRID BARS. IF THIS WERE THE CASE, THE REDUCTION IN FLOW WOULD BE VERY SLIGHT. IN THE WORST CASE F0R AN INDIVIDUAL CHANNEL THE EFFECT WOULD BE SIMILAR TO PLACING AN ORIFICE WITH FLOW ARIA APPROXIMATELY EQUAL TO THAT OF AN EMPTY FUEL CHANNEL ACROSS THE TOP of THE GRID BARS. ASSUMING THAT THE BROKEN N02ZLE LAYS ATOP THE GRID BARS ABOVE TEN FUEL BUNDLES, THE EFFECT ON THE TOTAL FLOW AND CORE DIFFERENTIAL PRESSURE WOULD BE VERY SMALL. IT WOULD NOT BE OBSERVABLE ON INSTRUMENTATION.
S89 C-IF THE NO22LE WERE TO ASSUME A POSITION AS DESCRIBED IN *B" ABOVE, CALCULATIONS THAT INCLUDE WEIGHT OF N022LE, BUOYASC5, AND DRAG FORCE CAUSED BY COOLANT FLOW INDICATE THAT THE NO22LE i
WILL NOT BE LIFTED FROM THE TOP OF THE GRID BARS. THE NET FORCE DOWNWARD UNDER THE MOST SEVERE CONDITIONS WAS 10.8 LB PER LINEAL FOOT OF THE N022LE.
i IN SECTION A.1.2/B/ OF THE PROPOSED TECHNICAL SPECIFICATION CHANGE 27.
PLEASE INSERT'THE FOLLOWING PARENTHETICAL PHRASE AT THE END OF THE '
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SENTENCE THAT READS *THE CORE SPRAY SYSTEM add SHUTDOWN COOLING SYSTEM SHALL BE OPERABLE AND. READY FOR SERVICE DURING REFUELING OPERATIONS.'
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/THE BP.EAXERS FOR MO 7070 AND MO 7071 SHALL BE TAGGED OPEN./
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N' ADDITION, TOUR STAFF REQUESTED FURTHER INFORMATION WITH REGARD TO THE s
TYPE OF TRANSIENT W AT WOdLD'CAUSE THE 3.2 DEGREE FAHRENHEIT PER SEC CHANGE REFERRED TO IN ANSWER *A* OF APPEN' II 2 IN THE PROPOSED CHANGE.
D W IS TRANSIENT OCCURS ON A RE CTOR SCRAM FROM 100 PERCENT POWER. ON A
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SCRAM THE TURBINE TRIPS, THUS EXT'RACTION STEAM IS LOST TO THE FEED-WATER HEATER TRAIN AND THE RAPID C00LDOWN AT THE TEEDWATER INLET N0ZZLES 70 THE STEAM DRUM OCCURS.. THE 300 DEGREE FAHRENHEIT PER HOUR "C00LDOWN RATE *. REFERRED 'TO IN QUESTION 'D' 0F THE SAME APPENDIX IS DEFINED AS WE 5MERGENCY C00LDOWN RATE IN'T E '" REACTOR TESSEL INSTRUCTION MANUAL.*
A '6'.4 DEGREE FAHRENHEIT PER MINUTE 5MERGENCY C00LDOWN RATE IS ALLOWED '
BY THE PRIMARY STEAM DRUM INSTRUCTION MANUAL.
100 CYCLES ARE ALLOW-ABLE AT THIS RATE.
THE ANSWERS TO THE TWO REMAINING QUESTIONS UILL BE SUBMITTED AS SOON AS THESE ANSWERS ARE AVAILABLE.
G J WALKE NUCLEAR FUEL MANAGEMENT ADMINISTRATOR i
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FROM.
DATE OF DOCUMENT.
DATE RECEIVED NO:
Consweers Power Conqpany 3-2-71 3-2-71
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RfG N O-DEsCR4P T SON (Must Be Upciassitted)
REFERRED TO DATE RECEevED ev DaTE TWX re Proposed Change Eo. 27 %
Ei 3-3-L Tech Specs sub=itting info re our W/9 cys for ACTION question concerning consequences of backup core spray nozzle parting &
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