ML20002D910
| ML20002D910 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 04/08/1971 |
| From: | Walke G CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Morris P, Skovholt D US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8101230382 | |
| Download: ML20002D910 (6) | |
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CONSUMERS POWER COMPANY p
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PARNALL ROAD OFFICE go. /g a
JACKSON, MICHIGAN
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TVX 517-7B7-1987 U.S. AT0*'#C thERGY COMM.
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4-8-71 5-20 PM
- s DR P A MORRIS, DIRECTOR 1
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hPED g F TECH SPEC CHANGE NO 27
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ATT-D J SKOVHOLT 4
YOUR STAFF HAVE RECEriTLY EXPRESSED C0tiCERt! OVER THE ACTUATION SCFEr.E CF M07C70 AND M07071. THIS CONCERf IS THAT THE 40 SECOND TIME DELAY IN OPENIt:C OF THESE VALVES AS DESCRIBED IN PARACRAPH H.3 / TABLE 6.1.4
/C/ OF TECH SPEC CHANCE NO 27/ VILL RESULT IN HIGHER IUIL CLAD TEt:FER-ATURES FOR THE BIC BREAK ACCIDENT COMBINED WITH A FAILURE IN ll'I ORIC-INAL CORE SFRAY SYSTEM TFAN SHOWN IN PREVIOUS SUBMITTALS.
AS A RESULT OF THIS CONCERN, VE HAVE REINVESTICATED POSSIBLE ACTUATION SCHEMES FOR THE CORE SPRAY SYSTEMS. AS A RESULT OF THESE INVESTIGATIONS, WE REQUEST THE SUBJECT TECH SPEC CHANCE RECUEST BE REVISED TO READ AS FOLLOVS -
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/A/ PARACRAPH M.2 /6.1.4/8//
- /B/ BACKUP CORE SPRAY SYSTEM CONTROL tg Q W $ Q )......................
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- TH[" BACKUP CdC) SPRAY SYSTEM SHALL DE AU).ATICALLY ACTUAT BY SIMULTANEOUSLY TRIPPING OF TEE *LOV REACTOR WATER LEVEL j7^L SENSOR
- ALONG WITH THE *LOV REACTOR PRESSURE DEVICE.* T REA'CTOR PRESSURE DEVICE" CONSISTS OF A PRESSURE SWITCF VALVES OPE? ING VHICH PREVENTS BACKUP CORE SPRAY SYSTEM ADMISSIOJ:
WHILE REACTOR PRESSURE IS ABOVE 2CC PSIG.*
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/B/
d PARACRAPH H.3 / TABLE 6.1.4/CXX//
ACTUATION SETTING ANO
~ SENSOR CONTACTS TOLERANCE PUNCTION LOV REACTOR 2 SVITCFES/ VALVE 200 PSIC ACTUATES f.07C7C PRESSURE 1 OUT OF 2 PLUS CR MINUS AND 7071 IN CON-COINCIDINCE 20 PSI JUNCTIO5 WITF LOU SWITCHES REACTOR WATER LEVEL VALVE POSITION SWITCHES M07051 LELETE SENSOR, ACTUATION CONTACTS, AND 7061 /2 SETTING AND TOLERANCE AND FUNCTION SWITCHES PER DESCRIPTIONS VALVE /
TIMI DELAY DELETE SENSOR, ACTUATION CORTACTS,
/2 SWITCHES /
SETTING AND TOLERANCE AND TUNCTION DESCRIPTIONS THE PORTIONS OF TABLE 6.1.4/C/ NOT DESCRIBED ABCVE SHOULD REM UNCHANCED.
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TYESE CHANGES VI(MLLOV BOTH M07C51 At:D 70611ND K
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BE ACTUATED IMMEDI ATELY UPON RECEIPT ' OT ' LOU REACTOR VATER LEVEL" AND LOV REACTOR PRESSURE" SIGt:ALS At:D ELIMINATE TFE TIME DELAY BITWEEN RECEIPT OF ACTUATION SIGNAL AND OPENING OF.M07070 AND 7071. FLOW CALCULATIONS HAVE BIEN PERFORf:ED To DETERMINE THE EFTECT OF S!MUL-TANE0US TLOV It! BOTH THE CORE SFRAY At:D BACKUP CORE STRAY SYSTEM 3 FOR THE CONPITIONS-A.
BOTP SYSTEMS INTACT B.
ORIGINAL CORE SPRAY LINE RUPTURED AT REACTOR VESSEL, BACKUF SYSTEM INTACT THE RESULTS OF TEESE CALCULATI0tS ARE /ASSU!*ING ELECTRIC FIRE FU::F rut:t:It:C/-
A..BOTK SYSTEMS INTACT 4
REACTOR FLOU F(OU PF.EISUF.E ORIGINAL BACKUP
/PSIG/
SYSTEM /GFM/
SYSTEM /GPM/
80 275 275 40 3 65 365 470 0
47C B.
ORIGINAL CORE SPRAY LINE RUPTURED AT THE REACTOR VESSEL, BACKUP LINE INTACT
. R EA CTOR TLOV OUT TLOV PRESSURE RUPTURE BACKUP 1
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/PSIC/
/GPM/,
SYSTEM GPf;
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)185 70 V
575 36 530 320.
Ti!IS CHANGE IN THE ACTUATION SEQUENCE WILL INSURE THE INTRODUCTION OF AN ADECUATE AMOUt:T OF TLOW TO COOL THE CORE IN THE MINIMUM AMOUNT OF TIME ASSUMING A RUPTURE IN TFE ORIGINAL CORE SPRAY SYSTEM. IMMEII ATEL RAKX2R IN AFTER INITIATION OF TEESE SIGNALS THE OPERATOR WILL JUDGE WEICF SYSTEM TO RD:0VE FROM SERVICE BY OBSERVATION OF VALVE POSITION INDICATI0t,
FLOW AND PRESSURE INSTRUMDJTATIONS.
THE DATA PRESD;TED ABOVE ASSUf'IS THE. CONTAINMENT SPRAYS ARE NOT It! OPER-ATION BECAUSE THE C0!:TAIN!:D T SFRAYS ARE NOT AUTO::ATICALLY ACTUATED UNTIL FIVE MINUTES AFTER RECEIFT OF A HIGP CONTAINMD:T PRESSURE SIG"AL.
PLANT OPERATING INSTRUCTIONS WILL BE CHANGED TO IN3URE THE OPERATCR3 REMOVE II1TER TEE CORE SPRAY OR BACKUP CORE SPRAY SYSTU: FR0!: SERVICI
/AS TvE PRECISE SITUATION DICTATES / AS SOON AS POSSIELE AFTER INITIATION OF TFE CORE STRAY SYSTD:3 AND BEFORE EITEER MANUAL OR AUTCMATIC It:ITI A--
TION OF THE CONTAINMD T SPRAY SYSTD:5.
VE ARE CURRENTLY INVESTIGATINC TKI AMOUNT OF VORK RECUIRED TO MAKE TFE CHANCES DESCRIBED ABOVE. TFESE CHANGES WILL BE MADE DURING TFE NEXT
- PLANT CUTAGE ASSUMING ALL NECE3SARY MATI.tI ALS ARE AVAILAELE AT TF AT T!!.E.
FLEASE NOTIFY U3 IMMEDI ATELY IF YOU DO NOT AGREE WITF THIS PLAMMED COURSE OF ACTION.
GERALD J WALKE A
NUCLEAR FUEL MANAGEMDIT ADMINISTRATOR CC-R L EAUETER R B SEWELL i
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CORRECTION - UNDER SECOND /B/ PARAGRAPH H.3
/ TABLE 6.1.4/C//
03 O ARE YOU THERE 0)
CPCO PARN JXN AEC RECD OK TNKS
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oATE or ooCuuENT:
DATE RECEsvEn N o.:
Ceasamers Power Ceepany 4 3 71 4-9-71
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Dr. Peter A. MORELS e;isoN NECE$$4RT h
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No action NECE$$4av 0 Co--E~T O
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POST OF F6CE F iLE CODE.
CLAN $iF :
50-155 y
REG, NO-REFERRED TO DATE RECENED SY DaT E (Must Be Uncl333ihed)
DESCRIPT.oN:
TUI re Change Request No. 27 to Tech Eiemann 4-9-71 Specs...taq Change Reguest be revised W/9 cys for ACTION to reed.........
DISTRIBUTION:
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