ML20204J109

Rev 7 to Emergency Operating Procedure EOP 3.1-46, Total Loss of Semi-Vital Power

ML20204J109
Person / Time
Site:	Millstone, Haddam Neck, 05000000
Issue date:	05/12/1987
From:	CONNECTICUT YANKEE ATOMIC POWER CO.
To:
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ML20204H467	List: A07413, Forwards Specific Emergency Operating Procedures for Use During Incident Response Ctr Activation ML20204H704 ML20204H734 ML20204H868 ML20204H928 ML20204H963 ML20204J027 ML20204J039 ML20204J092 ML20204J109 ML20204J115 ML20204J120 ML20204J128 ML20204J133 ML20204J139 ML20204J147 ML20204J497 ML20204J543 ML20204J565 ML20204J627 ML20204J633 ML20204J638 ML20204J642 ML20204J659 ML20204J669 ML20204J685 ML20204J707 ML20204J733 ML20204J739 ML20204J746 ML20204J767 ML20204J781 ML20204J786 ML20204J814 ML20204J824 ML20204J849 ML20204J853 ML20204J865 ML20204J878 ML20204J902 ML20204J914 ML20204J920 ML20204J939 ML20204J947 ML20204J954 ML20204J958 ML20204J965 ML20204J975 ML20204J982 ML20204J994 ... further results
References
EOP-3.1-46, NUDOCS 8810240540
Download: ML20204J109 (3)

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meest-i nov, e.es E0P 301-46 Rev 7 (MAJOR) '

E0P1 MAY 121987 Connecticut Yankee PLA T oranATioHs naview couaittas AppmovAL Emergency Operating Procedure No. E0P 3.1-46 [M M Operations h/- -

TOTAL LOSS OF SEMI VITAL POWER M3 YbMb

, , _ , , h "D"7C""Cr 1.0 DISCUSSION 1.1 This procedure applies to the operation of the reactor plant at any time following a total loss of semi-vital power, and the steam generators are available for heat removal. This procedure does not apply if the RCS pressure boundary integrity is breached. -

2.0 SYMPTOMS 2.1 Rx trip from SF/FF mismatch with a steam generator low level caused by the tripping of both feed pumps on low suction pressure. Auto auxiliary feedwater system wC1 start.

2.2 Loss of all RMS indications,::mo alarms, t~

2.3 Loss of RCP seal water return flows, lower bearing water temps, and labyrinth delta Ps.

2.4 Loss of individual loop Tavgs and loop delta Ts. Plant Tavg and' Plant delta T still functions.

2.5 Loss of all pressurizer temp. indications.

2.6 Loss of relief tank level, press, and temp. indications.

2.7 Charging flow control valve (s) will fail open.

2.8 Loss of aux, feed flow inoication. "

2.9 Loss of PORY control and indication. -

2.10 Alternate letdown inoperative due to DH trip valve and CCW TV for drain cooler failing closed.

2.11 Loss of all rod position indication - no rod bottom Ifghts.

G Page 1 of 3 8810240540 8810o7 DR ADOCK O y3

l E0P 3.1-46 Rev.7(MAJOR)

E0P1 2.12 Letdown valves g) c1csed. W 2.13 Loss of auto makeup capability to VCT.

3.0 AUTOMATIC ACTION 3.1 Reactor trip, turbine trip.

3.2 The standby charging pump auto starts.

3.3 The standby component cooling pump auto starts.

3.4 Charging pumps trip after 65 second time delay (trip can be defeated by placing UV defeat switch in bypass).

7 I

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. E0P 3.1-46 Rev.7(MAJOR)

E0P1

{ ACTION / EXPECTED RESPON5E RE5PONSE NOT OBTAINED MAYI 21987 4.0 IM9EDIATE OPERATOR ACTIONS 4.1 Perfonn immediate actions in E-0, Reactor Trip or Safety Injection, if not done.

4.2 Stop all RCPs.

4.3 If chg pump is running THEN 4.3 Open BA-MOV-386 (metering o wn BA-MOV-373 RWST to suction from RWST).

c.iarging pumps. Close CH-A0V-278. i-Start metering pump.

4.4 Close CH-MOV-257 VCT outlet.

4.5 Place chg pump UV defeat switch to bypass position.

5.0 SUBSEQUENT OPERATOR ACTION ,

5.1 Take manual control of E 5.1 Throttle CH-MOV-2928 and C.

charging flow using charging!-

C line FCY. 3 E

5.2 Reset auto aux feed and control FW flow manually.

5.3 Place both feed pumps and HTR drain pumps in TPO. f 5.4 Stop SG blowdowns.

4 5.5 Stop all liquid releases. '

5.6 Stop all gas releases.

5.7 Start auxiliary oil pump. 5.7 Start TG oil pump. I 5.8 Close seal water return MOVs. l 5.9 Return to procedure and step in effect. l i

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