ML20205C465
| ML20205C465 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Haddam Neck, 05000000 |
| Issue date: | 06/15/1988 |
| From: | CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | |
| Shared Package | |
| ML20204H467 | List:
|
| References | |
| EOP-35-FR-C.2, NUDOCS 8810260506 | |
| Download: ML20205C465 (9) | |
Text
. _ - _ _ _ _ _ _ _ _ _
I St'ph n E.
ace 3-31-87 87-12 Fcrm Apprsved by Stativ. SuperintCnd;nt Effective D ho 50RC Mtg. No.
r i.
STATION PROCEDURE COVER SHEET
(
A.
IDENTIFICATION V
Number: E0P 35 FR-C.2 4ev.
2
Title:
R.oPONSE TO DEGRADED CORE COOLING Prepared By: H. K. COVIN B.
REVIEW I have reviewed the above procedure and have found it to be satisfactory.
TITLE SIGNATURE DATE 7l A7 b, @,v 6 / f 17 DEPARTMENT HEAD 3
s i v j l
C.
SPECIFIC UNREVIEWED SAFETY QUESTION EVALUATION REQUIRED:
Modifies intent of pr3cedure and changes operation of systems as described in design documents.
YES [ ]
NO [-1" (If yes, perform written USQ determination and Safety Evaluation, and contact Manager, Safety Analysis Branch to determine need for Integrated Safety Evaluation.)
ENVIRONMENTAL REVIEW REQUIRED (Adverse environmental impact)
YES ( ]
NO [@
0.
SPECIFIC SAFETY EVALUATION PFOUIRED Affects response of safety systems, performance of systems which may have been credited in the safety analysis or non-credited systems which may indirectly affect safety system response.
YES [ ]
NO [Jr (If yes, perform written Safety Evaluation and contact Manager, Safety Analysis Branch to determine need for Integrated Safety Evaluation.)
E.
INTEGRATED SAFETY EVALUATION REQUIRED YES [ ]
NO(-Y F.
PROCEDURE REQUIRE h SORC REVIEW (In addition to rs W 6 ite with a YES response must be documented in the; OR SORC meeting minutes.)
YES [-T NO [ ]
G.
50RC APPROVAL SORC Meeting Number 3-8 7-///f H.
APPROVAL AND IMPLEMENTATION eby approved, and effective on the date below:
The attached r e
f dl - pr W
./
StatT6n/ Service / Unit Superintendent Effective Date ~
SF 301 Rev. 9 age 1 M 1 8910260506 001007 PDR ADOCK 05000213 P
E0P 35 FR 2
Page 1 Rev. 2 i
l RESPONSE TO DEGRADED CORE COOLING Page No.
Eff. Rev.
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RESPONSE TO DEGRADED CORE COOLING E0P 35 FR-C.2 Pege 2 Rev. 2
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A.
PURPOSE This procedure provides actions to restore adequate core cooling.
B.
ENTRY CONDITIONS This procedure was written for Modes 1, 2 and 3.
Using this procedure when not in these modes requires a step by step evaluation to determine if the required action is still applicable to current plant conditions.
This procedure is entered from E0P F-0.2, CORE COOLING Critical Safety Function Status Tree, on any ORANGE condition.
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RESPONSE TO DEGRADED CORE COOLING-E0P 35 FR-C.2 Page 3 Rev. 2
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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OETAINEO CAUTION If RWST level decreases to <520,000 gal, the ECCS Systems j
should be aligned for cold leg recirculation using E0P 35 ES-1.3. TRANSFER TO COLD LEO RECIRCULATION, 1
Verify ECCS Valve Alignment -
Manually align valves as PROPER EMERGENCY ALIGNMENT necessary 2
Verify ECCS Flow In All Trains a.
Charging pump SI flow a.
START pumps and align,
indicator - CHECK FOR FLOW valves as necessary b.
SI pump flow indicators -
b.
START pumps and align CHECK FOR FLOW valves as necessary c.
RCS pressure < 300 psia c.
Go to Step 3.
l (450 psia FOR O
ADVERSE CONTAINMENT) d.
RHR pump flow indicators -
d.
START pumps and align CHECK FOR FLOW valves as necessary 3
Check RCS Vent Paths a.
PZR PORVs - CLOSED a.
Manually CLOSE PZR PORVs.
IF any valve can NOT be closed, M manually CLOSE its olock valve, b.
Block valves - AT LEAST b.
OPEN block valve unless ONE OPEN it was closed to isolate an open PZR PORV.
c.
Reactor vessel head vent c.
CLOSE reactor vessel isolation valves - CLOSED head vent isolation valves.
d.
PZR vapor space sample d.
CLOSE PZR vapor space isolation valves - CLOSED sample isolation valves.
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e RESPONSE TO DEGRADED CORE COOLING EOP 35 FR-C.2 Peg 2 4 Rev. 2 STEP ACTION / EXPECTED NESPONSE RESPONSg NOT OSTAINED NOTE Normal conditions for running RCPs are desired BUT RCPs should NOT be tripped IF normal conditions can NOT be established or maintained.
4 Check RCP Status a.
At least one RCP - RUNNING a.
Go to step 7.
b.
RPCCW to RCPs - AVAILABLE b.
Establish RPCCW to RCPs.
c.
Seal injection to RCPs -
c.
Establish seal injection.
CHECK FOR FLOW d.
Seal water return from d.
Establish seal water RCPs - CHECK FOR FLOW 1e a ko f f.
5 Check RVLMS Indication a.
Plenum Indication 1 19%
a.
Go to Step 6.
b.
Return to procedure and s g step in effect 6
Check if One RCP Should Be Stopped a.
a.
Go to Step 8.
RUNNING b.
STOP one RCP using the following order as a guide (RCP 2, 1 THEN 3, 4) c.
Go to Step 8 7
Check Core Cooling a.
RVLMS plenum indication a.
Go to Step 8.
1 19%
b.
Core exit TCs < 720'F b.
IF decreasing, THEN return to Step 1.
1F E, THEN go to Step 8.
N c.
Return to procedure and step in effect.
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RESPONSE TO DEGRADED CORE COOLING E0P 35 FR-C.2 Page 5 Rev. 2 O
STEP
~
ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINED l
0 Check SI Accumulator Isolation Valve Status a.
Isolation valves - OPEN a.
Open isolation valves
{
as follows
- 2) OPEN isolation valves i
UNLESS closed after 6
accumulator discharge.
- 3) Remove power from l
isolation valves.
CAUTION u
1.
CST water source for AFW pumps will be necessary IF l
DWST level decreases to <80,000 gal.
l 2.
A faulted or ruptured SG should NOT be used in subsequent steps UNLESS no intact SG is available.
i 9
Check Intact SG Levels a.
Narrow range level a.
Raise total feed flow i
> 4% (34% FOR ADVERSE to restore narrow range CONTAINMENT) level > 4% (34% FOR ADVERSE CONTAINMENT) in at least one SG i
I b.
Control feed flow to maintain narrow range level l'etwe en 4%
}
(34% FOR ADVERSE CONTAINMENT) and 50%
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e RESPONSE TO DEGRADED CORE COOLING E0P 35 FR-C.2 Page 6 Rev. 2 N
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINEO CAUTION The following step may cause a red path condition in E0P 35 F-0.4, INTEGRITY CRITICAL SAFETY FUNCTION STATUS TREE. This procedure should be completed before transition of E0P ?.5 FR-P.1, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK.
10 Depressurize All Intact SGs To 134 psig a.
Maintain cooldown rate in RCS cold legs < 100*F/HR l
b.
Dump steam to condenser b.
Manually OR locally 1
dump steam from SGs to i
Atmosphere 1
c.
Check SG pressures c.
Return to Step 9.
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< 134 psig d.
Stop SG depressurization I
l CAUTION
195'F without RPCCW to the RHR HXs.
4
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I 11 Check RHR Pumps - RUNNING START pumps as necessary.
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OPMekt 344
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RESPONSE TO DEGRADED CORE COOLING EOP 35 FR-C.2 Page 7 Rev. 2 sTap AcT10N/expeciso RespoNas assPONas NOT OsTAINED 12 Check If SI Accumulators Should Be Isolated a.
At least two RCS hot leg a.
Go to Step 14.
temperatures < 375'F b.
Restore power to isolation valves i
(32-2R-RSF, 32-2W-R3J, 32-2R-F4M, 32-2W-F4M) c.
CLOSE all SI accumulator c.
Vent any unisolated isolation valves accumulator l
d.
Remove power from isolation valves CAUTION Symptoms for E0P 35 FR-C.1, RESPONSE TO INADEQUATE CORE COOLING, should be closely monitored during subsequent steps.
O 13 STOP All RCPs 14 Depressurize All Intact SGs To Atmospheric Pressure a.
Maintain cooldown rate in RCS cold legs < 100*F/HR b.
Dump steam to condenser b.
Manually OR_ locally dump steam from SGs to Atmosphere O
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RESPONSE TO DEGRADED CORE COOLING E0P 35 FR-C.2 Paga 8 Rev. 2 f
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~j STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINED
___15 Verify ECCS Flow Continue efforts to establish ECCS flow.
Return to Step 14.
a.
Charging pump SI flow indicator - CHECK FOR FLOW SE b.
SI pump flow indicators -
CIIECK FOR FLOW 93 c.
RHR pump flow indicators -
CHECK FOR FLOW 16 Isolate SI Accumulators a.
Restore power to isolation valves (32-2R-R5F, 32-2W-R3J, 32-2R-F4M, 32-2W-F4H) q q,,)
b.
CLOSE All SI Accumulator b.
Vent any unisolated Isolation Valves accumulator c.
Remove power from isolation valves 17 STOP All RCPs
___18 Check Core Cooling Return to Step 14.
a.
RVLMS plenum level
> 19%
b.
At least two RCS hot leg temperatures <350'F l
___19 Go to E0P 35 E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 12
-FINAL-(">
OPK441 1 44