ML20024C771

Emergency Operating Spec 69-1001168-01, Loss of Reactor Coolant/Rcs Pressure.

ML20024C771
Person / Time
Site:	Three Mile Island
Issue date:	05/15/1978
From:	Hallman D, Tracy Scott, Spangler W BABCOCK & WILCOX CO.
To:
References
TASK-*, TASK-02, TASK-2, TASK-GB 620-0024, 620-24, 69-1001168-01, 69-1001168-1, EOS-0162, EOS-162, GPU-0543, GPU-543, NUDOCS 8307130267
Download: ML20024C771 (11)

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TECHNICAL. DOCUMENT F

i ENERGBCY OPERATING SPECIFICATION

. 69 - 1001168 - 01 Doc. ID - Serial No., Revision No.

for LOSS OF REACTOR COOLAhT/ REACTOR COOLANT SYS17.H PRESSURE EOS 0162 m-T26800 CONFiii.:hiIAl PAGE 1 COUNSEL ONLY

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. TABLE OF CONTENTS / EFFECTIVE PAGE LIST 68-2001168-01' i

! stc7 ton Titti nst one. no.

l 1. 0 , PURPOSE 4 69-1001168-01 2.0 SYMPTOMS 4 69-1001168-01 5 69-1001168-01 j 3.0 AUTOMATIC ACTION 5 69-1001168-01

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! 4.0 IMEDIATE OPERATOR ACTION 5 69-1001168-01 5-1 69-1001168-01 5.0 SUB5EQUENT OPERATOR ACTION 6 69-1001168-01

. 7 69-1001168-01 6.0 RE."RENCES . 7 69-1001168-C1 7-1 69-1001168-01 I

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• "* CONI'lDENTIK l .

COUNSEL ONLY DATE: 2 24-78 PAGE 3

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69 1001168-01

TECHNICAL DOCUMENT i a  ;

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1.0 PURPCSE

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.i This specification describ.s the recanaended actions in the .vant j of an abnormal. decrease in Reactor Coolant System (RC3) pressure

or pressurizer level. The symptoms and actions are considered according to the severity of the accident.

1.1 Small leak - within the capability of one makeup pump to maintain

. RCS prassure.

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1.2 Intermediate leak - wi.hin the capability of the High Pressure Injection 017I) System to maintain RCS pressure.

j 1.3- Large leak - exceeds the capability of the HPI system to maintain

RCS pressure.

2.0 SYMPTOMS 2.1 Small Leak 2.1.1 Hakeup rank inventery decreasing during steady s. ate operation grea:e than the normal rate but less than the capacity of one makeup pump. ,

2.1.2 Makeup flow increasing with stable T,y,.

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! 2.1.2 Possible.radistics alar = in reae:cr building (R!) or other locatics that could indicate a RCS leak.

2.1J Possible R8 sump level increase. '

i 2.1.5 Greater than normal leakage during the routine performance of Reference 6.2.

2.2 Intermediate Leak 2.2.1 Pressurizer level and RCS pressure decreasing with stable T,y, and makeup flow increasing to an4==.

2.2.2 Makeup tank inventory decreasing greater than capacity of one

- askeup pump but less than capacity of HPI system.

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I 2.2.3 Radiation alarm in R3 or other location that could indicate a I RCS leak.

2.2.4 Increasing level in RB sump with possible high level alars.

2.2.5 Possible increase in RB pressure and temperature.

2.2.6 Possible makeup flow high alarm. bb 7, COUNSE!.OF 2 24 78 PAGE 4

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"'2 **l TECHNICAL DOCUMENT j 2.3 tarre Leak

! 2.3.1 Ra'id p decrease in press u i:er level and RCS press w e.

. - 2.3.2 Reactor and tubine trips accompanied by Engineered Safety Featwes Actuation System (ESFAS) actuation.

2.3.3 High radia-ion ala:n in R5 or other location that could indicate a RCS leak.

, 2.3.4 High reactor bu.ilding presswe .and temperature. -

^ ,! 2.3.5 High RB sump level with a high level ala:n. (01) 3.0 AUTOMATIC ACTION 3.1 Small Leak

, . Flow increases through pressuri:e level con =ol valve.

3.2 Intermediate Leak i

3.2.1 Flow increases through pressw i:e level control valve. (01)

- 3.2.2 Possible reactor trip (Low RCS pressure or low presswi:e level). (01) 3.2.3 Possible tu bine trip. (01) 3.2.4 Possible ESFAS actuation (Low RCS presswe). (01) 3.3 Larre Leak .

3.3.1 Reactor trip (Low RCS presswa or low pressuriser level)

( Turbine W.y

- 3.3.2 3.3.3 ESFAS Actuation (Low RCS presswe) f 4.0 IMMEDIATE CPERATOR ACTION i 4.1 Small Leak 4.1.1 Isolate letdown 4.1.2 Attempt to locate and isolate d e leak C0hFD&lTIAL T25804 0UNSEl. ONLY 2-24-78 PAGE 5 DATE:

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.mau ao-se semenaron owmen 69-1001168-01 TECHNICAL DOCUMENT l 4.2 Intermediate Leak 4.2.1 Tr'ip reactor and assure turbine trips 4.2.2 Isolate letdown

4. 2. 3 Initia o HPI 4.3 Large Leak 4.3.1 Verify automatic action has taken place.

4.3.2 Deleted. (01) 4.3.3 Trip all RC pumps if adequate suction pressure cannot be maintained. (01)

P CONFIDENT!AL T2see COUNSEL ONLY DATE: 2-24-78 PAG 3 5-1

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TECHNICAL DOCUMENT 68-1"116s-01 t

5.0 SUBSEQUENT OPERATOR ACTION h

, If a steam generator (SG) tube leak is suspected as the casualty (radiation in secondary steam system or other indication) when RC (01) pressure has been reduced below secondary safety valve setpoint, ischte the affected SG and use r===hMg SG for cooldown as reqi. ired. Additional measures to reduce seconda.y system contami-

. natian and to reduce or prevent the release of radioactive elements to the atmosphers should be taken.

5.1 Small Leak (01) 9 3.1.1 If leakage cannot be redu:ed to less than the limits of Reference 6.1 follow the actions required by Reference 6.1.

5.1.2 Maintain makeup tank level per Reference 6.3.

. 5.1.3 Te==inate RB purge if i= progress.

l 3.2 Inter:sediate Leak (01)

, 5.2.1 Operate third makeup pump to aid HPI as needed to maintain pressuri:er level.

i NOTE: It will be necessa.y to take water from the makeup tank periodically to prevent overfilling due to the return flow from RC pump seals.

5.2.2 Reduce the number of operatin2 RC pumps to one in each loop.

5.2.3 Te==inate R8 purge if in progress.

5.2.4 Cooldown the plant to cold shutdown.

5.2.5 Attempt to find and isolate the leak.

5.2.6 Prior to rizining out of water for HPI, or if HPI flow is below 900 GPM and pressure is above the ==*== allowed for the Decay Heat Removal System (DHRS), use the DHR pump to transfer water from the RS sump to HPI per References 6.3 and 6.8.

5.2.7 When RCS pressure allows, use DHR system in the RB st.. p recirculation mode per Reference 6.8.

NOTE: Insure refill and repressurisation of the RCS does not cause dead head of DHR pumps.

nssos ?NFIDENTTAT 3]Ur.' p m n y PAGE 6 DATE: 2-2a.73

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! 5.3 Large Leak (01)

5. 3.1 Verify proper operation of ESFAS, including initiation of low pressure injection when the setpoint is reached per Reference 6.4.

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5.3.2 Cooldown the plant in as near normal a manner as possible per Reference 6.6.

5.3.3 While still using water from the borated water storage tank (BWST),

assure adequate fluid supply to the high or low press =e injection -

systens will be available from the R1 sump prior to the BWST low level alarm per Reference 6.8.

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5.3.4 Esablish normal or RB sump recirculation decay heat removal as .

appropriate when the SW57 low level alarm setpoint is resched per Reference 6.g.

5.3.5 Sample RR hydrogen and initiate hydrogen removal procedures if required.

5.3.6 Secure 157AS components as necessary.

- NOTE: HPI may only be secured if the following conditions are .

met.

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(1) The low pressure injection system is in operation and the' flow is equal to or greater than that required to reseve the decay heat load or (2) HPI has been in operation for greater thsn 10 minutes, the pressurizer level is above the normal operating level and the system pressure is at least 50 PSIG (plus instrument error) above saturation pressure for the reactor outlet water temperature.

5.3. 7 Initiate long term cooling with the decay heat removal system per References 6.4 and 6.8.

6.0 REFERENCE 5

, 6 .1 Plant Technical Specifications .

6.2 RCS Leak Detection, 05 501 (01) 6.3 Makeup and Purification System Operation, 05 3521 nas<n CONFIDENTIAL COUNSEL ONLY DA71: 2*2'*78 PAGE

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. j 6.4 - ESFAS Operation, 05 2621 1

,.l 6.5 Reactor Trip, 505 0172 6.6 Plant Shutdown, OS 0135 6.7 Plant Limits and Precautions, OS 1101 6.8 Decay Heat Removal System Operation, OS 3621 I

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nssos CONFiDENTIA!.

COUNSEL ONL,Y DATE: 2-24-78 PAGE 7-1

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