ML20042C118

Loss of Reactor Coolant/Rcs Pressure, Revision 17

ML20042C118
Person / Time
Site:	Rancho Seco
Issue date:	03/08/1982
From:	SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
Shared Package
ML20042C116	List: ML20042C115 ML20042C117 ML20042C118 ML20042C120
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.2.13, TASK-TM D.5, TAC-45202, NUDOCS 8203300226
Download: ML20042C118 (19)

Text

9'

\\

P,'

(

(

3-8-82 Rev.

17 D.5 IDSS OF REACIOR COOLANT / REACTOR C00LAtir SYSTEM PRESSUPI V

t.

1.0 PURPOSE the event of loss j

To provide emergency procedures to be followed in of reactor coolant and/or reactor coolant system pressure.

j

2.0 DESCRIPTION

This procedure is divided into three cases:

Case Description i

1.

Small leak within the capacity of the makeup pump to control reactor coolant system (RCS) pressure and pressurizer (pzr) level (n>120 gpm, i.e. about 4 inches / minute drop in makeup tank level).

2.

Medium leak such as a letdown line or OTSG tube rupture, or EMOV failed open. The leak rate is within the capacity of the High Pressure Injection System (HPI) to control RCS pressure and pzr level.

t 3.

Large rupture in excess of high pressure injection system.

Requires evaluation for core flood line break.

({

NOTE:

When SEAS action is initiated, manual defeat of any. portion of the SEAS removes that auto-matic protection until the system is reset.

Significant core damage can result from bypass of core cooling systems and f ailure to recog-nize volds are being formed in the core. ONLY defeat SEAS when RCS parameters are stable and

~

reactor coolant is at least 50 F subcooled unless continued operation of SEAS will result in exceeding-the Technical Specifications for pressure, temperature limits.

3.0 SYMPTOMS

.1 Pressurizer level and/or reactor coolant (RC) system pressure decreasing without associated decrease in coolant average temperature.

.2 Reactor trip, turbine trip and SFAS initiated.

.3 Reactor building radiation level, temperature, and/or pressure increasing.

.4 Reactor building (RB) accumulator tank dumping frequency increased.

d Radiation monitor alarm (s) in Reactor building.

.5 0203300226 820317 PDR ADOCK 05000312 P

PDR D.5-1 Rev. 15

dt" 3.0 SYFTTOMS (Continued)

C-

.6 Makeup (MU) tank level' decreasing.

i

\\,.

.7 Possible annunciators:

.1 RC Loop A Pressure Hi-Lo.

.2 RC Loop B Pressure Hi-Lo.

.3 RC Loop B Pressure Lo-Lo,

.4 RB Pressure Hi-Lo.

.5 FRJ Tank LVL Hi-Lo.

.6 PZR LVL Hi-Lo.

.7 Radiation Monitor Alarms for air ejectior and gland steam exhaust.

.8 Immediate low-level alarm on one core flood (CF) tank, but not both, with one CF tank dropping level rapidly (CF line break).

.9 RC Makeup Flow Hi.

p-

.10 Loss of subcooling with attendant rise in PZR level.

L.)

.11 Rapid increase in PRT level / pressure.

NOTE:

1)

Coolant leak symptoms can be caused by excessive cooldown, a malfunction of the makeup system, or a steam line rupture, as well as a loss of coolant.

Assume the cause of the symptoms as a reactor coolant leak or rupture until the cause can be established.

2)

DO NOT stop HPI flow based on PZR level indication until subcooling is verified.

4.0 UTOMATIC ACTIONS

.1 Reactor / Turbine Trip 'at 1900-psig coolant pressure or 4-psig building pressure.

.2 SFAS initiation (High-Pressure Injection (HPI), Low-Pressure Injectio'n (LPI), RB Emergency Cooling, and RB isolation) at 1600-psig coolant pressure or 4-psig building pressure.

.3 RB spray at 30-psig building pressure (plus a 5-minute time 9l '

delay).

D.5-2 Rev. 15 O

k

?

4.0 AUTOMATIC ACTIONS (Continued)

.4 PZR heaters cutoff at 40 inches.

(

5.0 OPERATOR ACTIONS NOTE:

The following Sections 5.1, 5.2, and 5.3 contain Operator Actions for Cases 1, 2 and 3.

.1 CASE 1 - SMALL LEAK

.1 IbMEDIATE OPERATOR ACTION NOTE:

Any parameter marked with an asterisk (*) shall be verified when Step 5.1.2.1 is performed.

.1 Close the letdown isolation.

l 17

\\

.2 Reduce unit load as rapidly as possible in preparation for a normal shutdown.

.3*

Manually trip the reactor if:

f

.1 Pzr level is 160 inches and decreasing.

t

.2 Makeup tank level is 18 inches.

.3 RCS is not 300 F subcooled.

1p

.4 Perform the Case 2 - ikdius leak actions if HPI is initiated due to low RCS pressure.

.2 SUBSEQUENT OPERATOR ACTION

.1 Immediately upon completion of the necessary manual actions of the "Immediate Operator Actions" section, alternate instrumentation channels shall be checked to confirm key parameter readings.

.2 Notify the Shif t Supervisor, Dispatcher and Plant personnel.

.3 Increase RCS makeup flow if required by:

.1 Open SFV-23811, HPI Injection Loop A(provides flow to the normal makeup nozzle).

g

.2 Start the HPI pump lined up to the BWST inlet supply.

D.5-3 Rev.

17

O 5.0 OPERATOR ACTIONS (Continued)

.1

.2

.3

.3 Throttle SFV-23811 as necessary to control pressurizer level and RCS pressure.

l 17

.4 Restore the system tonormal level control as soon as possible (manual PZR level control requires frequent operator attention).

.5 Maintain pzr level at 150 50".

.4 Monitor RCS subcooling at the H2SFA and H2SFB (verify selector switches in " TEMP" position).

See S.O. 3-82 I

for reset.

Subcooling of less than 50*F will require:

.1 Increase RCS pressure (PZR heaters or RCS make-up) OR;

.2 Decrease RCS temperature (TBV's or ADV's).

.5 Trip the 4 RCP's if HPI is initiated due to low RCS pressure.

Verify HPI flow to each loop.

(FI's 23805 and 23807 0 H2SFA and FI's 23806 and 23808 0 H2SFB).

Perform the Case 2 - Medium Leak Actions.

NOTE:

17 Maintain CCW and seal injection a-to RCP's to ensure restart avail-ability.

.6 Determine if an OTSG tube leak exists by:

.1 Monitor air ejector off gas detector.

s

.2 Monitor gland exhaust detector.

.3 Monitor main steam line detectors R-15056 (Loop A) and R-15058 (Loop B) for any increased readings and/or alarms.

.4 Initiate sampling of secondary system immediately upon increasing activity, alert, or high alarm on condenser air ejector gas monitor R15004 or gland seal exhaust monitor R15021 or increasing 17' activity or alarm on A or B steam line monitors R15056 or R15058.

Operations personnel are to collect samples until Chem-Rad people are on site.

Refer to AP 306 V-11.

Call Chem-Rad people to the site.

.7 If determined to be an OTSG tube leak, isolate the affected OTSG as detailed in Case 2 Leak, Section 5.2.2.10 as soon as RCS pressure allows.

Reduce f

'l the number of in service polishers to three (3) as 17 soon as practicable.

Immediately divert the Plant l

D.5-4 Rev. 17

5.0 OPERATOR ACTIONS (Continued)

.1

.2

.7 effluent to a retention basin and stop cooling tower blowdown.

Line up the condensate pit sump in the

{

polisher pit sump.

Refer to Case 2 Leak, Section 5.2.2.9 for OTSG tube leak (rupture) guidelines.

.8 Commence normal shutdown and cooldown per procedure B.4.

Use the TBV's on both OTSG's during cooldown.

17 Continue to use TBV's on affected OTSG as long as a steaming capability and condensor vacuum exists or until OTSG has been isolated. Maintain cooldown rate of maximum (100*F/

hr) until the steam generator can be isolated.

If 50*F subcooling margin cannot be maintained trip all RCP's, activate HPI and perform " Natural Circulation" cooldown per OP B.4. Section 6 and Enclosure 7.1 of this procedure.

Do not exceed 100*F subcooled.

If the OTSG 1evel appears t a or we plan to be going high enough to spill into steam lines, have the hangers pinned prior to line being filled.

(>400" on full range.)

.9 When Plant conditions allow, isolate and/or repair leak. Monitor gas and particulate activity and radiation levels to determine when safe entry in the containment building can be made.

.2 CASE 2 - MEDIUM LEAK

.1 IMMEDIATE OPERATOR ACTION

#~

NOTE:

4 Any parameter marked with an asterisk (*)

shall be verified when Step 5.2.2 is performed.

.1 Verify reactor trip and high-pressure injection initiated (SFAS Channels 1A and B and 2A and B).

.2 Manually trip the 4 RCP's (immediately following RCS pressure decrease to 1600 psig).

.3 Verify both auxiliary FWP's running and auxiliary feedwater flow (FI-31801 and FI-31901 at H2PSA).

.4*

Verify RCS is subcooled (RCS "T-SAT" indicators at H2SFA and H2SFB).

.5 If RC pressure continues to decrease to 600 psig, complete Case 3 - Large Rupture Actions.

CAUTION:

With HPI automatically actuated due to low RCS pressure, DO NOT terminate or throttle SFAS flow until core cooling is adeauate.

1p 1)

LPl cooling is adequate:

Both low pressure inj-ection (LPI) pumps are in operation and flowing at a rate in excess of 1000 gpm each and the sit-(

untion has been stable for 20 minutes.

D.5-5 Rev.-

17 I

\\

s t

5.0 OPERATOR ACTIONS (Continued)

.2

.1

.5 OR

.g

. '4

.2)

OTSG cooling is adequate : RCS is >50*F and <100*F subcooled as indicated by the "T-SAT" indicators on H2SFA and B panels or as determined from curves in Enclosure 17 7.1 of this procedure and "Subcooled and Saturate" curve at HlRC panel.

Utilize the highest indicated temperature (Th Tc or incore thermocouples) and the lowest indi-cated RCS pressure.

AND

.3)

Th is no greater than 50*F above saturation temperature of the OTSG secondary side as determined from the "Subcooled and Saturate" curve at the HlRC panel.

Action is necessary to prevent pressurizer level from going of f-scale high.

17

.4)

If HPI has been terminated or throttled and if 50 *F subcooling of the RCS cannot be main-tained, the HPI shall be reactivated. If Th, I

Tc and/or incore Tc's indicate super-heated conditions exi.'" in the RCS, perf orm Casualty Procedure C.47 conjunction with the remainder

/i of this procedure.

.5)

Continued operation of the HPI could result in the EMOV or Code Relief discharging to the PRT.

Flow to the PRT must be allowed to continue until HPI is no longer required.

DO NOT drain this water from the PRT of reactor building until RCS parameters have been stabilized and with Station Management approval.

.6 The EMOV or relief valve operation will prevent RCS pressure from exceeding 2750 psig.

(RCS pressure recorder may indicate pressure instability 2500 psig). Maintaining >50*F but <100*F subcool-ing will ensure pressure / temperature limits are not 17 exceeded per curves in Enclosure 7.1 and Figure 101-2a of Process Standards.

If natural circulation flow cannot be verified.

utilize incore Tc's to determine RCS subcooling.

.2 SUBSEQUEST OPERATOR ACTION

.1 Immediate upon completion of the necessary immed-inte manual actions of "IMMEDIATE OPERATOR ACTIONS" S-section, alternate instrument channels shall be checked to confirm key parameter readings where available.

D.5-6 Rev. 17

5.0 OPERATOR ACTIONS (Continued)

.2

.2

.2 Notify Shif t Supervisor, Dispatcher and plant

{'

personnel.

s

.3 Maintain a temperature / pressure plot on Enclosure 7.1; use hot leg RTD's and highest Tc's.

NOTE:

Verify subcooling based on incore thermocouples (Enclosure 7.1) compares with subcooling meter reading. Then control subcooling utilizing subcool-ing meter.

Feedwater Flow Verification

.4 Verify auziliary feedwater flow to at least one OTSG and level is increasing to 50% on Operate Range or %130" on the Startup Range, in a controlled manner. Trip both main FWP's.

17 6

.5 If auxiliary RWP(s) are not available, con-tinue to operate HPI flow in accordance with' Immediate Operator Action. Restore feedwater as soon as possible in a controlled manner in accordance with 0F D.14, Loss of Steam'Gener -

g* '

ator Feed, in conjunction with the remainder b

of this procedure.

Natural Circulation Verification

.6 Perform Natural Circulation Cooldown in accord-ance with OP B.4, Section 6 in conjunction with the remainder of this procedure. Refer to 17.1.

HPI Balanced Flow Verification

.7 Verify balanced HPI flow to the RCS as indicated at the SFA's panels. Ensure the following:

.1 Both HPI pumps operable: No more than 250 gpm flow through each of the four injection nozzles.

.2 One HPI pump operable:

No more than 125 gpm flow through each of the four

~

injection nozzles.

.3

-Injection flows balanced by adjusting SFV-23809 and/or SFV-23811 (Loop A) and SFV-23810 and/or SFV-23812 (Loop B).

l

.4 Limit each HPI pump flow between 500 and 40 gpm to prevent runout and deadhead l

conditions.

D.5-7 Rev.

17 i

t

r 5.0 OPERATOR ACTIONS (Continued)

.2

.2 i

Failure Of One HPI Pump To Start

.8 If a diesel generator or HPI pump fails to start automatically, take the following action:

.1 Verify the make-up pump is lined up to receive power from the operating diesel generator in

~

accordance with A.15 Make-up, Purification and Letdown Procedure.

.2 Establish a pump suction flow path from the BWST.

.3 Verify the Make-up outlet valve is closed, SFV-23508.

.4 Adjust loads as necessary on the operating diesel generator to supply power to the Make-up pump (about 530 KW).

.5 Place the Make-up pump in service.

.6 Rebalance the HPI Loop A and B flows.

CAUTION:

Pressurizer level may increase due to loss of subcooling.

{[

NOTE:

When the RCS is 50*F subcooled RC pressure can be controlled by reducing HPI flow to avoid exceeding 100*F sub-cooled per Reactor Vessel integrity 77 limits per Enclosure 7.1.

.7 Verify RCP seal supply flow.

OTSG Tube Leak (Rupture)

.9 Determine if the leak is an OTSG tube failure by:

.1 Increased readings or alarms on the air ejector off-gas or gland exhaust monitors.

Increased readings and/or alart. on the main steam line detectors R-15056 or R-15058.

.2 Verify OTSG secondary level at or near 50%

on the Operate Range (130" Startup Range).

Close SFV-20577 and SFV-20578, auxiliary feed to A and B OTSG.

.3 Monitor both OTSG levels and auxiliary feed-water ficws. A high OTSG level with little/no feed flow could indicate the f;~. led steam generator.

y.

\\_

i D.5-8 Rev. 17

5.0 OPERATOR ACTION (Continued)

.2

.2

.9

.4 Initiate sampling of secondary system j-immediately upon increasing act1vity, alert, or high alarm on condenser air ejector gas monitor R15004 or gland seal exhaust monitor R15021 or increasing activity or alarm on A or B steam line monitors R15056 or R15058.

Operations personnel are to collect samples until Chem-Rad people are on site.

Refer to AP,'306 V-11.

Call Chem-Rad people to the site.

.5 Divert plant effluent to a retension basin.

.6 Stop cooling tower blowdown.

17

.7 Line up condensate pit sump to polisher demin, sump.

.8 Cool at rapid rate (100*F/hr) to %480*F

(%600 psi in OTSG).

NOTE:

50*F subcooling allows RCS pressure to less than 1050 psi.

.10 Isolate the affected OTSG by closing the following

' lT '.

valves:

Mu OTSG A OTSG B Control Panel _

Valve Name llV-20570 llV-20571 Il2PSB Main Steam Line Trap IIV-35070 llV-35069 Il2PSB Main Steam Line Trap llV-20569 HV-20596 Il2PSB Main Steam to Aux. FWP llV-20597 IIV-20598 ll2PSB Main Steam to Reheaters HV-20565 IIV-20560 ll2PSB Main Steam to Auic. Steam IIV-20587 IIV-20588 H2PSB Main Steam Sample IIV-32243 112PSB Main Steam to Pegging Steam PV-20561 PV-20564 H1RI Turbine Bypass Valve PV-20563 PV-20566 H1RI Turbine Bypass Valve PV-20571A PV-20562B li1RI Atmosphere Dump Valve PV-20571B PV-20562B li1RI Atmosphere Dump Valve PV-20571C PV-20562C lllRI Atmosphere Dump. Valve.

IIV-20609 IIV-20610

.,ll2PSB OTSG Blowdown CAUTION:

In the event the wrong OTSG is isolated (leak symptoms persist) restore the isolated OTSG to service BEFORE isolating the second generator.

f'

L r 3-9 Rev. 17 l

5.0 OPERATOR ACTIONS (Continued)

.2

.2

.11 With the leak identified as an OTSG tube failuce

("

and the OTSG isolated, cooldown the RCS by increasing steam flow from the unaffected OTSG.

During cooldown, OTSG tube-to-shell AT limits should be observed; 17 normal AT limits (60*F) apply when the tube leak is small (<50 gpm) and RCP's are running and the condenser is available, otherwise a 150*F AT limit should be observed.

.12 Decrease RCS pressure by venting the pressurizer to the PRT using the EMOV (PSV-21511, control at H1RC) or pressurizer vent (HV-21515 and HV-21517, controls at H2PSA).

CAUTION:

When depressurizing the RCS in this manner, ensure the RCS is approximately 50* subcooled.

If subcooling cannot be maintained >50*F, the RCP's shall be tripped if running and full HPI flow initiated to ensure adequate core cooling.

1

.13 Maintain PZR level 150 50 inches with HPI flow.

Ensure the: RCS:.is shbcooled 'whenrevhloating PZRT.luvbl.

I NOTE:

5 9L Maintaining the RCS 50*F subcooled while reducing RCS pressure will require constant steaming of the unaffected OTSG and frequent make-up to the RCS.

.14 Continue Aux. FWP flow to the affected OTSG until secondary pressure is equalized with primary pressure.

(If necessary, to equalize pressure, allow the affected OTSG to fill and over-flow into the steam line).

Steam line hangers should be pinned prior to filling 17!

lines.

.15 With affected OTSG pressure equalized with RCS pres-sure, isolate all feedwater to that unit. Allow affected OTSG pressure to " swing" with the RCS pressure.

Continued Cooldown-I

.16 Continue plant cooldown in accordance with OPOP B.4, Section 6. until all conditions have been met for restart of an RCP.

If one OTSG has been isolated, RCP restart must be by the 10 second jog method described in B.4, Section 6.

Preferred method of cooldown is with forced core cooling flow. Refer IF

[

to Enclosure 7.1.

D.5-10 Rev. 17

5.0 OPERATOR ACTIONS (Continued)

.2

.2

.16

.1)

To avoid hot leg flashing when placing DHR j"

in service following a natural.c'irculation cooldown, bump a pump in each loop just prior to placing DHR in service and conitor hot legs 1%

for caturate conditions.

If near saturate conditions exists in the hot legs, monitor DHR pumps for signs of cavitation.

RCS Isolation Points

.17 Attempt to isolate leak by:

.1 Verify Letdown 1st-off valve (SFV-22025) Closed.

.2 Isolate EMOV (Block valve HV-21505).

.3 Verify Spray valves and Spray block valve closed.

.4 Verify Pressurizer Vent / Sample valves closed.

HV-21515 or HV-21417 (Vent Valves)

HV-21516 or SFV-70003 (Sample Valves)

.18 Verify that Core Flood Tanks and Low Pressure Injection occurs if RCS pressure decreases at an uncontrolled rate.

With cooldown rate and RCS pressure under Operator control, block Core Flood Actuation at 700 psig.

If not, allow CFT to discharge.

Isolate CFT's before N is allowed to flov into the RCS.

2

.19 Establish a plot of RCS pressure / temperature / time using Enclosure 7.1.

Operation within the limits

!I of this curve assures Tech. Spec. limits are. not exceeded and RCS is at least 50*F subcooled.

Shift From HPI To LPI CAUTION:

The following step shall be performed only if both Decay Heat Systems are operable.

.20 Prior to switching the injection suction from the BWST to the RB sump, complete the following manual valve manipulations:

NOTE:

1 The valves must be repositioned prior to draining the BWST to reduce the possibility of personnel overexposure.

5 D.5-11 Rev. 17 i

5.0 OPERATOR ACTIONS (Continued)

/'

.2

.2

.20

.1)

Open DHS-001 or DHS-002 (orly one valve shall

~

be opened). DH Loop A/B suction manual isolation from Reactor Vessel.

CAUTION:

,Do not establish a flow path in any system isolated by the SFAS without review of_the potential release of radioactive gas or liquid.

i

. 21 Restart of an RCP is permissible in accordance with OPOP B.4, Section 6.

If at anytime 4150*F subcooling margin cannot be maintained, immediately trip TCP's and reinitiate full HPI flow.

g

,

' t_

I L

s f

D.5-12 Rev.

17

2 OPERATOR ACTIONS (Continued) 5.0 g.

.22 \\ During plant cooldown, maintain RCS in a subcooled condition using HP1 as required to pressurize the system and control pzr level at 150 + 50 inches.

(Pzr level will be reliable only when RCS is sub-cooled). Utilize available pressurizer heaters to assist in RCS pressure control.

NOTE:

126 KW worth of pzr heaters is available from each nuclent service bus 3A and 3B in accordance with pressurizer procedure A.3, Section 7.

0 F and 250 psig,

.23 / Prior to RCS being cooled to ;5280

/ sample the primary coolant for isotopic analysis and notify the Plant Superintendent of results before placing the LPI/DHS in service.

With RCS parameters stable, do not shif t LPI suction to the RB Sump until the decision has been made to complete cooldown with LPI/DHS.

Alternate cooldown method can be in accordance with OP B.4, Section 6, Convection Cooldown.

,~

.24ll On BWST LoLo level, shif t one IIPI pump suction from BWST to DHS pump discharge and that DHS pump suction to the RB sump in accordance with OP A.8, Section 4.2.

(D0 NOT use the LPI pump aligned in preceding step 5.2.2.20).

'.25 ll With one LPI/HPI supplied from the RB Sump, establish core cooling with the remaining LPI in the DHS mode in accordance with OP A.8, Section 4 at J& 1000 gpm.

RCP's may be stopped when core cooling is provided by a DHS flow of.h 1000 gpm.

Maintain seal water flow to all RCP's in anticipation of immediate restart should LPI flow be interrupted (one RCP/ Loop if required).

Should restart be required, use the jog start method described in B.4, Section 6.

326] When on DHS flow, core AT is monitored by comparing DRS pump inlet and cooler outlet temperature or incore thermocouples and cooler outlet temperature.

.2'7!l With core cooling provided by DHS and RCS pressure controlled by HPI and/or pressurizer control, continue r

RCS cooldown to S.1400 F.

l D.5-13 :Rev. 15 l

{

(

5.0

. OPERATOR ACTIONS (Continued)

,(

NOTE:

If LPI flow is interrupted and RCP flow is not available, continue RCS cooldown in accordance with OPOP B.4, Section 6.

.28 l j With core cooling provided by LPI, place OTGS's in wet.layup as conditions permit.

Stop Auxiliary FWP's.

Insure at least one is available for restart.

.29',j With core cooling provided by DHS and RCS pressure controlled by pressurizer, stop the HPI and establish Over Pressure Protection (do this only if both LPI's (DHS) are operating or available).

.30 iShift tolongterm cooldown in accordance with the

' Case 3 subsequent action.

.3 CASE 3 - LARGE RUPTURE

.1 IMMEDIATE OPERATOR ACTION

.1 Verify reactor tripped at 1900 psig, RCS pressure.

Perform Emergency Procedure D.2 in conjunction with y

the remainder of this procedure.

.2 Verify initiation of SFAS Channels lA/B and 2A/B at 1600 psig and equipment operation.

.3 Manually trip the 4 RCP's.

.4 Verify both auxiliary WP's running and Aux. FW flow on FI-31801 and FI-31901 at H2PSA.

.5 Determine if rupture is core flood line break by abserving CF tank level and LPI flow.

NOTE:

A CF line break is evident, if one CF tank blows down immediately, but not both, and there is LPI flow to the affected CF nozzle and 0 LPI flow, with RCS pressure greater than 240 psig, to the other loop.

For a CF line break, I

RCS pressure will remain greater than 600 psig for approximately 2.5 minutes.

.6 Verify injection from core flood tanks at 600 psig.

'k

.7 SFAS Channels 3 A/B and 4 A/B actuated at 30 psig building pressure and spray flow is initiated subsequent to the 5-minute time delay.

D. 5-14 Rev. 15

i

(

5.0 OPERATOR ACTIONS (Continued) 6 NOTE:

With HPI automatically actuated due to low RCS pressure, DO NOT

. terminate SEAS flow until:

1)

Both low pressure injection (LPI) pumps are in operation and flowing at a rate in excess of 1000 gpm each and the situation has been

. stable f or 20 minutes.

.2 SUBSEQUENT OPERATOR ACTION Notify Shif t Supervisor, dispatcher and plant personnel.

.1 Feedwater Flow

.2 Verify Auxiliary Feedwater Flow to at least one OTSG and icvel is increasing to 507. on Operate Range or 130" on the Startup Range.

If Aux FWP(s) are not available, continue to operate HPI flow in accordance with Immediate Operator Action unless LPI flow is established. Restore feedwater in a controlled manner in accordance with OP D.14, Loss of Steam Generator Feed inconjunction with the remainder of 4~~

l$.

this procedure.

CF Line Break - Both DHP's Running

.3 If a CF line break is suspected, verify unaffected LPI pump is running and proper flow path from BWST I

t,o unaffected CF nozzle is established; then, close affected loop SEAS injection valve and stop the

'affected loop LPI pump.

NOTE:

If CF line break, RCS ' pressure will remain greater than 240 psig for approximately 7 minutes, i.e., no LPI flow should exist in unaffected loop with RCS pressure 240 psig.

CF Line Break - One DHP Running

.4 If a CF line break is suspected and the unaffected LPI loop pump is not operating, establish LPI flow to the unaffected loop through cross connect valves, HV-26046 and HV-26047.

fs D. 5-15 Rev. 15

(

5.0 OPERATOR ACTIONS (Continued)

.5 Limit HPI flow to 500 gpm per pump.

Balance flow J ))

through each nozzle.

.6 Limit LPI flow to G 3750 gpm per pump.

Balance flow from each LPI.,

.7 When the LPI system is injecting water in the core, control the auxiliary feedwater flow to prevent flooding the steam generators.

HPI pumps should be stopped if both LPI pumps are injecting 21000 gpm/ loop (21500 gpm for one LPI pump and a CF line breat).

Recire of Reac, or Building Emergency Sump

.8 When the BUST reaches its Lo-Lo alarm point, shif t injection and spray pumps suction to reactor building emergency sump (see OP A.8, Section 4.2) within 4 minutes.

.9 Stop one DHS pump - leave on standby for immediate restart.

.10 Monitor gas and particulate activity and radiation levels to determine if penetration areas and emergency jf.

pump rooms are safe for personnel entry.

Do not establish a flow path.in any system icolated by the SEAS without review of the potential release of radioactive gas or liquid.

CBS Operation

.11 Sample periodically the RB sump recirculation water for pH and boron; maintain pH at 9.3 if CBS's are in use.

NOTE:

One spray additive tank should provide a pH of 9.3.

The second tank is available for pH adjustments.

.12 Monitor Reactor Building for hydrogen.

Initiate hydrogen purge when hydrogen concentration reaches 3.5%.

Verify hydrogen purge blowers are operable.

.13 As soon as practicable within seven (7) days, establish dilution flow to the reactor vessel to prevent boron precipitation by one of the following modes:

(

D. 5-16 Rev. 15

e A

t 5.0 OPERATOR ACTIONS (Continued)

.1 FDDE 1 (Preferred)

I

.1 Establish 1 LPI loop injecting into the reactor vessel with 1 HPI loop operating, taking suction from the operating LPI-pump discharge (see OP A.8, Section.4.2).

(Preferred HP1 pump is P-238A).

NOTE:

This provides additional reliability, i.e., maintains 2 operating flow paths to the reactor.

.2 Open the decay-heat loop suction valves inside the reactor building, HV-20001 and HV-20002.

.3 Remove clearance and rack in breaker 2A179, then throttle open HV-20003 to obtain at least 40 gpm flow to the reactor building sump as indicated by FI-20001, located on the H2PS panel in the control room.

.4 If a minimum of 40 gpm flow cannot be obtained, proceed to Mode 2.

.2 MODE 2

.1 Remove clearance and rack in breaker 2B179, then close HV-23801, high pressure injection stop to "D" cold leg.

.2 Open HV-23802, high pressure injection to pressurizer spray stop valve.

.3 Throttle open SFV-23810 to provide some flow when starting an HPI pump.

.4 Open the decay-heat system supply to the HPI suction and the decay-heat system crosstics if the opposite decay-heat system is in operation.

.5 Start the HPI pump and throttle SFV-23810 to provide a minimum of 105-gpm flow to the pressurizer (105 gpm required for HPI pump continuous operation.

D.5-17 Rev. 15

o 5.0 OPERATOR ACTIONS (Continued)

T Establish makeup water to the spray ponds from the C

14 Folsom South Canal or the site reservoir or the cire. water canal.

If makeup is unavailable, maintain the spray pond outlet temperature between 84 and 940 F by cycling NRW-041 (042) spray pond interlock valve as required (intermittent operation will reduce drift losses, initiate spray at 940 F and terminate spray at 840 F).

C t.

9

<N D.-.5-18 iRev. 15

S)

O O

O d

W tot ~ '--tm O

O O

O O

O O

O O

O O

O 4

N O

CO

\\O 4

N O

CO

%O 4

N N

N N

~

~

• =

~-

N

..!g :p-w 1 :r. &

9

^

l;, y p

I.ll. ill. !. 7.y..mlh:n,.. It. i, :.u. n.. n.".. n.l h. :;nij liliT ca-

...r---

u.

j

.U.

~.;!

U:

i.;lt.

i L

['1,y

, i,,

it..

e

,g, y g y i

((N !.U.i j!'

,I li:.

t

.N H

d O P 1

L Ij-lg 41,;:'.! !ln t:t h t-5 rk{n h.2' { {

d' i.rni.u r:4 he m.. !!:

M

n lii

..n ::.: :n: ;at bc.:;l l

i o

e p- :

r utstu n

-1 oa t

$m 3mO n

z a m a r. rs. e i' Mp d.d_ "[

g

:rt te.

1M n-M:

m =

=r;:t in;- :t7.J

. "np,...u.,.qjn:p: n..

n. u..al.j I.-l._It

.J;j "m m m u u o W N *

'H "w

t. : t. ;.u.n..:. in.

} u.

t

.4 _-

O x r i

z r

.m m

~t t w-e un

.n mi in 2

8 8 i *

• t u,t i..l

_w.1 -' o w

t z-1Si eRF' af tn it:

a:j'.;an:

!;n; ha a

'n..:n un! :n:.: n::n:

o <

HHHHH

.:.:h;,n.:n.h r!T.

c-ni:

n..i u t,.e e O i

mpp

r H

na l 18 1)"U'.

y j.

1. x p: y o

rt -

'tr r etr :m m1 ;n.lb r,

t-w n

11

l...l.

! "p-4i.

.ij

!! n.. H.: I

~

o m

. u,

[j:

n:

s. _3 w

n'

.. m

.t g

.e4 e

.u;.

u o

.o.

,n..n....

e 4

o o

2. ;_

dI l' '

'mw a g l"i

(

r w mn-Om 1

. [!

.. [au ijh. lj j':

r uT d..

g

m...

k.

u.h:=4 : p.m en :n:

e r i

n i

_i.g e

-~rrm

u...e gnO r=

u au n u..t t.=. ;

r u. u.. n 1

~.

..o w e

~~uuu n-y[>7jj:.

a

.l.[,,[ I,.:t, O O jll".j prU w

p

.3 n.

l n.a'..

y:l [_ !

2jj p

t.

.e y..

",n r' r r' r' r'

t. n.. t. d. j '. t. hn.. n 8--

b.

ew w mm 8

e W t

t. i.i

t. 1.

n+ g.

O

.a e

l. !.!.1ijll lict j

_z s 5

!!U_

e E

EE O m m,,

o.

O

,jjj

.! jfhj!}i.

. !!..m..!:P 1: a.e t! !!m:-thi ". i' m 1 t!H HF uit E e E

y

- ~. r.--m 4:

hu.3 g gt 1

a r

_ tic

,n,n; m

-mm n.

u 3

gi ijii iQi !U e jiD iiE i!U NINriiri!111Tiim!!" dii%iti ri e :h i # ilii iii, E: 1 d_1

_ lii.l i L

'lP li.i.i o

i u '.=. i to l

1 m.

.l

.l

[].

l

,llI'ul' E

W Uli H.g_!!!.!!!.i

+l 1

.lih' ~a'

. rL i

ii t

1 i l'

..,pt I

g f

ill.

m O

- ilh u

/,

O O

e w

a.n t i,

___t__.r am.

d y

rmi 3

i:/.a.i.

es 1

n a

.l.l I: nd

4 i O

,I

. t

1.... e v.

j i t

"l ni

l

.l H 3

_I l pli r w ml

+

,1.

in a

u t

I

'll L

m, t 4 H

ni i

a i

i nm

. M uL1 1

i

] {ki 41,1 $"

ji it 1

4

$u1, "o

E 2

n Lyg. l'r.Il 144 Q.'l_:e". gi,.

gt. 'si

.~_ tl i _ y*l 1[gIe 1 p !] iijiuuA gh 2

t e

m w p:..m 2

u a

~

u a t:

1'%>li. 2d. i e

3

!innog s n,u :n

..i ji, '

- hu.a 'y. riu ::d t

d 4.3.u d'i

/:

tu t-3; g hlutn t

n

n r wv y

O m

I

=l nts<

1W:

a o

.u.

O ly/ L1' 9d.4 qmq liH = e.j tLOi!

ol.'twu t e2..i m jtk th tL f d:

9

d.

r u.

u-til

!! bl e

i

< e 2;.p

=

l 1 " a, tc.

.c m

% =.

t 4

~

c m L a1

.t_uu m

I!!!

l t

i h

h kk b h h

b!

1}Ih h

9 ti '

ti

.tM

• mt "M

-U i'4j !'# 4 { j{,-}-

. j-g t<.t'i O} l'Q[:j10 lb:N" 8o

- 1. tg

-- fy O

$:1.s:huid:"

h it 1 0 un :nd. h N ;.1 il U

.11. O C

Ji 2'

e a o 61 1

ii ? H! Bij "g,

8 0 $

iii; N illl W !h J !!iNili! 11.'illJih '"

2 O

l S

}

ill ly?

15d L

.!..l M

l

_.h..~

. 'M I _.i..

_.{

l\\ )

.a}

t 6

o o lll!.Ul1...l.I'll.l] 1..pll 1

s yi-I L

uoa 4 t-._

pt _p,..

'r e

W Z

04 s. :n..L 2

3 j

3 gg g4 ii..f}

O M o 'd

mou ftI h;h fr.g q L! htf ;t }..

1! j,!Ij;pi,k,, tid!N t'

' g!

o i

$ }

.s.'!; lid: q'p' L I N $

'1 l.

-6E.

pip.g2%. t[j h,_,_14l11 i 's!!!{:ls41 tj J

q. Un

1. n in:

P

u:

A 3

b

!'!.N "t rar p t i-"g:".4U'QL

p'

$n:

1 n'

u w

igj ny n1 li:;h" I:

gg ia.. _ MIIigi,y 1

i:n r-l,7 g

~"j "p i 1.!! lxp tl}! QI - ++.

I M '

t l" q-l; p"H i ~: : '-

n eoa

_ c: V.., m : '.. i

.Z*

a

't:

.t

. :{ O w

8 ou u j",h{

r":".vu e

=: '1 u'

m CcA-

"[

• " e S Ij i

ijn p

) :-

Jtji d[d.d..[%

N'y jj

' :. O h':7

.[g 1

3 V

m[l[h.:tjj jjt T

e i.; i;n. M u ipI

'n i j :.:

d.-+h;

..w

jt, [.ji ln1a-t, q* -- uliH fj it..d t t. '

1" 1t!

,44 w

t: >

i O

.1 r=

-.;- p 7

f. !

.i y l 1 ll! !I!! ;IUili!..

,_ o - m a

- O dh H

iG!a! ilill!g lL. li ti a"2

,E, d8y 11!!j!!i C0-j N:

.:p n

n t1 sw u:- u;d;.9 Ud 7 8 m; E ma un L.

a c.

..: :j. a - w ty; l.Ill'u[ggdi ynl g

u ij $e li Uj!

a d

/.:J.il H! i!H hifll Q g ij;i.

? !.

• u !Ul aid!!!!

o r'-

b.j ap

.... o p!

9.E.g i.c e

1 hnj c:. ny uea u!j pi

.t. ij]- lit:

in au n

. l !i.un :n.

, '1:r *.q

. o 1,.u. :n. it a u na :t :p:.

O

n.,

1.p

.D

O n.

- q O

_....m. m ag

" u.

c'~ Q

!h

• e

.fi f!!

I.I N h'

i

1. h. i. mn u'! n' f.iI! !'

l '1.1e. &

pu.jp gi a; j!TT; dt j[f.4.t j nu jip m ha in. ;m nu :bj

h; up op ;l:.p-I

.":i,, !. ! l S.

. '.. f. :.. n'n b

i.f. ffj f

- un a u-

-o -

_...,.p.

..o g

cm e *O n:

ri 1-

!.m t

m :;

a n.-,n...n o

u na f..

n n t

ni F. :r.

n:; :.n u. m :.

..n na ::

.n

-k 1:st

.Stsd - w.s gM M m @w n @ng W

e_