ML20126B714

Rev 19 to Off-Normal Instruction ONI-12, High Activity Radiation Monitoring

ML20126B714
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Issue date:	08/20/1992
From:	PORTLAND GENERAL ELECTRIC CO.
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ML20126B698	List: ML20126B696 ML20126B706 ML20126B714 ML20126B718 ML20126B720 ML20126B723 ML20126B733 ML20126B741 ML20126B745 ML20126B749 ML20126B760
References
ONI-12, NUDOCS 9212220184
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PORTIAND GENERAL ELECTRIC COMPANY TROJAN NUCLEAR PLANT Level 1 Controlled Distribution Mointained by Document Control August 19, 1992 Do not remove this document 4

Revision 19 OFF-NORMAL INSTRUCTION - ONI-12 Q

High Activity Radiation Monitoring Responsible Department:

Ooerations Date:

2 iO Approved By:

Procedure Manager Effective Date:

f/M"D PURPOSE This instruction describes the necessary actions upon receiving any Area Radiation Monitoring System (ARMS) or Process Radiation Monitoring System (PRMS) high activity alarm and is divided into the following sections:

1.0 AREA RADIATION MONITORING SYSTEM 2.0 PROCESS RADIATION MONITORING SYSTEM 1.0 AREA RADIATION MONITORING SYSTEM 1.1 Symotoms 1.1.1 Indication of high activity on the local or remote meter, or activation of the ALERT or-HIGH activity alarm on any of the following ARMS channels:

Channel No.

Monitor AM-1 Auxiliary Building, Elevation 5-ft ARM-2 Auxiliary Building, Elevation 25-ft ARM-3 Radiation Sample Room ARM-4 Auxiliary Building, Elevation 45-ft ARM-5 Fuel Pool Area, Elevation 45-ft ARM-6 In-Core Monitoring Equipment Area ARM-7 Auxiliary Building,' Elevation 61-ft (near: elevator)

ARM-8 Fuel Building, Elevation 61-ft ARM-9 Radwaste Control AM-10 Waste Concentrates Tank ZNDM.875 ONI-12 Page 1 of 15 Revision 19 9212220184 921217 gDR ADOCK 05000344 PDR

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Channel No.

Monitor 4'

,f j

ARM-11 Control Room g

j ARM-12 Maintenance Shop

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ARM-13 New Fuel Storage j

ARM-14 Radwaste Drurening Station-ARM-15A Containment, PRZR Shed 138-ft ARM-ISB Containment Laydown area Wall West 106-ft ARM-17 RER Room East ARM-16 RER Room West ARM VCT Room Facade

. ARM-19 Letdown Line, Facade i

ARM-20 Manipulator Crane l

ARM-21 Entry to Bioshield ARM-22 North Site Boundary ARM-23 South Site Boundary

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ARM-25 Elect. Penetration Area l

1.2 Probable causes i

1.2.1 The release of radioactive materials, high reactor coolant activity, or degradation of shielding structures.

j 1.3 Automatic Actions j

1.3.1 IF a high radiation alarm from the Control Room area monitor ARM-11 is activated, verify the following sutomatia. actions occur:

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1.3.1.1 System CB-2 is shutdown.

It can be verified by the

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following:

(1) -At Panel C-290, verify outside air damper DM-10250-CB-2 i

closes.

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(2) At Panel C-19, verify ontside air fan VC-141 stops.

l (3) At Panel C-19,-verify Control Room fan V-141A/V-141B stops.

(4) At Panel C-19, verify Control Room recirc: fan VC-148 stops.

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(5) At Panel C241A. verify Control Room supply. dampers

.DM-10504A or B or both AND return dampers DM-10501A or B 1

or both close.

(6) At B-4782,. verify Control Room chilled water booster pump VP-142 stops.

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I ONI-12 Page 2 of 15-Revision 19

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1.3.1.2 Systems CB-3, CB-4, CB-5, CB-6, and CB-10 cre shutdown.

Thsse can be verified by their respective green indicating lights ON and red light OFF, at Panel C241At (1)

CB-3, Water Sampling Lab Exhaust System

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(2) CB-4 Toilet and Lunchroom Exhaust System (3)

CB-5, Control Building Supply System (4)

CB-6, Mechanical Room Exhaust System 4

(5) CB-10, Control Building Air Conditioning Supply System 1.4 famediatt Operator Actions 1.4.1 ALERT radiation alarm 1.4.1.1 Verify the validity of the alarm and ihmit access to *he i

affected area.

1.4.1.2 Notify Radiation Protection.

1.4.2 HIGH Radiation Alarm 1.4.2.1 Verify validity of alarm i

1.4.2.2 Notify Radiation Protection.

1.4.2.3 Determine if evacuation of area is credited and announce evacuation of personnel to controlled access point as i

necessary.

1.4.2.4 If Control Room Monitor (ARM-11) Alarma, verify auto actions.

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[CTL 20700]

1.4.2.5 If ARM-11 alarms AND CB-12 is operating, STOP CB-12 AND VERITY Dampers DM-10503A-AND DM-10538 close (Reference LER 87-17 and i

C92-0057-01-03).

[CTL 20700]

1.4.2.6 If ARM-11 alarms AND CB-13 is operating, STOP CB-13' (Reference LER 87-17).

1.4.2.7 IF ARM-12 and/or ARM-13. alarms high and fuel handling is in progress:

1.4.2.7.1 Determine if fuel' handling accident has occurred. Refer to FHP-13 (Emergency Fuel Handling Procedures).

1.4.2.7.2 VERIFY spent fuel pool (SFP) exhaust fan running.

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1 1.5 Subsequent Ooerator Actions

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i 1.5.1 Check emergency action level in Radiological Emergency Response

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Planning (RERP).

1.5.2 ALERT radiation alarm.

4 1.5.2.1 Evaluate the alarm and take appropriate action to limit,

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contain, or correct the condition.

1.5.3 HIGH radiation alarm.

1.5.3.1 IF personnel were in the affected area, determine what work they were doing and if this could have caused the alarm.

1.5.3.2 Monitor other areas and/or process monitors to help determine the source and magnitude of any releases or spills.

1.5.3.3 Make a survey of the affected area; rope and mark off the area if required in accordance with the Radiation Protection Manual.

1.5.3.4 IF high radiation alarm is Control Room Channel ARM-11:

1.5.3.4.1 START Control Room Emergency Ventilation (CB1 A/B) with outside air damper, DM 10251 A/B, open.

1.5.3.4.2 Verify Control Room Supplemental Ventilation (CB-16A/B) also starts.

1.5.3.4.3 Continue to operate Control Room emergency ventilation i

system CB-1A and B with outside air dampers, DM-10251A&B, OPEN. This provides a source of filtered air to allow Control Room pressure to be maintained above surrounding areas. This minimizes infiltration of radioactivity into the Control Room.

1.5.3.4.4 Have Radiation Protection monitor Control Room radiation levels.

Potassium iodide may be issued or respirators donned as required by the Radiation Protection Supervisor or his designee.

1.5.3.4.5 Ensure that the cable spreading room smoke exhaust system. CB-13, and the Control Room Smoke Exhaust System, CB-12 are not operating. They can degrade the Control i

Room positive pressurization.

1.5.3.5 IF Control Room evacuation is necessary, as detemined by the survey, refer to ONI-17, Control Room Inaccessibility.

1.5.3.6 Determine the cause of the high-radiation level and take appropriate steps to return conditions to normal.

l ONI-12 Page 4 of 15 Revision 19

1 2.0 PROCESS RADfATf0N MONITORING SYSIEd 2.1 Eymp.tsma 2.1.1 Indication of high activity on the local or remote meter, or activation of the ALERT / WARNING or HIGH activity alarm on any of the following PRMS channels:

Channel No, Monitor PRM-1 Containment PRM-2 Auxiliary Building Ventilation Exhaust i

PRM-3 Spent Fuel Pool Ventilation j

PRM-4 Gaseous Radwaste PRM-5 Vent Collection Header PRM-6 Condenser Air Discharge PRM-7 & 8 Component Cooling Water PRM-9 Liquid Radwaste Discharge PRM-10 Steam Generator (S/G) Sample PRM-13 Gross Failed Fuel PRM-14 Containment Sump Pump Discharge PRM-15 RCDT Pump Discharge PRM-16 A-D Main Steamline Radiation PRM-17 Steam Generator Blowdown 2.1.2 Indication of high activity on C-411. PRM-26 Control Panel, or activationofthePRM-26 ALERT,HI,orHIBIalarm(K-01,B.3,C.gg OR D.3, respectively) for PRM-26A, B, C, or D. Main Steam Line N I

2.2 Probable Causes 2.2.1 The release of radioactive materials,'or the presence of abnormally high radioactivity levels.

NOTE: High concentrations of noble gases may cause false high 2

indications on iodine monitorine levels.

NOTE: PRM-1 and PRM-2 particulate and gaseous channel readings J

can be used to indicate the source of the activity.

2.2.2 Ligh particulate activity relative to gaseous activity indicates l

the presence of short-lived gaseous. isotopes and their particulate daughters.

Such short-lived activity is due to direct leakage of reactor coolant or pressurizer vapor at power.

IF the particulate channel PRM-1 or PRM-2 reads greater than 100 times the gaseous channel, look for leakage from the Reactor Coolant System (RCS).

ONI-12 Page 5 of 15 Revision 19

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2.2.3 Low particulate activity relative to gaseous activity indicates the presence of only longer lived isotopes.

The leaking fluid.

I must have been out of the reactor for a longer time.

IF the I

gaseous channel on PRM-1 and PRM-2 reads 100 times greater than the particulate channel, the leakage is likely from the waste gas i

system, or the boric acid recovery systems.

2.2.4 Steam generator tube leak (s).

2.3 Automatic Actiona 2.3.1 PRM-1, Containment, HIGH radiation signal will:

2.3.1.1 Close all purge and hydrogen vent supply and exhaust valves.

2.3.1.2 Stop all purge and hydrogen vent supply and exhaust fans.

NOTE: When PERM 1 or 2 is in the Accident Mode, the parti-culate (1A & 1A) and Iodine (1B & 2B) channels are 4

removed from sample flow nath and are not operable.

2.3.1.3 Reaching the following PRM-1 channel setpoints will cause an auto shift.to ACCIDENT MODE:

Particulate 1A - 5.55 x 105 cpm Iodine IB - 2.06 x 105 cpm Mid-Gas ID - 7.61 x 105 cpm i

2.3.2 PRM-2, Auxiliary Building exhaust, setpoints will cause an auto shift to ACCIDENT MODE:

i Particulate 2A - 5.55 x 105 cpm Iodine 2B

- 2.06 x 10 cpm 2.3.3 PRM-4, gaseous radwaste, HIGH radiation signal will close CV-4369 waste gas decay tank discharge valve.

2.3.4 PRM-5, vent collection header, HIGH radiation signal will stop the vent collection header exhaust fan.

2.3.5 PRM-6, condenser air discharge, setpoints will cause an auto shift to ACCIDENT MODE:

Lo-Gas 6A - 2.24 x 106 cpm Mid-Gas 6B - 7.61 x 10 cpm 2.3.6 PRM-9, liquid radwaste discharge, HIGH radiation signal will close CV-4043, liquid-radwaste discharge header isolation valve.

I ONI-12 Page 6 of 15 Revision 19

4 2.3.7 PRM-10 4

2.3.7.1 A steam generator sample ALERT or HIGH radiation signal will close the following valves:

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(1) Steam generator blowdown containment isolation valves:

MO-2810 MO-2813 MO-2812 MO-2808 (2) Steam generator sample Containment isolation valves:

I CV-2811 i

CV-2880 CV-2814 CV-2809 2.3.7.2 A steam generator sample ALERT radiation signal will close steam generator sample to the cold lab valves:

1 6V-5696 SV-5697 SV-5698 SV-5699 2.3.8 PRM-14, Containment sump pump discharge line, HIGH radiation signal will close CV-4181 Containment isolation valve.

2.3.9 PRM-15, RCDT pump discharge line, HIGH radiation signal will close CV-4006 Containment isolation valve.

2.3.10 PERM 17 i

2.3.10.1 PERM 17 alert signal will close the following:

CV-4910 SGBD Tank Inlet Control Valve CV-4911 SGBD Tank Inlet Control Valve i

CV-4912 SGBD Tank Inlet Control Valve CV-4913 SGBD Tank Inlet Control Valve CV-2818 SGBD Discharge to.D&DS 2.3.10.2 PERM 17 alert signal will switch SGBD from D&DS to main condenser.

2.3.10.3 PERM 17 high will close the following:

CV-4910 SGBD Tank Inlet Control Valve CV-4911 SGBD Tank Inlet Control Valve CV-4912 SGBD Tank Inlet Control Valve

-CV-4913 SGBD Tank Inlet Control Valve CV-2818 SGBD Discharge to D&DS CV-4919 SBGD Discharge to Main Condenser ONI-12 Page 7 of 15 Revision 19

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2.4 Imagdiate Operator Actions I

2.4.1 IT the alarm is caused by work in progress and known to the Control Room operator, perform the following otherwise go to

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Steps 2.4.2 and then Section 2.5 for the affected alarm.

2.4.1.1 Verify that the alarm is caused by the known work.

4 2.4.1.2 Acknowledge and then reset the alarm.

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2.4.1.3 IF the alarm cannot be reset in a reasonable time, go to l

Step 2.4.2 and then Section 2.5 for the af fected alarm.

2.4.2 Verify automatic actions occur.

2.5 Subs equen t Operator Actions 2.5.1 Consult RERP 2.5.2 ALERT radiation alarm on any channel except PERM 6, 10, and 17:

s 2.5.2.1 Evaluate validity of t!.e alarm.

2.5.2.2 Take appropriate actions to limit, contain or correct the l

condition.

2.5.3 ALERT on PERM 6 i

2.5.3.1 Verify validity of the alarm.

h 2.5.3.2 Notify Chemistry.

2.5.4 ALERT on PERM 10 2.5.4.1 Bypass the Alert radiation signal.

2.5.4.2 OPEN S/G sample containment isolation valves one at a time to determine which S/G is leaking:

CV-2811 CV-2880 CV-2814 CV-2809 2.5.4.3 C'ECK-PERM 6, 16 A-D, and 17 fer abnormal readings.

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ONI-12

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.Revisic.: 19'

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2.5.4.4 C1,0SE SGBD tenk inlet flow control valves on C-164:

CV-4910 CV--4911 CV-4912 CV-4913 2.5.4.5 OPEN SGBD containment isolstion valvest MO-2810-MO-2813 MO-2812 MO-2808 2.5.4.6 Place SCBD system in service per Operating Instruction (01)-8-6.

2.5.4.7 Direct Chemistry to flush PERM-10.

2.5.4.8 Open the fc11owing valves after PERM-10 has been flushed:

SV-5696 SV-5697' SV-5698 SV-5699 2.5.5 ALERT on FERM 17 2.5.5.1 Check PF.M1 6, 10 and 16 f.-D for abnormal indication.

I 2.5.5.2 Reset alert radiation alarm and-if required, flush PERM 17 per 01-8-6.

2.5.5.3 Restart SGBD per 0I-8-6.

2.5.5.4 Sample outlet of on service SGBD ion exchanger.

2.5.5.5 Shift ion exchanger, if required, per 01-8-6.

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% '. a ONI-12. Page 9 of 15 Revision 19 1

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2.5.6 ALERT on PRM-26 J

NOTE:

PRM-26 radiation detectort are mounted beneath the main steam-lines-downstream of the Main. Steam Isolation Valves.

Locations of the detectero are from North to South:

RE-1555 (S/G A), RE-1558 (S/G D), RE '1557 (S/G C), and then RE-1556 (S/G B).

IF one channel is indicating high activity, adjacent channel (s) may exoerience hisher than normal indication (s).

9 2.5.6.1 Check that the affected channel, on C-411, is indicating

>10 spd.

i RIS-1555A for PRM-26A l

RIS-1556A for PRM-26B i

RIS-1557A for PRM-26C RIS-1558A for PRM-26D 4

2.5.6.2 Direct Chemistry to perform the following:

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2.5.6.2.1 Take backup grab sample (s) per Chemistry Manual Procedure l

(CMP)-1, Primary-to-Secondary Leakrate.

i 2.5.6.2.2 Increase sample frequency from weekly to daily or per CMP-1.

1 NOTF:

RR-1555, PRM-26 recorder, may be used for trending rate g

of leak rate increase.

2.5.6.3 Monitor other PRMs to confirm leakage PRM-6, condenser air discharge PNK-10, steam generator sample PRM-16, main steam line radiation PRM-17, steam generator-blowdown 2.5.7 PRM-1 HIGH radiation alarm, Containment 1

2.5.7.1 Evacuate Containment.

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2.5.7.2 D2termine what work was bcing done cnd if this could h:va cause the alarm.

NOTE:

If the source of the alarm cannot be determined, ADVANCE the filter paper for about 15 seconds to confirm that the alarm will clear temporarily and that detector response is normal.

It also may be desirable to purge the detector with instrument air (use tape deck operation on peripheral entry controller 'i advance Filter #3). Notify Chemistry l

thal _th3 Illter p12er was advanced.

2.5.7.3 Send ltadiation Protection personnel to make observatior.s.

evaluate radiological conditions and, if possible, determine the source of the radiation.

2.5.7.4 Monitor process instruments to determine if there is a reactor coolant leak into the Containment and the magnitude of the leak.

2.5.7.5 IF rad:tation levels return to normal, permit routine entry into Containment.

2.5.7.6 IF the alarm is valid, exclude Containment entry (except for the radiation survey required above) unless authorized by a revised Radiation Work Permit (RWP).

2.5.7.7 Determine and correct the cause of the alarm.

2.5.7.8 Have Radiation Protection personnel monitor any evacuated personnel.

2.5.8 PRM-2 HIGH radiation alarm, Auxiliary Building ventilation exhaust 2.5.8.1 Evacuate the controlled aree.

2.5.8.2 STOP the vent collection header exhaust fan.

2.5.8.3 IF a gaseous radwaste discharge was in progress, CLOSE CV-4369, waste gas decay tank discharge header isolation valve.

2.5.8.4 IF personnel were in the controlled area. determine what work they were doing and if this could have caused the alarm.

2.5.8.5 Monitor tank levels, sump levels, and system pressures of those systems located in the Fuel and Auxiliary Buildings to help determine the source of the radiation.

l ONI-12 Page 11 of 15 Revision 19

2.5.8.6 Survey the controlled area for sources of airborne activity, i

NOTE:

IF the source of the alarm cannot be detemined, I

ADVANCE the f11ter paper for about 15 seconds to confim that the alam will clear temporarily and -

that detector response is normal.

It also may be j

desirable to purge the detector with instrument air (use tape deck operation on peripheral entry j

controller to advance yllter #3). Notify Chemistry j

that the filter omoer was advanced.

2.5.8.7 After location of the source, isolate it.

2.5.8.8 Survey any evacuated personnel.

2.5.8.9 IF the radiation level returns to normal, permit routine entry into the controlled area and restore the ventilation systems to a normal lineup after the cause of the alarm has been i

determined.

2.5.9 PRM-3 HIGH radiation alaria, Spent Fuel Pool Ventilation.

2.5.9.1 START STP Exhaust Fan.

2.5.9.2 Evacuate the spent fuel pool area.-

2.5.9.3 IF personnel were in the spent fuel pool area, determine what work they were doing and if this could have caused the alam.

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2.5.9.4 Survey the spent fuel pool area for sources of airborne activity.

I 2.5.9.5 After location of the source, isolate it.

2.5.9.6 Survey any evacuated personnel.

2.5.9.7 IF the radiation level returns to nomal, permit routine entry into the controlled area.

2.5.10 PRM-4 HIGH radiation alarm, Gaseous Radwaste 2.5.10.1 Resample the gas decay tank that was-being released-to verify the alam.

2.5.11 PRM-5 HIGH radiation alarm, Vent Collection Header 2.5.11.1 It may be necessary to sample and/or survey the various equipment that' vents. to the vent collection header.

2.5.11.2 After location of-the source, isolate it.

L 2.5.11.3 Survey any evacuated personnel.

t 2.5.11.4 IF the radiation level returns-to normal, the vent collection

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l header exhaust fan may be restarted.

.0NI-12 Page 12 of 15 e

Revision 19 i

2.5.12 PRM-6 HIGH radiation alarm, Condenser Air Discharge.

2.5.12.1 Refer to ONI-6, Excessive Reactor Coolant Leakage, and ONI 3-12, Steam Generator Tube Leak.

2.5.12.2 Inform Chemistry._

2.5.13 PRM-7 or PRM-8 HIGH radiation alarm, Component Cooling Water Channel.

2.5.13.1 Determine where the inleskage is by observing temperature-and/or flow indicstion associated with the component cooling water and the equipment serviced by it.

2.5.13.2 Isolate the leak.

2.5.13.3 Refer to ONI-6. Excessive Reactor Coolant Leakage AND/OR ONI 4-2, Component Cooling k'ater System.

2.5.14 PRM-9 HIGH radiation alarm, Liquid _iadwaste-Discharge 2.5.14.1 Resample the tank that was-being discharged to verify the alrrm.

2.5.15 PRM-10 HIGH radiation a?. arm, Steam Generater. Sample 2.5.15.1 Refer to ONI 6. Excessive Reactor Coolant Leakage, and CNI 3-12, Steam Generator _ Tube Leak.

2.5.15.2 If there has not been an SI, DIRECT Chemistry to locally flush PRM-10 AND RESTORE SGBD sampling one S/G at a time to identify the leaking C/G.

2.5.16 PRM-13 HIGH radiation alarm, Gross Failed Fuel Monitor 2.5.16.1 Refer to ONI-5, High Reactor Coolant Act:1vity.

2.5.17.PRM-14 HIGH radiation alarm, Containment Surp Discharge Line..

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2.5.17.1-Refer to ONI-6, Excessive Reactor Coolant Leakage.

2.5.I8 PRM-15 HIGU radiation alarm. RCDT Pump Discharge Line 2.5.18.1 Refer to ONI-6, Excessive Reactor Coolant Leakage.

2.5.19' PRM-16 HIGH ' radiation alatm. Main Steam Line Monitor 2.5.19.1-hefer tof0NI-6 Excessive Reacter Coolant Leakage. and ONI 3-12, Steam Generator Tube Leak.

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i 2.5.20 PERM 17 BICH Radiation Alarm-2.5.20.1 " Check PERM 6. 10, and 16 A-D-for abnormal indication..

j i-2.5.20.2 Reset alert and hi radiation alarm,_if required flush PERM 17

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per 01-8-6.

i 2.5.20.3 Restart SGBD per 01-B-6.

i 2.5.20.4 Sample on service SGBD ion exchanger outlet.

2.5.20.5 Shitt ion exchangers if required._

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2.5.20.6 Refer to ONI-6. Excessive Reactor Coolant leakage, and ONI 3-12, Steam Generator Tube Leak.

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2.5.21 HIGH on'IP.M-26 NOTE: -PRM-26 radiation detectors are mounted beneath the main steam lines downstream of the Main Steam Isolation i

Valves.

Locations of the-detectors are from North-to i

South: RE-1555 (S/G A), RE-1558 -(S/C D), RE-1557 i

(S/G C), and then RE-1556 (S/G B).

IF one channel As i

indicating high activity, adjacent channel (s) may REP.tI113.tt.hi&htI than_ normal inglicatIDnf a h l

2.5.21.1 Check that the affected channel, on C-411, is. indicating'-

>25 gpd.

1 RIS-1555A for PRM-26A RIS-1556A for PRM-26B l-RIS-1557A for PRM--260 i

RIS-1558A for PRM-26D 2.5.21.2' Direct Chemistry to perform the following:

i 2.5.21.2.1 Take backup grab sample (s) per CMP-le Primary.to-Secondary.

l Leakr a te.-

2.5.21.2.2 Increase sample :f requency to_:at least ' daily or per CMP-1.

L 2.5.21.3 Monitor other PRMs to confirm leakage:-

7 PRM-6, condenser air discharge PRM-10. steam generator sample PRM-16, main steam line radiation PRM-17, steam generator' blowdown NOTE: RR-1555, PRM+26 recorder, may -be used for _ trending 1 rate -

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of_ltA): rata. increase.

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-L 5.21.4.. Consider Plant shutdown per OMI-3-12,-Steam Gener.#. tot Tube" j

Leak, based on -grab sample results, other PRM indicatic.6s,

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and/or rate -of leak rate increase.

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2.5.22 HIGH SIGH on PRM-26 a

1 NOTE: PRM-26 radiation detectors are mounted beneath the main

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steam lines downstream of the Main Steam Isolation

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Valves. Locations of the detectors are from North to.

South: RE-1555-(S/G A),_RE-1558-(S/G D), RE-1557 (S/G C), and then RE-1556 (S/G B). - IF-one channel is Indicating high activity, adjacent channel (s) may

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exceriangg_ higher than normal indication (s).

i 2.5.22.1 Check that the affected~ channel, on C-411, is indicating

>50 spd.

4 3IS-1555A for PRM-26A RIS-1556A for PRM-26B RIS-1557A for PRM-260 RIS-155&A for FRM-26D 2.5.22.2 IF FRM-26 leakage indication (>50 GFD) appears to be valid, then' initiate a rapid Plant shutdown per ONI 3-12 Stens Generator Tube 1.eak.

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