ML20216D974

Rev 3 to Abnormal Operating Instruction SO23-13-14, Reactor Coolant Leak

ML20216D974
Person / Time
Site:	San Onofre
Issue date:	05/07/1999
From:	SOUTHERN CALIFORNIA EDISON CO.
To:
Shared Package
ML20216D971	List: ML20216D967 ML20216D974
References
SO23-13-14, NUDOCS 9907300212
Download: ML20216D974 (25)

Text

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Attachment Abnormal Operating Instruction SO23-13-14

" Reactor Coolant Leak" i

I l-9907300212 990729 PDR ADOCK 05000361-P PDR

NUCLEAR ORGANIZATION ABNORMAL OPERATING INSTRUCTION S023-13-14 UNITS 2 AND 3 REVISION 3 PAGE 1 0F 24 EFFECTIVE DATE MAY 0 7 5M6, REACTOR COOLANT LEAK TABLE OF CONTENTS SECTION EAGE 1.0.

SYMPTOMS 2

2.0 IMMEDIATE OPERATOR ACTIONS 2

3.0 SUBSEQUENT OPERATOR ACTIONS...................... 3

4.0 REFERENCES

18 S.O RECORD...............................

18 ATTACHMENT 1

RE-7870 Steam Generator Radiation and Leakage Readings....

19 2

RE-7818A Steam Generator Radiation and Leakage Readings....

22 RECENEDCDM MAY 0 71999 t14-3.wS1 QA PROGRAM AFFECTING Dee Fox SITEFILECOPY

r.

f NUCLEAR ORGANIZATION ABNORMAL OPERATING INSTRUCTION S023-13-14 UNITS 2 AND 3 REVISION 3 PAGE 2 0F 24 R MCTOR COOLANT LEAK 1.0 SYMPTONS 1.1 Performance of S023-3-3.37 has identified the existence of:

J 1.1.1 Unidentified RCS leak rate 2 1 gpm.

1.1.2 Identified RCS leak rate 1 10 gpm.

1.1.3 CVCS leak 1.2 Ctemistry has identified leakage of a 5 GPD through either Steam Ginerator.

1.3 More frequent automatic makeup to the VCT.

i 1.4 Charging flow greater than Letdown flow with plant conditions stable.

1.5 Increasing pressures, temperatures, levels, and/or radiation levels in systems which interface with the RCS or CVCS.

1.5.1 Steam Generators 1.5.2 Component Cooling Water 1.5.3 Quench Tank 1.5.4 Containment 1.6 57C10, CONTAINMENT RADIATION HI, Illuminated.

1.7 57C20, RCS LEAKAGE DETECTION ACTIVITY HI (UNIT 3 ONLY), Illuminated Al 1.8 57043, RCS LEAKAGE ABNORMAL /RECIRC SYS VV MISALIGNED, Illuminated

[ Mode 1-4 only]

1.9 RCDT inlet flow high alarm on CFMS 15 gpm.

1.10 Containment Sump inlet flow 1 1 gpm on the CFMS.

1.11 60A46, SECONDARY RADIATION HI, Illuminated 2.0 IMEDIATE OPERATOR ACTIONS 2.1 None

-NUCLEAR ORGANIZATION ABNORMAL OPERATING INSTRUCTION S023-13-14 UNITS 2 AND 3 REVISION 3 PAGE 3 0F 24 3,0 SUBSEQUENT OPERATOR ACTIONS PERF. BY

[1] INITIALS 1

Myl[QB Do not place system in " MANUAL" unless misoperation in " AUTOMATIC" is apparent.

Systems placed in " MANUAL" must be checked frequently to ensure proper operation.

3.1 Reactor Coolant Leak 3.1.1 ENSURE additional Charging Pumps are operating to maintain Pressurizer Level and blended makeup system is maintaining VCT level.

3.1.2 If unable to maintt'in Pressurizer Level QI if unable to determine location of leak,.then ISOLATE Letdown.

.1 CLOSE HV-9204, LTDN Isolation Valve or

.2 CLOSE TV-0221, LTDN Temperature Control Valve or

.3 CLOSE TV-9267, LTDN Containment Isolation Valve 3.1.3 If the leak rate exceeds the capacity of the I

available Charging Pumps with Letdown isolated,

.then TRIP the Reactor and Turbine, i

.1 GO TO S023-12-1, Standard Post Trip Actions and TERMINATE the use of this procedure.

3.1.4 11 Pressurizer Level can be maintained,.then CONTINUE the use of this procedure.

[1]

Initial column is an operator aid and is intended to be used:

Initial each Completed Action. Do not write NA. Leave blank items that are not applicable. Proceed through the instruction performing all applicable steps, frequently rechecking those steps passed over to ensure action is taken when applicable.

NUCLEAR ORGANIZATION ABNORMAL OPERATING INSTRUCTION S023-13-14 UNITS 2 AND 3 REVISION 3 PAGE 4 0F 24 3.0 SUBSEOUENT OPERATOR ACTIONS (Continued)

PERF. BY INITIALS NOTE:

Chemical analysis differentiates between Reactor Coolant (Boric Acid), Component Cooling Water or Chilled Water (nitrates) andSteamGeneratorwater(Hydrazine and/orAmines).

3.1.5 If Primary to Secondary Leakage (S/G Tube Leakage) is suspected 1 hen GO TO Section 3.4.

3.1.6 llana actuation of 57C43, RCS LEAKAGE ABNORMAL /RECIRC SYS VV MISALIGNED alarm, then COMPLETE the following:

.1 VERIFY Containment Sump level at RCOT level increase indicates 2 1 gpm on CFMS.

.2 If indicated flow to the Containment Sump or RCDT is 2 1 gpm, lhEn REQUEST Chemistry Technician to sample the Containment Sump or RCDT effluent.

3.1.7 PERFORM Operating Instruction S023-3-3.37.

NOTE:

Results of the RCS Water Inventory Balance shall be recorded in the Control Operator's and Shift Manager's log books.

3.1.8 The Shift Manager shall NOTIFY the Manager, PlantOperationsUnits2/3orhisdesignee and the Shift Technical Advisor to discuss the situation and determine the requirement for event classification per S0123-Vill-1 and the reporting requirements of S0123-0-14

NUCLEAR ORGANIZAT10N ABNORMAL OPERATING INSTRUCTION S023-13-14 UNITS 2 AND 3 REVISION 3 PAGE 5 0F 24 3.0 10BSEOUENT OPERATOR ACTIONS (Continued)

PERF. BY INITIALS 3.1.9 With any Pressure Boundary Leakage,.then be in at least Hot Standby within six (6) hours. Refer to Technical Specification LC0 3.4.13. " Reactor Coolant System 1

Operational Leakage".

3.1.10 With any Reactor Coolant System leakage greater than any one of the following limits, IDENTIFY and REDUCE the leakage rate to within limits within four (4) hours or refer to Technical Specification LCO 3.4.13.

RCS leakage exceeds one (1) gpm and the source af the leakage is not identified.

RCS identified leakage exceeds 10 gpm.

e Primary-to-secondary leakage exceeds 1 gpm total leakage through all Steam Generators and 150 gallons per day (approx. 0.1 gpm) through any one Steam Generator.

3.1.11 With any Reactor Coolant System pressure isolation valve leakage greater than 0.5 gpm per nominal inch of valve size up to a maximum of 5 gpm at an RCS pressure a 2215 psia and s; 225S psia (Tech. Spec. SR 3.4.14.1), ISOLATE the high pressure portion of the affected system from the low pressure portion by use of one closed manual, deactivated automatic, or check valve within four (4) hours or refer to Tech. Spec. LC0 3.4.14.

3.1.12 INSPECT the Auxiliary Building and Penetration Building for visual signs of leakage.

.1 SAMPLE Containment atmosphere to determine the level of airborne radioactivity (particulate and gaseous) in the Containment.

3.1.13 H RCS leak is determined per 5023-3-3.37,

_then GO TO Section 3.2, RCS Leakage.

3.1.14 H CVCS leak is determined per 5023-3-3.37, i

.then GO TO Section 3.3, CVCS Leakage.

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NUCLEAR ORGANIZATION ABNORMAL OPERATING INSTRUCTION S023-13-14 UNITS 2 AND 3 REVISION 3 PAGE 6 0F 24 3.0 SUBSE00ENT OPERATOR ACTIONS (Continued)

PERF. BY INITIALS 3.2 RCS Leakaae 3.2.1 CHECK Radiation Monitoring Panel L-103 and 2/3L-104 for any indicated increase in levels of radiation.

.1 H diagnosis includes increasing activity in the Steam Generator Blowdown Sample radioactivity monitoring system, Neutralization Sump effluent or Condenser Air Ejector exhaust, lhen GO TO Section 3.4, Primary to Secondary Leakage.

CAUTION During a Containment entry the direct radiation dose rate may exceed 10 REM /hr, therefore every effort shall be made to hold the personnel radiation dose to a minimum during the Containment entry.

3.2.2 While the above actions are being taken, the Plant Superintendent and the Health Physics Foreman should be contacted for permission to enter Containment.

.1 H the particulate and gaseous activity of the Containment atmosphere permits, lhen Containment entry may be made by at least two people.

3.2.3 H Containment entry is deemed necessary and permissible, lhen ENTER the Containment and ATTEMPT to locate and isolate the leak.

.1 H the leak is identified as PRESSURE BOUNDARY LEAKAGE, then COMPLY with Tech. Spec. Action LC0 3.4.13.

.2 H the leak can be isolated, lhga plant operations may continue.

.3 H the leak is from an instrument fitting And it is possible to isolate the instrument without disabling any required protective devices, then the instrument should be isolated and operation continued.

.4 Identified Reactor Coolant System leaks that do not exceed 10 gpm should be referred to the Onsite Review Conrnittee for evaluation.

1. 0

%IlRSFallFNT DPFRATOR ACTfDNS (Continued)

PERF. BY NUCLEAR ORGANIZATION ABNORMAL OPERATING INSTRUCTION S023-13-14 UNITS 2 AND 3 REVISION 3 PAGE 7 0F 24

3.0 SUBSEQUENT OPERATOR ACTIONS (Continued)

PERF BY INITIALS NOTE:

Leakage from the RCS to other closed systems may result in high radiation levels near components of the affected system and this will be of prime concern to the Committee in their evaluation of the effects of continued operation.

3.2.4 VERIFY the backup Charging Pumps are operating and Pressurizer Level is returning to normal.

.1 H Pressurizer Level is nat returning to normal, then OPERATE backup Charging Pumps as Pressurizer Level dictates.

3.2.5 H the event evaluation determines continued operation is safe. 1 hen INITIATE monitoring the status of the leak per 5023-3-3.37, or other accepted procedure, at a frequency determined by the Onsite Review Committee.

.1 H the leak rate changes, then NOTIFY the Onsite Review Committee for their evaluation.

3.3 cvCS Leakage 3.3.1 MAINTAIN steady state plant conditions while attempting to locate and isolate leak, t

.1 INSPECT the Auxiliary Building and Penetration Building for visual signs of leakage.

.2 H leak can be isolated 1 hen RETURN Charging and Letdown to normal per S023-3-2.1, CVCS Charging and Letdown, fRI.108 H the Charging Pumps are aligned with suction to the RWST,.then their use should be minimized to prevent excessive cooldown and depressurization.

l

.3 H the VCT Makeup System cannot maintain level, 1 hen VERIFY Charging Pump suction shifts to the RWST.

NUCLEAR ORGANIZATION ABNORMAL OPERATING INSTRUCTION S023-13-14 UNITS 2 AND 3 REVISION 3 PAGE 8 0F 24 3.0 SUBSEQUENT OPERATOR ACTIDl6 (Continued)

PERF. BY INITIALS 3.3.1.4 H the Charging Pumps must be run to maintain Pressurizer Level with suction from the RWST,

.then REDUCE turbine load, as necessary, to follow the boration power reduction.

.5 ATTEMPT to recover VCT level using the makeup system in the MANUAL mode if automatic has 1

failed.

NOTE:

Flushing of the SIS headers can be accomplished by maintaining the l

SIS header pressure above the SIT pressure and below the RCS pressure while recirculating back to the RWST for approximately ten (10) minutes.

.6 H the Charging Pump discharge will be aligned to the SIS headers due to leak location, and the VCT Makeup System is available,.then it may be possible to minimize boration of the 1

RCS by flushing the SIS headers.

.6.1 H Pressurizer Level drops below 30%, then ABORT recirculation, RECOVER RCS inventory control, and REDUCE turbine load, as necessary, to follow the boration power reduction.

3.3.2 H the break is downstream of the Charging Pumps, lhen RE-ESTABLISH charging flow:

.1 H the break is downstream of HV-9200 or 52(3)1208MUO91, then PERFORM the following:

.1.1 OPEN S2(3)1208MUO65, Charging Pump to HPSI Suction Header Isolation Valve.

.1.2 OPEN S2(3)1208MU005, Charging Header to Loop 1 Hot leg Injection.

.1.3 OPEN, HV-9323, Loop 1A Safety Injection Valve.

.1.4 OPEN, HV-9329. Loop 2A Safety Injection Valve.

.1.5 CLOSE, S2(3)1208MUO91, Charging Header Isolation Valve.

NUCLEAR ORGANIZATION ABNORMAL OPERATING INSTRUCTION S023-13-14 UNITS 2 AND 3 REVISION 3 PAGE 9 0F 24 3.0 SUBSEOUENT OPERATOR ACTIONS (Continued)

PERF. BY INITIALS 3.3.2.1.6 START Charging Pump (s) to establish charging flow.

STOP and START Charging Pumps as necessary to maintain Pressurizer Level between 30% and 53%.

.1.7 ISOLATE the leak to preclude possible back flow via charging line check valves:

2lJ.1DR The following Step places the Unit in a Tech. Spec. LCO 3.0.3 action by isolating ECCS and Charging flow paths. This is a management preapproved entry.

.1.8 CLOSE, HV-9202, Charging to RCS Loop 1A Isolation Valve.

.1.9 CLOSE, HV-9203, Charging to RCS Loop 2A Isolation Valve.

.l.10 CLOSE, HV-9200, Charging Containment Isolation Valve.

.2 11 the break is on the P-190 side of S2(3)1208MUO64, Charging Pump P-190 Disch. Block,

.t. hen PERFORM the following:

.2.1 STOP P-190, Charging Pump.

.2.2 CLOSE S2(3)1208MUO64, Charging. Pump P-190 Discharge Block Valve.

.2.3 OPEN breaker 80413 for P-190 pump protection.

.2.4 START P-191, Charging Pump, and/or P-192, Charging Pump, to establish charging flow.

.2.5 STOP and START P-191, Charging Pump, or P-192, Charging Pump, as necessary to maintain Pressurizer Level between 30% and 53%.

NUCLEAR ORGANIZATION ABNORMAL OPERATING INSTRUCTION S023-13-14 UNITS 2 AND 3 REVISION 3 PAGE 10 0F 24 3.0 SUBSE00ENT OPERATOR ACTIONS (Continued)

PERF. BY INITIALS 3.3.2.3 11thebreakisontheP-191/P-192sideof 52(3)1208MUO64AndupstreamofS2(3)1208MUO91, then PERFORM the following:

.3.1 SECURE all Charging Pumps.

.3.2 CLOSE S2(3)1208MUO64, Charging Pump P-190 Discharge Block.

.3.3 OPEN S2(3)1208MUO65, Charging Pump to HPSI Suction Header Isolation Valve.

.3.4 OPEN S2(3)1208MU005, Charging Header to Loop 1 Hot Leg Injection.

.3.5 OPEN, HV-9323, Loop 1A Safety Injection Valve.

.3.6 OPEN, HV-9329, Loop 2A Safety Injection Valve.

fallI1QM The following step places the Unit in a Tech. Spec. LC0 3.0.3 action by isolating ECCS and Charging flow paths. This is a Management pre-approved entry.

.3.7 CLOSE, HV-9200, Charging Containment Isolation Valve.

.3.8 CLOSE, S2(3)1208MUO91, Charging Header Isolation Valve.

.3.9 START Charging Pump P-190 to establish Charging flow.

.3.10 STOP and START P-190 as necessary to maintain Pressurizer Level between 30% and 53%.

.3.11 ISOLATE the leak to preclude possible back flow via charging line check valves:

.3.12 CLOSE, HV-9202, Charging to RCS Loop 1A Isolation Valve.

.3.13 CLOSE, HV-9203, Charging to RCS Loop 2A Isolation Valve.

NUCLEAR ORGANIZATION ABNORMAL OPERATING INSTRUCTION S023-13-14 UNITS 2 AND 3 REVISION 3 PAGE 11 0F 24 3.0 SUBSEOUENT OPERATOR ACTIONS (Continued)

PERF. BY INITIALS CAUTION H the Charging Pumps are aligned with suction to the RWST or are being used for Emergency Boration, ihan their use should be minimized to prevent excessive cooldown and depressurization.

3.3.2.4 H repairs necessitate a plant cooldown without Letdown, _then EMERGENCY BORATE as needed per 5023-13-11, Emergency Boration oftheRCS/InadvertentDilutionorBoration.

.5 H forced circulation is being used during a cooldown without Letdown, then ALLOW Pressurizer Level to rise to 57% during the Emergency Boration to provide sufficient volume to reach or exceed a Xenon Free Cold (200*F) Shutdown Margin greater than 5.15% AK/K.

(Tech. Spec. LCO 3.4.9)

.6 TRANSFER the Charging Pump Suction to the RWST.

if available, after completing the Boration.

.7 MAINTAIN Pressurizer Level at approximately 57% during the cooldown. (Tech. Spec. LCO 3.4.9)

.8 ENSURE Pressurizer Spray is used to equalize boron concentration.

.9 H natural circulation is being used during a cooldown without letdown.1 hen ALLOW Pressurizer Level to rise up to a maximum of 57% during the baration from the BAMU Tanks.

(Tech. Spec. LCO 3.4.9)

.10 After reaching a Xenon Free Cold (200*F) shutdown margin of at least 5.15% AK/K, then TRANSFER the Charging Pump Suction to the RWST

.11 During the subsequent natural circulation cooldown, ALLOW Pressurizer Level to return to approximately 39% to provide an available volume for Pressurizer cooldown using Auxiliary Spray.

.12 ENSURE Auxiliary Spray is used to minimize the spread between Pressurizer Boron Concentration and RCS Baron Concentration.

NUCLEAR ORGANIZATION ABNORMAL OPERATING INSTRUCTION S023-13-14 UNITS 2 AND 3 REVISION 3 PAGE 12 0F 24 3.0

$UBSEQUENT OPERATOR ACTIONS (Continued) 3.4 Primary to Secondarv Leakagg 3.4.1 An immediate notification to the Resident NRC Inspector is required for either of the following conditions: (This notification will normally be performed by Drerations Management, however it may need to be performed by the Shift Manager if Operations Management can not be contacted.)

(Ref. 4.4.1) total Steam Generator Tube leakage of a 5 GPD an increase in Steam Generator Tube leakage of e

2 5 GPD from the previous leakage rate 3.4.2 INCREASE monitoring of Radiation Monitors until suspected /identifiedSteamGeneratorTubeLeakhas stabilized. Utilize the following frequencies:

When the leak is > 5 and < 30 gpd, then e

PERFORM Attachments 1 and 2 every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

When the leak has stabilized, (< 10% increase per hour average), lhen TERMINATE the use of Attachments 1 and 2.

CONTINUE to check the radiation monitors on a frequent basis.

• When the leak is > 30 gpd, Ihtn PERFORM Attachments 1 and 2 every 15 minutes.

When the leak has stabilized

(< 10% increase per hour average), then PERFORM Attachments 1 and 2 every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

When the leak has been stable for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, itign TERMINATE the use of Attachments 1 and 2.

CONTINUE to check the radiation monitors on a frequent basis.

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NUCLEAR ORGANIZATION ABNORMAL OPERATING INSTRUCTION S023-13-14 I

UNITS 2 AND 3 REVISION 3 PAGE 13 0F 24 3.0 SUBSE0 VENT OPERATOR ACTIONS (Continued)

PERF. BY INITIALS 3.4.3 When leak is stable, then ADJUST the setpoints onRE-7870(pCl/sec)and/orRE-7818A(cpm),

Condenser Air Ejector Radiation Monitors, to 30 GPD above the current leak rate.

.1 J.f any of the following Radiation Monitors are 005 then INITIATE an AR for a Priority 1 M0:

RE-7870 ( Ci/sec), Condenser Air Ejector Radiation Monitors RE-7816A (cpm), Air Ejector Radiation Monitors e

RE-7874A and/or RE-7874B, Main Steam Line e

Radiation Monitors RE-6753and/orRE-6759,SteamGeneratorBlowdown e

Radiation Monitors NOTES:

1. Main Steam Line Monitors will not respond to Tech. Spec. primary to secondary leakage limits or 1 gpm total, with ty ical RCS activities (i.e., < 1% failed fuel.

2. The butidup of waste gas in the Nitrogen System j

may result in an increased indication of leakage on RE-7870 and/or RE-7818. Indication of waste gas buildup in the Nitrogen Syste'n can be indicated on PI-5104, Nitrogen Pressurr. to Waste Gas System f

indicating 190 psig.

3.4.4 The following table applies to RE-7870 ( Ci/sec) and RE-7818A (cpm), Condenser Air Ejector Radiation Monitors.

MP-054 STATUS RE-7870 RE-7818 HIGH Setpoint on HIGH Setpoint on 0FF calibration sticker calibration sticker (gpd) is valid (gpd) is valid Reset HIGH setpoint fhr ading s ON corresponding to a 100 gpd leak rate [1]

induction through MP-054 AEJs.

l(

3.4.5 REQUEST Chemistry to confirm and quantify Steam Generator Tube leak by Condenser Air Ejector sample.

[1] A setpoint of 100 gpd is necessary to obtain a representative value due to l(

the high flowrate from the vacuum pump,

NUCLEAR ORGANIZATION ABNORMAL OPERATING INSTRUCTION S023-13-14 UNITS 2 AND 3 REVISION 3 PAGE 14 0F 24 3.0 - $UBSEQUENT OPERATOR ACTIONS (Continued)

PERF. BY INITIALS 3.4.5.1 The methodology for determining S/G Tube leakage, using the Air Ejector Radiation Monitors, in Attachments 1 and 2 is:

RE-7870/7818A INDICATION vs S/G LEAK RATE RE-7870 DI 7818A indication may be used as an aid in assessing the rate of S/G tube leakage. The following equationsusetherelationshipbetweenRE-7870/7818A actual indication, RE-7870/7818A HIGH SETPOINT, and a pre-determinedS/GLeakRateValuetocalculateS/G Tube Leakage.

NOTE: Based on the current RCS Activity level, the High Radiation Setpoint would be adjusted to Alarm at an activity Cf/sec) or (cpm) e to a pre-determined S G Leak Rate Value (qualgpd).

RE-7870 INDICATION x (S/G Leak S/Gfube RE-7870 HIGH SETPOINT Rate Value)

Leakage (gpd)

OR RE-7818A INDICATION x(S/GLeak S/GTube RE-7818A HIGH SETPOINT Rate Value), Leakage (gpd) 3.4.6 PERFORM the following to deterniine the affected Steam Generator:

.1 OBSERVE an increase on RI-6753 or RI-6759, Steam Generator Blowdown Radiation Monitor.

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.2 REQUEST Chemistry to sample Steam Generators.

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NUCLEAR ORGANIZATION ABNORMAL OPERATING INSTRUCTION S023-13-14 UNITS 2 AND 3 REVISION 3 PAGE 15 0F 24 3.0 SijBSE00ENT OPERATOR ACTIONS (Continued)

PERF. BY INITIALS 3.4.7 H the leak rate has.increated by 60 gallons per day within any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period, DE the leak rate through any Steam Generator is

> 150 gpd, lhtn:

.1 CONFIRM Steam Generator Tube leak by observing anincreaseonRI-6753and/orRI-6759, Steam Generator Blowdown Radiation Monitors.

.2 H the increase in the leak rate is determined to be an instrument spike or malfunction; 1han, at the discretion of the Shift Manager, a rapid shutdown of the Reactor is n01 required.

.3 PLACE A-361, Air Ejector Exhaust Unit, in DIRECT, And discontinue using Att. 1 and 2.

.4 H the leak rate has increased by 60 gallons per day within any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period, iban CONDUCT a rapid shutdown of the Reactor (1 to 5 %/ min) per the guidelines in S023-5-1.7, Power Operations, Section for Guidelines for Rapid Downpower Transients.

.5 H the leak rate through any Steam Generator is 2 150 gpd, then Commence a controlled shutdown to be in Hot Standby within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (Ref. 4.4.4)

.6 Shift Manager should NOTIFY the Plant Superintendent or designee that a Reactor Shutdown is in progress.

NOTE:

The objective is to cooldown to less than 530*F 1solate the affected Steam Generator, and depressurize the RCS as soon as possible.

.7 When power is less than 35%, then TRIP the l

Reactor and PERFORM the actions of S023-12-1, Standard Post Trip Actions.

NUCLEAR ORGANIZATION ABNORMAL OPERATING INSTRUCTION S023-13-14 UNITS 2 AND 3 REVISION 3 PAGE 16 0F 24 3.0 SUBSE00ENT OPERATOR ACTIONS (Continued)

PERF. BY INITIALS 3.4.7.8 Take the following actions to minimize contamination:

.8.1 When the affected Steam Generator has been identified, lhen ISOLATE Blowdown for that Steam Generator.

.8.2 PLACE LV-3245, Condenser Draw Off Valve, to DISABLE.

.8.3 PLACE Condenser Hotwell Overboarding System in MANUAL.

.8.4 SECURE Turbine Building Ventilation.

.8.5 PLACE Turbine Building Sumps in 0FF And INSTALL Caution tags stating " Chemistry Must Sample Before Pumping Sump".[3]

.9 BYPASS Full-Flow Condensate Polishers:

.9.1 OPEN FV-4902A, Full Bypass Valve.

.9.2 CLOSE HV-4900A, FFCPD Inlet Isolation Valve.

.9.3 CLOSE HV-49008, FFCPD Outlet Isolation Valve.

.10 SECURE steam drain lines that are aligned for blowdown to atmosphere.

3.4.8 11 Chemistry determines Steam Generator Activity

>2.0E-6 pCi/cc, then PERFORM the following;

.1 MONITOR radiation levels using RE-7870/7818A, Condenser Air Ejector Radiation Monitor, once per 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> in Attachments 1 or 2.

.2 REQUEST Chemistry to evaluate calculating a new RE-7870/7818A, Air Ejector Radiation Monitor, High Setpoint above the present stable S/G1eakagerate.

.3 ENSURE RE-7870 High Radiation Setpoint is updated by Radmonitoring, as applicable.

lf.

whenever Vacuum Pump status (pump started / stopped)ischanged.

.4 NOTIFY Chemistry that Condenser Hotwells must be sampled for activity weekly until leakrate has stabilized.

.5 INSTALL a Caution tag at CR-53 stating " Notify Chemistry Before Overboarding Hotwells." [3]

[3]

Document placement in Caution Tag Log.

NUCLEAR ORGANIZATION ABNORMAL OPERATING INSTRUCTION S023-13-14 UNITS 2 AND 3 REVISION 3 PAGE 17 0F 24 3.0 SUBSEQUENT OPERATOR ACTIONS (Continued)

PERF. BY INITIALS 3.4.8.6 ALIGN Control Bldg. Sump to the BPS Sump per S023-2-16, Attachment for Pumping Auxiliary Building Sump.

.7 INSTALL Caution tags stating " Chemistry Must Sample Before Pumping Sump" at the following locations [3]:

.8 P-1008, AFW Doghouse Sump Pump Control Switch (located at top of ladder in AFW Doghouse).

.9 2(3)Q03111, 2(3)P-469 Rainwater Sump Pump Power Supply (2(3)MCC BX) or 2(3)XN2 YDS 011.[2]

.10 2003824, 2P-470 Rainwater Sump Pump Power Supply (MCC 2BV) or 2XN2YD024.

(MarkN/AifUnit3.)

[2]

.11 3QO3115, 3P-470 Rainwater Sump Pump Power Supply (MCC 3BX) or 3XN2YD015.

(MarkN/AifUnit2.)

[2]

3.4.9 EVALUATE effects of Tube Leakage:

.1 NOTIFY Chemistry to sample secondary plant systems for activity.

.2 NOTIFY 70' HP Control Point to evaluate secondary plant Radiation levels and establish radiological controls.

.3 CONTINUE to monitor process Radiation Monitors for increase tube leakage.

.4 EVALUATE Placing A-361, Air Ejector Exhaust Unit, in Direct mode after RE-7870/7818A,CondenserAirEjector Radiation Monitor, has alarmed.

3.5 Record date and time procedure terminated and unit affected.

Unit Date Time

[2]

11 Operating the pump from the Disconnect Switch 1han hang the CAUTION TAG locally at the MSIV Trench area.

[3]

Document placement in Caution Tag Log.

4.0 ~ REFERENCES

< NUCLEAR ORGANIZATION ABNORMAL OPERATING INSTRUCTION S023-13-14 UNITS 2 AND 3 REVISION 3 PAGE 18 0F 24 l

!4.0-REFEREEIS l

4.1

-Licensina Commitment 4.1.1 Technical Specifications

.4.2 Procedure 4.2.1 S0123-VIII-1, Recognition and Classification of Emergencies 4.3 'Doeratina Instructions

4. 3.1.

S0123-0-25, Trip /TransientReview j

4.3.2 50123-0-14, Notification and Reporting of Significant Events 4.3.3 S023-2-16, Operation of Waste Water Systems 4.3.4 S023-3-2.1, CVCS Charging and Letdown 4.3.5 S023-3-3.37, Reactor Coolant System Water Inventory Balance 4.3.6 S023-12-1, Standard Post Trip Actions

)

4.3.7 S023-13-11, EmergencyBorationoftheRCS/ Inadvertent Dilution or Boration 4.3.8 S023-5-1.7, Power Operations 4.4 Other 4.4.1 E-Mail to R.Waldo from M. Trillo, dated December 11, 1993,

Subject:

Steam Generator Tube Leakage (RMS-264) 4.4.2 E-mail from M.A. Jones to T. Vogt, dated 27 October 1997; subject; S/G Tube Leakage Monitors Expectations: States Administrative Guidelines for minimum required Operable Radiation Monitors for Steam Generator Tube Leak detection.

4.4.3 DCP 2005.00SJ and Calc J-BBB-021. Changed maximum pressurizer level from 58% to 57% due to Total Loop Uncertainty.

4.4.4 EPRI PWR Primary-to-Secondary Leak Guidelines (A01-429).

5.0 REC 0h4 5.1 F!1e per S0123-0-25 t14-3.w61

NUCLEAR ORGANIZATION ABNORMAL OPERATING INSTRUCTION S023-13-14 UNITS 2 AND 3 REVISION 3 PAGE 19 0F 24 ATTACHMENT 1 RE-7870 STEAM GENERATOR RADIATION AND LEAKAGE READINGS UNIT DATE TIME PERF. BY 1.0 PREREOUISITES INITIALS 1.1 Verify this document is current by checking a controlled copy or by using the method described in 50123-VI-0.9.

2.0 PROCEDURE NOTES: 1. When MP-054, Condenser Vacuum Pump, is not operating.

than RE-7870, Condenser Air Ejector Radiation Monitor, is set to alarm at a S/G Tube Leak Rate (gpd) listed on the latest calibration sticker.

2.

When MP-054. Condenser Vacuum Pump, li operatin9. 1 hen RE-7870, Condenser Air Ejector Radiation Monitor, is settoalarmataS/GTubeLeakRateof100gpd.

lA 3.

Depressing the "EFF" pushbutton results in displaying effluent activity in units of C1/sec.

4.

When the leak is > 5 and < 30 gpd, then readings should be taken every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

A/

5.

When the leak is 1 30 gpd, lhen readings should be taken every 15 minutes.

2.1 RECORD RE-7870 information from the Calibration Sticker.

2.1.1 RE-7870(setpoint) pC1/sec 2.1.2 Pre-determinedS/G Tube Leak Rate Value gpd 2.1.3 If a new setpoint is installed in RE-7870, durtrig the performance of this Attachment, then use the new updated setpoint for further Leak Rate calculations. And note the time of the new setpoint in the Comments Section.

2.2 CALCULATE S/G tube leakage in the following table at the appropriate f requency stated in Section 3.4.

2.3 If the Vacuum Pump is operating when a required calculation is to be i

performed, then RECORD the Date and Time, and leave the calculation steps blank. Make a note in the comments section (e.g., Calculation not performed due to Vacuum Pump operating). Also, note start anu

~

stop times of the Vacuum Purrp in Comments section.

ATTACHMENT 1 PAGE 1 0F 3

nienenntne 1 NUCLEAR ORGANIZATION ABNORMAL OPERATING INSTRUCTION S023-13-14 UNITS 2 AND 3 REVISION 3 PAGE 20 0F 24 ATTACHMENT 1 2.0 PROCEDURE (Continued)

_RE-78 _70 STEAM GENER _ATOR RADIATION _AND LEAKAG,E READINGS [2]l&

m m

DATE TIME RE-7870

+

RE-7870 x

S/GTube S/G Tube INITIALS

=

Indication Setpoint Leak Rate LEAKAGE PERF/INDVER (Reading)

(2.1.1)

Value (gpd)

[1]

(2.1.2)

+

x

=

pC1/sec C1/sec gpd gpd

+

x

=

pCi/sec pCi/sec gpd gpd

+

x

=

pCi/sec pCi/sec gpd gpd

+

x

=

pCi/sec pC1/sec gpd gpd

+

x

=

pC1/sec pCi/sec gpd gpd

+

x

=

pCi/sec p',i/sec gpd gpd

+

x

=

pC1/sec Ci/sec gpd gpd

+

x

=

pC1/sec pC1/sec gpd gpd

+

x

=

pCi/sec pCi/sec gpd gpd

+

x

=

pct /sec pCi/sec gpd gpd

+

x

=

pC1/sec pCi/sec gpd gpd

+

x

=

pC1/sec pCi/sec gpd gpd

[1] 11 a flow constant is installed..thEn multiply the Radmonitor reading by (Actual SCFM + Flow Constant) to obtain Actual Radmonitor reading.

[2] Use additional sheets, as necessary.

lg ATTACHMENT 1 PAGE 2 0F 3

p NUCLEAR ORGANIZATION ABNORMAL OPERATING INSTRUCTION S023-13-14 UNITS 2 AND 3 REVISION 3 PAGE 21 0F 24 ATTACHMENT 1 2.0 PROCEDURE -(Continued) l COMMENTS:

REVIEWED BY:

DATE:

SR0 Ops. Supv.

FILE DISPOSITION:

File per S0123-0-25.

i ATTACHMENT 1 PAGE 3 0F 3 i

L J

NUCLEAR ORGANIZATION ABNORMAL OPERATING INSTRUCTION S023-13-14 UNITS 2 AND 3 REVISION 3 PAGE 22 0F 24 ATTACHMENT 2 i

RE-7818A STEAM GENERATOR RADIATION AND LEAKAGE READINGS UNIT DATE TIME l

PERF. BY 1.0 PREREOUISITES INITIALS 1.1 Verify this document is current by checking a controlled copy or by using the method described in 50123-VI-0.9.

2.0 PROCEDURE NOTES: 1.

H RE-7870, Condenser Air Ejector Radiation Monitor, is not available, _then RE-7818A may be used to monitor for Steam Generator Tube leakage.

2.

When 2(3)MP-054, Condenser Vacuum Pump, is operating then air induction from the Vacuum Pump assist air ejectors will cause RE-7818A HIGH setpoint to no longer correspond to the latest calibration sticker.

4.

When the leak is > 5 and < 30 gpd,.then readings should be taken every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

5.

When the leak is a 30 gpd,.then readings should be k

taken every 15 minutes.

2.1 RECORD RE-7818A information from the Calibration Sticker.

l 2.1.1 RE-7818A (setpoint)

CPM 2.1.2 Pre-determinedS/G Tube Leak Rate Value gpd 2.1.3 11 a new setpoint is installed in RE-7818A, during the performance of this Attachment, then use the new updated setpoint for further Leak Rate calculations, and note the time of the new setpoint in the Coments Section.

2.2 CALCULATES /Gtubeleakageinthefollowingtableatthe appropriate frequency stated in Section 3.4.

ATTACHMENT 2 PAGE 1 0F 3

NUCLEAR ORGANIZATION ABNORMAL OPERATING INSTRUCTION S023-13-14 UNITS 2 AND 3 REVISION 3 PAGE 23 0F 24 ATTACHMENT 2 2.0 PROCEDURE (Continued) 2.3 If the Vacuum Pump is operating when a required calculation is to be perfortred, then RECORD the Date and Time, and leave the calculation steps blank. Make a note in the coments section (e.g., Calculation not performed due to Vacuum Pump operating). Also, note start and i

stop times of the Vacuum Pump in Coments section.

RE-7818A STEAM GENERATOR RADIATION AND LEAKAGE READIN

======== mem==se summmmmmme muun muassumummm numa amenumammen - meme==GS [1]

l&

mm ummunsamme=_

DATE TIME RE-7818A

+

RE-7818A x

S/GTube S/G Tube INITIALS

=

Indication Setpoint Leak Rate Leakage PERF/INDVER (Reading)

(2.1.1)

Value (gpd)

(2.1.2)

+

x

=

cpm cpm gpd gpd

+

x

=

cpm cpm gpd gpd

+

x

=

cpm cpm gpd gpd

+

x

=

cpm cpm gpd gpd

+

x

=

cpm cpm gpd gpd

+

x

=

cpm cpm gpd gpd

+

x

=

cpm cpm gpd gpd

+

x

=

cpm cpti gpd gpd

+

x

=

cpm cpm gpd gpd cpm cpn gpd gpd

+

x

=

cpm cpm gpd gpd

+

x

=

cpm cpm gpd gpd m

[1] Use additional sheets, as necessary.

l A/

ATTACHMENT 2 PAGE 2 0F 3 l

NUCl. EAR ORGANIZATION ABNORMAL OPERATING INSTRUCTION S023-13-14

'i UNITS 2 AND 3-REVISION 3 PAGE 24 0F 24 ATTACHMENT 2 2.0 PROCEDURE (Continued)

COPMENTS:

REVIEWED BY:

DATE:

SR0 Ops. Supv.

FILE DISPOSITION:

File per 50123-0-25.

ATTACHMENT 2 PAGE 3 0F 3