Text

Rev 04.01 to Procedure 41AO-1ZZ08, SG Tube Leak
	ML20056D395
Person / Time
Site:	Palo Verde
Issue date:	08/09/1993
From:	; ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	;
Shared Package
ML17310A512	List: ML17310A510; ML20056D395; ML20056D396;
References
	41AO-1ZZ08, 41AO-1ZZ8, NUDOCS 9308130105
	Download: ML20056D395 (34)
	v • d • e

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NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page-1 of.33 ,

STEAM GENERATOR TUBE LEAK Revision . Il 41AO-1ZZ08 04.01 i

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i OBJECTIVE This procedure gives guidance on how to mitigate a S/G Tube leak that is less than :

80 gpm. The objective is to cooldown to Mode 5 if the leak is between .5 gpm and 80'gpm, ;

or to provide adequate guidance to the operators if the leak is less than .5 gpm and to ;

minimize any radioactive release to the environment. Instructions are also provided for ;

draining the Condenser Hotwell to the Low TDS Sump. '!

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NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 2 of 33 j RnMon STEAM GENERATOR TUBE LEAK 41AO-1ZZO8 04.01

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TABLE OF CONTENTS - s i

SECTION PAGE !

I 1.0 Entry Conditions................ ... . .......... .....................................................................3- !

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2.0 Event Control ........... ... .. .. ..... ................................................................................3 i t

f 3.0 Steam Generator Isolation ....... ... ... . . . . . . ................................................10 i

4.0 P roce d u r e Exit. . . . . . .. . .. .. . .. . . . .. ... .. . .. . . . . . . . . . .. . . .... . . . . . .. . . .. . . . . . . .. . . .. . . .. . .. . ... . .. . . . . . . .. . . .. . . . . . .. . ... . . 15 i

APPENDICES ;

APPENDIX .PAGE i

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t Appendix A - Moderate to Large Leak Rr4te Calculation .. ... ..... .. ................ ..... ....... . . . . . .. .. . . . 16 l Appendix B - Cundensate Isolation Checklist .. . .. .................................................................19 +

4 Appendix C - Steam Generator 1 1 solation Checklist . . .... ............ . .. ............... ........ ..... .......... 20 '!

Appendix D - Steam Generator 2 Isolation Checklist . ........................ .............. ....... .. . ....... ... 22 }

Appendix E - Steam Generator 1 Level Reduction Checklist .. .. ....... ........................ ... ... ........ 24 I Appendix F - Steam Generator 2 Level Reduction Checklist ...... ... .... .................................. ...... 27 Appendix G - Draining the Hotwell to the Low TDS Sump.................. .. .................. .. . . .. . . . . . .. . 3 0 ' .I E

6 Ap pen dix II - References ............. .............. ...... ... . .............................................................32 l h

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NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 3 of 33 Rnis>n STEAM GENERATOR TUBE LEAK 41AO-1ZZO8 ,

04.01 1.0 Entry Conditions

_ 1.1 Check that any of the following entry conditions for a steam generator tube leak exists:

Condenser vacuum off-gas radiation monitor, RU-141 is increasing above a previously stable background level.

l Activity is detected above expected levels in a secondary side sample.

A main steam line radiation monitor, RU-139 or RU-140, is increasing above a previously stable background level.

A blowdown radiation monitor, RU-4 or RU-5, is increasing above a previously stable background level. .

l There are indications of an increase in primary to secondary leakrate. !

1.2 E any of the entry conditions for a steam generator tube leak exists, THEN continue in this procedure.

E NOT. THEN GO TO the applicable operating procedure for existing plant conditions.

2.0 Event Control 2.1 E all available charging pumps are operating, ANIl pressarizer level continues to decrease, THEN isolate letdown.

Close CHN-UV-515 on B03 to isolate letdown.

2.2 E, at any time during this procedur e, anI of the following conditions exist:

PZR level falla below 33% with all available charging pumps running, and letdmvn isolated.

Leak rate is above 80 gpm.

TIIEN perform the following:

1. Trip the reactor.

2. GO TO Emergency Operations,41EP-1EOO1, beginning at the entry to the Safety Function Flowcharts.

2.3 Direct Chemistry to perform actions in accordance with Abnormal Occurence Checklist,74DP-9ZZO5, for a steam generator tube leak.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 4 of 33 Rnision STEAM GENERATOR TUBE LEAK 41AO-1ZZO8 04.01 Event Control (cont) 2.4 Ensure that the event is being classified in accordance with the Emergency Plan.

Direct an SRO or EC qualified person to CONCURRENTLY PERFORM Emergency Classification, EPIP-02, beginning with Step 4.0.

. . . ggyg The CRS may elect to perform one or both of the following leak rate determination methods. Moderate to Large Leak Rate Calculation, -

Appendix A takes approximately 20 minutes to complete but is not extremely precise. RCS Water Inventory Balance,41ST-1RC02 is more precise, but takes over two hours to complete.

2.5 Measure the leak rate using one or both of the following methods:

CONCURRENTLY PERFORM Moderate to Large Leak Rate Calculation, Appendix A to this procedure.

CONCURRENTLY PERFORM RCS Water Inventory Balance,41ST-1RC02.

2.6 Select the THRU FILTER MODE position with the Air Removal Post Filter Mode Select Switch, ARN-HS-19, on panet B07.

2.7 Ensure that the SBCS valves that release to the condenser are in auto:

Ensure VALVE 1 MODE SELECT, SGN-HS-1001 is in auto. ,

Ensure VALVE 2 MODE SELECT, SGN-HS-1002 is in auto.

Ensure VALVE 3 MODE SELECT, SGN-HS-1003 is in auto.

Ensure VALVE 4 MODE SELECT, SGN-HS-1004 is in auto.

Ensure VAIXE 5 MODE SELECT, SGN-HS-1005 is in auto.

Ensure VALVE 6 MODE SELECT, SGN-HS-1006 is in auto.

2.8 Ensure that the SBCS valves that release to the atmosphere are closed:

Select OFF on VALVE 7 MODE SELECT, SGN-HS-1007.

Select OFF on VALVE 8 MODE SELECT, SGN-IIS-1008.

1 NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 5 of 33

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STEAM GENERATOR TUBE LEAK 41AO-1ZZO8 04.01 Event Control (cont) ;

2.9 Ensure that the ADVs are closed:

Select CLOSE on SG 1 LINE 1 ISOL VLV, IW-184, SGA-IN-184A.

Select CLOSE on SG 1 LINE 1 ISOL VLV, HV-184, SGC-HY-184B.

Select CLOSE on SG 1 LINE 2 ISOL VLV, HV-178, SGB-HY-178A. ;

Select CLOSE on SG 1 LINE 2 ISOL VLV, HV-178, SGD-HY-178B. !

Select CLOSE on SG 2 LINE 1 ISOL VLV, HV-185, SGB-HY-185A.

Select CLOSE on SG 2 LINE 1 ISOL VLV, HV-185, SGD-HY-185B. ,

Select CLOSE on SG 2 LINE 2 ISOL VLV, HV-170, SGA-HY-179A.

Select CLOSE on SG 2 LINE 2 ISOL VLV, HV-179, SGC-HY-179B. ;

2.10 Align the demineralized water system to the condensate service header. i

1. Throttle open the Demineralized Water Feed to Condensate Service Header f Valve, CDN-HV-275, to obtain a pressure ofs 100 psig on CDN-PI-201.

2. Direct an auxiliary operator to close the Condensate Service Header Pressure Controller Outlet Isolation Valve, CDN-V099, located at the 110 ft level of the turbine building between the condensate pumps and the C condenser. .

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NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page e of 33 Revision j STEAM GENERATOR TUBE LEAK 41AO-1ZZO8 04.01 l Event Control (cont) l l

2.11 E two condensate demineralizers are not in service, THEN perform the following to place two in service:

1. Ensure two service vessels are ready to be placed in service. Ensure the two service vessels to be placed in service have the service vessel inlet valves, A1, ,

open. l

2. Ensure CONDENSATE POLISHING DEMIN INLT VLV, CDN-HS-191, is open on B05.

3. Ensure the outlet valves for the two service vessels to be placed in service are open. Ensure the two service vessels to be placed in service have the service vessel outlet valves, E1, open.

4. Ensure CDN-V195, CONDENSATE POLISHING DEMINERALIZER BYPASS VALVE, is open. Ensure CDN-PDIC-195, "DEMIN DIFF PRESS CONT" is in manual and has a 0 output signal. CDN-PDIC-195 is located in the unit control ;

room on B05.

5. Ensure CNDS POLISHING DEMIN OUTLT VLV, CDN-HV-199, is open on B05.

6. Adjust flow through the condensate demineralizers. Throttle close CDN-V195 by slowly adjusting CDN-PDIC-195 untilit indicates approx. 50 paid.

7. Ensure CDN-PDIC-195, CONDENSATE POLISHING DEMINERALIZER BYPASS VAINE, is in AUTO.

2.12 E greater than two condensate demineralizers are in service, THEN contact chemistry to determine if any condensate demineralizers should be removed from service.

Remove condensate demineralizers from service per Operating The Condensate Demineralizer System,410P-ISC03, as directed by chemistry.

2.13 Ensure the blowdown demineralizers are in service. Place a blowdown i demineralizer in service per Regeneration of the Blowdown Demineralizer, 400P-9SC05 2.14 Isolate the condensate system from the CST and the condensate cross-tie header.

Direct an auxiliary operator to perform Condensate Isolation Checklist, Appendix B to this procedure.

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k NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL-Page 7 of 33 R W on STEAM GENERATOR TUBE LEAK '

41AO-1ZZ08 04.01 Event Control (cont) 2.15 E auxiliary steam is available from another unit or an auxiliary boiler, TILFE ensure the auxiliary steam cross-tie header is isolated from main steam:

1. Ensure CROSS-TIE HEADER ISOLATION VALVE, ASN-V015 is open.

2. Close REDUCER INLET VALVE, SGN-V093. l l

3. Close REDUCER INLET VALVE, SGN-V094. l

4. Close REDUCER INLET VALVE, SGN-V095. !

2.16 E auxiliary steam is NOT available from another unit or an auxiliary boiler, THEN ensure main steam is supplying auxiliary steam.

1. Ensure CROSS-TIE HEADER ISOLATION VALVE, ASN-V015 is closed. l

2. Close CROSS-TIE HEADER BYPASS VALVE, ASN-V014 is closed. f 2.17 Direct RP to perform surveys of the condensate demineralizers, blowdown '

demineralizers, and other areas that may be affected.

2.18 Identify the steam generator that has the tube leak.

Evaluate the following parameters in the table below and identify the leaking steam generator. Some or all of these parameters may be present:

Parameter Steam Generator 1 Steam Generator 2' Highest sample activity-4 Main steam line activity in ALERT RU-139 RU-140 or HIGH alarm or increasing trend Steam Generator blowdown activity RU-4 RU-5 in ALERT or HIGH alarm or increasing trend 4

2.19 WHEN Chemistry reports testing results, THEN record the following data:

Steam Generator tube leak rate gpm. ,

l Steam Generator Dose Equivalent Iodine pei/ gram.

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STEAM GENERATOR TUDE LEAK 41AO-1ZZO8 04.01 !

Event Control (cont) j l

CAUTION The time limits given in the following step help ensure that the pounds mass of RCS transferred to the secondary system, does not exceed the amount analyzed in the i UFSAR (75,275 lbm).

l 2.20 E the tube leak is between 0.035 gpm (50 gpd) and 80 gpm, TJEN perform a plant shutdown:

Perform a plant shutdown at a rate which will ensure the affected steam generator is isolated within the following time limits:

Isolation time limit Primary to Secondary Leak Rate (From Leak Detection to Steam Generator Isolation) l 0.035 gpm to 10.0 gpm 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months 10.0 gpm to 20.0 gpm 7.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ,

20.0 gpm to 30.0 gpm 5 hot rs 30.0 gpm to 40.0 gpm 3.5 hou.s 40.0 ppm to 50.0 gpm 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 50.0 gpm to 60.0 gpm 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 60.0 gpm to 70.0 gpm 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 10 min 70.0 ppm to 80.0 Finn I hour 50 min GO TO Step 2.25 in this procedure.

2.21 E the secondary activity is greater than 0.10 pci/ gram dose equivalent I-131, l TIIEN perform a plant shutdown in accordance with 'Ibeh Spec 3.7.1.4.

GO TO Step 2.25 in this procedure.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 9 of 33 Raision -

STEAM GENERATOR TUBE LEAIC 41AO-1ZZ08 04.01 Event Control (cont) j i

2.22 E the primary to secondary leak rate is less than 10 gallons per day, ;

THEN perform necessary notifications and exit this procedure. 1

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1. Notify operations management of the tube leak. ;

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2. Direct chemistry to continue steam generator samples in accordance with.

Abnormal Occurence Checklist,74DP-9ZZ05. .

3. Continue to monitor available indications to verify the leak rate is stable. T l

4. Exit this procedure. I i

2.23 E the primary to secondary leak rate is between 10 gallons per day and 50 gallons i per day (0.035 gpm), i THEN request Unit Chemistry management to perform the following:

l Review continued operation of the plant.

Direct chemistry to continue steam generator samples in accordance with ;

Abnormal Occurence Checklist,74DP-9ZZO5. j 2.24 E plant shutdown is ngt required, THEN exit this procedure.

CAUTION During the performance of the CRS Diagnostic logic Tree in Emergency Operations, j 41EP-1EO01, the operator may be directed to Steam Generator Tube Rupture, 41EP-1ROO3. If Steam Generator Tube Rupture,41EP-1ROO3,is performed, no further ,

action is required in this procedure. -!

2.25 Perform a plant shutdown to Mode 3. Shutdown the unit per sne of the following combinations of procedures: !

Power Operations,410P-1ZZO5, Plant Shutdown Mode 1 to Mode 2, .!

410P-1ZZ07, and Reactor Shutdown,410P-1ZZO8.

l Rapid Shutdown,41AO-1ZZ56, and Emergency Operations,41EP-1EOO1.

2.26 Check that all Section 2.0 steps have been addressed.

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04.01 l

41AO-1ZZ08 i l

3.0 Steam Generator Isolation '

3.1 E any of the following conditions occur while performing this procedure, i Loss of RCS forced circulation.

Loss of condenser vacuum.

Pressurizer level below 33%, and not recovering. i TIEN exit this procedure and perform Emergency Operations,41EP-1EOO1. ;

3.2 WHEN the plant is stabilized in Mode 3.0, TIIEN initiate performance of RCS and Pressurizer Heatup and Cooldown .

Rates,40ST-9RC01. '

3.3 E all of the following conditions exist: ,

Pressurizer pressure approaches the low pressure pretrip setpoint. j

__ The pretrip alarm, LO PZR PRESS CH PRE-TRIP, actuatea.

t SIAS is NOT actuated. l l

TIIEN perform hath of the following: ;

1. Ensure that the pressure reduction is due to deliberate actions.

2. Direct the secondary operator to maintain the automatic Pressurizer Pressure -

Low setpoint below actual pressurizer pressure.

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NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 11 of 33 1 Raision i STEAM GENERATOR TUDE LEAK 41AO-1ZZO8 04.01 Steam Generator Isolation (cont) :

i 3.4 Direct the primary operator to lower pressurizer pressure to reduce the steam i generator tube leakage. ;

1. CONCURRENTLY. PERFORM Pressurizer Main Spray Cycle Log in RCS and Pressurizer Heatup and Cooldown Rates,40ST-9RC01. !

2. De-energize available class backup heaters.

3. Ensure d of the following: f I

Acceptable RCP NPSH. See RCP NPSH Curve, on the control board. !

l Acceptable RCS subcooling. See Normal Contamment RCS P/T Limits, on the ;

control board. ,.

RVLMS level at least 41% in the RVUH. l i

4. Lower and maintain pressurizer pressure to within 100 psid of the minimum i subcooling limit. See Normal Contaimnent RCS P/T Limits [ Harsh j Containment RCS P/T Limita], on the control board. i 3.5 LE d of the following conditions exist:

Steam generator pressun approaches the low pressure pretrip setpoint. !

The pretrip alarm, LO SG PRESS CII PRE-TRIP, actuates. -

MSIS is NOT actuated. ]

THEN perform hath of the following:

1. Ensure that the pressure reduction is due to deliberate actions. -l

2. Direct the secondary operator to maintain the automatic Steam Generator - !

Low setpoint below steam generator pressure. ,

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CAUTION Maintaining T hbelow 555 F will prevent steam generator safety valve actuation and radioactive release.

3.6 Reduce and stabilize RCS Th at less than 555'F using the SBCS to the condenser. l i

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. Revision STEAM GENERATOR TUBE LEAK ,

41AO-1ZZO8 04.01 t Steam Generator Isolation (cont) 3.7 WHEN RCS Th is below 555'F, i TIIEN isolate the steam generator with the tube leak. :

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1. Raise steam generator water levels to between 72 and 80% WR. ;

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2. Refer to the table below and perform the attachment for the leaking steam generator:

Steam Generator 1 Steam Generator 2 l SG 1 Isolation Checklist, Appendix C SG 2 Isolation Checklist, Appendix D l to this procedure. to this procedure. i i

3.8 Ensure that the most affected steam generator is isolated !

i of the following parameters to confirm that the most affected steam Evaluate gJll generator is isolated. Some or g11 of these parameters may be present:

Steam Generator 1 Steam Generator 2 :

Decreases in readings for the condenser Decreases in readings for the condenser 1 off-gas radiation monitor: off-gas radiation monitor: J RU-141 RU-141 4 Check for increasing steam generator Check for increasing steam generator- )

level with no feedwater flow. level with no feedwater flow. i 1

Steam generator blowdown activity in Steam generator blowdown activity in ALERT or 111G11 alarm on RU-4 or ALERT or IIIGli alarm on RU-5 or increasing trend. increasing trend.

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NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page la of 33 RnMon STEAM GENERATOR TUDE LEAK 41AO-1ZZ08 04.01 Steam Generator Isolation (cont) 3.9 IE the wrong steam generator was isolated, TIIEN perform all of the following:

1. Place the isolated steam generator back in service. Establish auxiliary feed and steam flow from the isolated steam generator.

2. Isolate the most affected steam generator. Refer to the table below and perform the attachment for the leaking steam generator:

Steam Generator i Steam Generator 2 SG 1 Isolation Checklist, Appendix C SG 2 Isolation Checklist, Appendix D to this procedure. to this procedure.

3.10 CONCURRENTLY PERFORM Ilot Standby to Cold Shutdown Mode 3 to Mode l 5,410P-1ZZ10, beginning with Section 4.0.

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i NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUALL Page 14 of! 33-

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41AO-1ZZ08 04.01 Steam GeneratorIsolation (cont)

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Steaming the isolated steam generator will reduce the pressure and affect the tube leak rate. The isolated steam generator should not be steamed unless the PZR pressure is less than or equal to the isolated steam generator pressure. Draining the steam generator with the blowdown system will reduce level without excessively reducing the steam generator pressure. : s

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When the PZR pressure is equalized with the pressure in the isolated steam generator, the tube leakage will be stopped. Using blowdown to drain large amounts of water should not be necessary.

I 3.11 Maintain the isolated steam generator level between 50% and 80% NR by performing the following: -

Feed the isolated steam generator to maintain the level above 50% NR, using !

auxiliary feedwater. '

Drain the isolated steam generator to maintain the level below 80% NR, using the :

steam generator blowdown system at the ABNORMAL rate by performing the attachment indicated in the table below:

Steam Generator 1 Steam Generator 2 SG 1 Level Reduction Checklist, SG 2 Level Reduction Checklist, .

Appendix E to this procedure. Appendix F to this procedure.

t 3.12 Cool and depressurize the isolated steam generator as the RCS cooldown proceeds.

Feed the steam generator to maintain level greater than 50% NR, using auxiliary feedwater. 1 Drain the steam generator to maintain levelless than 80% NR, using the steam.-

generator blowdown system.

3.13 Direct an AO and Chemistry to initiate performance of Chemical Waste Neutralization Tank Surveillance 'Ibst,74ST-9ZZO2.

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STEAM GENERATOR TUBE LEAK 41AO-1ZZO8_ ~ 04.01 Steam Generator lsolation (cont) l 3.14 IE the hotwell high level alarm actuates,- .l' THEN direct an operator to drain the hotwell.

Direct an operator to use Draining ihe Hotwell to the Low TDS Sump,- ;

Appendix G to this procedure, to drain the hotwell. ;

3.15 Check that all Section 3.0 steps have been addressed. j 4.0 Procedure Exit 4.1 Ensure equipment log entries have been made in the control room log. ;

4.2 Ensure that the event classification has been logged in the unit log.

4.3 Ensure that any 'Ibch Spec LCOs that were entered have been complied with and 1 that the LCO status is entered in the unit log: -

RCS leakage limits per hch Spec 3.4.5.2. ;

Secondary coolant system activity per %ch Spec 3.7.1.4. !

Evaluate for any other LCOs that may have been entered.

t 4.4 WHEN shutdown cooling has been established, l!

' THEN exit this procedure.

END OF PROCEDURE i I

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NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 16 of 33 RnNon STEAM GENERATOR TUBE LEAK 41AO-1ZZ08 04.01 Appendix A Page1of3 Appendir A - Moderate to Large Leak Rate Calculation This appendix provides the actions necessary to perform a leakrate calculation for a moderate to large steam generator tube leak.

1.0 Leakrate Calculation HOIE -- --- -- -- - -- - -

Any transients may cause false indications of RCS leakage.

1.1 Establish and maintain all of the following conditions:

RCS Tc is constant within 1*F.

PZR pressure is stabilized at 2235 to 2265 psia.

CVCS letdown is aligned to the VCT.

PZR level is stabilized.

All RCS sampling is stopped.

1.2 Ensure makeup to the RCS is disabled by performing the following substeps:

1. Place CHN-FIC-210X in manual with zero output.

2. Place CHN-FIC-210Y in manual with zero output. l

3. Place CHN-HS-527 in the CLOSED position and verify that CHN-UV-527, MAKE-UP TO CHRG PMPS (VCT BYPASS) VLV indicates closed.

4. Place CHN-HS-210, MAKEUP MODE SELECT SWITCH, in MANUAL.

1.3 IE the leak rate causes the VCT level to approach 15%,

THEN record the final data, allow makeup to the VCT, and calculate the leak rate over the time period measured.

1.4 Record the time the leak rate calculation is started in Table 1 and the initial leak rate data in Table 2.

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NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 17 of 33 Revision STEAM GENERATOR TUDE LEAK 41AO-1ZZO8 04.01 Moderate to Large Leak Rate Calculation (cont) Appendix A Page 2 of 3 1.5 WIIEN 15 minutes lias elapsed, QJ11 VCT level can no longer be maintained above 15%, ;

THEN record final time and finalleak rate data in Tables 1 and 2, using the same instruments as before. ,

Table 1.-Elapsed Time Table 2.-Leak Rate Data .

PZR Level % VCT Level % Im E Instrument #

Initial Time Initial Value Final Time Final Value Elapsed Time A Value 1,6 Calculate the elapsed time in Table 1 and subtract the final values from the initial values in Table 2 to attain a A value. >

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i NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 18 of 33 .

Revision STEAM GENERATOR TUBE LEAK 41AO-1ZZO8 04.01 l

Appendix A Page 3 of 3 1

1 1.7 Perform the following calculations based on the elapsed time value from Table 1 i and the A values from Table 2, on the previous page.

APZR Level % x 6G.49 gall'7c A. = gpm l l Elapsed Time (min) (A) l 1

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AVCT Level % x 40.34 galNc gpm B. =

Elapsed Time (min) (B) j C.

AToy T x 117 gaW = Epm l Elapsed Time (min) (C)

D. Calculate the RCS Leak Rate as follows:

[(A) gpm + (B) gpm]-(C) gpm = KPm l

1.8 Place the MAKE-UP MODE SELECTOR, CHN-HS-210, in the AUTO position.

END OF APPENDIX i

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NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 19 of 33 i

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STEAM GENERATOR TUBE LEAK 41AO-1ZZ08 04.01 Appendix B Page1of1 l l

Appendix B - Condensate Isolation Checklist This appendix provides the direction for isolating the condensate system in the affected unit to prevent the contamination of the other units or the auxiliary boiler.

1.0 Condensate Isolation 1.1 Close the Auto Drawoff Manual Isolation Valve, CDN-V062, for CDN-LV-75.

CDN-V062 is located on the 110 ft level of the turbine building north corridor, west of the fire station.

1.2 Close the Auto Drawoff Bypass ManualIsolation Valve, CDN-V862, for CDN-LV-75.

1.3 Close the Unit Condensate Cross-tie Inlet Isolation Valve, CDN-V250. CDN-V250 is located at turbine b1dg.100 ft level northwest wall. ;

1.4 Close the Unit Condensate Cross-tie Inlet Bypass Isolation Valve, CDN-V252.

CDN-V252 is located at turbine bldg 100 ft level northwest wall.

1.5 Close the Unit Condensate Make-up Cross-tie Isolation Valve, ASN-V164.

ASN-V164 is located at turbine bldg 100 ft level northwest wall.

1.6 Ensure ASN-V088, Aux Steam Condensate 'Ib Main Condenser Isolation is open.

ASN-V088 is located at turbine bldg 130 ft level northeast of heater drain tank A.

1.7 Ensure that the Condensate Receiver Tank to Cross-tie Header Valve, ASN-V024, is closed. ASN-V024 is located at turbine bldg 130 ft level on the east end of heater drain tank A.

L8 E the auxiliary boiler is using this unit for makeup, TIIEN direct the boiler operator to align another source of makeup water to the auxiliary boiler.

END OF APPENDIX

u NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 20 of' 33 STEAM GENERATOR TUBE LEAK 41AO-1ZZO8 04.01 !

Appendix C Page 1 of 2 Appendix C - Steam Generator 1 Isolation Checklist This appendix provides the direction for isolating steam generator 1 to reduce the' amount of contanunation that is released, in the event that steam generator 1 has the tube leak. i l

1.0 Steam Generator 1 Isolation 'l 1.1 IE Essential Steam Driven Auxiliary Feedwater Pump, AFA-P01, is in service, :

THEN ensure that the steam supply is from steam generator 2. l

1. Open SG 2 STM SPLY TO PMP, SGA-HS-138A. :

2. Close SG 1 STM SPLY TO PMP, SGA-HS-134A. ?

1.2 Ensure that the ADVs for steam generator 1 are closed.

1. Ensure that hath of the ADVs an e closed: l SG 1 LINE 1 VALVE CONTROL, SGA-HIC-184A. .

SG 1 LINE 2 VALVE CONTROL, SGB-HIC-178A. i i

2. Ensure that all of the following ADV permissives are closed: l SG 1 LINE 1 ISOL VLV, SGA-HS-184A.

f SG 1 LINE 1 ISOL VIN, SGC-HS-184B.

SG 1 LINE 2 ISOL VLV, SGB-HS-178A. .

SG 1 LINE 2 ISOL VLV, SGD-HS-178B. l L3 Ensure that the MSIVs and the MSIV bypass are closed.

{

1. Press sne of the following: ]

LINE 1/2 MSIV FAST CLOSE, SGA-HS-251.

LINE 1/2 MSIV FAST CLOSE, SGB-HS-253. j

2. Ensure that the MSIV bypass valve is closed as indicated by the green light on ;

above MSIV BYPASS ISOL VLV. SGA-HS-169A. j 1.4 Ensure that the downcomer and auxiliary feedwater valves for steam generator 1 l are closed. Close all of the following valves: i AUX FW TO SG 1 DOWNSTREAM VLV, AFB-HS-34A. I DOWNCOMER ISOL VLV, SGA-HS-177 i DOWNCOMER ISOL VLV, SGB-HS-130.

1 AFW TO SG 1 DOWNSTREAM VLV, AFC-HS-36A. ,

I

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i NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL ' Page 21'~ of 33' l

Revision STEAM GENERATOR TUBE LEAIC 41AO-1ZZO8 04.01 -;

Steam Generator 11 solation Checklist (cont) Appendix C Page 2 of 2 i

1.5 Ensure that the economizer feedwat er isolation valves and chemicalinjection valve ~ ;

for steam generator 1 are closed. j

1. Fast close hath of the following valves: ;

ECONO FWIV FAST CLOSE, SGA-HS-1740. !

ECONO FWIV FAST CLOSE, SGB-HS-1320. !

2. Close SG 1 CHEMICAL INJ, SGB-HS-200. ;

1.6 Ensure that the upstream trap isolation valves for steam generator 1 are closed.'

Close hath of the following valves: :

STM TRAP SGN-M23 ISOL VLV, SGA-HS-1133.

B STM TRAP SGN-M01/M02 ISOL VINS, SGB-HS-1135. ;

1.7 Ensure that steam generator 1 blowdown is stopped. Ensure that SG 1 BLOWDOWN PATH SELECTOR VLVS, SCN-HS-1 is selected to OFF. j l

. . ... ..... .. ggg . . . ...... ........... ......

i Hot leg blowdown sample valves are left open for sampling.

{

1.8 Ensure that the sample valves for steam generator 1 are closed. Close all of the following valves:

SG 1 DOWNCOMER BLODN UPSTR VLV, SGA-HS-220.

SG 1 DOWNCOMER BLODN DNSTR VLV, SGB-HS-221. !

SG 1 COLD LEG BLODN UPSTR VLV, SGA-HS-21L '

SG 1 COLD LEG BLODN DNSTR VLV, SGB-HS-228. f 1.9 GO TO Step 3.8 in this procedure.

'l END OF APPENDIX 4 k

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NUCLEAR ADMINISTRATIVE'AND TECHNICAL MANUAL Page 22 of '33-

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STEAM GENERATOR TUBE LEAK 41AO-1ZZ08 04.01 ;

Appendix D Page 1 of 2 -

Appendix D - Steam Generator 2 Isolation Checklist !

This appendix provides the direction for isolating steam generator 2 to reduce the amount of .

contammation that is released, in the event that steam generator 2 has the tube leak. .

1.0 Steam Generator 2 Isolation 1.1 If Essential Steam Driven Auxiliary Feedwater Pump, AFA-P01, is in sen' ice, TIIEN ensure that the steam supply is from steam generator 1. l

1. Open SG 1 STM SPLY TO PMP, SGA-HS-134A.

2. Close SG 2 STM SPLY TO PMP, SGA-HS-138A.

J 1.2 Ensure thr.t the ADVs for steam generator 2 are closed. j L Ensure that b_qth of the ADVs are closed:

SG 2 LINE 1 VALVE CONTROL, SGB-HIC-185A. !

SG 2 LINE 2 VALVE CONTROL, SGA-HIC-179A. j i

2. Ensure that a}l of the following valve permissives are closed:

SG 2 LINE 1 ISOL VLV, SGB-HS-185A. i SG 2 LINE 1 ISOL VLV, SGD-HS-185B. .

SG 2 LINE 2 ISOL VLV, SGA-IIS-179A. i SG 2 LINE 2 ISOL VLV, SGC-HS-179B.

l 1.3 Ensure that the MSIVs and the MSIV bypass valve are closed.

1. Press one of the following: ,

LINE 1/2 MSIV FAST CLOSE. SGA-HS-250. ;

i LINE 1/2 MSIV FAST CLOSE. SGB-HS-252.

2. Ensure that the MSIV bypass valve is closed as indicated by the green light on above MSIV BYPASS ISOL VLV. SGB-HS-183B. .

1.4 Ensure that the downcomer and auxiliary feedwater valves for steam generator 2 !

are closed. Close all of the following valves:

AFW TO SG 2 DOWNSTREAM VLV, AFA-HS-37A.

DOWNCOMER ISOL VLV, SGA-HS-175. l i'

DOWNCOMER ISOL VLV, SGB-HS-135.

AUX FW TO SG 2 DOWNSTREAM VLV, AFB-HS-35A.

J

1 l NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 23 of 33 R W on .{

STEAM GENERATOR TUBE LEAK 41AO-1ZZO8 04.01 Steam Generator 2 Isolation Checklist (cont) Appendix D Page 2 of 2 1.5 Ensure that the economizer feedwater Isolation valves and chemicalinjection valve for steam generator 2 are closed.

1. Fast close hath of the following valves: !

ECONO FWIV FAST CLOSE, SGA HS-177C. :i ECONO FWIV FAST CLOSE, SGB-HS-1370.

2. Close SG 2 CHEMICAL INJ, SGB-HS-201.

1.6 Ensure that the upstream trap isolation valves for steam generator 2 are closed.

Close hath of the following valves:

STM TRAP SGN-M24 ISOL VLV, SGA-HS-1134.

STM TRAP SGN-M03/M04 ISOL V1NS, SGB-HS-1136.

t 1.7 Ensure that steam generator 2 blowdown is stopped. Ensure that SG 2 BLOWDOWN PATH SELECTOR VLVS, SCN-HS-2 is selected to OFF.

NOTE --- ----------------------------- :i Hot leg blowdown sample valves are left open for sampling. ;

1.8 Ensure that sample valves for steam generator 2 are closed. Close all of the '

following valves:

SG 2 DOWNCOMER BLODN UPSTR VLV, SGB HS-226. !

SG 2 DOWNCOMER BLODN DNSTR ISOL VLV, SGA-HS-227.

SG 2 COLD LEG BLODN UPSTR VLV, SGB-HS-222.

SG 2 COLD LEG BLODN DNSTR VLV, SGA-HS-223. )

1.9 GO TO Step 3.8 in this procedure. ~

END OF APPENDIX l

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 24 of 33 STEAM GENERATOR TUBE LEAK 41AO-1ZZO8 04.01 Appendix E Page1of3 Appendix E - Steam Generator 1 Level Reduction Checklist This appendix provides the direction for reducing the steam generator 1 level to prevent the over pressurization of the steam generator, causing further complications, and control the spread of contamination.

1.0 Steam Generator 1 Level Reduction CAUTION Draining the leaking steam generator to the condenser via the blowdown system will result in a direct transfer of RCS inventory to the hotwells. This will cause increased radiation levels in the vicinity of blowdown piping and the condenser hotwells.

1.1 Inform Radiation Protection that steam generator draining to the condenser will occur.

1.2 E the blowdown demineralizer is NOI available, QB high rate blowdown is required to maintain the steam generator level at less than 80'7c NR, THEN GO TO step 1.18 in this attaclunent.

1.3 E all of the following conditions exist:

Long path recirculation has been established.

. Adequate condensate flow to maintain temperature of blowdown out of the blowdown heat exchanger less than 133*F.

Blowdown demineralizer is available.

TIIEN continue in this procedure.

E HQT, THEN GO TC step 1.18 la this attachment.

1.4 Throttle SCN-VA59 and SCN-VA60, Bldwn IIX Cond Cig Wtr Flow Control Valves to ED Pump Discharge, to maintain Blowdown Demineralizer Inlet'Ibmperature, as read on SCN-TI-10, s 133*F, and ensure less than 600 gpm condensate flow on each of the following: ,

SCN-FI-006A, located at the 100 ft level of the turbine building, under heater drain tank A.

SCN-FI-006B, located at the 100 ft level of the turbine building, north of heater drain tank B.

1.5 Select OFF with the steam generator 1 Path Selector VALVES switch, SCN-HS-1.

l NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 25 of 33 l l

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STEAM GENERATOR TUBE LEAK 41AO-1ZZO8 04.01 Steam Generator 1 Level Reduction Checklist (cont) Appendix E Page 2 of 3 l 1.6 Select THRU DEMIN MODE LV-3B at DEMINERALIZER MODE SELECTOR VLVS, SCN-HS-3.

1.7 Direct an auxiliary operator to ensure that hath of the following valves are open, to send water to the blowdown flash tank:

SG 1 ABNORMAL BLOWDOWN TO FLASH TANK SCN-HV-1B OUTLET, SCN.

V054.

SG 1 ABNORMAL BLOWDOWN TO FLASH TANK SCN-HV-1B INLET, SCN-V003.

1.8 Select ABNORMAL on the SG 1 Rate Selector VALVES switch, SCN-HS-18.

1.9 Ensure that une of the following valves is open:

SG 1 COLD LEG ISOL VIN, SGN-HS-41.

SG 1 HOT LEG ISOL VLV, SGN-HS-43.

1.10 Open SG 1 COMMON UPSTR ISOL VLV, SGA-HS-500P.

1.11 Orn SG 1 COMMON DNSTR ISOL VLV, SGB-HS-500Q.

1.12 Inform personnel in the turbine building that blowdown flow will be initiated, and to stand clear of blowdown piping.

1.13 Select BLDWN TANK with the SG 1 PATH SELECTOR VALVES switch, SCN-HS-1, 1.14 WHEN the steam generator 1 level is at 50% NR, THEN select OFF with the SG 1 PATH SELECTOR VALVES switch, SCN-HS-1.

1.15 Inform the CRS that steam generator 1 has been drained to 50% NR.

1.16 PERFORM Steps 1.13 through 1.15 as necessary to maintain the steam generator level below 80% NR.

1.17 WHEN draining the steam generator is finished, THEN close in>.ih of the following volves:

SG 1 COMMON UPSTR ISOL VIX, SGA-HS-500P.

SG 1 COMMON DNSTR ISOL VLV. SGB-HS-500Q.

AND Exit this appendix.

1.18 IE the blowdown demineralizer is NQI available, OE high rate blowdown is required in maintain the steam generator level at less than 80% NR, THEN lower the steam generator level with steam generator blowdown to the condenser.

1.19 Select OFF with the SG 1 PATH SELECTOR VAINES switch, SCN-HS-1.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 26 of 33

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STEAM GENERATOR TUBE LEAK 41AO-1ZZ08 04.01 Steam Generator 1 Level Reduction Checklist (cont) Appendix d Page 3 of 3 L20 Direct an auxiliary o,>erator t, ensure that all of the following valves are open, to send water to the condenser:

SG 1 HIGH RATE BII)WDOWN TO CONDENSER SCN-HV-18C OUTLET, SCN- ,

V088.

SG 1 HIGH RATE BLOWDOWN TO CONDENSER SCN-HV-180 INLET, SCN-V099.

SG 1 ABNORMAL BLOWDOWN TO CONDENSER SCN-HV-18B OUTLET, SCN-V071.

SG 1 ABNORMAL BLOWDOWN TO CONDENSER SCN-HV-18B INLET, SCN.

V072.

1.21 Select the desired rate on the SG 1 Rate Selector VALVES switch, SCN-HS-18:

HIGH RATE.

ABNORMAL.

1.22 Ensure that nne of the following valves is open:

SG 1 COLD LEG ISOL VLV, SGN-HS-41.

SG 1 HOT LEG ISOL VLV, SGN-HS-43.

1.23 Open SG 1 COMMON UPSTR ISOL VLV, SGA-HS-500F, g 1.24 Open SG 1 COMMON DNSTR ISOL VLV, SGB-HS-500Q.

i 1.25 Inform personnel in the turbine building that blowdown flow will be initiated, and to stand clear of blowdown piping. ,

1.26 Select COND with the SG 1 PATH SELECTOR VALVES switch, SCN HS-1.

1.27 WHEN the steam generator 1 level is at 50% NR, THEN select OFF with the SG 1 PATH SELECTOR VALVES switch, SCN-HS-1.

1.28 Inform the LRS that steam generatur 1 has been drained to 50% NR.

1.29 PERFORM Steps 1.26 through 1.28 as necessary to maintain the steam generator level below 80% NR.

1.30 WHEN draining the steam generator is fmished, THEN close halb of the following valves:

SG 1 COMMON UPSTR ISOL VLV, SGA-HS-500P.

P SG 1 COMMON DNSTR ISOL VLV. SGB-HS-500Q.

END OF APPENDIX P

i l

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 27 of 33 l i

Rem. .n i STEAM GENERATOR TUBE LEAK 41AO-1ZZO8 04.01 l

Appendix F Page 1 of 3 l Appendix F - Steam Generator 2 Level Reduction Checklist This appendix prmides the direction for reducing the steam generator 2 level to prevent the over '

pressurization of the steam generator, causing further complications, and control the spread of contamination. l 1.0 Steam Generator 2 Level Reduction :

CAUTION

, Draining the leaking steam generator to the condenser via the blowdown system will result in a direct transfer of RCS inventory to the hotwells. This will cause increased radiaticu levels in the vicinity of blowdown piping and the condenser httwells.

1.1 Inform Radiation Protection that steam generator tiraining to 'he condenser will occur.

1.2 E the blowdown demineralizer is NDI available, QB high rate blowdown is required to maintain the steam generator level at less than 80'7e NR, THEN GO TO step 1.18 in this attaclunent. ,

l 1.3 IE all o.~the following conditions exist: -

Long pat': i ecirculation has been established.

Adeqt ata cW usate flow to maintain outlet temperature from the blowdown heat exchange . r- 133*E :

Blowdow-i %~ .. u 't is available.

TlIEN continue in this procedure. i IE NOT. THEN GO TO step 1.18 in this attachment.

1.4 Throttle SCN-VA59 and SCN VA60, Bldwn HX Cond Clg Wtr Flow Control Valves to ED Pump Discharge, to maintain Blowdown Demineralizer Inlet 'Ibmperature, -

as read on SCN-TI-10, _<; 133*F, and ensure less than 600 gpm condensate flow on each of the following:

SCN-FI-006A, located at the 100 ft level of the turbine building, under heater drain tank A.

SCN-F1-006B, located at the 100 ft level of the turbine building, north of heater drain tank B.

1.5 Select OFF with the SG 2 PATH SELECTOR VALVES switch, SCN-HS-2.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 28 of 33 Revision STEAM GENERATOR TUDE LEAK ,

41AO-1ZZO8 04.01 Steam Generator 2 Level Reduction Checklist (cont) Appendix F Page 2 of 3 1.6 Select THRU DEMIN MODE LV-3B at DEMINERALIZER MODE SELECTOR VLVS, SCN-HS-3.

1.7 Direct an auxiliary operator to ensure that hath of the following valves are open, to send water to the blowdown flash tanic SG 2 ABNORMAL BLOWDOWN TO FLASHTANK SCN-HV-2B OUTLET, SCN-V055.

SG 2 ABNORMAL BLOWDOWN TO FLASHTANK SCN-HV-2B INLET, SCN-V006. -

1.8 Select ABNORMAL on the SG 2 RATE SELECTOR VALVES switch, SCN-HS-19.

L9 Ensure that une of the following valves is open:

SG 2 HOT LEG ISOL VLV, SGN-HS-42.

SG 2 COLD LEG ISOL VLV, SGN-HS-44.

1.10 Open SG 2 COMMON UPSTR 1801, VLV, SGB-HS-500R.

1.11 Open SG 2 COMMON DNSTR ISOL VLV, SGA-HS-500S. ,

1.12 Inform personnel in the turbine building that blowdown flow will be initiated, and to stand clear of blowdown piping.

1.13 Select BLDWN TANK with the SG 2 PATH SELECTOR VALVES switch, SCN-HS-2.

1.14 WHEN the steam generator 2 level is at 50% NR, TIIEN select OFF with the SG 2 PATH SELECTOR VALVES switch, SCN-HS-2.

L15 Inform the CRS that steam generator 2 has been drained to 50% NR.

L16 PERFORM Steps L13 through L15 as necessary to maintain the steam generator level below 80% NR. ,

1.17 WHEN draining the steam generator is finished, THEN close hath of the following valves:

SG 2 COMMON UPSTR ISOL VLV, SGB-HS-500R.

SG 2 COMMON DNSTR ISOL VLV, SGA-US-500S.

AND Exit this appendix.

1.18 IE the blowdown demineralizer is NDI available, QB high rate blowdown is required to maintain the steam generator level at less than 80% NR, THEN lower the steam generator 2 level with steam generator blowdown to the condenser.

L19 Select OFF with the SG 2 PATH SELECTOR VALVES switch, SCN-HS-2.

i

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 29 of 33

- i" STEAM GENERATOR TUDE LEAK 41AO-1ZZ08 04.01 Steam Generator 2 Level Reduction Checidist (cont) Appendix F Page 3 of 3 1.20 Direct an auxiliary operator to ensure that all of the followhg valves are open, to send water to the condenser:

SG 2 HIGH RATE BLOWDOWN TO CONDENSER SCN-HV-19C OUTLET, SCN-V103.

SG 2 HIGH RATE BLOWDOWN TO CONDENSER SCN-HV-19C INLET, SCN-V104.

SG 2 ABNORMAL BLOWDOWN TO CONDENSER SCN-HV-19B OUTLET, SCN-V073.

SG 2 ABNORMAL BLOWDOWN TO CONDENSER SCN-HV-19B INLET, SCN-V074.

1.21 Select the desired rate on the SG 2 Rate Selector VALVES switch, SCN-HS-19:

HIGH RATE.

ABNORMAL.

1.22 Ensure that 9ng of the following valves is open:

SG 2 COLD LEG ISOL VLV, SGN-IIS-44.

SG 2 HOT LEG ISOL VLV, SGN-HS-42.

1.23 Open SG 2 COMMON DNSTR ISOL VLV, SGA-HS-500S.

1.24 Open SG 2 COMMON UPSTR ISOL VLV, SGB-HS-500R. i 1.25 Inform personnel in the turbine building that blowdown flow will be initiated, and to stand clear of blowdown piping.

1.26 Select COND with the SG 2 PATH SELECTOR VALVES switch, SCN-HS-2.

L27 WHEN the steam generator 2 level is at 50% NR, IIIEN select OFF with the SG 2 PATH SELECTOR VALVPS switch, SCN-HS-2. ,

1.28 Inform the CRS that steam generator 2 has been dre'.ned to 50% NR.

1.29 PERFORM Steps 1.26 through 1.28 as necessary to maintain the steam generator level below 80% NR.

1.30 WHEN draining the steam generator is finished, THEN close hath of the following valves:

SG 2 COM. MON UPSTR ISOL VLV, SGB-HS-500R.

SG 2 COMMON DNSTR ISOL VLV, SGA-IIS-500S.

END OF APPENDIX i

3 NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 30 ' of 33 !

STEAM GENERATOR TUBE LEAK **"

41AO-1ZZO8 04.01 !

Appendix G Page 1 of 2 :

i Appendix G - Draining the llotwell to the Low TDS Sump This appendix provides the direction for draining the contaminated water in the hotwell to the low f TDS sump to control the spread of the contamination. !

1.0 Draining the Hotwell to the Low TDS Sump !

l 1.1 Ensure that the LRS IIUTh have space to receive water. )

i 1.2 IE the LRS HUTS have space to receive water, i THEN drain the hotwell to the LRS IIUT in service. !

i

1. Ensure that the Low TDS Sump is aligned tarsceive water. !

.I

2. Close Low TDS to Circulating Water Valve, CMN-V076.

3. Open Low TDS to LRS Holdup Valve, CMN-V091. l i

4. Throttle open the following resin trap drain valve (s) for the mixed bed (s) in service. Do not exceed the capacity of the Low TDS sump pump. ;

Vessel A Resin Trap Drain Valve, SCN-V801.

Vessel B Resin 'IVap Drain Valve, SCN-V811. i Vessel C Resin Trap Drain Valve, SCN-V821. i Vessel D Resin Trap Drain Valve, SCN-V831. l Vessel E Resin 'IYap Drain Valve, SCN-V841. !

Vessel F Resin Trap Drain Valve, SCN-V851. .

1

5. WHEN hotwell level is less than 40 inches, !

THEN close Low TDS to LRS Holdup Valve, CMN-V091. j i

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NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 31 of 33 Revision STEAM GENERATOR TUBE LEAK 41AO-1ZZ08 04.01 Draining the Hotwell to the Low TDS Sump (cont) Appendix G Page 2 of 2 1.3 IE the LRS HUTS did NOT have space to receive water, THEN drain the hotwell to the neut ralizing tank.

1. Close Low TDS to Circulating Water Valve, CMN-V076.

2. Open Low TDS to Neutralizing Tank Valve, CMN-V077.

3. Ensure that Chemical Waste Outlet to Retention Basin Valve, CMN-V055, is closed.

4. Throttle open the following resin trap drain valve (s) for the mixed bed (s)in service. Do not exceed the capacity of the Low TDS sump pump.

Vessel A Resin Trap Drain Valve, SCN-V801.

Vessel B Resin Trap Drain Valve, SCN-V811. [

Vessel C Resin Trap Drain Valve, SCN-V821.

Vessel D Resin Trap Drain Valve, SCN-V831.

i Vessel E Resin Trap Drain Valve, SCN-V841. j Vessel F Resin Trap Drain Valve, SCN-V851. 1

5. WHEN hotwelllevel is less than 40 inches, I THEN close Low TDS to Neutralizing Tank Valve, CMN-V077.

END OF APPENDIX i

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 32 of 33 E"* "

STEAM GENERATOR TUBE LEAK 41AO-1ZZO8 04.01 Appendix H Page 1 of 2 Appendix H - References E 1.0 Implementing i

1.1 RCS and Pressurizer Heatup and Cooldown Rates,40ST-9RC01 1.2 Rapid Shutdown,41AO-1ZZ56 ,

1.3 Emergency Operations,41EP-1EOO1 1.4 Steam Generator Tube Rupture 41EP-1ROO3 1.5 Power Operations,410P-1ZZO5 ;

1.6 Plant Shutdown Mode 1 to Mode 2,410P-12Z07 1.7 Reactor Shutdown,410P-1ZZO8 I 1.8 Hot Standby to Cold Shutdown Mode 3 to Mode 5,410P-1ZZ10 1.9 Operating The Condensate Demineralizer System,410P-1SC03 1.10 RCS Water Inventory Halance,41ST-1RCO2 9

1.11 Determination of Primary to Secondary Leak Rate,74CH-9ZZ66 1.12 Secondary System Activity Surveillance 'Ibst,74ST-9SG01 1.13 Chemical Waste Neutralization Tank Surveillance '1bst,74ST-9ZZO2 1.14 Secondary System Waste Discharge,74ST-92Z07 1.15 Turbine Building Waste Discharge,74ST-9ZZO8 1.16 Radiological Surveys,75RP-9RP07 1.17 Emergency Classification, EPIP-02

.l 1.18 Abnormal Occurence Checidist, 74DP-9ZZO5 ;

9

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 33 of 33

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STEAM GENERATOR TUBE LEAK 04.01 41AO-1ZZ08 References (cont) Appendix H Page 2 of 2 2.0 Developmental 2.1 Technical Specifications 2.2 Steam Generator Tube Rupture. 41EP-1ROO3 2.3 C.E. Emergency Procedure Guidelines, Rev. 2.

2.4 P & ID's 01-M-SGP-001 01-M-SGP-002 01-M-AFP-001 2.5 RCTS #038218 2.6 EER 87-RC-254 2.7 EER 93-SF-003 P

2.8 EER 93-RC-018 2.9 Letter from Bill Barley to John Dennis,215-010640WHB/TSG ,

2.10 Letter from J. A. Scott and P. W. Hughes to John Dennis,214-00873-JAS END OF APPENDIX t

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