ML20138K323
| ML20138K323 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 01/31/1997 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML20138K159 | List:
|
| References | |
| RP-6A, NUDOCS 9702180159 | |
| Download: ML20138K323 (52) | |
Text
NUCLEARPOWER BUSINESS UNIT- RP 6A -
REFUELING PROCEDURES MAJOR IPTE STEAM GENERATOR CREVICE FLUSH Revision 9 (VACUUM MODE) Januarv 31.1997 WIT RECORD DATE FnocEcuxE vuurrED CURRENT AND C}ECKED FORRMPORARY C}MNGES IF FIELD DSS #*** "*"""'""" " # # ** ** ""
BY: DATE:
1.0 PURPOSE Removal of soluble materials from tubesheet crevice areas.
2.0 REFERENCES
IR 96-006, NRC Inspection Report; NRC Commitment for Operations procedures PMT/QC reviews.
3.0 PRECAUTIONS AND LIMITATIONji 3.1 RCS temperature MIJjiI be controlled s200 F when containment integrity is not established.
3.2 Maintain RCS temperature s195 F. Immediately secure RCPs and verify O CCW flow is cut into the RHR heat exchangers if RCS temperature exceeds 195'F.
3.3 Applicable to OP-4B, " Reactor Coolant Pump Operation" 34 Vacuum in steam generators and steam header should not exceed 19" Hg to prevent damage to the diaphragms on the sacrificial flanges and the non-returned valves.
3.5 Cycles 1 and 2 will be completed with the reactor coolant pumps running.
Subsequent cycles will require reactor coolant pumps to be stopped and staned.
3.6 To prevent drying of the tubesheet, it is imponant to establish steam generator water level as soon as the steam generator goes empty.
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97021eotS9 97021o Page1 of47 REFERENCE USE PDR ADOCK O 301 @g -
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NUCLEAR POWER BUSINESS UNIT RP 6A REFUELING PROCEDURES MAJOR IPTE STEAM GENERATOR CREVICE FLUSH Revision 9 (VACUUM MODE) January 31.1997 INITIALS 4.0 INITIAL CONDITIONS 4.1 Onerations 4.1.1 Training on this procedure for all Operations personnel has been completed.
Training 4.1.2 RCS filled and vented per OP-4A.
4.1.3 Both steam generators are drained.
4.1.4 Determine the voltage axis for Attachment A, Figures 3A-l&2 and 3B-1&2, while the steam generators are drained.
4.1.5 Add 12-18 inches of water and 1000 ml of catalyzed hydrazine to each steam generator. ,
l 4.1.6 Set up the PPCS/HDSR to trend the following. This will require the use of two PPCS cansoles.
Set span for T-630 from 185*-205'F with the baseline at 190 F.
- b. Loop A hot and cold leg temperature (T-450B and T-450C). Set span from 160 -200 F with the baseline at 190 F.
- c. Loop B hot and cold leg temperature (T-451B and T-451C). Set span from 160#- 200'F with the baseline at 190*F.
4.1.7 Set PPCS high alarm at 196'F and high-high alarm at 198*F for point T-630 RHR HX inlet temperature.
4.1.8 RHR system in operatinn.
4.1.9 Both RCPs running.
4.1.10 RCS temperature being maintained between 190 F and 195 F.
l Page 2 of 47 REEERENCE USE ,
NUCLEAR POWER BUSINESS UNIT RP 6A REFUELING PROCEDURES MAJOR IPTE STEAM GENERATOR CREVICE FLUSH Revision 9 (VACUUM MODE) January 31.1997 4.1.11 Steam generator atmospheric steam dumps operable.
4.1.12 Auxiliary feedwater system available to add water to steam generators and for chemical additions.
4.1.13 Valve lineup per Attachment B complete.
4 l.14 Facade sump lined up to WHUT 4.1.15 CSTs are split. For Unit I flush, the north CST shall be lined up to AFP. For Unit 2 flush, the south CST shall be lined up to AFPs.
4.1.16 South (north) CST filled to 17 feet (indicated on C-01).
4.1.17 Check shut: '
AF-13(14)- CST drain MS-119 - ST-2036 inlet MS-122 - ST-2093 inlet i
- CAUTIONa THE ENDS OF THE TYGON HOSES MUST BE RUN TO A ELEVATION OF ~15 FT. ABOVE EL. 44'.
l 4.1.18 MS-119 and MS-122 adapter with hoses installed per Attachment A, Figure 1. Adapter and hoses are stored above i the OPS shop. I 4.1.19 Hoses installed at blowdown tank per Attachment A, Figure 2.
Hoses and adapter stored in gang box near U2 blowdown tank.
4.1.20 Main steam line hangers blocked per Step 4.3.4.
4.1.21 Fill the main steam header by opening valves:
MS-Il9 ST-2036 inlet MS-120A ST-2036 header drain !
MS-122 ST-2093 inlet MS-123A l ST-2093 header drain AF-13(14) CST drain l Page 3 of 47 REFERENCE U; E
NUCLEAR POWER BUSINESS UNIT RP 6A REFUELING PROCEDURES MAJOR IPTE STEAM GENERATOR CREVICE FLUSH Revision 9 (VACUUM MODE) January 31,1997 g
INITIALS T l 4.1.22 Monitor water level in steam lines by tygon level. Final level should be 2 to 3 ft above El. 44'. Mark tygon with final level.
4.1.23 Vacuum pump water separator drain lines routed to facade sump via facade floor drain.
4.1.24 Communications established between Control Room and vacuum pump operator.
4.1.25 Operator available to monitor steam header pressure at the main steam non-retum valves.
4.1.26 Steam generator crevices flush data sheet, Form PBF-2026, available.
I 4.2 JAC 4.2.1 Wide range level channels LT-460A and LT-470A for steam 1 I
generators connected to a digital voltmeter in Control Room to provide level indication from the lower tap to about four feet above the tubesheet.
4.2.2 Compound pressure gauges, with drain valves, installed at following locations to monitor steam header vacuum.
"A" steam header sample line near the main steam non-retum valves.
"B" steam header sample line near the main steam non-return valves.
PT-484 Steam header press at El. 8' turbine hall 4.2.3 Instrument transmitters listed on Attachment C are equalized and isolated.
4.2.4 LT-460A and LT-470A, SG wide range level, filled and vented.
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NUCLEAR POWER BUSINESS UNIT RP 6A REFUELING PROCEDURES MAJOR IPTE STEAM GENERATOR CREVICE FLUSH Revision 9 (VACUUM MODE) January 31.1997
[ INITIALS 4.3 Maintenance
. 4.3.1 Steam generator secondary side intact. >
- a. Main steam safety valves or blanks installed. !
l
- b. Secondary handhole covers installed.
- c. Secondary manway covers installed.
. 4.3.2 MS-235 and MS-237 valve bonnets removed and flange adapter
, with hose connections installed. Flange adapters stored in the ,
j maintenance shop mezzanine, Cabinet D-3.
4 4.3.3 Vacuum hose run from MS-235 and MS-237 flange adapters to suppliers vacuum pump.
4.3.4 Steamline hangers blocked per Attachment D-1, Unit 1, or Attachment D-2, Unit 2.
O 4.3.5 The following steam traps are removed:
- d. ST-5900 Steam Dump Valve MS-2050
- f. ST-5904 Steam Dump MS-2054 4.3.6
' Set up crevice flush equipment at vacuum pump, including pre-separator and hoses. Vacuum hoses stored in the east Quonset hut; flanges, bolts and gaskets stored in the i
non-nuclear room.
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NUCLEAR POWER BUSINESS UNIT RP6A REFUELING PROCEDURES MAJOR IPTE STEAM GENERATOR CREVICE FLUSH Revision 9 (VACUUM MODE) _
January 31.1997 INITIALS 4.4 Chemistrv 4.4.1 Chemistry coverage arranged for gamma scan, tritium, and chemical analysis of draindown samples for release accountability, retention pond acceptability (Ref. RAM 4.2) and evaluation of crevice flush effectiveness.
4.4.2 Bottles of catalyzed hydrazine made up and placed in AFP room. Bottles shall be 1000 ml each.
4.4.3 Clean sample bottles for steam generator draindown samples provided at C-59.
4.4 4 Pump operator provided with portable radio.
4.5 IP_TE l
4.5.1 Senior line management briefing complete.
4.5.2 Third SRO assigned as test coordinator.
4.5.3 Second licensed operator assigned to assist the control operator.
5.0 PROCEDURE (RCPs Running) 5.1 Control room staffing is adequate to support performance of crevice flush procedure.
DSS DSS 5.2 Verify south (north) CST level approximately 17 ft.
5.3 Check shut steam generator atmospheric steam dumps.
5.4 Record main steam header pressure on data sheet.
Pressure gauge installed at PT-484.
O l Page 6 of 47 REFERENCE US2 ,
NUCLEAR POWER BUSINESS UNIT RP 6A REFUELING PROCEDURES MAJOR l IPTE i STEAM GENERATOR CREVICE FLUSH Revision 9 l (VACUUM MODE) January 31.1997 Cycle 1 Cycle 2 1
5.5 Using auxiliary feed pumps, fill both steam generators to
~24" above the tubesheet. Refer to Attachment A, Figures 3 A and 3B. During the fill add 1000 ml of l catalyzed hydrazine to each steam generator. N/A ;
5.6 Record SG fill stop times and levels on data sheet. N/A 5.7 Verify SG levels are ~24" above the tubesheet. Refer to ;
Attachment A, Figures 3A and 3B.
- CAUTIONa IMMEDIATELY SECURE RCPS AND VERIFY CCW FLOW CUT INTO THE RHR HEAT EXCHANGERS IF RCS TEMPERATURE EXCEEDS 195 F.
5.8 Maintain RCS temperature between 190 F and 195'F using RHR system.
O 5.9 Have the vacuum pump operator close vacuum breaker I l
and initiate flow. Record time on the data sheet. _
NOTE 1: Steam generator atmospheric steam dumps may be usedin an emergency toprevent the steam generator vacuumfrom exceeding 19" Hg.
NOTE 2: If the "A " and "B" steam generator vacuum readings are i
different, or Indicate no vacuum, vent the sensing lines to evacuate any water that may have collectedin them. ;
Sensing lines may need to be drained between each cycle.
5.10 When steam generator vacuum reaches the maximum attainable, but not to exceed 19" Hg, as indicated on --
gauges installed near the main steam non-retum valves, !
have the vacuum pump operator adjust his pump speed or vacuum breaker to maintain that pressure. I r
5.11 Record time and SG pressures on data sheet.
! Page 7 of 47 REFERENCE USE
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NUCLEAR POWER BUSINESS UNIT RP 6A REFUELING PROCEDURES MAJOR IPTE STEAM GENERATOR CREVICE FLUSH Revision 9 (VACUUM MODE) January 31.1997 INITIALS Cvele 1 Cycle 2 5.12 Verify the main steam non-return valves and sacrificial flanges MQI under vacuum. 1 5.12.1 Steam header pressure not less than 2 psig from reading recorded i- Step 5.4. Record pressure on data sheet.
5.12.2 Tygon level indication above the non-return J valves.
5.13 Boil steam generators for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> nr until steam generator levels reach 14" to 16" above the tubesheet.
DO NOT ADD WATER DURING THIS PERIOD.
5.14 Have vacuum pump operator secure the pump, or reduce pump speed to minimum.
5.15 Break vacuum in the steam generator by opening vacuum breaker valve at vacuum pump.
NOTE: Steam generator volume is ~36 gallons per inch.
5.16 Record time, levels, and volume on data sheet. !
l 5.17 Commence draining both steam generators to the facade i
sump. Draining takes approximately one hour.
5.18 Fifteen minutes after draindown begins, have operator obtain a one-liter sample from each steam generator.
Label as to date, time, cycle, unit, SG, and initials. Bottles to be provided by Chemistry and located at C-59. 1 1
5.19 Obtain a screen print of the last four hours for the HDSR i
l points selected to trend in Step 4.1.6. Note on the graphs which cycle they are for and attach them to the cresice flush data sheet.
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i NUCLEAR POWER BUSINESS UNTT RP 6A 1 REFUELING PROCEDURES MAJOR IPTE STEAM GENERATOR CREVICE FLUSH Revision 9 (VACUUM MODE) January 31.1997
'O v INITIALS Cycle 1 Cycle 2 l
5.20 As soon as the steam nenerators go emotv, commence i
refilling each steam generator to ~24" above the tubesheet. l Refer to Attachment A, Figures 3A and 3B. During the fill, add 1000 ml of catalyzed hydrazine to each steam generator. N/A 5.21 Record SG fill stop times and levels on data sheet. N/A i 5.22 As soon as the steam generators no emotv. commence
, refilling each steam generator to ~12" above the !
tubesheet. Refer to Attachment A, Figures 3A and 3B.
During the fill add 1000 ml of catalyzed hydrazine to each steam generator. N/A 5.23 Drain the "A" and "B" steam generator vacuum sensmg
< lines at gauges located near the main steam non-return valves.
5.24 Repeat Steps 5.1 through 5.23 for Cycle 2. N/A 5.25 Upon completion of Cycle 2, proceed to Section 6.0 (RCPs secured). N/A O
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NUCLEAR POWER BUSINESS UNIT RP 6A l REFUELING PROCEDURES MAJOR l IPTE !
STEAM GENERATOR CREVICE FLUSH Revision 9 (VACUUM MODH) January 31,1997 g
INITIALS T Cycle 3 4 5 6 6.0 PROCEDURE (Reactor Coolant Pumps Secured) j (Cycles 3 through 6)
)
6.1 !
Control room staffing is adequate to support '
performance of crevice flush procedure.
DSS DSS DSS DSS 6.2 Verify south (north) CST level approximately 17 fl.
6.3 Check shut steam generator atmospheric steam dumps.
6.4 Record main steam header pressure on data sheet.
Pressure gauge installed at PT-484.
- CAUTIONa RCS TEMPERATURE MUST BE CONTROLLED s200*F IF CONTAINMENTINTEGRITY IS NOT ESTABLISHED.
"CAUTIONa IF RCS TEMPERATURE EXCEEDS 195 F, THEN IMMEDIATELY VERIFY RCPS SECURED AND CCW FLOW CUT INTO THE RHR HEAT EXCHANGERS.
6.5 Verify RCS temperature between 190*F and 195 F. Adjust as necessary.
6.6 Have the vacuum pump operator close vacuum breaker and initiate flow. Record time on data sheet. Hold for 10 minutes.
6.7 Secure both reactor coolant pumps. Record times on data sheet.
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NUCLEARPOWER BUSINESS UNIT RP 6A REFUELING PROCEDURES MAJOR IPTE STEAM GENERATOR CREVICE FLUSH Revision 9 (VACUUM MODE) January 31.1997 INITIALS Cycle 3 4 5 6
- CAUTIONa RCS TEMPERATURE MUST BE CONTROLLED s200*F IF CONTAINMENT INTEGRITY IS NOT ESTABLISHED.
- CAUTION
- IF RCS TEMPERATURE EXCEEDS 195"F, THEN IMMEDIATELY VERIFY RCPS SECURED AND CCW FLOW CUT INTO THE RHR HEAT EXCHANGERS.
6.8 Adjust RHR cooling to try and maintain RHR outlet temperature. Between 185 and 190 F.
3 6.9 Continue filling each steam generator to ~24" above the tubesheet. Refer to Attachment A,
& Figures 3A and 3B.
! 6.10 Record steam generator fill stop times and levels on data sheet.
j aCAUTIONa RCS TEMPERATURE MUST BE CONTROLLED s200 F IF CONTAINMENT INTEGRITY IS NOT ESTABLISHED.
aCAUTION* IF RCS TEMPERATURE EXCEEDS 195*F, THEN IMMEDIATELY VERIFY RCPS SECURED AND CCW FLOW CUT INTO THE RHR HEAT EXCHANGERS.
6.11 Verify RHR outlet temperature between 180 F and 190*F. Attempt to maintain temperature between 185* and 190*F. .
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NUCLEAR POWER BUSINESS UNIT RP 6A REFUELING PROCEDURES MAJOR IPTE STEAM GENERATOR CREVICE FLUSH Revision 9 (VACUUM MODE) January 31.1997 INITIALS Cycle 3 4 5 6 NOTE 1: Steam generator atmospheric steam dumps may be usedin an emergency toprevent the steam generator vacuumfrom exceeding 19" Hg.
NOTE 2: If the "A " and "B" steam generator vacuum readings are dtfferent or indicate no vacuum, vent the sensing lines to evacuate any water that may have collectedin them. Sensing lines may need to be drained between each cycle.
6.12 When steam generator vacuum reaches the maximurn attainable, but not to exceed 19" Hg as indicated on gauges installed near the raain steam non-return valves, have the vacuum pump operator adjust his pump speed or vacuum breaker to maintain that pressure.
6.13 Record time and SG pressures on data sheet.
6.14 Verify the main steam non-return valves and sacrificial flanges NQT under vacuum.
6.14.1 Steam header pressure not less than 2 psig from reading recorded in Step 6.4. Record pressure on data sheet.
6.14.2 Tygon levelindication above the non-return valves.
6.15 Boil steam generators for one hour or until steam generator levels reach 14" to 16" ind;cated.
DO NOT ADD WATER DURING THIS PERIOD.
6.16 Notify the vacuum pump operator that vacuum may increase, then fill the steam generator to a level above the first support plate (~55"). Hold for 30 minutes.
l Page 12 of,47 REFERENCE USE
NUCLEAR POWER BUSINESS UNIT RP 6A REFUELING PROCEDURES MAJOR !
IPTE STEAM GENERATOR CREVICE FLUSH Revision 9 (VACUUM MODE) January 31.1997 ;
INITIALS Cycle 3 4 5 6 l 6.17 Have vacuum pump operator secure the pump, or ;
reduce pump speed to minimum.
6.18 Break vacuum in the steam generator by opening vacuum breaker valve at vacuum pump.
NOTE: Steam generator volume is ~36 gallonsper ;
inch.
6.19 Record time, levels, and volume on data sheet. !
6.19.1 Notify PAB operator that an initial draindown sample will be required after 5 minutes of draining. Sample is to be j delivered to Chem. for retention pond 1 acceptability. Start draining both S/Gs.
1 (7 6.19.2 After 5 minutes, secure draining both l
V S/Gs, notify PAB operator to take a '
facade sump sample.
6.19.3 Based on sample results of facade sump, align facade sump pumps to retention pond or WHUT.
i 6.20 Continue draining both steam generators to the facade sump. Draining takes approximately two i hours.
6.21 Fifteen minutes after draindown begins, have operator obtain a one-liter sample from each steam generator. Label as to date, time, cycle, unit, SG, -
l and initials. Bottles to be provided by Chemistry '
and located at C-59.
6.22 Obtain a screen print of the last four hours for the l HDSR points selected to trend in Step 4.1.6. Note on the graphs which cycle they are for and attach them to the crevice flush data sheet.
l Page 13 of 47 REFERENCE USE
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1
NUCLEAR POWER BUSINESS UNIT RP 6A REFUELING PROCEDURES MAJOR IPTE STEAM GENERATOR CREVICE FLUSH Revision 9 (VACUUM MODE) January 31.1997 INITIALS Cvele 3 4 5 6 NOTE: Ifadditional cycles are required, proceed with Step 6.23. If this is thefinal cycle, go to Step 7.27. Steps 6.23 through 7.26 become N/A.
6.23 As soon as the steam cenerators no emotv, commence refilling each steam generator to ~12" above the tubesheet. Refer to Attachment A, Figures 3 A and 3B. During the fill, add 1000 ml of catalyzed hydrazine to each steam generator.
6.24 Start both RCPs per OP-4B. Record stan times on data sheet.
aCAUTION" RCS TEMPERATURE MUST BE CONTROLLED s200 FIF CONTAINMENT INTEGRITY IS NOT ESTABLISHED.
- CAUTIONa IF RCS TEMPERATURE EXCEEDS 195 F TIIEN i IMMEDIATELY VERIFY RCPS i SECURED AND CCW FLOW CUT INTO TIIE RIIR IIEAT EXCIIANGERS. l 6.25 Adjust RHR cooling to maintain RCS temperature between 190*F and 195*F.
6.26 Retum to Step 6.1 for next cycle.
N/A 6.27 For additional cycles (7 through 10) to Section 7.0. N/A N/A N/A O'
l Page 14 of 47
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NUCLEAR POWER BUSINESS UNIT RP6A l REFUELING PROCEDURES MAJOR IPTE STEAM GENERATOR CREVICE FLUSH Revision 9 (VACUUM MODE) January 31.1997 l INITIALS Cycle 7 8 9 10 7.0 PROCEDURE (Reactor Coolant Pumps Secured)
(Cycle 7 through 10) i I
7.1 Control Room staffing is adequate to support the performance of crevice flush procedure. t
7.2 Verify south (north) CST level approximately l
, 17 fl.
- 7.3 Check shut steam generator atmospheric steam dumps. i 1
7.4 Record main steam header pressure on data sheet.
Pressure gauge installed at PT-484.
- CAUTIONa RCS TEMPERATURE MUST BE Q CONTROLLED s200*F IF Q CONTAINMENT INTEGRITY IS NOT ESTABLISHED.
4 aCAUTIONa IF RCS TEMPERATURE EXCEEDS 195 F, THEN IMMEDIATELY VERIFY RCPS
' SECURED AND CCW FLOW CUT INTO THE RHR HEAT EXCHANGERS.
7.5 Verify RCS temperature between 190*F and 195*F. Adjust as necessary.
7.6 Have the vacuum pump operator close vacuum breaker and initiate flow. Record time on data sheet. Hold for 10 minutes.
7.7 Secure both reactor coolant pumps. Record times on data sheet.
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NUCLEAR POWER BUSINESS UNIT RP 6A REFUELING PROCEDURES MAJOR IPTE STEAM GENERATOR CREVICE FLUSH Revision 9 (VACUUM MODE) January 31.1997 INITIALS Cycle 7 8 9 10 aCAUTIONa RCS TEMPERATURE MUST BE CONTROLLED s200 F IF CONTAINMENTINTEGRITY IS NOT ESTABLISHED.
- CAUTIONa IF RCS TEMPERATURE EXCEEDS 195'F, THEN IMMEDIATELY VERIFY RCPS SECURED AND CCW FLOW CUT INTO THE RHR HEAT EXCIIANGERS.
7.8 Adjust RHR cooling to try and maintain RHR outlet temperature. Between 185* and 190 F.
7.9 Continue filling each steam generator to ~24" above the tubesheet. Refer to Attachment A, Figures 3A and 3B.
l 7.10 Record steam generator fill stop times and levels on data sheet.
"CAUTIONa RCS TEMPERATURE MUST BE CONTROLLED s200 F IF CONTAINMENT INTEGRITY IS NOT ESTABLISHED. !
I
- CAUTION
- IF RCS TEMPERATURE I EXCEEDS 195'F, THEN I IMMEDIATELY VERIFY RCPS .
1 SECURED AND CCW FLOW CUT INTO THE RHR HEAT EXCHANGERS.
7.11 Verify RHR outlet temperature between 180 F and 190'F. Attempt to maintain temperature between 185* and 190 F.
O l Page 16 of 47 REFERENCE USE e .
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i NUCLEAR POWER BUSINESS UNIT RP 6A i REFUELING PROCEDURES MAJOR IPTE STEAM GENERATOR CREVICE FLUSH Revision 9 (VACUUM MODE) Januarv 31.1997 Cycle 7 8 9 10 i i
NOTE 1: Steam generator atmospheric steam dumps I may be usedin an emergency toprevent the ,
steam generator vacuumfrom exceeding 19" Hg.
NOTE 2: If the "A " and "B" steam generator vacuum readings are different or indicate no vacuum, vent the sensing lines to evacuate any water ,
that may have collectedin them. Sensing lines may need to be drained between each cycle 7 12 When steam generator vacuum reaches the maximum attainable, but not to exceed 19" Hg as indicated on gauges installed near the main steam non-return valves, have the vacuum pump operator adjust his pump speed or vacuum breaker to maintain that pressure.
7.13 Record time and SG pressures on data sheet.
7.14 Verify the main steam non-retum valves and sacrificial flanges N_QI under vacuum.
7.14.1 Steam header pressure not less than 2 psig from reading recorded in Step 7.4. Record pressure on data sheet.
7.14.2 Tygon levelindication above the non-return valves.
, 7.15 Boil steam generators for one hour pr until steam
~
generator levels reach 14" to 16" as indicated. -
DO NOT ADD WATER DURING THIS PERIOD.
7.16 Notify the vacuum pump operator that vacuum may increase, then fill the steam generator to a level above the first support plate (~55"). Hold for 30 minutes.
O .
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' REFERENCE USE g .,,
NUCLEAR POWER BUSXNESS UNIT RP 6A REFUELING PROCEDURES MAJOR IPTE STEAM GENERATOR CREVICE FLUSH Revision 9 (VACUUM MODE) January 31.1997 INITIALS Cycle 7 8 9 10 7.17 Have vacuum pump cperator secure the pump, or reduce pump speed to minimum.
7.18 Break vacuum in the steam generator by opening vacuum breaker valve at vacuum pump.
NOTE: Steam generator volume is ~36 gallons per inch.
7.19 Record time, levels, and volume on data sheet.
7.19.1 Notify PAB operator that an initial draindown sample will be required after 5 minutes of draining. Sample is to be delivered to Chem. for retention pond acceptability. Start draining both S/Gs.
7.19.2 After 5 minutes, secure draining both S/Gs, notify PAB operator to take a facade sump sample.
7.19.3 Based on sample results offacade sump, align facade sump pumps to retention pond or WHUT.
7.20 Continue draining both steam generators to the facade sump. Draining takes approximately two hours.
7.21 Fifteen minutes after draindown begins, have operator obtain a one-liter sample from each steam generator. Label as to date, time, cycle, unit, SG and initials. Bottles to be provided by Chemistry and located at C-59.
7.22 Obtain a screen print of the last four hours for the l HDSR points selected to trend in Step 4.1.6. Note on the graphs which cycle they are for and attach them to the crevice flush data sheet.
l Page 18 of 47 REFERENCE USE O
NUCLEAR POWER BUSINESS UNIT RP 6A REFUELING PROCEDURES MAJOR IPTE STEAM GENERATOR CREVICE FLUSH Revision 9 (VACUUM MODE) January 31.1997 Cycle 7 8 9 10 NOTE: If additional cycles are required, proceed with Step 7.23. Ifthis is thepnal cycle, go to Step 7.27. Steps 7.23 through 7.26 become N/A.
7.23 As soon as the steam nenerators no emnty, commence refilling each steam generator to ~12" above the tubesheet. Refer to Attachment A, Figures 3A and 3B. During the fill, add 1000 ml of catalyzed hydrazine to each steam generator. N/A 7.24 Start both RCPs per OP-4B. Record start times on data sheet. N/A
- CAUTIONa RCS TEMPERATURE MUST BE CONTROLLED s200 FIF CONTAINMENT INTEGRITY IS NOT ESTABLISHED.
aCAUTION* IF RCS TEMPERATURE EXCEEDS 195 F, THEN IMMEDIATELY VERIFY RCPS SECURED AND CCW FLOW CUT INTO THE RHR HEAT EXCHANGERS.
7.25 Adjust RHR cooling to maintain RCS temperature between 190 F and 195'F. N/A 7.26 Return to Step 7.1 for next cycle. N/A 7.27 Using the AFPs, fill each steam generator to a level -
between 100 and 120 inches. Chemical addition not required.
7.28 Notify Chemistry to:
7.28.1 Sample both steam generators for discharge.
7.28.2 Provide chemicals for both steam generators refill to 510" l Page 19 of 47 REFERENCE USE
1 NUCLEAR POWER BUSINESS UNIT RP 6A REFUELING PROCEDURES MAJOR l IPTE l STEAM GENERATOR CREVICE FLUSH Revision 9 !
(VACUUM MODE) January 31.1997 INITIALS 7.29 Start one or both RCPs as directed by the DSS.
7.30 Adjust RHR cooling to maintain RCS temperature s195'F.
NOTE: Section 8.0 (Recovery) may be workedin conjunction with the remaining steps ofSection 7.0.
7.31 Completely orain both steam generators.
7.32 Refill both steam generators to 510" and add chemicals as requested by Chemistry.
8.0 RECOVERY 8.1 Operations 8.1.1 Shut Valves MS-119 ST-2036 inlet isolation MS-122 ST-2093 inlet isolation MS-120A ST-2036 header drain MS-123A ST-2093 header drain MS-177 Z-54, air eject. moisture sep. outlet AF-13(14) South (north) CST drain 8.1.2 Disconnect hose at AF-13(14) and route to turbine building sump.
8.1.3 Drain steam header, open valves:
MS-119 ST-2036 inlet isolation MS-122 ST-2093 inlet isolation MS-137 ST-2048 inlet isolation MS-204 ST-2049 inlet isolation MS-210 Z-54 air ejector moisture sep. inlet MS-2016 "A" atmospheric steam dump MS-2015 "B" atmospheric steam dump Disconnect lower sensing line on LC-2031 to drain steamline to air ejector moisture separator and gland steam.
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REFERENCE USE
NUCLEAR POWER BUSINESS UNIT RP 6A REFUELING PROCEDURES MAJOR IPTE STEAM GENERATOR CREVICE FLUSH Revision 9 (VACUUM MODE) January 31.1997 8.1.4 Disconnect tygon hose at MS-120A and MS-123A. Store tygon hose above the OPS shop.
8.1.5 Open steam line elbow vents:
MS-10A/10B MS-15A/15B 8.1.6 Check shut MS-269 and MS-270 at blowdown tank.
Disconnect and store hoses and adapters in gang box at U2 blowdown tank area.
{
8.1.7 Notify Chemistry to sample the south (north) CST to determine '
if the water can be saved or if the CST must be dumped.
8.1.8 When steam lines have drained:
l
,q a. Shut valves MS-Il9 and MS-122. '
'V
- b. Open valves MS-120A and MS-123A.
- c. Disconnect hose and adapter. Store above the OPS shop.
d Connect lower sensing line to LC-2031.
l
- c. Notify Maintenance that steamline hanger blocks may be removed.
8.1.9 Perform valve lineup per Attachment E, which aligns valves per CL-13A.
8.1.10 Realign CSTs per DSS, based on sample results.
8.2 1&C 8.2.1 Remove SG level instrumentation installed on LT-460A and LT-470A.
V l Page 2,1 of 47
. REFERENCE USE -
NUCLEAR POWER BUSINESS UNIT RP6A l REFUELING PROCEDURES MAJOR '
IPTE STEAM GENERATOR CREVICE FLUSH Revision 9 (VACUUM MODE) January 31e 1997 INITIALS 8.2.2 Remove pressure gauges and reconnect tubing at:
"A" steam header sample line near the main steam non-return valves.
"B" steam header sample line near the main steam non-return valves.
Steam header pressure, PT-484, El. 8' turbine hall.
8.2.3 Return instruments listed in Attachment C to service. ._
8.3 Maintenance 8.3.1 After steam lines have drained, reference Step 8.1.8, remove hanger blocks per Attachment D-1, Unit 1, or Attachment D-2, Unit 2. _
8.3.2 Inspect main steam line hangers and snubbers for damage.
8.3.3 Remove hoses and flange adapters from MS-235 and MS-237, then install valve bonnets. Store flange adapters in the maintenance shop mezzanine Cabinet D3. Install caps on vacuum line and tape bags over ends of vacuum hose.
8.3.4 Remeve flanges and hoses from the vacuum pump and pre-separator. Install cap on vacuum line and tape bags on ends of the vacuum hose.
8.3.5 Store hoses in the east Quonset hut and spare flanges, gaskets and bolts in U2 non-nuclear room.
O' l Page 22 of 47 REFERENCE USE t s e
NUCLEAR POWER BUSINESS UNIT RP 6A REFUELING PROCEDURES MAJOR IPTE STEAM GENERATOR CREVICE FLUSH Revision 9 (VACUUM MODE) January 31.1997 '
INITIALS
- 8.3.6 Install steam traps
- d. ST-5900 Steam dump valve MS-2050
- f. ST-5904 Steam dump MS-2054 PMT l 8.3.7 Check components listed in Steps 8.2.2, 8.3.3, and 8.3.6 for i
leakage when system is at normal operating pressure.
O a
l
. \
l i i
i O
Page 23 of 47 REFERENCE USE
1 NUCLEAR POWER BUSINESS UNIT RP 6A REFUELING PROCEDURES MAJOR !
IPTE ,
STEAM GENERATOR CREVICE FLUSH Revision 9 l (VACUUM MODE) January 31.1997 l
ATTACHMENT A l
FIGURE 1 l
8 fA Q
v l >
CST Hort: 17 TT or !
t I E . LIVIL WILL !
EQUAL A 6 FT WATER SEAL ON IEE NON.RZn!RN '
VALVES.
1
{
33 t 35 34 i 36 I
I TTCON IREL IND. RUN TO un aan Itzv. u. rT.
e J
{
I q 1**.
I "'
=
h,I 'I A O C L k 75eA l h
[3" TIE &$P00LFIECE l ,
I U2 2 ~ x0SE
- > = ;i -
f ;; :
\
123A V
^ 123 \
-s frIAM TRAPS 37-2036 & 2093 s .J xanorm.
O l , Page 24 of 47
, . REFERENCE USE
_ = .- -
NUCLEAR POWER BUSINESS UNIT RP6A REFUELING PROCEDURES MAJOR IPTE STEAM GENERATOR CREVICE FLUSH Revision 9 (VACUUM MODE) January 31,1997 O ATTACHMENT A FIGURE 2 i
4 TACADE I' ColCAINGJfr
, us-tat a
w" ' ns-2045 9 MS 5959 A
i l 8
- iI ;0 X X M s/c as ara Ms-266' Ms-220 W
TDe0AARY F m270 MS-268 v d,'
Mosts t :- (U2 o nY ,
f N
' SAMPLES I'
fj-k ,
ns-2042 ,
ns-5958 i
- _b f 4 >C W 5/C i m.ni Ms.26f, MS-218 MS-267 7( (U2DNLY{T 1
i ll MS.278 TACADE 4
sme 4
i I Page 25 of 47 REFERENCE USE-9
NUCLEAR POWER BUSINESS UNIT RP6A REFUELING PROCEDURES MAJOR IPTE STEAM GENERATOR CREVICE FLUSH Revision 9 i
(VACUUM MODE) Januarv 31.1997 ATTACHMENT A FIGURE 3A.1 "A" STEAM GENERATOR c c -.
, ( , >
= -~
g
_ _ _ _ _ _ _ _ _ _ _ _ _l i o .-
p-s - _.
=
_ _ _ _ _ - - - = = _ __ __ - -_ _ _ -_y ,- -
= ._ ._
= - _ -- _
A _ .- _
-y d
_ _ _ = - _ _ _ _ _ - -
=
y_ - _ -. - -
/
= _ _ _ _ - -. _ -
._ _ _ = = -- -- - _ -- = -
.- L -. - - _ _ _-.
7 N y
/ .__ _
O O '
/ ,,,
T L ,
/
7 E ~ -
/ ~
1 -
/
_ - -. .--- /
- =
y .- _ .--- - -
_. - .-- j -. --- - .- _ __
.. ._ - --- - - 4 - -
1/
_= .-.-
y _ _- _
/ - -.- - _ _. _
-.A .
= -- -- - _ _
i, _/ ._
T / - _ - - _ _ -. _ .- _,
y -. -
a _ _
4 I i -
\
11 IJ 11 11 31 t
7 .2 INCHES ABOVE 7HE TUBESHEET NOTE 1:
The " volts" axis ofthisfigure must be determined when the steam generator is drained Record the drained down voltage reading on the bottom line of the voltage axis. Fillin the remainder of the voltage axis, based on each minor division being equivalent to 0.01 volts.
l Page 26 of 47 REFERENCE USE .
l NUCLEAR POWER BUSINESS UNIT RP6A l REFUELING PROCEDURES MAJOR IPTE STEAM GENERATOR CREVICE FLUSH Revision 9 (VACUUM MODE) January 31.1997 ATTACHMENT A FIGURE 3 A-2 "A" STEAM GENERATOR i r l
l =i- l l
-p y
_r
_ _.._ ._. _. . . .-._. -.._ .- - - .- __. _ -.I '
o ._le
_- = - . _ - - - _ . - .
, 7-s
_y -
-4
- = _ -- = - - ---- .- -. _. - - - - --
.- - _. =
=
_y f . -
-J - ._ - -- -. .. _
Z -. - - -. _ _-.
7 7_
v
.- - - - - - - - - p _
O o - / -
T L ,
E T -
/ -
S 2
r - --
1
_ J
/
y -. _. --
- ' _- .- - = = _. m
\
. 4. --
W \
=
/ =
/ _
= - _ _. _
o 1.
.,4 1
/
T
, y. - .-. -. . . ..
2 ...-
4 -
w .$ 4e, r ?, .h ;2 :
INCHES ABOVE THE TUBESHEET NOTE 1: The " volts" axis of thisfigure must be determined when the steam generator is drained.
Record the drained down voltage reading on the bottom line of the voltage asis. Fillin the remainder ofthe voltage axis, based on each minor division being equivalent to 0.01 wits.
1 I
i Page 27 of 47
. ', REFERENCE USE
- , e
. - _ . - . .-- . - . _ . . - . . -- - - - . - - - - . - - . - - - . - - .- ~ - - - - --
NUCLEAR POWER BUSINESS UNIT RP 6A 4
REFUELING PROCEDURES MAJOR -
- STEAM GENERATOR CREVICE FLUSH Revision 9 :
4 (VACUUM MODE) January 31,1997 ATTACHMENT A O
l FIGURE 3B-1 l "B" STEAM GENERATOR !
! l I l l v i i l
! O I L I fi l s __
- / {
- j. / l j f i 1 /
. / .
l /
i N V /
(
i O /
- T t f r'
j E s t
! 1 /
' /
e j d
! /
, f l "
- /
0
! L !
! 7 m /
i I /
j /' l .
l II b 12 11 3t L7 qi i
) INCHESABOVE THE TUBESHEET NOTE 1:
- The " volts" axis of thisfigure must be determined when the steam generator is drained Record the drained down voltage reading on the bottom line ofthe voltage axis. Fillin the i
remainder of the voltage axis, based on each minor division being equivalent to 0.01 volts.
fl Page 28 of 47 REFERENCE USE
NUCLEAR POWER BUSINESS UNIT RP 6A ;
REFUELING PROCEDURES - MAJOR l IPTE l STEAM GENERATOR CREVICE FLUSH Revision 9 (VACUUM MODE) January 31.1997 lO ATTACHAENT A l FIGURE 3B-2 i "B" STEAM GENERATOR l
- I '! l l
lIfIiiii:
, I I 1 i ,
I II I ii i i i .
o ,
IIIIiiili 1
} l 1 I i l l l Yi '
l ; l I!
I I'It i .
l l If I i i i
,V, t i ! I i s [ l j ,
/ - I l / 1 l
- N v / -
O o
L j --
l i T T /.
- E s f '
' / r r '
l s -
/
/ ,
I j / I
! [ / -
i r /
1 / l
/, I l
} 3e 41 NB 51 SS G3 f T-INCHESABOVE THE TUBESHEET l l
l
- NOTE 1
- The " wits" axis of thisfigure must be determined when the steam generator is drained Record the drained down witage reading on the bottom line of the voltage axis. Fillin the (
j remainder of the witage axis, based on each minor division being equivalent to 0.01 wits. '
1 Page 29 of 47 REFERENCE USE
NUCLEAR POWER BUSINESS UNIT RP 6A REFUELING PROCEDURES MAJOR IPTE STEAM GENERATOR CREVICE FLUSH Revision 9 (VACUUM MODE) January 31.1997 I
UNIT ATTACHMENTB
_YALVE IJNEUP BEFORE CREVICE FLUSH !
Control Room Descrintion Position Initials MS-2026 LH turbine stop valve S MS-2032 No. 3 governor valve S MS-2033 No. I governor valve S MS-2027 RH turbine stop valve S MS-2034 No. 4 governor valve S MS-2035 No. 2 governor valve S MS-2018 "A" main steam stop S MS-2017 "B" main steam stop S MS-2016 "A" atmospheric steam dump O i MS-2015 "B" atmospheric steam dump O MS-5958 "A" SG blowdown isolation O MS-5959 "B" SG blowdown isolation O MS-2042 "A" SG blowdown isolation S t MS-2045 "B" SG blowdown isolation S AF-4001 P-29 discharge to "A" SG S AF 4000 P-29 discharge to "B" SG I S
MS-2083 "A" SG sample isolation S
MS-2084 "B" SG sample isolation S
AF-4023 P-38A discharge to l A SG (U1 flush only) S AF-4021 P-38B discharge to IB SG (Ul flush only)
S AF-4022 P-38A discharge to 2A SG (U2 flush only) S AF-4020 P-38B discharge to 2A SG (U? ."ush only) S Turbine Drain valves MS-2701-2706 O
l O
l Page 30 of 47 REFERENCE USE -
e
NUCLEAR POWER BUSINESS UNIT RP 6A REFUELING PROCEDURES MAJOR IPTE STEAM GENERATOR CREVICE FLUSH Revision 9 (VACUUM MODE) January 31.1997 i b)
%. Attachment B Containmean Descriotion Position Initials MS-213 * "A" steam generator vent IVTC S MS-214' "B" steam generator vent IVTC S
~
MS-215 "B" steam generator tubesheet drain O MS-216 "B" steam generator sample isolation O '
MS-217 "B" steam generator sample penetration test connection S MS-217A "B" steam generator blowdown line drain S MS-217B "B" steam generator blowdown line drain (U2 only) S MS 217C "B" steam generator blowdown line vent (U2 only) S MS-218 "B" steam generator blowdown isolation O Remarks:
4
'MS-213 and 214 for Unit I are located in the facade El. 85' '
I N
i MS-5958 "B" steam generator blowdown isolation Air On 2 MS-219 "A" steam generator sample penetration test connection S MS-219A "A" steam generator blowdown line drain S MS-219B "A" steam generator blowdown line drain (U2 only) S MS-219C "A" steam generator blowdown line vent (U2 only) S i MS-220 "A" steam generator blowdown isolation O MS-5959 "A" steam generator blowdown isolation Air On MS-221 "A" steam generator tubesheet drain O MS-222 "A" steam generator sample isolation O MS-211 "A" steam generator vent (see note below) LO MS-212 "B" steam generator vent (see note below) LO NOTE: Valves MS-211 & 212 are on top ofsteam generator and will be left in the locked open position with redlock and chain. Visual verificationfrom (remote area) to check rising stem on valve andredlock in place is sufficient to satisfy thisposition check.
C
, Page ,31 of 47
. REFERENCE USE 9
NUCLEAR POWER BUSINESS UNIT RP 6A REFUELING PROCEDURES MAJOR IPTE STEAM GENERATOR CREVICE FLUSH Revision 9 (VACUUM MODE) January 31,1997 Attachment B l
Facade. EL. Sj' Description Position Initials l
MS-223 "A" SG vent S i
MS-2016 "A" SG atmospheric steam dump Air On MS-227 l MS-2016 inlet O MS-228 "A" header drain and trap isolation O MS-229 "A" header drain to blowdown tank S MS-231 ST-2029 inlet S l MS-232 ST-2029 bypass S MS-233 ST-2029 outlet O MS 2018 "A" main steam stop Air Off MS-234 MS-2018 bypass O MS-2017 "B" main steam stop Air Off MS-236 MS-2017 bypass O l MS-238 "B" header drain and trap isolation O MS-239 "B" header drain to blowdown tank S MS-241 ST-2028 inlet S MS-242 ST-2028 bypass S g MS-243 MS-7.015 ST-2028 outlet O W "B" SG atmospheric steam dump Air On MS-244 MS-2015 inlet O MS-248 "B" SG vent S Remarks O
l Page 32 of47 REFERENCE USE 9
NUCLEAR POWER BUSINESS UNIT RP 6A l REFUELING PROCEDURES MAJOR l IPTE l STEAM GENERATOR CREVICE FLUSH Revision 9 (VACUUM MODE) Januarv 31.1997 r'N Q Attachment B ;
Facade. EL. 85' Descriotion Position Initials l
MS-249 "A" main steam line sample isolation (El. 66') O !
MS-249A "A" main steam line sample isolation (El. 66') O MS-250 "B" main steam line sample isolation (El. 66') O MS-250A "B" main steam line sample isolation (El. 66') O PAB. El 44' & 39' H
MS-251 Radwaste steam supply angle stop check "A" steam header S MS-251 A P-29 governor sensing line isolation S I MS-252 Radwaste steam supply angle stop check "B" steam header S MS-252A P-29 governor sensing line isolation S MS-2019 P-29 steam supply LH MS-2020 P-29 steam supply LH Blowdown System - Facade. El 39'. 26' & 6' !
l
/
MS-267 "A" steam generator blowdown line drain (U2 only) S {
MS-265 "A" steam generator blowdown isolation O MS-266 "B" steam generator blowdown isolation l O ;
MS-268 "B" steam generator blowdown line drain (U2 only) S l MS 2042 "A" steam generator blowdown Air On MS-2045 "B" steam generator blowdown Air On ;
MS-269 "A" steam generator blowdown line drain S MS-270 "B" steam generator blowdown line drain S l MS-271 "A" steam generator blowdown to T26 S MS-272 "B" steam generator blowdown to T26 !
S ;
MS-278 "A" steam generator blowdown to HX-18A S j MS-282 "B" steam generator blowdown to HX-18B S l l
Remarks:
c Nf ,
I i
l h Page 33 of47 !
REFERENCE USE .
g 9
t NUCLEAR POWER BUSINESS UNIT RP 6A REFUELING PROCEDURES MAJOR IPTE STEAM GENERATOR CREVICE FLUSH Revision 9 (VACUUM MODE) Januarv 31.1997 Attachment B Turbine Buildine. El 46' Position Initials l
MS-2A Vacuum breaker O MS-3 MS-2746 inlet S sis-4 MS-2746 bypass S u' 5 Cylinder heating strainer blowdown S se-7 ST-2739 (cylinder heating) inlet S MS-8 ST-2739 bypass S MS-10 MS-2027 (RH turbine stop) bypass S MS-10A PX-2025 - first offisolation S MS-10B PX-2025 - second offisolation S MS-2751 MS-2027 (RH turbine stop) bypass Air Off MS 14 PT-2716 (governor valve inlet pressure) isolation S MS-15 MS 2026 (LH turbine stop) bypass S MS-ISA PX-2024 - first offisolation S MS-15B PX-2024 - second offisolation S MS-2750 MS-2026 (LH turbine stop) bypass Air Off MS 17 MS-2745 inlet S MS-18 MS-2745 bypass S MS-20 Cylinder heating stramer blowdown S MS-21 ST-2740 (cylinder heating) inlet S MS-22 ST-2740 bypass S
MS-2088 "A" MSR steam supply Air Od MS 25 MS-2088 inlet isolation S MS-25A MS-2088 leakoff to condenser O MS-26 "A" MSR purge isolation O
MS-26A "A" MSR purge valve S
MS-2087 "B" MSR steam supply MS 27 Air Off MS-2087 inlet isolation S MS-27A MS-2087 leakoff to condenser MS-28 O
"B" MSR purgeisolation MS-28A O
"B" MSR purge valve S
MS-2086 "C" MSR steam supply MS-31 Air Off MS-2086 inlet isolation S
MS-31 A MS-2086 leakoff to condenser MS-30 O
"D" MSR purge isolation MS-30A O
"D" MSR purge valve S
O l Page 34 of 47
, REFERENCE USE
NUCLEAR POWER BUSINESS UNIT RP 6A REFUELING PROCEDURES MAJOR
! IPTE STEAM GENERATOR CREVICE FLUSH Revision 9 (VACUUM MODE) January 31,1997 Turbine Buildine. El 46' Position Initials MS-2085 "D" MSR steam supply Air Off MS-29 MS-2085 inlet isolation S MS 29A MS-2085 leakoff to condenser O MS-32 "C" MSR purge isolation O ~
MS-32A "C" MSR purge valve S ;
Remarks:
I l
lf3
! V 1
l l
l l Page 35 of 47 REFERENCE USE O e
NUCLEAR POWER BUSINESS UNIT RP 6A REFUELING PROCEDURES MAJOR IPTE STEAM GENERATOR CREVICE FLUSH Revision 9 (VACUUM MODE) January 31.1997 Attachment B Turbine Buildine. El 26' Position Initials MS-33 ST-2093 ("A" header) isolation O MS-34 ST-2093 ("A" header) isolation O MS-35 ST-2036 ("B" header) isolation O MS-36 ST-2036 ("B" header) isolation O MS-39 ST-2009 inlet S MS40 ST-2009 bypass S MS-44 ST-2014 inlet S MS-45 ST-2014 bypass S MS-47 ST-2389 (SA feedwater heater extraction) inlet S MS-48 ST-2389 bypass S MS-50 ST-2390 (SB feedwater heater extraction) inlet S MS-51 ST-2390 bypass S MS-53 ST-2351 (SA feedwater heater extraction) inlet S MS-54 ST-2351 bypass S MS-56 ST-2349 (SB feedwater heater extraction) inlet S MS-57 ST-2349 bypass S MS-59 ST-2381 (extraction to building heating) inlet S MS-60 ST-2381 bypass S MS-62 ST-2392 (4A feedwater heater extraction) inlet S MS-63 ST-2392 bypass S MS-65 ST-2391 (4B feedwater heater extraction) inlet S MS-66 ST-2391 bypass S MS-83 ST-2753 inlet S MS-84 ST-2753 bypass S
MS-86 Header drain at ST-2753 S MS-89 MS-2710 inlet S MS-91 MS-2710 bypass S
CS-143 CS-481 outlet isolation S CS-145 CS-476 outlet isolation S CS-146 CS-145 bypass S
CS-151 CS-466 outlet isolation S CS-152 CS-151 bypass S
CS-154 CS-480 outlet isolation S Remarks:
s O
! ,, , Page 36 of 47 REFERENCE USE
NUCLEAR POWER BUSINESS UNIT RP 6A REFUELING PROCEDURES MAJOR IPTE STEAM GENERATOR CREVICE FI,USH Revision 9
_( VACUUM MODE) January 31.1997 Attachment B Turbine Buildina. El 8' Position Initials MS-121 ST-2036 ("B" header) outlet S MS-120 ST-2036 bypass S MS-120A ST-2036 header drain S MS-124 ST-2093 ("A" header) outlet S MS-123 ST-2093 bypass S MS-123A ST-header drain S RS-67 Radwaste steam trap header x-conn isolation at Unit I LP trap header (Unit 1 only) S MS-126 P-29 (auxiliary feed pump) steam supply S '
MS-130 ST-2094 inlet S MS-131 ST-2094 bypass S MS-137 ST-2048 inlet S MS-138 ST-5908 inlet S MS-139 ST-2048, ST-5908 bypass S MS-140 ST-2048 outlet isolation S MS-142 Steam dump headerisolation S I',)
D MS-143 Isolation MS-142 bypass S
{
MS-144 ST-5900 header isolation O l MS-145 ST-5900 inlet O 1 MS-146 ST-5900 bypass O MS 147 ST-5900 outlet S MS-148 ST-5901 header isolation O MS-149 ST-5901 inlet O MS-150 ST 5901 bypass O MS-151 ST-5901 outlet S MS-152 ST-5902 header isolation O MS-153 ST-5902 inlet O MS-154 ST-5902 bypass O MS-155 ST-5902 outlet S MS-156 ST-5903 headerisolation O MS-157 ST-5903 inlet O MS-158 ST-5903 bypass O MS-159 ST-5903 outlet S MS-164 LP trap header condenser isolation S MS-165 LP trap header atmospheric blowoff tank S MS-166B ST-2395 isolation S (qj
, MS-210 Remarks:
Z54 inlet S l Page 37 of 47 REFERENCE USE I
NUCLEAR POWER BUSINESS UNIT RP6A REFUELING PROCEDURES MAJOR IPTE STEAM GENERATOR CREVICE FLUSH Revision 9 (VACUUM MODE) January 31.1997 Attachment B Turbine Buildine. El 8'(Cont'd) Position Initials MS-178 254 bypass S MS-181 MS-2031 outlet isolation S
.MS-182 ST-5907 header isolation O MS-183 ST-5907 inlet O MS-184 ST-5907 bypass O MS-185 ST-5907 outlet S MS-186 ST-5906 header O MS-187 ST-5906 inlet O MS-188 ST-5906 bypass O MS-189 ST-5906 outlet S MS-190 ST-5905 headerisolation O MS-191 ST-5905 inlet O MS 192 ST-5905 bypass O MS-193 ST-5905 outlet S MS-194 ST-5904 headerisolation O MS-195 ST-5904 inlet O MS-196 ST-5904 bypass O
MS-197 ST-5904 outlet S MS-198A LP trap header south (north) isolation LS MS-203 ST-2049, ST-5909 bypass S MS-204 ST-2049 inlet S MS 205 ST-5905 inlet S MS 206 ST-2049 outlet isolation S MS-208 Steam dump header isolation S
MS-209 MS-208 steam dump header isolation bypass S Rtmarks:
l O
l Page 38 of 47 REFERENCE USE -
NUCLEAR POWER BUSINESS UNIT RP 6A REFUELING PROCEDURES MAJOR IPTE STEAM GENERATOR CREVICE FLUSH Revision 9 (VACUUM MODE) January 31,1997 (m\
V Uru.t ATTACHMENT C
_SG CREVICE FLUSH INSTRUMENTATION IAC '
Isolated Restored Turbine Buildinc. El 46' Initials Initials MS-14 PI-2716 (governor valve inlet pressure)
Containment FT-464 ("A' SG steam flow)
FT-465 ("A" SG steam flow)
FT-474 ("B" SG steam flow)
FT-475 ("B" SG steam flow)
LT-460B "A" SG wide range level LT-461 "A" SG narrow range level
,e LT-462 "A" SG narrow range level
(
LT-463 "A" SG narrow range level LT-470B "B" SG wide range level !
LT-471 "B" SG narrow range level LT-472 "B" SG narrow range level LT-473 "B" SG narrow range level PAB. El 66' PT-478 ("B" SG pressure)
PT-479 ("B" SG pressure) _
PT-483 ("B" SG pressure)
PAB. El 46'
~~
PT-469 ("A" SG pressure)
PT-482 ("A" SG pressure) ~
Remarks:
O V) i l Page 39 of 47
- REFERENCE USE
__ ______._i
NUCLEAR POWER BUSINESS UNIT RP 6A REFUELING PROCEDURES MAJOR IPTE STEAM GENERATOR CREVICE FLUSH Revision 9 (VACUUM MODE) January 31.1997 Attachment C PAB. El 26' Unit 1 (PAB. El 8' Unit 2) Initials Initials FT-4036 "A" SG total aux. feed flow FT-4037 "B" SG total aux. feed flow Maintenance Mezzanine. El 39'- Unit 1 Water Treatment. El 26'- Unit 2 PT-2289 Feed line pressure, "A" SG FT-466 "A" SG feed flow FI-466 "A" SG feed flow local indication FT-467 "A" SG feed flow FT-477 "B" SG feed flow FT-476 "B" SG feed flow F1-476 "B" SG feed flow localindication PT-2290 Feed line pressure, "B" SG Remarks:
l O
Page 40 of 47 REFERENCE USE
1 NUCLEAR POWER BUSINESS UNIT RP 6A !
REFUELING PROCEDURES MAJOR IPTE STEAM GENERATOR CREVICE FLUSH Revision 9 (VACUUM MODE) January 31.1997 N.
ATTACHMENT D-1 UNIT 1 STEAM LINE HANGERS (Ref Drawines Listed Below) l Blocks Hanger Number Location Column Installed Removed Initials Initials EB-1-H1 "B" main steamline 37.5' TB PC-8.6 EB1-H2 "B" main steamline 37.5' TB E-9 '
EB-1-H11 "A" main steamline 37.5' TB C-9 EB-1 H12 "A" main steamline 37.5' TB D-9.5 EB-1-H13 "A" main steamline 37.5' TB E-9.9 EB-1-H 14 Common steam header 37.5' TB F-9.9 EB-2-H1 Steam header 20' TB F-9 EB-2 H14 Condenser dump hdr 20' TB F-8/9 EB-2-H16 Condenser dump hdr 20' TB DP-8.6 EB-2-H2 Condenser dump hdr 20' TB F-8 EB-4-13 "A" MSR steam supply 39.5' TB F-5 EB-4-8 "B" MSR steam supply 39.5' TB F-6 EB 1 "C" MSR steam supply 39.5' TB F-8 EB-4-4 "D" MSR steam supply 39.5' TB F-8 "A" Sacrificial Flange "A" steam header 30' turbine hall "B" Sacrificial Flange "B" steam header 30' turbine hall
Reference:
Drawings P-107 (Bechtel)
Drawings 6EB-4-1,2,3 and 4 (Tubco)
IE Bulletin 79-14, pages 4 and 5 Remarks:
l Page 41 of 47 . REFERENCE USE
NUCLEAR POWER BUSINESS UNIT RP 6A REFUELING PROCEDURES MAJOR IPTE STEAM GENERATOR CREVICE FLUSH Revision 9 (VACUUM MODE) January 31.1997 ATTACHMENT D-2 UNIT 2 STEAM LINE HANGERS (Ref Drawines Listed Below)
Blocks Hanger Number Location Column Installed Removed Initials Initials EB-1-H1 "B" main steamline 37.5' TB DC-14.4 _._
EB-1-H2 "B" main steamline 37.5' TB E-14 EB-1-H11 "A" main steamline 37.5' TB C-14 EB-1-H12 "A" main steamline 37.5' TB D-13.1 EB-1-H13 "A" main steamline 37.5' TB E-13.1 EB-1-H 14 Common steam header 37.5' TB F-13.1 EB-2-HI Steam header 20' TB F-14 EB-2 H14 Condenser dump hdr 20' TB E-14 EB-2-H2 Condenser dump hdr 20' TB F-15 EB-4-2H10 "A" MSR steam supply 39.5' TB F-16 EB-4-2H9 "A" MSR steam supply 39.5' TB F-16 EB-4-2H8 "A" MSR steam supply 21' TB F-16 EB-4-2H2 "B" MSR steam supply 39.5' TB F-17 EB-4 2HI "B" MSR steam supply 36' TB F-16 EB-4-2H16 "C" MSR steam supply 39.5' TB F-18 EB-4-2H21 "D" MSR steam supply 39.5' TB F-17 EP-4 2H2O "D" MSR steam supply 33.5' TB F-17 "A" Sacrificial Flange "A" steam header 30' turbine hall "B" Sacrificial Flange "B" steam header 30' turbine hall
Reference:
Drawings P-107 (Bechtel)
Drawings 6EB-4-1,2,3 and 4 (Tubco)
IE Bulletin 79-14, pages 4 and 5 Remarks:
O l Page 42 of 47 REFERENCE USE ,
9
NUCLEAR POWER BUSINESS UNIT RP6A REFUELING PROCEDURES MAJOR IPTE STEAM GENERATOR CREVICE FLUSH Revision 9 (VACUUM MODE) January 31.1997 v.-
ATTACHMENT E VALVE LINEUP AFTER CREVICE FLUSH Control Room Description Position Initials MS-2026 LH turbine stop valve S MS-2032 No. 3 governor valve S MS-2033 No. I governor valve S
- MSV-2027 RH turbine stop valve S MS-2034 No. 4 governor valve S MS-2035 No. 2 governor valve S MS-2018 "A" main steam stop S MS-2017 "B" main steam stop S MS-2016 "A" atmosphere steam dump O MS-2015 "B" atmosphere steam dump O MS-5958 "A" SG blowdown isolation O
( MS-5959 "B" SG blowdown isolation O MS-2042 "A" SG blowdown isolation S MS-2045 "B" SG blowdown isolation S AF-4001 P-29 discharge to "A" SG S AF-4000 P-29 discharge to "B" SG S MS 2083 "A" SG sample isolation O MS-2084 "B" SG sample isolation O AF-4023 P-38A discharge to I A SG (Ul flush only) S AF-402 P-38B discharge to IB SG (U1 flush only) S AF-4022 P-38A discharge to 2A SG (U2 flush only) S AF-4020 P-38B discharge to 2B SG (U2 flush only) S Turbine drain valves MS-2701-2706 O Containment --
MS-215 "B" steam generator tubesheet drain S MS-221 "A" steam generator tubesheet drain S Remarks:
O V
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1 NUCLEAR POWER BUSINESS UNIT RP6A REFUELING PROCEDURES MAJOR IPTE STEAM GENERATOR CREVICE FLUSH Revision 9 I (VACUUM MODE) January 31,1997 Attachment E EAc.Ade. EL 85' Position Initials MS-223 "A" steam generator vent DSS MS-229 "A" header drain to blowdown tank O MS-234 MS-2018 bypass S MS-236 MS-2017 bypass S MS-239 "B" header drain to blowdown tank O MS-248 "B" steam generator vent DSS MS-249 "A" main steam line sample isolation (El. 66') S MS-249A "A" main steam line sample isolation (El. 66') S MS-250 "B" main steam line sample isolation (El. 66') S MS-250A "B" main steam line sample isolation (El. 66') S PAB. El 44' & 39' MS-251 A P-29 governor sensing line isolation LO MS-252A P-29 governor sensing line isolation LO MS-2019 P-29 steam supply LH MS-2020 P-29 steam supply LH Turbine Buildine. El 46' MS-2A Vacuum breaker S MS-3 MS-2746 inlet O MS-7 ST-2739 inlet O MS-10A PX-2025 - 1st offisolation 1 turn i
open MS-10B PX-2025 - 2nd offisolation Iturn open MS-14 PT-2716 (governor viv inlet press.) isolation O MS-1SA PX-2024 - 1st offisolation ;
1 turn '
open 1 MS-ISB PX-2024 - 2nd offisolation 1 tum open MS-17 MS-2745 inlet 1 O
MS-21 ST-2740 inlet !
O !
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NUCLEAR POWER BUSINESS UNIT RP 6A REFUELING PROCEDURES MAJOR 4
IPTE STEAM GENERATOR CREVICE FLUSH Revision 9 (VACUUM MODE) January 31.1997 Attachment E Turbine Buildine. El 26' Position Initials MS-39 ST-2009 inlet O ,
MS-40 ST-2009 bypass I turn open MS-44 ST-2014 inlet O MS-45 ST-2014 bypass I turn open MS-47 ST-2389 (5A feedwater heater extraction) inlet O MS-50 ST-2390 (SB feedwater heater extraction) inlet O MS-53 ST-2351 (5 A feedwater heater extraction) inlet O MS-56 ST-2349 (SB feedwater heater extraction) inlet O MS-59 ST-2381 (extraction to building heating) inlet O MS-62 ST-2392 (4A feedwater heater extraction) inlet O MS-65 ST-2391 (4B feedwater heater extraction) inlet O MS-83 ST-2753 inlet O MS-84 ST-2753 bypass I turn open MS-86 Header drain at ST-2753 1/2 turn open Remarks:
. O 4
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NUCLEAR POWER BUSINESS UNIT RP 6A REFUELING PROCEDURES MAJOR IPTE STEAM GENERATOR CREVICE FLUSH Revision 9 (VACUUM MODE) January 31.1997 Attachment E Turbine Building. El 8' Position Initials MS-119 ST-2036 ("B" header) inlet O MS-120A ST-2036 header drain S MS-121 ST-2036 ("B" header) outlet O MS-120 ST-2036 bypass I turn open MS-122 ST-2093 ("A" header) inlet O MS-123 A ST-2093 header drain S MS-124 ST-2093 ("A" header) outlet O MS-123 ST-2093 bypass 1 turn open MS-126 P-29 (auxiliary feed pump) steam supply LO MS-130 ST-2094 inlet O MS-131 ST-2094 bypass S MS-137 ST-2048 inlet O MS-138 ST-5908 inlet O MS-139 ST-2048, ST-5908 bypass 1 turn open MS-140 ST-2048 outlet isolation O MS-142 Steam dump headerisolation O ,
MS-143 Isolation MS-142 bypass S MS-147 ST-5900 outlet O MS-146 ST-5900 bypass 1 turn open MS-151 ST-5901 outlet O MS-150 ST-5901 bypass I tum open MS-155 ST-5902 outlet O MS-154 ST-5902 bypass 1 turn open MS-159 ST-5903 outlet O MS-158 ST-5903 bypass I turn open MS-164 LP trap header condenserisolation S MS-165 LP trap header to atmospheric blowoff tank l O
MS-166B ST-2395 isolation )
O MS-210 Z54 inlet O MS-178 Z54 bypass S MS-181 MS-2031 outlet isolation O MS-185 ST-5907 outlet O MS-184 ST-5907 bypass 1 turn open MS-189 ST-5906 outlet O MS-188 ST-5906 bypass l
1 turn open MS-193 ST-5905 outlet 0 i l Page 46 of 47 REFERENCE USE
NUCLEAR POWER BUSINESS UNIT - RP 6A REFUELING PROCEDURES MAJOR .
5 IPTE STEAM GENERATOR CREVICE FLUSH Revision 9 (VACUUM MODE) January 31.1997 hrbine Buildine. El 8'(Cont'd) Position Initials MS-192 ST-5905 bypass Iturn open MS-196 ST-5904 bypass 1 turn open MS-197 ST-5904 outlet O MS-198A LP trap header south isolation S MS-203 ST-2049, ST-5909 bypass Iturn -
l open MS-204 ST-2049 inlet O MS-198A LP trap header south isolation S MS 203 ST-2049, ST-5909 bypass Iturn open MS-204 ST-2049 inlet O MS-205 ST-5909 inlet O MS-206 ST-2049 outlet isolation O MS-208 Steam dump headerisolation O
( MS-209 MS-208 steam dump header isolation bypass S Remarks:
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NUCLEAR POWER BUSINESS UNIT 01 INDEX OPERATING INSTRUCTIONS- Revision 176 knuary 30,1997 INDEX BIENNIAL h.C\ PROCEDURE NUMDER REVISION EFFECT NE DATE REVIEW PROCEDURE TITLE NUMBER DATE 01-1 A 1HX-1 A, Steam Generator Leak Check, Unit 1. .5 R 10/17/96 10/17/96 01 1B lHX-1B, Steam Generator Leak Check, Unit 1. .5 R 10/17/96 10/17/96 01-2 Ul Main Steam Generator Leak Check (Renumbered to OI-1 A & 01-1B) 01-2 U2 Main Steam Generator Leak Check (Renumbered to OI-2A & 01-28)
OI-2A 2HX-I A, Steam Generator Leak Check, Unit 2. .11 R 10/17/96 10!!7/96 012B 2HX-1B, Steam Generator Leak Check, Unit 2. .10 R 10/17/96 10/17/96 01-3 Thimble Plug llandling Tool.. .7 I 11/05/92 11/05/92 01-4 Fpent Fuel Assembly Handling Tool. .5 1 10/08/92 10/08/92 01-5 Irradiation Capsule Handling Tool. .6 1 10/21/92 10/21/92 01 6 Guide Tube Insert Handling Tool . .7 I 06/25/93 06/25/93 01-7 Burnable Poison Rod Assembly (BPRA)/ Plug Device Handling Tools (Z-100 0ld/New). .10 1 04/01/96 10/21/92 01-8 Portable Load Cell Instrument. .1 1 04/15/93 04/15/93 01-10 Boron Recycle . .5 R 02/23/96 02/23/96 01-11 Steam Generator Nozzle Dam Operation Guide.. .5 1 10/25/96 10/25/96 01-12 Off-Line Condenser Leak Check . .5 1 02/11/94 02/11/94 01-13 Steam Dump Valves Modulating and Trip Test . .11 1 09/13/96 10/21/94
- 01-13 APP. A Condenser and Atmospheric Steam Dump Valve 01-13B UI Placing Condensate System Heat Exchangers in Wet Lay-Up . .1 1 05/18/93 05/18/93 01-138 U2 Placing Condensate System Heat Exchangers in Wet Lay Up. 1 I 05/18/93 05/18/93 01-14 Steam Generator Blowdown Operation 10 I 10/02/96 10/28/94 01-15 Charging Pump Local Control Station Operation . 6 1 06/10/96 06/10/96 OI-15 A Charging Pump Alternative Mode Operation. .0 R 05/20/96 05/20/96 0116 Blowdown Evaporator Operation. .16 1 01/07/97 01/07/97 0117 Letdown Gas Stripper Operation. .10 R 01/25/97 08/01/94 O! 17A Letdown Gas Stripper Preparation for Maintenance and Recovery, Unit 1. 2 R 01/25/97 12/22/95 0117B Letdown Gas Stripper Preparation for Maintenance and Recovery, Unit 2. .2 R 01/25/97 12/22/95 OI-18 A Shifting Radwaste Steam Supplies. .1 R 12/02/92 12/02/92 01-19 Spent Fuel Pit Demineralizer Resin Flush and Recharge, U6. .9 1 01/06/95 01/06/95 01-20 Resin Transfer Cask and Resin Storage Tank (T-112) . .25 1 02/02/96 04/28/93 01-21 Mixed Bed (HOH) Demineralizer Resin Flush and p Recharge, I Ul A(B) and 2UI A(B).. .15 1 12 " 5/95 02/11/94 y/ 01-22 Changing Primary Coolant Micron Filters. .20 1 044 J/95 05/02/94 C = Continuous Use (T - Temporary Change) R = Reference Use
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NUCLEAR POWER BUSINESS UNIT OI INDEX OPERATING INSTRUCTIONS Revision 176 January 30,1997 INDEX BIENNIE REVISION EFFECTIVE REVIEW PROCEDURE PROCEDURE TITLE NUMBER DATE DATE
._ NUMBER Changing Reactor Coolant Micron Filter (FI) . .10 R 01/30/97 01/06/95 0122A Changing Seal Water Return Filter (F2).. .7 R 01/30/97 12/21/93 0122B 0122C Changing Spent Fuel Pool Filter (F6) . .6 R 01/30/97 12/21/93 Changing Seal Water Injection Filters (F39 A&B) . .9 R 01/30/97 06/08/95 O! 22D Changing Letdown Gas Stripper Filters (F60A&B) . .7 R 01/30/97 12/21/93 0122E 0122F Changing Boric Acid Filters (F3) 3 R 01/30/97 04/15/93 Of 22G Changing Boric Acid Evaporator Feed Filters (F8). .5 R 01/30/97 04/15/93 012211 Changing Boric Acid Concentrates Filters (F-5 A&B) . 5 R 01/25/97 12/21/93 01 23 Containment Fuel Transfer Equipment. 9 1 01/18/94 01/18/94 01 24 Evaporator Feed lon Exchanger Resin Flush and Recharge 1Ul2A, B. C and 2U12. Ii 1 04/15/93 04/15/93 01-26 Deborating Demineralizer Resin Flush and Recharge IU2A(B) and 2U2A(B). 10 1 04/15/93 04/15/93 01-27 Cation Bed Demineralizer Resin Flush and Recharge 1U9 and 2U9 .10 1 04/l5/93 04/15/93 01-28 Condensate Demineralizer Resin Flush and Recharge 9 04/15/93 04/15/93 U3 A (U3B) [U3C] .
01-29 Water Polishing Demineralizer Resin Flush and Recharge T108A(T108B) . .9 04/15/93 04/15/93 01-30 Securing X01/X02 Transformers for Maintenance. 6 09/03/93 09/03/93 01-31 Rod Drive Motor Generator Set. 4 R 07/16/91 08/30/93 0132 liydrogen System Operation 17 R 01/25/97 07/08/94 01-33 Battery Charger Paralleling and Restoration 19 C 01/12/96 08/16/95 01-35 Electrical Equipment Operation 22 1 10/06/95 07/18/94 0135A Standby Emergency Power Alignment 2 R 12/19'96 04/01/95 01-36 Procedure for Removing No 5 Feedwater lleater From Sersice 8 1 06/14/93 08/22/94 01-37 Shifting ofInstrument Supply Bus Feeders .28 R T 11/03/96 03/24/94 01-38 Circulating Water System Operation.. .10 1 T 03/10/95 03/10/95 OI-38 A SF-6 Condenser Tube Leak Test. .0 03/02/95 03/02/95 01-30 Controlled Side Ventilation System. 9 1 07/17/95 02/20/95 01-40 Fire Detection System Reset Instructions For Alarms and Detectors. .3 1 T 10/13/94 06/11/91 01-41 Deluge Valve Operation. .2 1 07/16/91 07/16/91 01-42 Total Flooding lialon 1301 Fire Protection Systems. 6 R 02/20/95 03/03/93 Ol-48A Transferring Lube Oil. 3 R 03/29/93 03/29/93 0148B Lube Oil Filter Changeouts .4 R 01/25/97 07/08/94 OI-48C Operation of Lube Oil Purifier 2 R 03/29/93 03/29/93 Ol-48D Establishing Water Seal In Settling Compartment of Bowser . 2 R 03/29/93 03/29/93 l 0148E EH Fluid System. .15 R 01/30/97 03/24/94 C = Contmuous Use (T- Temporary Change) R = Reference Use Page 2 of 5 1 = Informatic:. Use
NUCLEAR POWER BUSINESS UNIT 01 INDEX OPERATING INSTRUCTIONS Revision 176 January 30,1997 INDEX 4 BIENNIAL s PROCEDURE REVISION EFFECTIVE REVIEW EUMBER PROCEDURE TITLE NUMBER DATE DATE .
OI-48F Seal Oil System . .6 R 07/03/95 10/10/94 01-49 Extension Building Battery Charger Power Supply. .1 R 01/18/93 01/04/95 01-50 Charging Pump Isolation. .9 R 03/22/96 07/17/95 01-51 Spent Fuel Pool / Transfer Canal Doors . .5 R 09/28/95 09/28/95 01-52 Spent Fuel Pool Skimmer Suction Strainer Changeout. 5 R 09/28/95 09/28/95 t 01-53 Positioning of the Fuel Transfer Cart. .2 R I1/20/95 10/23/91 01-54 Radioactive Waste Gas System Operation. .10 1 04/15/93 04/15/93 ;
, 01-55 Primary Leak Rate Calculation . .7 R 11/18/94 11/18/94 ;
01 56 Draining and Refilling the Transfer Canal . .8 R 03/22/96 06/08/95 L 01-57 Reactor Coolant Drain Tank Pump Priming
- and Operation.. .5 R 04/15/93 04/15/93 01-58 Leak Testing of Containment Isolation Valves - ,
Units 1 & 2 General Instructions and Information . .13 I T 09/03/93 09/03/93 i 01-60 Renumbered to OI-48E 01-61 Freeze Plug. .5 1 10/21/92 10/04/94 OI-62A Motor-Driven Auxiliary Feedwater System !
(P-38 A&B) . .I1 1 04/10/95 04/10/95 01-62B Turbine-Driven Auxiliary Feedwater System (P-29) . . 4 1 04/30/92 04/30/92 01-63 Heating Boiler Operation . .14 1 01/12/96 08/16/95 ;
01-64 Cleaning and Lubrication of Purge Supply and i
Exhaust Valves 3244,3245,3213 and 3212 .16 1 04/26/96 04/26/96 O! 64A Installation and Removal of Purge Valve Component Bypass Lines 6 R 01/25/97 03/10/95 01-65 Post-Maintenance Pressure Testing 19 1 06/08/95 06/08/95 l Part i Diesel Hydro Pump Operation 1 1 05/14/91 07/13/93 [
j Pan 2 Partek Liqua-Blaster Hydro Pumps . 1 I 05/14/91 07/13/93 i 1 Part 3 Low Capacity Hydro Pump Operation. .3 1 05/14/91 07/13/93 l Part 4 Hand-Operated Hydro Pump Operation . .2 1 06/18/92 07/13/93 !
01-66 Facade Sump Pumping. .3 1 10/18/93 10/18/93 .
01-67 Operation of the AMF Waste Evaporator and Waste Condensate System . .3 1 04/15/93 04/15/93 01-69 Renumbered to OI-48F 01-70 Service Water System Operation . .10 1 09/11/96 10/30/95 01-71 Component Cooling Water Heat Exchanger Operation. . .3 1 12/14/94 06/03/94
, 01-72 Containment Air Recirculation System. .6 1 09/28/93 09/28/93 01-73 Water Treatment Demineralizer Plant Operation. .15 1 T 09/11/96 02/04/94 OI-73F Water Treatment Pretreatment Plant Operation . .8 1 06/21/96 09/28/93 Ol-73G Sludge Treatment Plant Operation. .3 1 06/03/94 06/03/94 Ol-73H Brine Cleaning Anion Resins. .2 R 09/19/94 09/19/94 ,
l C = Conunuous Usc (T - Temporary Change) R = Reference Use 4
, Page.1of5 1 = Informanon Use e
NUCLEAR POWER BUSINESS UNIT 01 INDEX OPERATING INSTRUCTIONS Revision 176 January 30,1997 INDEX BIENNIAL PROCEDURE REVISION EFFECTIVE REVIEW
.SUMBER_ PROCEDURE TITLE NUMBER DATE DATE 0173J Water Treatment Resin Sampling . .2 1 01/25/97 09/27/91 OI-N Spent Fuel Rack Poison Handling Tool .3 I 10/21/92 10/21/92 01-75 RCC Change Tool (Z-023H). .6 I 10/18/93 10/21/92 01-78 Preparation of Secondary Systems for Major Outage. .17 R 10/02/96 05/25/93 01-79 Establishing or Maintaining Condenser Vacuum With Heating Steam . .6 I 03/23/93 08/04/94 01-80 RMS, Control Terminal .8 1 07/16/91 07/13/93 01 81 RMS, Troubleshooting and Startup. .10 1 08/16'95 08/16/95 01-82 Communication Systems Operation. 8 1 02/23/96 10/13/94 01-84 Operation of the Spent Fuel Canister Lid Tool . .3 1 04/10/95 04/10/95 01-85 Varian Helium Leak Detection . .4 1 07/16/91 07/16/91 01 86 Instrument Air K2A/K2B and Senice Air K3A/K3B Compressor Run-in Operating Instructions . .6 I 01/25/97 12/21/93 OI-86A Instrument Air Dryer Z-3 i Operating Instructions .2 1 01/25,97 06/03/94 OI-86B Instrument Air Dryer Z-39 Operating Instructions. .1 1 08/26/94 06/03/94 01-88 Fire Dampers . .2 1 05/02/94 05/02/94 01-89 Baron II High Pressure Breathing Air Fill System. .1 1 09/27/91 09/27/91 01-90 Control, Computer, and Cable Spreading Room Ventilation Systems. .9 I 02/03/95 02/03/95 01-91 SFP Bridge Hoists. 8 1 09/28/95 04/10/95 Ol-92A Fuel Oil Ordering, Receipt, Sampling and T-173 Fill Tank Draining (Replaces 01-92) 0 1 T 06/05/96 06'05/96 01-92B Lube Oil / Ell Fluid Sampling and Lube Oil Viscosity Testing (Replaces 01-92) 0 1 06/05/96 06:05'06 01-93 Microlog Vibration Data Collectors 2 1 01/13/95 01/13/95 01-94 Fuel Assembly Loading Guides (Z-701 and Z-702). .4 1 10/02/96 10/02/96 01-95 Obtaining A Sump "A" Sample.. .4 R 05/05/95 05/05/95 01-96 Steam Generator Tube Leakage Calculation and Evaluation.. .6 I T 11/27/95 11/18/94 01-97 Battery Room Ventilation Systems . .1 1 09/28/93 09/28/93 01-98 Regeneration of Ferric.eer Iron Filters . .1 1 03/29/93 03/29/93 01-99 Shifting On Senice Boric Acid Storage Tank. .4 1 05/05/95 05/05/95 OI 99A Boric Acid Piping Temperature Monitoring .1 1 06/08/95 06/08/95 l 01100 Adjusting SI Accumulator Level and Pressure. .6 R T 12/27/96 12/27/96 l 01-101 Receipt of Chlorination / Dechlorination Chemicals . .3 1 07/08/94 07/08/94 l 01-103 Removing From sed Returning to Senice A Heater Drain Tank Pump . .3 1 07/28/95 02/04/94 01-104 . Spray Additive Tank Level Adjustment and Recirculation . .4 C 04/10/95 04/10/95 01-105 RCS Heatup/Cooldown Plotting .2 R 03/04/96 03/04/96 C = Conunuots Use j (T - Temporary Change) R = Reference Use i Page 4 of 5 1 = Informanon Use I
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NUCLEAR POWER BUSINESS UNIT 01 INDEX OPERATING INSTRUCTIONS Revision 176 January 30,1997 INDEX BIENNIAL PROCEDURE REVISION EFFECTIVE REVIEW NUMBER PROCEDURE TITLE NUMBER DATE DATE 01-106 Facade Freeze Protection System Operation. .8 R 03/22/96 07/28/95 01-107 Shifling Station Batteries.. .6 C T 09/28/95 08/16!95 01 108 Turbine Building Ventilation Operation . .2 1 04/01/95 04/01/95 01-109 Spent Fuel Pool Cask Laydown Area Vacuum Cleaning . 1 R 11/20/95 11/20/95 01-110 Gas Turbine Operation (Replaces OP-16A).. .1 R 01/12/96 09/20/95 01-111 Ventilated Storage Cask (VSC) Daily Surveillance.. .1 1 03/04/96 09/01/95 i 01-112 Aligning Equipment to Appendix R Power Supply. .I R 05/20/96 05/20/96 01-114 Returning CCW to the CCW System . .0 R 11/04/96 11/04/96 01 115 SFP Service Water Cooling Isolation for Maintenance . 2 R 01/25/97 09/13/96
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C = Continuous Use (T - Temporary Change) R = Reference Use Page 5 of 5 1 = Information Use
NUCLEAR POWER BUSINESS UNIT 01 SUBJECT INDEX OPERATING INSTRUCTIONS - Revision 176 January 30,1997 SUBJECT INDEX BIENNIAL (Q/ PROCEDURE.
NUMDER PROCEDURE TITLE REVISION NUMBER EFFECTIVE DATE REVIEW DATE PRIMARY SYSTEM Ols 01-10 Boron Recycle . .5 02/23/96 02/23/96 01-11 Steam Generator Nozzle Dam Operation Guide.. .5 10/25/96 10/25/96 01-15 Charging Pump Local Control Station Operation.. .6 06/10/96 06/10/96 OI-15 A Charging Pump Alternative Mode Operation. ~0 05/20/96 05/20/96 OI 16 Blowdown Evaporator Operation. .16 01/07/97 01/07/97 01 17 Letdown Gas Stripper Operation. .10 01/25/97 08/01/94 Of 17A Letdown Gas Stripper Preparation for Maintenance and Recovery, Unit 1. .2 01/25/97 12/22/95 01 17B Letdown Gas Stripper Preparation for Maintenance and Recovery, Unit 2. .2 01/25/97 12/22/95 01-39 Controlled Side Ventilation System. .9 07/17/95 02/20/95 01-50 Charging Pump Isolation. .9 03/22/96 07/17/95 01-54 Radioactive Waste Gas System Operation . .10 04/15/93 04/15/93 01-55 Primary Leak Rate Calculation. .7 11/18/94 11/18/94 01-57 Reactor Coolant Drain Tank Pump Priming and Operation . .5 04/15/93 04/15/93 01-61 Freeze Plug. .5 10/21/92 10/04/94 b 01-66 Facade Sump Pumping. .3 10/18/93 10/18/93 01-67 Operation of the AMF Waste Evaporator and Waste Condensate System . .3 04/15/93 04/15/93 01-71 Component Cooling Water Heat Exchanger Operation . 3 12/14/94 06/03/94 01-72 Containment Air Recirculation System .6 09/28/93 09/28/93 01 80 RMS, Control Terminal. 8 07/16/91 07/13/93 01-81 RMS, Troubleshooting and Startup. 10 08/16/95 08/16/95 01-95 Obtaining A Sump "A" Sample. .4 05/05/95 05/05/95 01-96 Steam Generator Tube Leakage Calculation and Evaluation.. .6 T 11/27/95 11/18/94 01-99 Shifting On Service Boric Acid Storage Tank. .4 05/05/95 05/05/95 OI-99A Boric Acid Piping Temperature Monitoring. .1 06/08/95 06/08/95 01100 Adjusting SI Accumulator Level and Pressure. .6 T 12/27/96 12/27/96 01-104 Spray Additive Tank Level Adjustment and Recirculation.. .4 04/10/95 04/10/95 01-105 RCS Heatup/Cooldown Plotting . .2 03/04/96, 03/04/96 01-114 Returning CCW to the CCW System. .0 11/04/96 11/04/96 A
b (T - Temporary Change)
Page1of5
NUCLEAR POWER BUSINESS UNIT 01 SUBJECT INDEX l OPERATING INSTRUCTIONS Revision 176 !
January 30.1997 )
SUBJECT INDEX BIENNIAL ,
PROCEDURE REVISION EFFECTIVE REVIEW I NUMJ3_EJR_ PROCEDURE TITLE NUMBER DATE DATE SECONDARY SYSTEMS Ols OI-1 A liiX-1 A, Steam Generator Leak Check. Unit 1. .5 10/17/96 10/17/96 01 1B lilX-1B, Steam Generator Leak Check, Unit 1. .5 10/17/96 10/17/96 )
OI-2A 2HX-1 A, Steam Generator Leak Check, Unit 2. .I1 10/17/96 10/17/96 01-2B 2HX-1B, Steam Generator Leak Check, Unit 2. .10 10/17/96 10/17/96 01-13B Ul Placing Condensate System Heat Exchangers l in Wet Lay-up . .1 05/18/93 05/18/93 l 01-13B U2 Placing Condensate System Heat Exchangers in Wet Lay-up . 1 05/18/93 05/18/93 01-14 Steam Generator Blowdown Operation . .10 10/02/96 10/28/94 01-18 A Shifting Radwaste Steam Supplies. .I 12/02/92 12/02/92 0132 flydrogen System Operation.. .17 01/25/97 07/08/94 01-36 Procedure for Removing No. 5 Feedwater Heater From Senice. .8 06/14/93 08/22/94 01-38 Circulating Warer System Operation . .10 T 03/10/95 03/10/95 OI-38 A SF-6 Condenser Tube Leak Test. .0 03/02/95 03/02/95 OI-48A Transferring Lube Oil. .3 03/29/93 03/29/93 0148B Lube Oil Filter Changecuis.. .4 01/25/97 07/08/94 OI-48C Operation of Lube Oil Tarifier. .2 03/29/93 03/29/93 OI-48D Establishing Water Seal in Settling Compartment of Bowser .2 03/29/93 03/29/93 l 0148E EH Fluid System . 15 01/30/97 03/24/94 OI-48F Seal Oil System 6 07/03/95 10/10/94 Ol-62A Motor-Driven Auxiliary Feedwater System (P-38 A&B) . I1 04/10/95 04/10/95 OI-62B Turbine-Driven Auxiliary Feedwater System (P-29) 4 04/30/92 04/30/92 01-63 Heating Boiler Operation . .14. 01/12/96 08/16/95 01-70 Service Water System Operation . .10 09/11/96 10/30/95 01-73 Water Treatment Demineralizer Plant Operation.. .15 T 09/11/96 02/04/94 OI-73F Water Treatment Pretreatment Plant Operation. .8 06/21/96 09/28/93 OI-73G Sludge Treatment Plant Operation. .3 06/03/94 06/03/94 OI-73H Brine Cleaning Anion Resins. .2 09/19/94 09/19/94 0173J Water Treatment Resin Sampling . .2 01/25/97 09/27/91 01-78 Preparation of Secondary Systems for Major Outage . .17 10/02/96 05/25/93 01-79 Establishing or Maintaining Condenser Vacuum With Heating Steam .6 03/23/93 08/04/94 01 86 Instrument Air K2A/K2B and Service Air K3 A/K3B Compressor Run-in Operating Instructions. .6 01/25/97 12/21/93 0186A Instrument Air Dryer Z-31 Operating Instructions. .2 01/25/97 06/03/94 01-86B Instrument Air Dryer Z-39 Operating Instructions. .1 08/26/94 06/03/94 (T - Temporary Change)
Page 2 of 5
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NUCLEAR POWER BUSINESS UNIT 01 SUBJECT INDEX !
OPERATING INSTRUCTIONS Revision 176 January 30.1997 SUBJECT INDEX i O BIENNIAL l V PROCEDURE PROCEDURE TITLE REVISION NUNtBER EFFECTIVE DATE REVIEW DATE 4
EUA1!LE2 SECONDARY SYSTEMS Ols (Cont.)
01-89 Baron II High Pressure Breathing Air Fill System .1 09/27/91 09/27/91 01-98 Regeneration of Ferricleer Iron Filters . .1 03/29/93 03/29/93 01 10i Receipt of Chlorination / Dechlorination Chemicals. .3 07/08/94 07/08/94 01-103 Removing From and Returning to Service A Heater Drain Tank Pump . .3 07/28/95 02/04/94 01-108 Turbine Building Ventilation Operation. . .2 '
04/01/95 04:01/95 01-110 Gas Turbine Operation (Replaces OP-16A) . .I 01/12/96 09/20/95 1 IEECTRICAL SYSTEM Ols 01-30 Securing X01/X02 Transformers for Maintenance .6 09/03/93 09/03/93 01-31 Rod Drive Motor Generator Set 4 07.'16/91 08'30 93 01-33 Battery Charger Paralleling and Restoration . 19 01/12'96 08/16/95 01-35 Electrical Equipment Operation. . 22 10/06/95 07/18/94 '
0135A Standby Emergency Power Alignment. .2 12/19/96 04/01/95 01-37 Shifting ofInstrument Supply Bus Feeders. .28 T I1/03/96 03/24/94 :
01-49 Extension Building Battery Charger Power Supply. 1 01/18/93 01/04/95 l 01-82 Communication Systems Operation. .8 02/23/96 10/13/94 01-90 Control, Computer, and Cable Spreading Room Ventilation Systems 9 02.'03 95 02/03/95 01-97 Battery Room Ventilation Systems 1 09:28:03 09'28/93 01-106 Facade Freeze Protection System Operation S 03'22 90 07 28 95 01-107 Shifting Station Batteries 6 T 09 28 45 08'1695 01-112 Aligning Equipment to Appendix R Power Supply 1 05 20 90 05 20,06 ELRE SYSTEM Ols 01-40 Fire Detection System Reset Instructions For Alarms and Detectors. .3 T 10/13/94 06/11/91 01-41 Deluge Valve Operation. .2 07/16/91 07/16/91 01-42 Total Flooding Halon 1301 Fire Protection Systems. . 6 02/20/95 03/03/93 01-88 Fire Dampers . .2 05/02/94 05/02/94 b !
d (T Temporary Change)
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NUCLEAR POWER BUSINESS UNIT 01 SUBJECT INDEX OPERATING INSTRUCTIONS Revision 176 January 30,1997 SUBJECT INDEX BIENNIAL PROCEDURE REVISION EFFECTIVE REVIEW NUMBER PROCEDURE TITLE NUMBER DATE DATE RESIN AND FILTER REPLACEMENT 01-19 Spent Fuel Pit Demineralizer Resin Flush and Recharge, U6. .9 01/06/95 01/06/95 01-20 Resin Transfer Cask and Resin Storage Tank (T-112). .25 '02/02/96 04/28/93 01-21 Mixed Bed (11011) Demineralizer Resin Flush and Recharge, IUl A(B) and 2Ul A(B). .15 12/15/95 02/11/94 01-22 Changing Primary Coolant Micron Filters .20 04/10/95 05/02/94 0122A Changing Reactor Coolant Micron Filter (FI) . .10 01/30/97 01/06/95 0122B Changing Seal Water Return Filter (F2) . 7 01/30/97 12/21/93 0122C Changing Spent Fuel Pit Filter (F6) .6 01/30/97 12/21/93 0122D Changing Seal Water injection Filters (F39A&B) . .9 01/30/97 06/08/95 0122E Changing Letdown Gas Stripper Filters (F60A&B) . .7 01/30/97 12/21/93 0122F Changing Boric Acid Filters (F3). .3 01/30/97 04/15/93 0122G Changing Boric Acid Evaporator Feed Filters (F8) . .5 01/30/97 04/15/93 012211 Changing Boric Acid Concentrates Filters (F-5A&B) . 5 01/25/97 12/21/93 01-24 Evaporator Feed Ion Exchanger Resin Flush and Recharge iUl2A, B, C and 2U12. .I1 04/15/93 04/15/93 01-26 Deborating Demineralizer Resin Flush and Recharge IU2A(B) and 2U2A(B) . .10 04/15/93 04/15/93 01-27 Cation Bed Demineralizer Resin Flush and Recharge 1U9 and 2U9. .10 04/l5/93 04/15/93 01-28 Condensate Demineralizer Resin Flush and Recharge U3 A (U3B) [U3CJ 9 04/15/93 04/15/93 01-29 Waste Polishing Demineralizer Resin Flush and Recharge T108A(T108B). .9 04/15/93 04/15/93 REFUEIEO AND SPENT FUEL POOL Ols 01-3 Thimble Plug 11andling Tool. .7 11/05/92 11/05/92 01-4 Spent Fuel Assembly Handling Tool .5 10/08/92 10/08/92 01-5 Irradiation Capsule liandling Tool. .6 10/21/92 10/21/92 01 6 Guide Tube Insen llandling Tool. .7 06/25/93 06/25/93 01-7 Burnable Poison Rod Assembly (BPRA)/ Plug Device liandling Tools (Z-100 Old/New) . .10 04/01/96 10/21/92 01 8 Portable Load Cell Instrument. 04/15/93
.1 04/15/93 01-23 Containment Fuel Transfer Equipment.. .9 01/18/94 01/18/94 01-51 Spent Fuel Pool / Transfer Canal Doors . .5 09/28/95 09/28/95 01-52 Spent Fuel Pool Skimmer Suction Strainer Changeout. .5 09/28/95 09/28/95 01-53 Positioning of the Fuel Transfer Cart . .2 11/20/95' 10/23/91 (T- Temporary Change)
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NUCLEAR POWER BUSINESS UNIT 01 SUBJECT INDEX OPERATING INSTRUCTIONS Revision 176 January 30.1997 SUBJECT INDEX
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PROCEDURE NUMBER PROCEDURE TITLE REVISION NUMBER EFFECTWE DATE BIENNIAL REVIEW DATE ,
i llEFUELING AND SPENT FUEL POOL 013 (Cont.)
01-56 Draining and Refilling the Transfer Canal . .8 03/22/96 06/08/95 01-64 Cleaning and Lubrication of Purge Supply and i Exhaust Valves,3244,3245,3213 and 3212. .16 04/26/96 04/26/96 !
0164A Installation and Removal of Purge Valve Component Bypass Lines . .6 01/25/97 03/10/95 01-74 Spent Fuel Rack Poison Handling Tool . .3 10/21/92 10/21/92 01-75 RCC Change Tool (Z-023H). .6 10/18/93 10/21/92 01-84 Operation of the Spent Fuel Canister Lid Tool . .3 04/10/95 04/10/94 01-91 SFP Bridge Hoists.. .8 09/28/95 04/10/95 01-94 Fuel Assembly Loading Guides (Z-701 and Z-702) .4 10/02/96 10/02/96 01-109 Spent Fuel Pool Cask Laydown Area Vacuum Cleaning . .I 11/20/95 11/20/95 01-11I Ventilated Storage Cask (VSC) Daily Surveillance.. .1 03/04/96 09/01/95 01 115 SFP Service Water Cooling isolation for Maintenance. 2 01/25/97 09/13/96 TESTING OJ3 *
(
\ 01-12 Off-Line Condenser Leak Check . .5 02/11/94 02/11/94 01-13 Steam Dump Valves Modulating and Trip Test . I1 09/13/96 10/21/94 01-58 Leak Testing of Containment Isolation Valves -
Units 1 & 2 General Instructions and information .I3 T 09/03/93 09/03/93 01-65 Post-Maintenance Pressure Testing . .19 06/08/95 06/08/95 Part 1 Diesel Hydro Pump Operation. .1 05/14/91 07/13/93 Part 2 Partek Liqua-Blaster Hydro Pumps . .1 05/14/91 07/13/93 Part 3 Low-Capacity Hydro Pump Operation . .3 05/14/91 07/13/93 Part 4 Hand-Operated Hydro Pump Operation.. .2 06/18/92 07/13/93 01-85 Varian Helium Leak Detection . .4 07/16/91 07/16/91 OI-92A Fuel Oil Ordering, Receipt, Sampling and T-173 Fill Tank Draining (Replaces 01-92). .0 T 06/05/96 06/05/96 01 928 Lube Oil / EH Fluid Sampling and Lube Oil Viscosity Testing (Replaces 01-92) . .0 06/05/96 06/05/96 01-93 Microlog Vibration Data Collectors . .2 01/13/95 01/13/95
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(T- Temporar) Change)
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