ML031130710
| ML031130710 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 04/01/2003 |
| From: | Reid J Public Service Enterprise Group |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| Conte R | |
| References | |
| 50-354/03-301 50-354/03-301 | |
| Download: ML031130710 (300) | |
Text
NC.TQ-WB.ZZ-031 0(Z)
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: HOPE CREEK SYSTEM: 215004 Source Range Monitor TASK: SRM/IRM Rod Block Bypassing during refueling operations IAW HC.OP-SO.SE-0001 Section 5.4. Perform independent verification of installed jumpers.
TASK NUMBER: 215004 A1.04 JPM NUMBER: 2003-NRC-LSRO-S1 ALTERNATE PATH: m K/A NUMBER: 233000 A2.02 APPLICABILITY: IMPORTANCE FACTOR: 3.1 3.3 EO RO EX SROF7X LSRO X RO SRO EVALUATION SETTING/METHOD: REACTOR BUILDING/ SIMULATE
REFERENCES:
HC.OP-SO.SE-0001 Rev 10 TOOLS AND EQUIPMENT: Flashlight VALIDATED JPM COMPLETION TIME: 5 min.
TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A niin.
APPROVED:
N/A BARGAINING UNIT 6LLE,-aQK TRAINING SUPERVISOR k1DZ-Xk OPP"TIONMANAGER REPRESENTATIVE Q-2'ckpesi9Pee CAUTION: No plant equipment shall be operated during the performance of a JPM without the following:
- 1. Permission from the OS or Unit CRS;
- 2. Direct oversight by a qualified individual (determined by the individual granting permission based on plant conditions).
- 3. Verification of the "as left" condition by a qualified individual.
ACTUAL JPM COMPLETION TIME: Imin.
ACTUAL TIME CRITICAL COMPLETION TIME: N/A min.
JPM PERFORMED BY: _ GRADE: a SAT 2 UNSAT REASON, IF UNSATISFACTORY:
EVALUATOR'S SIGNATURE: DATE:
Nuclear Common Page 1 Rev. 0 2003-NRC-LSRO-S1
NC.TQ-WB.ZZ-031 0(Z)
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:
DATE:
SYSTEM: 215004 Source Range Monitor TASK: SRM/IRM Rod Block Bypassing during refueling operations IAW HC.OP-SO.SE-0001 Section 5.4. Perform independent verification of installed jumpers TASK 215004 A1.04 INITIAL CONDITIONS:
- You are the Refueling SRO.
- The plant is in Operational Condition 5.
- All fuel has been moved to the Fuel Pool.
INITIATING CUE: Perform the Independent Verification requirements of steps 5.4.4 and 5.4.6 following l&C jumper installation lAW HC.OP-SO.SE-0001.
Successful Completion Criteria:
- 1. All critical steps completed.
- 2. All sequential steps completed in order.
- 3. All time-critical steps completed within allotted time.
- 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made (and NRC concurrence is obtained).
Nuclear Common Page 2 Rev. 0 2003-NRC-LSRO-Sl
NC.TQ-WB.ZZ-031 0(Z)
OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: 215004 Source Range Monitor TASK: SRM/IRM Rod Block Bypassing during refueling operations IAW HC.OP-SO.SE-0001 Section 5.4. Perform independent verification of installed jumpers.
STEP COMMENTS
(*Denotes a Critical Step) STANDARD EVAL (Required for
(#Denotes a Sequential Step) S/ U UNSAT evaluation)
START TIME: Operator proceeds to panel 10C635, opens the Cabinet door and locates terminal strip PERFORM an independent verification of DD.
the installed jumper from Step 5.4.3. Operator locates terminals DD-1 9 and DD-20.
INITIAL Attachment 1.
Examiner Cue: What do you expect to see?
Operator states a wire jumper should be installed between terminals DD-19 and DD-20.
Examiner Cue: A jumper is installed on the terminals indicated.
Examiner Note: Initialing Attachment 1 is not critical.
Operator initials Attachment 1 as independent verifier.
Nuclear Common Page 3 REV.: 0 2003-NRC-LSRO-S1
NC.TQ-WB.ZZ-031 0(Z)
OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: 215004 Source Range Monitor TASK: SRM/IRM Rod Block Bypassing during refueling operations IAW HC.OP-SO.SE-0001 Section 5.4. Perform independent verification of installed jumpers.
STEP STEP COMMENTS
- NO. (*Denotes a Critical Step) STANDARD EVAL (Required for
(#Denotes a Sequential Step) S/U UNSAT evaluation) 5.4.5 INSTALL a jumper in Panel 10C636 from Examiner Cue: "The l&C technician has AA35 to AA36. completed step 5.4.5" INITIAL Attachment 1.
- 5.4.6 PERFORM an independent verification of Operator proceeds to panel 10C636, opens the installed jumper the Cabinet door and locates terminal strip from Step 5.4.5. AA.
INITIAL Attachment 1. Operator locates terminals AA-35 and AA-36.
Examiner Cue: What do you expect to see?
Operator states a wire jumper should be installed between terminals AA-35 and AA-36.
Examiner Cue: A jumper is installed on the terminals indicated.
Operator initials Attachment 1 as independent verifier.
Nuclear Common Page 4 REV: 0 II 1 , I' 1i 1
NC.TQ-WB.ZZ-031 0(Z)
OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: 215004 Source Range Monitor TASK: SRM/IRM Rod Block Bypassing during refueling operations IAW HC.OP-SO.SE-0001 Section 5.4. Perform independent verification of installed jumpers.
STEP STEP COMMENTS
- NO. (*Denotes a Critical Step) STANDARD EVAL (Required for
(#Denotes a Sequential Step) SIU UNSAT evaluation)
Operator notifies Control Room that independent verification is complete.
STOP TIME: Terminating Cue: This JPM is complete.
Nuclear Common Page 5 REV.: 0 2003-NRC-LSRO-S1
JOB PERFORMANCE MEASURE INITIAL CONDITIONS:
- You are the Refueling SRO.
- The plant is in Operational Condition 5.
- All fuel has been moved to the Fuel Pool.
INITIATING CUE: Perform the Independent Verification requirements of steps 5.4.4 and 5.4.6 following I&C jumper installation IAW HC.OP-SO.SE-0001.
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ALL C7-VE J\---E- -.-.ANGES MUST BE ATTACHED TOR 7 _LD USE HC.OP-SO.SE-00 I (Q) 5.3.7 To bypass (trip disable) an OPRM, PERFORM the following:
A. PLACE OPRM MANUAL BYPASS/AUTO/OPRM MANUAL ENABLED Switch (S4) to the OPRM MANUAL BYPASS position. (1 0C608)
B. OBSERVE Annunciator Window Box C3-F3 -
TRIP BYP/INOP/TRBL is illuminated.
C. WHEN OPRM MANUAL BYPASS is not required, PLACE MANUAL BYPASS/AUTO/OPRM MANUAL ENABLED Switch (S4) to the AUTO position. (I 0C608)
D. OBSERVE Annunciator Window Box C3-F3 -
TRIP BYP/INOPITRBL is extinguished.
5.4 SRM/IRM Rod Block Bypassing during Refueling Operations.
NOTE 5.4 A. All steps in this Section are to be completed in sequence.
B. Installation and removal of jumpers should be performed by a qualified l&C Technician.
5.4.1 ENSURE all prerequisites are satisfied lAW Section 2.4.
5.4.2 LOG bypassing of SRM/IRM Control Rod Blocks in the Tech Spec Action Statement Log.
INSTALL a jumper in Panel 10C635 from DDl9 to DD20.
5.4.3 INITIAL Attachment 1. 4 5.4.4 PERFORM an independent verification of the installed jumper from Step 5.4.3.
INITIAL Attachment 1.
Hope Creek Page 17 of 20 Re%,. I 0
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FELD USE 0O30 108 l-C.OP-SO.SE-000 1(Q) 5.4.5 INSTALL a jumper in Panel I 0C636 from AA35 to AA36.
INITIAL Attachment 1.
5.4.6 PERFORM an independent verification of the installed jumper from Step 5.4.5.
INITIAL Attachment 1.
5.4.7 SRM/IRM Rod Blocks are now bypassed. Control Rod withdrawal should be permitted.
5.4.8 WHEN the SRM/IRM refueling Rod Block bypass is no longer desired.
REMOVE the jumper in Panel 10C635 from DDI9 to DD20.
INITIAL Attachment 1.
5.4.9 PERFORM an independent verification of the removed jumper from Step 5.4.8.
INITIAL Attachment 1.
5.4.10 REMOVE the jumper in Panel I 0C63 6 from AA35 to AA36.
INITIAL Attachment 1.
5.4.11 PERFORM an independent verification of the removed jumper from step 5.4.10.
INITIAL Attachment 1.
5.4.12 VERIFY SRM/IRM rod blocks are functioning AND CLEAR the action statement log.
Hope Creek Page 18 of 20 Rev. I0
T MUST BE ATTACHED FOR FIELD USE AL_ ACTIVE QN- HE-SPOT CHANGES 20030309 HC.OP-SO.SE-0001 (Q)
ATTACHMENT I (Page 1 of 1)
Installation and Removal of Jumpers for SRM/IRM Rod Blocks STEP NOMENCLATURE PERFORMER VERIFIER 5.4.3 & JUMPER INSTALLED PANEL I0C635 5.4.4 DD] 9 TO DD20 jI&C 5.4.5 & JUMPER INSTALLED PANEL 10C636 5.4.6 AA35 TO AA36 I&C 5.4.8 & JUMPER REMOVED PANEL 10C635 5.4.9 DD19 TO DD20 I&C 5.4.10 & JUMPER REMOVED PANEL 10C636 5.4.1 1 AA35 TO AA36 ]&C I-lopec Creek Page 20 of 20 Rev. I10
NC.TQ-WB.ZZ-0310(Z)
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: HOPE CREEK SYSTEM: 204000 RWCU System TASK: Align RWCU for Alternate Decay Heat Removal IAW Section F of HC.OP-AB.RPV-0009 TASK NUMBER: 295021AA104 JPM NUMBER: 2003-NRC-LSRO-S2 ALTERNATE PATH: =
K/A NUMBER: 295021 AA1.04 APPLICABILITY: IMPORTANCE FACTOR: 3.7 3.7 EO = RO = SRO L LSRO 3 RO SRO EVALUATION SETTING/METHOD: REACTOR BUILDING - SIMULATE
REFERENCES:
HC.OP-AB.RPV-0009(Q) Rev 0; HC.OP-SO.BG-0001(Q) Rev 33 TOOLS AND EQUIPMENT: Survey map of Room 4506 VALIDATED JPM COMPLETION TIME: 20 min.
TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A min.
APPROVED:
N/A BARGAINING UNIT CAL&
TRAINING SUPERVISOR OP RkTI)ON MANAGER REPRESENTATIVE K-b-or(pesidnee CAUTION: No plant equipment shall be operated during the performance of a JPM without the following:
- 1. Permission from the OS or Unit CRS;
- 2. Direct oversight by a qualified individual (determined by the individual granting permission based on plant conditions).
- 3. Verification of the "as left" condition by a qualified individual.
ACTUAL JPM COMPLETION TIME: min.
ACTUAL TIME CRITICAL COMPLETION TIME: N/A min.
JPM PERFORMED BY: GRADE: F2 SAT Cl UNSAT REASON, IF UNSATISFACTORY:
EVALUATOR'S SIGNATURE: DATE:
Nuclear Common Page 1 Rev. 0 2003-N RC-LSRO-S2
NC.TQ-WB.ZZ-031 0(Z)
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:
DATE:
SYSTEM: 204000 RWCU System TASK: Align RWCU for Alternate Decay Heat Removal IAW Section F of HC.OP-AB.RPV-0009 TASK NUMBER: 295021AA1.04 INITIAL CONDITIONS:
- The plant is in Operational Condition 4
- Reactor Recirc Pumps are not available
- RWCU is in service in a normal line-up
- Reactor coolant temperature is rising slowly
- RWCU is required for Alternate Decay Heat Removal lAW Condition F of HC.OP-AB.RPV-0009 INITIATING CUE:
Perform the required actions for Condition F of HC.OP-AB.RPV-0009.
Successful Completion Criteria:
- 1. All critical steps completed.
- 2. All sequential steps completed in order.
- 3. All time-critical steps completed within allotted time.
- 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made (and NRC concurrence is obtained).
Nuclear Common Page 2 Rev. 0 2003-NRC-LSRO-S2
NC.TQ-WB.ZZ-031 0(Z)
OPERATOR TRAINING PROGRAM NAME: . . .
JOB PERFORMANCE MEASURE DATE:
SYSTEM: 204000 RWCU System TASK: 295021AA1.04 Align RWCU for Alternate Decay Heat Removal lAW Section F of HC.OP-AB.RPV-0009 STEP STEP COMMENTS
- NO. (*Denotes a Critical Step) STANDARD EVAL (Required for
(#Denotes a Sequential Step) S/U UNSAT l______ _ llevaluation)
Operator obtains procedure HCOP- Operator obtains the correct procedure.
AB.RPV-0009.
Examiner Note: Once operator locates correct procedure, provide copy of HC.OP-AB.RPV-0009 procedure to operator for markup as necessary.
Operator reviews AB-RPV-0009 List of Operator determines Section F of HC.OP-Conditions. AB.RPV-0009 is applicable.
Operator determines beginning step of the Operator determines correct beginning step procedure to be F.1 F. RWCU is required for Alternate Decay Operator reads steps F.1, F.2, and F.3.
Heat Removal F.1 Ensure RWCU is in service Operator verifies RWCU is in service from Cue sheet.
Examiner Note:
Initialing steps is not critical.
Nuclear Common Page 3 REV.: 0 2003-NRC-LSRO-S2
NC.TQ-WB.ZZ-031 0(Z)
OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: 204000 RWCU System TASK: 295021AA1.04 Align RWCU for Alternate Decay Heat Removal IAW Section F of HC.OP-AB.RPV-0009 STEP STEP
-V COMMENTS
(*Denotes a Critical Step) STANDARD EVAL (Required for
(#Denotes a Sequential Step) SIU UNSAT evaluation) a I v- I_ _.__
_ I F.2 FULLY OPEN ED-V035. Operator determines valve location from page 10 of HC.OP-AB.RPV-0009.
Operator enters Reactor Building and locates ED-V035 in room 4504E (145 ft elev. Corridor outside RWCU Regen &
Non-Regen HX Room along wall)
- Operator simulates opening ED-V035 fully START TIME by rotating the valve handle Clock-Wise (as viewed from the corridor) until the pointer shows 100 percent open.
Examiner Cue: The valve operator indicated has been rotated in the direction indicated and has come to the position indicated.
F.3 If necessary, THEN Bypass the Operator asks if Bypassing the Regenerative heat exchanger to maximize Regenerative Heat Exchanger is decay heat removal. necessary.
Examiner Cue: Ten minutes has passed.
RPV temperatures are still increasing.
Nuclear Common Page 4 REV:- 0 2003-NRC-LSRO-S2
NC.TQ-WB.ZZ-031 0(Z)
OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: 204000 RWCU System TASK: 295021AA1 .04 Align RWCU for Alternate Decay Heat Removal IAW Section F of HC.OP-AB.RPV-0009 STEP STEP COMMENTS
- NO. (*Denotes a Critical Step) STANDARD EVAL (Required for
(#Denotes a Sequential Step) SU UNSAT l_ l evaluation)
Operator determines Bypassing the Regenerative Heat Exchanger is necessary.
Operator obtains procedure HC.OP- Operator obtains the correct procedure.
SO.BG-0001.
Examiner Note: Once operator locates correct procedure, provide copy of HC.OP-SO.BG-0001 procedure to operator for markup as necessary.
Operator reviews precautions and Operator reviews precautions and limitations. limitations.
Examiner Cue: If excessive time is taken reviewing precautions and limitations, inform operator that all are satisfied.
5.9 Bypassing the Regenerative Heat Operator determines correct beginning step Exchangers to be 5.9.1 Nuclear Common Page 5 REV.: 0 2003-NRC-LSRO-S2
NC.TQ-WB.ZZ-031 0(Z)
OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: 204000 RWCU System TASK: 295021AA1.04 Align RWCU for Alternate Decay Heat Removal IAW Section F of HC.OP-AB.RPV-0009 STEP STEP COMMENTS
- NO. (*Denotes a Critical Step) STANDARD EVAL (Required for
(#Denotes a Sequential Step) SU UNSAT
___ l__ll __l evaluation) 5.9.1 ENSURE all prerequisites of Section 2.9 are Operator asks for permission to open the satisfied. Regen HX Bypass line.
Examiner Cue: OS/CRS permission has been obtained to open the Regen Hx bypass line. Reactor Coolant temperature is less than 200 degrees F.
If Operator asks if Full or Partial Bypass is required, Cue: Full bypass.
5.9.2 IF bypass of the Regenerative Heat Examiner Note: The following valves are Exchangers is required, located inside the Regen & Non-Regen HX THEN PERFORM the following: room, which is a high radiation, contaminated area.
Once the operator determines the following valves are inside the RWCU HX Room, provide the operator with room map.
Valve 1BG-V233 is visible through the viewing window.
Examiner Cue: Simulate the following steps from outside the HX Room.
Nuclear Common Page 6 REV.: 0 2003-NRC-1 SRC)-S2
NC.TQ-WB.ZZ-031 0(Z)
OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: 204000 RWCU System TASK: 295021AA1.04 Align RWCU for Alternate Decay Heat Removal IAW Section F of HC.OP-AB.RPV-0009 STEP STEP COMMENTS
- NO. (*Denotes a Critical Step) STANDARD
(#Denotes a Sequential Step) UNSAT 5.9.2.A UNLOCK AND OPEN V231, Bypass Valve. Operator simulates removal of locking device and rotates V231 handwheel in the Counter-Clock-Wise direction until the handwheel stops in the full open position.
Examiner Cue: The valve stated is in the position stated.
- 5.9.2.B UNLOCK AND OPEN V233, Bypass Valve. Operator simulates removal of locking device and rotates V233 handwheel in the Counter-Clock-Wise direction until the handwheel stops in the full open position.
Examiner Cue: The valve stated is in the position stated.
- 5.9.2.C CLOSE V230, Hx Outlet Valve. Operator simulates rotating the V230 handwheel in the Clock-Wise direction until the handwheel stops in the full closed position.
Examiner Cue: The valve stated is in the position stated.
Nuclear Common Page 7 REV. 0 2003-NRC-LSRO-S2
NC.TQ-WB.ZZ-031 0(Z)
OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: 204000 RWCU System TASK: 295021AA1.04 Align RWCU for Alternate Decay Heat Removal IAW Section F of HC.OP-AB.RPV-0009 STEP STEP COMMENTS
- NO. (*Denotes a Critical Step) STANDARD EVAL (Required for
(#Denotes a Sequential Step) S/U UNSAT l_ l lllll evaluation) 5.9.2.D ADJUST system flowrate (for 2 pump Operator should request the Control Room operation) to approx. 300- 320 gpm. to adjust flow lAW 5.9.2.D (flow rate may change due to the Examiner Cue: The Control Room crew difference in system resistance due to will complete this step.
heat exchanger being removed from service. Flow adjustments should be made using HV-F042.)
STOP TIME Examiner Cue: This JPM is complete.
Nuclear Common Page 8 REV.: 0 2003-NRC-LSRO-S2
JOB PERFORMANCE MEASURE INITIAL CONDITIONS:
- The plant is in Operational Condition 4
- Reactor Recirc Pumps are not available
- RWCU is in service in a normal line-up
- Reactor coolant temperature is rising slowly
- RWCU is required for Alternate Decay Heat Removal IAW Condition F of HC.OP-AB.RPV-0009 INITIATING CUE:
Perform the required actions for Condition F of HC.OP-AB.RPV-0009.
Nuclear Common Page 9
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ALL) ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only Page I of 1 PSEG NUCLEAR L.L.C.
HOPE CREEK GENERATING STATION HC.OP-SO.BG-0001(Q) - Rev. 33 REACTOR WATER CLEANUP SYSTEM OPERATION USE CATEGORY: II A. Biennial Review performed Yes No V N/A B. Change Package(s) and Affected Document Number(s) incorporated into this revision.
- OTSC No(s) or None REVISION
SUMMARY
I Based on request made under Order 80037826 (T/S Amendment 140) prerequisite 2.8.3, and Notes 5.2.3.1 and 5.2.4.F were revised to change reference from T/S 3/4.4.4 to a reference to UFSAR section 5.2.3.2.2.2 (where the T/S direction was moved to). Editorial Change lAW NC.DM-AP.ZZ-0001(Q) allowances.
IMPLEMENTATION REQUIREMENTS Effective date l A Implementation of T/S Amendment 140 APPROVED: _- -- A,e, ,, _
Manager - Hope Ok Operations Date
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122-PSEG Internal Use Only HC.OP-SOBG-0001(Q)
REACTOR WATER CLEANUP SYSTEM OPERATION TABLE OF CONTENTS SECTION TITLE PAGE 1.0 PURPOSE .............................. ........................................................ 2 2................
2.0 PREREQUISITES .......... 2 3.0 PRECAUTIONS AND LIMITATIONS ........................ .. 6 4.0 EQUIPMENT REQUIRED ........................... . 10 5.0 PROCEDURE .................................................................... ................................ 11 5.1 System Fill and Vent ............................... ,.,.,.11 5.2 Placing RWCU In-Service ....................... 15 5.3 Warm-up of RWCU Recirc Pumps . 20 5.4 Blowdown Operation .. 28 5.5 Hot Standby Operation Without Reactor Recirc Flow -
Maximizing Bottom Head Drain Flow ............................ ,.,.,... 31 5.6 Blowdown During Refueling Operation .. 33 5.7 Reducing Flow through or Bypassing the Filter/Demins ......................... 35 5.8 Removing RWCU Pump/System from Service .37 5.9 Bypassing the Regenerative Heat Exchanger .. 40 5.10 Placing the Regenerative Heat Exchangers In-Service ............................ 44 5.11 Flushing A RWCU Pump prior to Maintenance ................................ 45
6.0 REFERENCES
..................0.......N............................................................................... 48 ATTACHMENTS Attachment I - Maximum RWCU Return To Feedwater Flow -2 Pump Operation .50 Attachment 2 - Maximum RWCU Return To Feedwater Flow - I Pump Operation .51 Attachment 3 - Computer Point A196 Substitute Value Instructions .52 Hope Creek Page 1 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.BG-0001(Q)
REACTOR WATER CLEANUP SYSTEM OPERATION 1.0 PURPOSE This procedure outlines the steps necessary for System Fill and Vent, Warm-up, Startup, Shutdown, Blowdown, Hot Standby, and Refueling Operation of the Reactor Water Cleanup (RWCU) System.
2.0 PREREQUISITES 2.1 System Fill and Vent 2.1.1 RWCU System Valves are aligned lAW applicable SAP/WCM operational mode.
2.1.2 RWCU Major Component Electrical lineup is complete 1AW applicable SAP/WCM operational mode.
2.1.3 BB-HV-F023A, Reactor Recirc Pumps Suction Valve, and/or BB-HV-F023B, Reactor Recirc Pumps Suction Valve, are open.
2.1.4 Radiation Protection should be contacted prior to performing venting and/or draining in this procedure. The individual(s) performing the venting and/or draining should obtain instructions AND approval from the Radiation Protection Shift Technician OR Radiation Protection Supervisor.
2.2 Placing RWCU System in Service 2.2.1 RWCU System is filled AND vented IAW Section 5.1 of this procedure.
2.2.2 An idle RWCU Recirc pump shall be warmed up IAW Section 5.3, IF the temperature difference between the pump casing AND Reactor Vessel water is > 150 0 F AND Reactor water temperature is > 212 0 F. [CD-886X]
2.2.3 RWCU System Valves are aligned IAW applicable SAP/WCM operational mode.
2.2.4 RWCU Major Component Electrical lineup is complete IAW applicable SAP!WCM operational mode.
Hope Creek Page 2 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE
.20030122 PSEG Internal Use Only HC.OP-SO.BG-0001(Q) 2.2.5 Chemistry Technician is available AND at least one RWCU Filter/Demin is ready for service X desired to place Filter/Demin in-service immediately upon placing the system in-service).
2.2.6 Reactor Auxiliaries Cooling Water (RACS) is in-service supplying water to the RWCU Heat Exchangers and Pumps.
2.2.7 Instrument Air System is in-service supplying air to air operated valves.
2.2.8 BB-HV-F023A, Reactor Recirc Pump Suction Valve, and/or BB-HV-F023B, Reactor Recirc Pump Suction Valve, are open.
2.2.9 AE-HV-F0I IA, Feedwater Inlet Valve, and/or AE-HV-FO IIB, Feedwater Inlet Valve, are open.
2.2.10 AE-HV-F074A, Feedwater Outboard Isolation Check Valve, and/or AE-HV-F074B, Feedwater Outboard Isolation Check Valve, actuator open.
2.2.11 WHEN both RWCU Pumps have been idle, THEN I&C should be notified to vent the delta flow transmitters FT-N041A(D), FT-N036A(D),
ANT) FT-N012A(D))
2.3 Warm-up of RWCU Reeirc Pumps 2.3.1 RWCU System Valves are aligned IAW applicable SAP/WCM operational mode (except for individual RWCU Pump(s).
2.3.2 RWCU Major Component Electrical lineup is complete IAW applicable SAP/WCM operational mode.
2.3,3 Condensate Storage and Transfer System is in-service.
2.3.4 RWCU Recirc Pump (s) oil level at "oil level' mark AND oiler cup full. -
2.3.5 Instrument Air System in-service.
2.3;6 BB-HV-F023A, Reactor Recirc Pump Suction Valve, and/or BB- HV-F02313, Reactor Recirc Pump Suction Valve, are open.
Hope Creek Page 3 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.BG-0001(Q) 2.3.7 Reactor Auxiliaries Cooling Water (RACS) is in-service to supply cooling water to RWCU Recirc Pumps.
2.3.8 NUMAC's ISKXR-1 1497 and ISKXR-1 1499 RWCU differential flow displays have been checked AND IF DP "WC/(MA) column Channel "A" does not agree with Channel "D" (should read 3.0 to 4.0 MA with no RWCU flow)
THEN NOTIFY I&C to fill and vent Delta flow transmitters.
2.4 Blowdown Operation 2.4.1 RWCU System is in-service 1AW Section 5.2 of this procedure.
2.4.2 At least one of the following systems is in-service:
- Radwaste Equipment Drain (Waste Collection Tanks)
- Main Condenser 2.5 Hot Standby Operation Without Reactor Reeirc Flow - Maximizing Bottom Head Drain Flow 2.5.1 RWCU System is in-service lAW Section 5.2 of this procedure.
2,5.2 Reactor is in Hot Standby condition, with both Recirc Pumps out of service.
2.6 Blowdown During Refueling Operation 2.6.1 RWCU System is in-service IAW Section 5.2 of this procedure.
2.6.2 Reactor is shutdown for refueling.
2.6.3 At least one of the following systems is in-service:
- Radwaste Equipment Drain (Waste Collector Tanks)
- Main Condenser 2.7 Reducing Flow through or Bypassing the Filter/Demins RWCU System is in-service 1AW Section 5.2 of this procedure.
Hope Creek Page 4 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only E[C.OP-SO.BG-0001(Q) 2.8 Removing RWCU Pump/System from Service 2.8.1 RWCU System is in-service LAW Section 5.2 of this procedure.
2.8.2 Chemistry Technician is available to remove Filter Demins from service.
2.8.3 Chemistry Technician is cognizant of OR has been notified of the following:
- Sampling requirements of UFSAR section 5.2.3.2.2.2 (IF applicable)
- Required pH analysis once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, per UFSAR section 5.2.3.2.2.2, when RWCU is taken out-of-service OR flow to pH analyzer is interrupted.
2.9 Bypassing the Regenerative Heat Exchangers OS/CRS permission has been obtained to open the Regen Hx bypass line.
2.10 Placing the Regenerative Heat Exchangers in Service None 2.11 Flushing a RXVCU Pump prior to Maintenance.
2.11.1 Radwaste has been notified that pump flushing is to start.
2.11.2 RWCU Pump to be-flushed has been secured.
2.11.3 Rad Protection standing by to survey RWCU Pump.
Hope Creek Page 5 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.BG-001(Q) 3.0 PRECAUTIONS AND LIMITATIONS 3.1 Precautions 3.1.1 Improper operation of RWCU Pumps can cause cavitation, improper pressurization of idle pumps, and internal thermal shock, which can lead to premature seal failures. [CD-445D]
3.1.2 Following a trip, it is recommended to start RWCU Pump immediately, if possible, to avoid thermal stresses to piping and associated components.
An idle RWCU Recirc Pump shall be warmed up if the temperature difference between pump casing and Reactor Vessel water is > 150 0 F and Reactor water temperature is > 212'F. [CD-886X]
3.1.3 To avoid thermal stress to the Feedwater nozzles, the maximum RWCU flow should be maintained when a low flow condition exists. jCD-786DJ 3.1.4 HV-F 102, RECIRC LOOP SUCT HDR, should NOT be closed to the point where the RWCU Recirc Pump(s) start to cavitate on low suction pressure. This corresponds to approximately 135 gpm on computer point B2058 REAC BOTTOM HEAD DRAIN (Ambient conditions AND normal RPV level).
3.1.5 The rate of RWCU Pump warm-up shall NOT exceed 250 F per minute to prevent pump damage.
3.1.6 Loss of a RWCU Pump, when in two pump operation, can cause pump runout. Flow must be reduced immediately by closing HV-F044, FILTER DEMIN BYPASS, (if open)
OR throttling HV.-F042, REGEN HX RTN ISLN, UNTIL Chemistry can remove a Filter/Demin from service.
3.1.7 To prevent a containment isolation of the BG-HV-F001 AND BG-HV- F004 valves while venting RWCU delta transmitters (2.2.1 1). The following guidance should be taken:
A. All the transmitters in one channel should be vented first before venting the transmitters in the other channel.
AND B. The associated breaker should be open for the channel being venting IAW Tech Spec 3.6.3 prior to venting.
Hope Creek Page 6 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.BOOO1 (Q) 3.1.8 Chemistry should isolate CAVS System prior to removing RWCU from service AND when securing the RWCU System for leak isolation.
3.1.9 The RWCU System contains potentially radioactive contaminated fluid.
3.1.10 A gross failure of a differential pressure transmitter ISKXR-11497 OR 1SKXR-11499 (1OC609, 10C611),
does NOT cause an automatic RWCU isolation for the associated inbd/otbd isol vlv (transmitter input > 21 ma OR < l ma as sensed by the monitor). In this condition, a RWCU System differential flow between influent AND effluent outside Containment > 56 gpm for 45 seconds (time delay) isolation function will NOT occur if a high flow condition exists. Tech Spec Action Statement 3.3.2, Isolation Actuation Instrumentation, shall be entered. (The same logic is programmed into the monitors for the case of a failed thermocouple unit, i.e.., NO isolation occurs, AND is intended to minimize isolations due to sensor failures).
3.1.11 Increasing blowdown flow beyond 215 gpm (CRIDS A2947) will cause the delta flow transmitters FT-NO12A(D) differential pressure range to be exceeded (output clamped at a maximum value of 215 gpm, up arrows indicated at the NUMAC).
While NO additional increase in blowdown flow will be indicated in gpm, ma indication will increase until a gross failure occurs (reference Precaution 3.1. 1 0), AND feedwater return flow will continue to indicate a decrease.
3.1.12 Unless a substitute value of 0.0 is installed for Process Computer point A196 RWCU FLOW (WCU), the Process Computer heat balance will use the last "good" value sensed AND calculate a negative value for power loss in the Cleanup Demineralizer System (QCU), whenever the system is removed from service while at power.
3.1.13 Following a RWCU automatic isolation, OR manually isolating sections of the RWCU System for >1 hr, "Cleanup Filter Demin Inlet" sample must be isolated by Chemistry to maintain RWCU System pressure AND unnecessary venting of RWCU A flow transmitters. {PR 9708031031 Hope Creek Page 7 of 53 Rev. 33 M
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only . C.OP-SO.BG-0001(Q) 3.2 Limitations 3.2,1 Dumping unfiltered water into the Main Condenser should be avoided unless absolutely necessary as this can introduce water-borne radioactive contaminants into Condensate System.
3.2.2 IF the valve OR electrical lineup CANNOT be completed as required, THEN the OS/CRS will determine whether the system should NOT be placed in-service OR standby, as required.
3.2.3 During blowdown operations, HV-F034, RWCU Discharge to Main Condenser, AND HV-F035, RWCU Discharge Drain to Waste Collector Tank, should NOT be simultaneously opened WHEN Condenser is under vacuum. Main Condenser vacuum can be lost through Radwaste piping.
3.2.4 Before opening HV-F034, RWCU to the Main Condenser, I-RC-V005, Three-way Diverting Valve, from Sample Panel 10C251 to the Condenser OR CRW System, (located on the 132' EL in the Reactor Bldg. outside of Room 4402) should be turned 90° manually to the closed position to divert flow to the CRW System. This evolution is performed to reduce the risk of loosing Main Condenser vacuum during sample sink operation.
3.2.5 Non-Regenerative HX maximum outlet temperature is limited to 130WF for Hot Standby OR Startup conditions. However, for normal operation the temperature is limited to 1200F.
3.2.6 Non-Regenerative Heat Exchanger maximum coolant (RACS) outlet temperature is limited to 180'F for Hot Standby, Startup, OR Blowdown conditions.
3.2.7 RWCU Pump Cooling Water (RACS) inlet temperature must NOT exceed I110W.
3.2.8 WHEN in Hot Standby Operation without Recire Flow -
Maximizing Bottom Head Drain Flow, THEN Cleanup System Outlet Temp must be maintained
< 434WF to prevent thermal shock to the feedwater nozzles.
[CD-389E]
3.2.9 During Normal operation the Filter Demins will both be in-service at approximately 148 to 150 gpm each, except as necessary to Backwash/Precoat the Filter Deemins.
Hope Creek Page 8 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.B-0001(Q) 3.2.10 WHEN it becomes necessary to operate the RWCU System with I pump operation, THEN the system flow should be maintained IAW direction in Section 5.2 for single pump operation, 3.2.11 The Regen Heat Exchanger bypass shall only be used during Cold Shutdown, OR Refueling Modes OR Start-up Mode (Condition 2) to maintain temperature < 2000 F. During Normal operation, the bypass valves will be locked closed.
3.2.12 DO NOT exceed 200 gpm of blowdown flow (CRIDS A2947) unless operating under emergency conditions. (Administrative limit based on conditions described in 3.1.11) 3.2.13 Manually operated gate valves 1-AE-V188 AND I-E-V189, on the RWCU Return Headers to the A AND B Feedwater Loops, when closed, allows for continued operation of the RWCU System with return flow to either the A OR B Feedwater Headers isolated. These alignments shall ONLY be used during outages in support of LLRT testing.
3.3 Interlocks 3.3.1 The RWCU System will be automatically isolated with the closure of HV-FO01, Inboard Isolation Valve, AND HV-F004, Outboard Isolation Valve, under any of the following conditions:
A. Reactor water level < -38 inches (Level 2)
B. Non-Regeneritive Heat Exchanger outlet temperature
> 1400 F (HV-F004 only)
C. Plant Leak Detection System actuation upon RWCU Pipe Chase Room 4402 (>1600 F)
OR RWCU Pipe Chase Room 4505 (>135 0F)
OR RWCU Pump Rooms AND Heat Exchangers Rooms (>140'F)
D. Standby Liquid Control System actuation:
- System A isolates HV-FOO1
- System B isolates HV-F004 Continued next page Hope Creek Page 9 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.BG-0001(Q)
3.3.1 (continued)
E. Nuclear Steam Supply Shutoff System Isolation F. RWCU System differential flow between influent AND effluent outside Containment> 56 gpm for 45 seconds (time delay).
G. RRCS Standby Liquid Control actuation:
Channel A or B RRCS Standby Liquid Control actuation isolates both the HV-F001 and HV-F004.
3.3.2 The following conditions will trip the RWCU Recirculation Pumps:
A. Pump suction flow < 70 gpm (after pump start time delay of 15 minutes). This trip will only occur if the common pump suction flowpath is < 70 gpm.
B. HV-FOOI, Containment Inboard Isolation Valve, AND HV-F004, Containment Inboard Isolation Valve, NOT fully opened (time delayed 11 sec for F/D to go into Hold).
3.3.3 HV-F033 valve auto closes on upstream pressure < 5 psig OR downstream pressure > 140 psig.
4.0 EQUIPMENT REQUIRED
- Pyrometer - 0 to 600'F or equivalent
- Magnetic Thermocouple (Ensure compatibility between probe and box)
Hlope Creek Page 10 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-S4).BG-0001(Q)
NOTE 5.0 All operations are performed from Panel 10C651C unless otherwik;e noted.
5.0 PROCEDURE 5.1 System Fill and Vent 5.1.1 ENSURE all prerequisites of Section 2.1 are satisfied.
A. IF the system is aligned for service or inservice JAW Section 5.2 THEN GO TO Step 5.1.4.
B. IF the system is removed from service AND is not isolated 1AW Section 5.8, THEN GO TO Step 5.1.3.
C. IF the system is removed from service and is isolated JAW Section 5.8, THEN GO TO Step 5.1.2 5.1.2 ESTABLISH a make-up water supply path from the Condensate Storage and Transfer as follows:
A. ENSURE BG-HV-FOO and BG-HV-F004 are CLOSED.
B. CLOSE 1-BG-V024(1-BG-V030), A(B) RWCU Recirc Pmp Csg Drn Vlv.
C. OPEN the following valves:
- 1. 1-BG-V022 (1-BG-V028), A(B) RWCU Recire Pmp Csg Drn Vlv.
- 2. 1-BG-V023 (1-BG-V029), A(IB) RWCU Recirc Pmp Csg Drn Vlv.
Continued next page Hope Creek Page 11 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.BG-OO01(Q) 5.1.2 (continued)
NOTE 5.1.2.D The fill rate of the Pump Seal Cavity should NOT exceed 2.5 gpm.
D. THROTTLE OPEN l-AP-V142(l-AP-V143), Condensate and Storage Transfer to RWCU Recirc Pmp A(B) Seal Fill Is n Vlv.
5.1.3 ESTABLISH the vent and fill flow path as follows:
A. OPEN 1-BG-V004, A RWCU Recirc Pmp Suction Vlv AND 1-BG-V008, B RWCU Recirc Pmp Suction Vlv.
B. OPEN 1-BG-V200, A RWCU Recire Pmp Dsch Byp Vlv AND 1-BG-V210, B RWCU Recirc Pmp Dsch Byp Vlv.
C. THROTTLE OPEN HV-F044, Fltr Demin Byp Vlv as necessary to allow make-up water flow to the down stream piping while venting.
NOTE 5.1.4 The action verb VENT is defined as "To open a vent valve until a solid stream of water Issues, then return the vent valve to the closed position."
5.1.4 VENT using the following valves until a solid stream of water issues as seen at FG-1 077(1076), A(B) RWCU Recirc Pump A(B) Vent sight glass (local):
A. 1-BG-V026, RWCU Recire Pmp A Seal Flush Vent Vlv, AND 1-BG-V027, RWCU Recirc Prmp A Seal Flush Vent Vlv B. 1-B G-V073, RWCU Recirc Pmp B Seal Flush Vent Vlv, AND I -BG-V074, RWCU Recirc Pmp B Seal Flush Vent Vlv Hope Creek Page 12 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030 122 PSEG Internal Use Only HC.OP-SO.BG-0001(Q) 5.1.5 VENT using the following valves until piping is vented (Local):
A. 1-BG-V173, RWCU Pmp Suet Hdr Vent, (RM 4505)
AND 1-BG-V174, RWCU Pmp Suet Hdr Vent, (RM 4504D).
B. l-13G-V032, RHX Tube Side Inlet Hdr Vent, (RM 4508B)
AND 1-BG-V033, RHX Tube Side Inlet Hdr Vent (RM 45063).,
C. 1-BG-V037, -RHXBE207 Tube Side Vent, (RM 4506B)
AND l-BG-V038, RHX BE207 Tube Side Vent, (RM 4506B).
D. I-BG-V041, RHX AE207 Tube Side Vent, (RM 4506B)
AND I -BG-V042, RHX AE207 Tube Side Vent, (RM 4506B).
E. 1-BG-V049, Non-RHX AE208 Tube Side Vent, (RM 4506B)
AND l-BG-V050, Non-RHX AE208 Tube Side Vent (RM 4506B).
F. 1-BG-V054, Non-RIX Outlet Hdr Vent, (RMd 4506C)
AND 1-BG-V055, Non-RHX Outlet Hdr Vent, (RM 4506C).
G. 1-BG-VD57, RHX AE207 Shell Side Vent, (RM 4506C)
AND 1-BG-VO58, RHX AE207 Shell Side Vent, (RM 4506C).
H. l-BG-V062, RHX BE207 Shell Side Vent, (RM 4506B)
AND l-BG-V063, RHX BE207 Shell Side Vent, (RM 4506B).
NOTE 6.1.5.1 Additional throttling of HV-F044, Fltr Demin Byp Vlv may be required to ensure adequate make-up water flow to the down stream piping while venting.
I. 1-BG-V066, RHX Shell Side Outlet Hdr Vent, (Ri 4506A)
AND l-BG-V067, RHX Shell Side Outlet Hdr Vent, (RM 45088).
Hope Creek Page 13 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.BG-0001(Q) 5.1.6 IF opened in Step 5.1.3, THEN:
A. CLOSE 1-BG-V004, A RWCU Recirc Pmp Suction Vlv AND 1-BG-V008, B RWCU Recirc Prnp Suction Vlv.
B. CLOSE 1-BG-V200, A RWCU Recirc Pmp Dsch Byp Vlv AND 1-BG-V210, B RWCU Recirc Pmp Dsch Byp Vlv.
C. CLOSE HV-F044, Fltr Demin Byp Vlv.
5.1.7 IF Condensate Storage and Transfer Tank was used to fill in Step 5.1.2, RESTORE the system as follows:
A. CLOSE the following valves:
- 1. 1-AP-V142(1-AP-V143), Condensate and Storage Transfer to RWCU Recirc Pmp A(B)
Seal Fill IsIn Vlv.
- 2. l-BG-V022(l-BG-V028), A(B) RWCU Recirc Pmp Csg Drn Vlv.
- 3. l-BG-V023(l-BG-V029), A(B) RWCU Recirc Pmp Csg Drn VIv.
B. OPEN I-BG-V024(1-BG-V030), A(B)RWCURecirc Pmp Csg Dln Vlv.
5.1.8 OPEN BG-HV-F001 and BG-HV-F004.
Hope Creek Page 14 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.0P-S0.BG-90001(Q)
NOTE 5.2 A. CRIDS points B2081 and A2856, OR NUMAC Drawers 1SKXR-1 1497 OR 1SKXR-1 1499 (10C609, 10C611) may be used to obtain temperature compensated flows.
B. In the event HV-F044, FLTR DEMIN BYPASS, is unavailable or inoperable, the operator may use HV-F104, CLEANUP BYPASS, to throttle open/closed in order to place RWCU Pumps & Demins in-service, CAUTION 5.2 A. Following a trip, it is recommended to start RWCU Pump immediately, If possible, to avoid thermal stresses to piping AND associated components.
B. To avoid thermal stress to the Feedwater nozzles, the maximum RWCU flow should be maintained when a low flow condition exists. [CD-786D]
5.2 Placing RWCU System in Service [CD-937B]
5.2.1 ENSURE all prerequisites of Section 2.2 are satisfied.
NOTE 5.2.2 Reactor Engineering may be contacted as necessary for assistance with the restoration of the Restore to Scan function.
5.2.2 IF the Process Computer heat balance (OD-3d) value for power loss in the Cleanup Demineralizer System (QCU), had a substitute value of 0.0 inserted for Computer Point Al 96 RWCU FLOW (WCU),
when the system was removed from service, THEN RETURN Computer Point A196 to AUTOMATIC using
- Attachment 3 - Computer Point Al 96 Substitute Value Instructions, Hope Creek Page 15 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.BG-0001(Q) 5.2.3 IF in two pump operation, THEN PERFORM the following:
A. CLOSE HV-F044, FLTR DEMIN BYPASS, by pressing the DECREASE push-button until CLOSE lamp is illuminated.
CAUTION 5.2.3.B time delay of RWCU Recirc Pumps trip on low flow < 70 gpm (after pump start flowpath is 15 minutes). This trip will only occur If the common pump suction
<70 gpm.
B. START A(B)P221, A(B) RWCU PUMP.
C. THROTTLE OPEN HV-F044 FLTR DEMIN BYPASS UNTIL Computer point A2856 RWCU OUTLET FLOW indicates approximately 140 to 160 gpm.
CAUTION 5.2.3.D pump runout.
Loss of a RWCU Pump, when in two-pump operation, can cause BYPASS, Flow must be reduced immediately by closing HV-1F044, FILTER DEMINcan remove (if open) R throttling HV-F042, REGEN HX RTN ISLN, until Chemistry a Fliter/Demin from service.
1). START B(A)P221, B(A) RWCU PUNP.
E. THROTTLE OPEN HV-F044, FLTR DEMIN BYPASS, UNTIL Computer Point A2856 RWCU OUTLET FLOW indicates approximately 300 to 320 gpnm F. WHEN the first Filter/Demin is to be placed in-service, THEN CONTACT Chemistry Department to place A(B)
Filter/Demin in-service AND slowly raise flow.
Continued next page Page 16 of 53 Rev. 33 Hope Creek
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.BG-0001(Q) 5.2.3 (continued)
G. MONITOR Computer Point A2856 RWCU OUTLET FLOW AND MAINTAIN flow at or below maximum RWCU return to feedwater flow value determined using Attachment I by throttling closed on HV-F044, FLTR DEMIN BYPASS, UNTIL Computer Point B2951 (B2952) FILTER DEMIN A(B) EFL FLOW indicates a maximum of 150 gpm AND has stabilized. IPR 9805150861 H. WHEN the second Filter/Demin is to be placed in-service, THEN PERFORM the following:
- 1. REQUEST Chemistry Department to place B(A) Filter/Demin in-service AND slowly raise flow.
- 2. MONITOR Computer Point A2856 RWCU OUTLET FLOW AND MAINTAIN flow at or below maximum RWCU return to feedwater flow value determined using Attachment 1 by throttling closed on HV-F044 FLTR DEMIN BYPASS until Computer Point B2952 (B2951) FILTER DEMIN B(A) EFL FLOW indicates a maximum of 150 gpm AND has stabilized. [PR 980515086]
NOTE 5.2.3.1 Compliance with UFSAR section 5.2.3.2.2.2 is required.
I. MONITOR {he following CLEANUP FILTER DEMINERALIZERS (10C650):
- 1. - CR-R601-G33, INLET //CONDUCTIVITY,
<1.0 MMHO/cm
- 2. CR-R603(Red), DEMINERALIZER A OUT CONDUCTIVITY, < 0.1 MMHO/.cm
- 3. CR-R603(Blue), DEMINERALIZER B OUT CONDUCTIVITY, < 0.1 MMHO/cm Continued next page Hope Creek Page 17 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.BG-0001(Q) 5.2.3 (continued)
J. MONITOR the following parameters as required:
Table BG-001 Computer Point Name INST # Computer Point CLEANUP SYSTEM INLET TEMP TE-N004 A214 CLEANUP SYSTEM OUTLET TEMP TE-NO 15 A215 RWCU REGEN HX OUTLET TIIEMP TE-N006 A2945 RWCUN-REGEN HX OUTLET TEMP TE-N019 A2944 RWCU REAC SUCT FLOW FT-N036A B2081 RWCU SYSTEM OUTLET FLOW TO FT-NQ41A A2856 FDW 5.2.4 IF in single pump operation, THEN PERFORM the following:
A, CLOSE HV-F044 FLTR DEMIN BYPASS by pressing the DECREASE push-button until the CLOSE lamp is illuminated.
CAUTION 6.2.4.B RWCU Recirc Pumps trip on low flow <70 gpm (after pump start time delay of 15 minutes).
B. START AQ3)P221, A(B) RWCU PUMP.
C. THROTTLE OPEN HV-F044, FLTR DEMIN BYPASS, UNTIL Computer Point A2856 RWCU OUTLET FLOW indicates approximately 140 to 160 gpm.
D. WHEN RWCU OUTLET FLOW is between 140 and 160 gpm, THEN REQUEST Chemistry Department to place either one OR both Filter/Demin in-service AND slowly raise flow.
Continued next page Hope Creekc Page 18 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122
-PSEG Internal Use Only HC.OP-SO.BG-0001 (Q) 5.2.4 (continued)
CAUTION 5.2.4E During system operation with flow from the Reactor Bottom Head Drain ONLY, System flow should be maintained LESS THAN 135 GPM to preclude pump cavitation.
E. MONITOR Computer Point A2856 RWCU OUTLET FLOW AND MAINTAIN flow at or below maximum RWCU return to feedwater flow value determined using Attachment 2 by throttling closed on HV-F044 FLTR DEMIN BYPASS UNTIL Computer Point B295 1 (B2952) FILTER DEMIN A(B)
EFL FLOW indicates a maximum of 150 gpm and has stabilized.
NOTE 5.2.4.F Compliance with UFSAR section 5.2.3.2.2.2 is required.
F. MONITOR the following CLEANUP FILTER DEMINERALIZERS (10C650):
- 1. CR-R601-G33, INLET H/CONDUCTIVITY,
<1.0 MMHO/cm
- 2. CR-R603(Red), DEMINERALIZER A OUT CONDUCTIVITY, < 0.1 MMHO/.cm
- 3. CR-R603(Blue), DEMINERALIZER B OUT CONDUCTIVITY, < 0.1 MMHO/cm Continued.next page Hope Creek Page 19 of 53 -Rev.33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.BG-OOOI(Q) 5.2.4 continued G. MONITOR the following parameters as required:
Table BG-001 Computer Point Name INST # Computer Point CLEANUP SYSTEM INLET TEMP TEN004 A214 CLEANUP SYSTEM OUTLET TEMP TE-NO15 A2 15 RWCU REGEN HX OUTLET TEMP TE-N006 A2945 RWCU N-REGEN HX OUTLET TEMP TE-N019 A2944 RWCU` REAC SUCT FLOW FT-N036A B208 1 RWCU SYSTEM OUTLET FLOW TO FDW FT-NO4IA A2856 NOTE 5.3 A. An idle RWCU Recirc Pump shall be warmed up lAW'this procedure if temperature difference between pump casing and Reactor Vessel water is > 1507F and Reactor water temperature is > 212 0F. [CD-886X]
B. All operations are performed locally unless noted otherwise.
CAUTION 5.3 The rate of RWCU Pump warm-up shall NOT exceed 250 F per minute to prevent pump damage 5.3 Warm-up of RWCU Recire Pumps
[CD-937B, CD-445D]
5.3.1 ENSURE all prerequisites of Section 2.3 are satisfied.
Hope C~reek Page 20 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.BG-0001(Q) 5.3.2 IF fill and vent of A(B)P221, RWCU Pump, is necessary, THEN PERFORM the following:
A. ENSURE the following valves are CLOSED:
- 1. 1-BG-V004 (V008), A(B) RWCU Recirc Pmp Suction Vlv
- 2. l -BG-V006 (VO 10), A(B) RWCU Recirc Pmp Dsch Vlv
- 3. 1-BG-V200 (V2 10), A(B) RWCU Recirc Pmp Dsch Byp Vlv
- 4. 1-BG-V024 (V030), RWCU Recirc Pmp A(B) Csg Drn Vlv B. OPEN the following valves:
- 1. 1-BG-V022 (V028), A(B) RWCU Recirc Pmp Csg Drn Vlv
- 2. l -BG-V023 (V029), A(B) RWCU Recirc Pmp Csg Drn Vlv NOTE 5.3.2.C The fill rate of the Pump Seal Cavity should NOT exceed 2.5 gpm.
C. THROTTLE OPEN l-AP-V142 (V143) Cond Stor & Xfr to RWCU Recirc Pmp A(B) Seal Fill Isin Vlv.
Continued next page Hope Creek Page 21 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.BG-0001(Q) 5.3.2 (continued)
NOTE 5.3.2.D The action verb VENT is defined as "To open a vent valve until a solid stream of water issues, then return the vent valve to the closed position,"
D. VENT using the following valves UNTIL a solid stream of water issues from FG- V1077 (1076)
A(B) RWCU Recirc Pmp A(B) Vent sight glass:
- l-BG-V026 (V073), A(B) RWCU Recirc Pmp Seal Flush Vent Vlv
- 1-BG-V027 (V074), A(B) RWCU Recirc Pmp Seal Flush Vent Vlv E. CLOSE the following valves:
- 1. 1-AP-V 142 (V143), Cond Stor and Xfr to A(B)
RWCU Recire Pmp Seal Fill Isln VIv
- 2. 1-BG-V022 (V028), A(13) RWCU Recire Pmp Csg Dmn Vlv
- 3. 1-B G-V023 (V029), A(B) RWCU Recirc Pmp Csg Drn Vlv F. OPEN 1-BG-V024 (V030), RWCU Recirc Pmp A(B)
Csg Drn Vlv.
5.3.3 PERFORM the following to warm-up the first RWCU Pump:
[CD-886X, CD-937D_
A. ENSURE I--BG-V003 (1-BG-V007), A(B) RWCU Recirc Pmp Outbd Suction Vlv, is OPEN.
B. Slowly OPEN I-BG-V004 (1-BG-V008), A(B) RWCU Recirc Pmp Suction VWv.
Continued next page H~ope Creek Page 22 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.BG-0001(Q) 5.3.3 (continued)
C. WHEN fully open, THEN LOCK 1-BG-V004 (1-BG-V008),
A(B) RWCU Recirc Pmp Suction Vlv.
D. ENSURE the following valves are CLOSED: [PR 970803103]
S HV-F042 S HV-F044 HV-F104 E. IF desired, THEN INSTALL a magnetic thermocouple on RWCU Recirc Pump Casing by placing the magnetic probe on the inlet side of the pump casing approximately midway between the inlet flange and the outlet flange.
F. READ the initial temperature on RWCU Recire Pump A(B) casing using a Pyrometer OR the installed Magnetic thermocouple.
NOTE 6.3.3.G The following~steps will slowly heat up the pump casing so as NOT to thermally shock the pump. The intent of the following steps is to allow a gradual heatup without the 15 minute low flow timer initiating. Maximum heatup rate will be attained after cracking open DISCH Bypass Valve then tapers off sharply.
CAUTION 5.3.3.G RWCU Recirc Pump(s) trip on a low flow < 70 gpm if the common pump suction flowpath is < 70 gpm after pump start time delay of 15 minutes. The time should be marked AND computer point B2081 RWCU REAC SUCT FLOW should be monitored so as to establish adequate flow prior to the 16 minute timer Initiation for the first pump going into service.
G. START A(B)P22 1, A(B) RWCU Recirc Pump.
Continued next page Hope Creek Page 23 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.BG-O001(Q) 5.3.3 (continued)
H. IF RWCU diff flow isolation signals alarm for >10 see, in the following steps THEN THROTTLE back on HV-F044, HV-F104 OR 1BG-V200 (I-BG-V210), [PR 970803103]
I. WHEN A(B)P221, A(B) RWCU Recirc Pump, has operated approximately 10 seconds at a shutoff head, THEN slowly CRACK OPEN I-BG-V200 (I-BG-V210),
(- 0-4 turns) RWCU A(B) DISCH BYPASS VALVE, to pressurize system to F104 and F044. [PR9708031031 NOTE 5.3.3.J When opening HV-F044 use 10 seconds opening time initially, then 1 second intervals.
S. MONITOR Comp Point A2950 AND WHEN pressure equals Rx pressure OR local pump discharge pressure, THEN PERFORM ONE of the following until system parameters change, indicating system pressurization or flow. [PR 9708031031
- 1. Slowly THROTTLE OPEN HV-F104 OR
- 2. Slowly THROTTLE OPEN HV-F044 AND HV-F042 K. THROTTLE OPEN 1-BG'-V200 (l-BG-V210) RWCU "A" (B)
DISCH Bypass Valve and/or HV-F044 as necessary to establish a 250F/min. heat-up rate using pyrometer OR magnetic thermocouple. [PR 970803103]
L. Slowly OPEN I-BG-V006 (1-BG-VOI0), RWCU Pump A(B) Discharge Valve.
M. CLOSE 1-BG-V200 (1-BG-V210), RWCU Recirc Pump A(B) Dsch Byp Vlv.
Continued next page Hope Creek Page 24 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.B3G-0001(Q) 5.3.3 (continued)
NOTE 5.3.3.N A. If the HV-F044 is unavailable in the following step, HV-F104 may be opened to provide a flowpath.
B. RWCU outlet flow may be throttled to a reduced value in the following step in support of Startup or Shutdown flow restrictions to prevent flashing in the suction venturi as specified in HC.OP-1O.ZZ-0003(Q), and/or HC.OP-IO.ZZ-0004(Q).
N. THROTTLE OPEN HV-F044, FLTR DEMIN BYPASS, UNTIL Computer Point A2856 RWCU OUTLET FLOW indicates - 140 to 160 gpm.
- 0. IF desired to place a RWCU F/D in-service, THEN GO TO Step 5.2.4.D.
5.3.4 PERFORM the following to warm-up the second RWCU Pump:
[CD-886X]
A. ENSURE I-BG-V003 (I-BG-V007), A(B) RWCU Recirc Pmp Outbd Suction Vlv, is OPEN.
B. PERFORM one of the following:
- 1. READ the initial temperature on the RWCU Recirc Pump A(B) Casing using a Pyrometer OR by installing a magnetic thermocouple on RWCU Recirc Pump Casing by placing the magnetic probe on the inlet side of the pump casing approximately midway between the inlet flange AND the outlet flange.
- 2. USE the following equation to calculate a warm up time based on the use of the bypass valve only with NO monitoring of the pump casing (ALARA):
Rx Recirc Loop Temperature - (1 00 0F + Ambient Rm Temp) = Warm up Time I 0 0/min Continued next page Hope Creek Page 25 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SOBG-0001(Q) 5.3.4 (continued)
CAUTION 5.3.4.0 The RWCU Pump must be running to cool the shaft seal for that portion of the warm-up above 200°F at the pump.
C. Slowly OPEN l-BG-V004 (1-BG-VO08), A(B) RWCU Recirc Pmp Suction Vlv.
D. WHEN fully open, THEN LOCK 1-BG-V004 (1-BG-V008), A(B) RWCU Recirc Pmp Suction Vlv.
E. START A(B)P221, A(B) RWCU Recire Pump.
NOTE 5.3.4.F The following steps will slowly heat up the pump casing so as to NOT thermally shock the pump. Maximum heatup rate will be attained after cracking open DISCH Bypass Valve then tapers off sharply.
F. WHEN A(B)P221, A(B) RWCU Recire Pump, has run at shutoff head for approximately 10 seconds, THEN SLOWLY OPEN 1-BG-V200 (l-BG-V210),
RWCU A(B)-Disch Bypass Valve, to establish a heat up rate of less than 250 F per minute. [PR 970803103]
Continued next page Hope Creek Page 26 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.BG-001(Q) 5.3.4 (continued)
NOTE 5.3.4.G Minimum pump to RWCU inlet differential temperature should be <1 000 F to complete warm-up.
CT. WHEN casing temperature (as monitored using pyrometer OR thermocouple) is within 1000 F of Rx temperature, OR WHEN warm-up time (as calculated in step 5.3.4.B.2) is up, THEN SLOWLY OPEN l-BG-V006 (1-BG-V010),
RWCU Pump A(B) Discharge Valve, while monitoring Computer Point A2856 RWCU OUTLET FLOW AND maintaining between 300 to 320 gpm by throttling open on HV-F044, FLTR DEMIN BYPASS.
H. CLOSE 1-BG-V200 (l-BG-V210), RWCU Recirc Pmp A(B) Dsch Byp Vlv.
I. IF a first OR second Filter/Demin is to be placed in-service, THEN GO TO Step 5.23.F OR 5,2.3.H.
Hope Creek Page 27 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.BG-0001(Q)
NOTE 5.4 CRIDS points B2081 andA2856, OR NUMAC Drawers 1SKXR-11497 OR 1SKXR-11499 (10C609, 10C611) may be used to obtain temperature compensated flows.
CAUTION 5.4 Loss of a RWCU Pump, when in two pump operation, can cause pump runout.
Flow must be reduced immediately by closing HV-FO44, FILTER DEMIN BYPASS, (If open) OR throttling HV-F042, REGEN HX RTN ISLN, until Chemistry can remove a FilterlDemin from service.
5.4 Blowdown Operation 5.4.1 ENSURE all prerequisites of Section 2.4 are satisfied..
CAUTION 6.4.2 Before opening HV-F034 (RWCU to the Main Condenser), I-RC- V005, Three Way Diverting Valve, from Sample Panel 1OC251 to the Condenser or CRW System, (located on the 132' EL in the Reactor Bldg. outside of Room 4402) should be turned 90d manually to the vertical position to divert flow to the CRW System.
This evolution is performed to reduce the risk of loosing Main Condenser vacuum during sample sink operation.
5.4.2 ENSURE that 1-RC-V005, Three Way Diverting Valve, is in the VERTICAL position.
Hope Creek Page 28 of 53 Re~v. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.BG-0001(Q)
NOTE 5.4.3 This mode of operation is used to maintain Reactor water level when operating at low power levels due to CRD input AND Reactor coolant expansion during heatup.
CAUTION 6.4.3 A. Non-Regenerative Hx outlet temperature is limited to < 130'F and must be observed during blowdown due to low Regenerative Hx coolant flow.
B. Blowdown valves HV-F034 AND HV-F035 should NOT be simultaneously opened when Condenser Is under a vacuum as Main Condenser vacuum can be lost through Radwasto piping.
C. HV-F033 valve auto closes on upstream pressure < 5 psig OR on downstream pressure > 140 psig.
D. The system trips on RWCU Differential Flow > 56 gpm for 45 seconds (time delay).
E. A gross failure of a differential pressure transmitter I SKXR-11497 OR 1SKXR-11499 (IOC609, 10C611), does NOT cause an automatic RWCU isolation for the associated lnbd/otbd isol vIv (transmitter input > 21 ma OR < 1 ma as sensed by the monitor). In this condition, a RWCU System differential flow between influent AND effluent outside Containment
> 56 gpm for 45 seconds (time delay) isolation function will NOT occur If a high flow condition exists. Tech Spec Action Statement 3.3.2, Isolation Actuation Instrumentation, shall be entered. (The same logic Is programmed into the monitors for the case of a failed thermocouple unit, i.e.., NO Isolation occurs, AND is intended to minimize isolations due to sensor failures).
5.4.3 PERFORM the following to establish a flow path for blowdown:
A. IF blowdown to Main Condenser is required, THEN OPEN HV-F034, RWCU RTN TO CNDSR.
B. IF blowdown into Waste Collector Tanks is required, THEN OPEN HV-F035, RWCU TO EQPT DRN.
Hope Creek Page 29 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.BG-0001(Q) 5.4.4 OPEN HV-F033, HIC-R606 DRAIN FLOW CONTROL, by pressing INCREASE push-button until Computer Point A2947 RWCU DISCH to COND AND EQUIP DRAIN FLOW indicates desired flow.
5.4.5 CHECK that RWCU DIFFERENTIAL FLOW at 1SKXR-1 1499 AND lSKXR-1 1497 indicates < 56 gpm (1OC61 1, 10C609).
5.4.6 MONITOR A2944, RWCU N-REGEN HX OUTLET TEMP, for< 1300 F.,
5.4.7 IF increased blowdown rate is desired, THEN PRESS the INCREASE push-button for HV-F03 1, DRN FL ORF BYPASS.
5.4.8 IF NRFHX outlet temperature approaches 1330F, THEN THROTTLE closed on HV-F033 HIC-R606 DRAIN FLOW CONTROL to reduce flow rate. (This drop in flow will lower NRHX outlet temperatures.)
5.4.9 WHEN blowdown operation is complete, THEN CLOSE the HV-F03 1, DRN FL ORF BYPASS.
5.4.10 CLOSE HV-F033, HIC-R606 DRAIN FLOW CONTROL VALVE.
5.4.11 CLOSE HV-F034, RWCU RTN TO CNDSR, OR HV-F035, RWCU TO EQPT DRN.
5.4.12 IF flow to the Main Condenser is required, THEN RETURN l-RC-V005, Three Way Diverting Valve, to the horizontal position.
Hope Creek Page 30 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.BG-OOO1(Q)
NOTE 5.5 CRIDS points B2081 and A2856, OR NUMAC Drawers 1SKXR-11497 OR 1SKXR-11499 (10C609, 1OC611) may be used to obtain temperature compensated flows.
, .1 CAUTION 5.5 Loss of a RWCU Pump, when in two pump operation, can cause pump runout.
Flow must be reduced immediately by closing HV-F044, FILTER DEMIN BYPASS, (If open) OR throttling HV-F042, REGEN HX RTN ISLN, or throttling HV-Fl 04, CLEANUP :BYPASS.
5.5 Hot Standby Operation Without Reactor Recire Flow - Maximizing Bottom Head Drain Flow
-5.5.1 ENSURE all prerequisites of Section 2.5 are satisfied.
5.5.2 REMOVE both Filter Demins from service JAW Section 5.7 of this procedure, NOTE 5.5.3 A. HV-F102, RECIRC LOOP SUCT HDR, valve is throttled to maintain uniform Reactor Vessel temperature during Hot Standby.
B. Steps 5.5.3 AND 5.5,4 should be performed concurrently.
5.5.3- PERFORM the following to establish RWCU recirculation flow, bypassing Regenerative and Non-Regenerative HXs:
A. ENSURE HV-F101, SUCT FROM RPV BOT DRN, is open.
Continued next -page Hope Creeks Page 31 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.BG-OOO1(Q) 5.5.3 (continued)*
CAUTION 6.5.3.8 HV-F1 02, RECIRC LOOP SUCT HDR VALVE, should NOT be closed to the point where the RWCU Recirc Pump(s) start to cavitate on low suction pressure. This corresponds to approximately 135 gpm on computer point B2058 REAC BOTTOM HEAD DRAIN (ambient conditions AND normal RPV level).
B. THROTTLE CLOSED HV-Fl 02, RECIRC LOOP SUCT HDR, until Computer Point B2058 REAC BOTTOM HEAD DRAIN flow increases to between 115 and 125 gpm.
CAUTION 6.6.4 CLEANUP SYSTEM OUTLET TEMP must be maintained < 4340 F to prevent thermal shock to the feedwater nozzles. [CD-389E) 5.5.4 PERFORM the following to establish RWCU recirculation flow, bypassing Regenerative and Non-Regenerative HXs:
A. THROTTLE CLOSE HV-F042 REGEN HX RTN ISLN by pressing the DECREASE push-button until RWCU OUTLET FLOW (Computer Point A2856) is approximately 250 gpm.
B. THROTTLE OPEN HV-F104 CLEANUP BYPASS by pressing the INCREASE push-button until RWCU OUTLET FLOW (Computer Point A2856) is approximately 300 gpm.
C. ADJUST the positions of HV-F042 AND HV-F 104, such that RWCU OUTLET FLOW (Computer Point A2856)is approximately 300 to 320 gpm AND CLEANUP SYSTEM OTLT TEMP (Computer Point A215) is <4340 F. [CD-389E]
Continued next page Hope Creek H Page 32 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.BG-0001(Q) 5.5.4 (continued)
D. WHEN CLEANUP SYSTEM OTLT TEMP (Computer Point A215) can be maintained
- 4340 F WITH HV-F042 fully closed, THEN PERFORM the following:
- 1. CLOSE HV-F042, REGEN HX RTN ISLN. _
AND
- 2. THROTTLE HV-F104, CLEANUP BYPASS, until RWCU OUTLET FLOW (Computer Point A2856) is approximately 300 to 320 gpm.
NOTE 6.6 CRIDS points B2081 and A2856, OR NUMAC Drawers 1SKXR-11497 OR ISKXR-11499 (10C609, 10C611) may be used to obtain temperature compensated flows.
CAUTION 6.6 Loss of:a RWCU Pump, when in two pump operation, can cause pump runout.
Flow must be reduced immediately by closing HV-F044, FILTER DEMIN BYPASS, (if open) OR throttling HV-F042, REGEN HX RTN ISLN, until Chemistry can remove a Filter/Demin from service.
5.6 Blowdown During Refueling Operation 5.6.1 ENSURE all prerequisites of Section 2.6 are satisfied.
5.62 ENSURE that l-RC-VO05, Three Way Diverting Valve, is in the VERTICAL position.
Hope Creek Page 33 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.BG-0001(Q) 5.6,3 IF blowdown required during Refueling, THEN PERFORM the following:
CAUTION 6.6.3.A & B HV-F033, DRAIN FLOW CONTROL, valve auto closes on upstream pressure
< 5 psig PR on downstream pressure > 140 psig.
A. IF desired AND the Main Condenser is available, THEN OPEN HV-F034, RWCU RTN TO CNDSR.
B. IF the Main Condenser is NOT available, THlDj AFTER notifying Radwaste of pending input, OPEN HV-F035, RWCU TO EQPT DRN_
C. OPEN HV-F03 1, DRN FL ORF BYPASS.
D. THROTTLE CLOSED HV-F042, REGEN HX RTN ISLN, by pressing the DECREASE push-button AND THROTTLE OPEN HV-F033, HIC R606 DR FL COND, by pressing INCREASE push-button until Computer Point A2947 RWCU DISCH to COND AND EQUIP DRAIN FLOW indicates desired flow.
5.6.4 WHEN blowdown operation is complete, THEN THROTTLE OPEN HV-F042, REGEN HX RTN ISLN, AND THROTTLE CLOSED HV-F033, HIC R606 DR FL COND. _
5.6.5 ENSURE the following valves are closed:
- HV-F034, RWCU RTN TO CNDSR
- HV-F031, DRN FL ORF BYPASS Hope Creek Page 34 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE
-20030122 PSEG Internal Use Only HC.OP-SO.BG-0001(Q)
NOTE 6.6.6 If 1-RC-V005, Three Way Diverting Valve, is to be left in the vertical position, then SAPIWCM should be updated to show the valve in an "off-normal" OR "tagged for CRS" position.
5.6.6 IF NO additional blowdowns are anticipated, THEN RETURN 1-RC-V005, Three Way Diverting Valve, to the horizontal position, for flow to Main Condenser.
CAUTION 5.7 Loss of a RWCU Pump, when in two pump operation, can cause pump runout Flow must be reduced immediately by closing HV-F044, FILTER DEMIN BYPASS, (if open) OR throttling HV-F042 REGEN HX RTN ISLN until Chemistry can remove a FlIterlDemin from service OR the flow is reduced through the two IS Demineralizers.
5.7 Reducing Flow through or Bypassing the Filter/Demins 5.7.1 ENSURE all prerequisites of Section 2.7 are satisfied,
[CD-937B, CD445D]
5.7.2 IF it is desired to reduce flow through the RWCU Demineralizers, THEN PERFORM one or both of the following:
NOTE 6.7.3 and 5.7.4 In the event HV-F044, FLTR DEMIN BYPASS, is unavailable or inoperable, the operator may use HV-F104, CLEANUP BYPASS, AND Computer Point A2081 to throttle open/closed in order to bypass OR restore flow to Filter/Demins.
A. THROTTLE BG-HV-F042, REGEN NX RTN ISLN, until system flow is limited to the desired value.
B. DIRECT Chemistry to reduce flow through the in service Demineralizer(s) until flow is limited to the desired value.
Hope Creek Page 35 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.BG-0001(Q) 5.7.3 WHEN flow is no longer required to be limited THEN THROTTLE BG-HV-F042, REGEN HX RTN ISLN to restore desired system flow and/or DIRECT Chemistry to return the Demineralizer(s) flow controllers to their normal settings.
5.7.4 IF it is desired to remove a RWCU Filter/Demineralizer from service THEN PERFORM the following:
A. DIRECT Chemistry to slowly reduce flow on the affected Filter/Demineralizer AND remove it from service.
B. MONITOR Computer Point A2856 (or equivalent)
AND THROTTLE OPEN on HV-FO44 as necessary to maintain flow at or below maximum RWCU return to feedwater flow value determined using Attachment 1 for 2 pump operation OR Attachment 2 for l pump operation.
5.7.5 WHEN it is desired to restore flow through a RWCU Filter/Demineralizer THEN PERFORM the following:
A. DIRECT Chemistry to place the Filter/Demineralizer in service AND SLOWLY RAISE flow. _
B. MONITOR Computer Point A2856 (or equivalent)
AND THROTTLE CLOSED on HV-F044 as necessary to maintain flow at or below maximum RWCU return to feedwater flow value determined using Attachment 1 for 2 pump operation OR Attachment 2 for 1 pump operation.
Hope Creek Page 36 of 53 Rev. 33 E
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.BG-0001(Q) 5.8 Removing RWCU Pump/System from Service JCD-937BJ 5.8.1 ENSURE all prerequisites of Section 2.8 are satisfied.
5.8.2 REQUEST Chemistry isolate the CAVS System prior to removing RWCU System from service.
NOTE 5.8.3 System flow should be maintained as indicated by Computer Point A2856 +/-20 gpm.
5.8;3 IF 2 RWCU Filter Demins (F/D) are in-service, THEN REQUEST Chemistry to remove 1 F/D from service OR reduce flow to maintain both Demins in-service AND flow between 140 - 160 gpin.
5.8.4 THROTTLE closed HV-F044, FLTR DEMIN BYPASS, push-button until Computer Point A2856 indicates approximately 140 to 160 gpm.
5.8.5 IF both RWCU Pumps are running, THEN STOP A(B)P221, A(B) RWCU PUMP. CD-937B]
5.8.6 IF Reactor Vessel water temperature is > 212'F AND the pump is to be out-of-service for more than approximately 15 min, THEN PERFORM the following to isolate the pump: [CD-937B]
A. CLOSE 1-BG-V006 (1-BO-VO10), A(B) RWCU Recirc Pmp Dsch Vlv.
B. ENSURE 1-BG-V200 (1-BG-V210), A(B) RWCU Recire Pmp Dsch Byp Vlv is closed.
C. CLOSE 1-BG-V004 (1-BG-VO08), A(B) RWCU Recirc Pmp Suction Vlv.
'Hope Creek Page 37 of 53 .Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.0P-SO.BG-OOO1(Q)
NOTE 5.8.7 A. If only one RWCU Pump and F/D are to be removed from service, then the remaining steps are NOT required.
B. System flow should be maintained as indicated by Computer Point A2856
+/- 20 gpm to prevent pump trip on low flow.
5.8.7 IF a second RWCU Pump is to be removed from service, THEN DIRECT Chemistry Department to perform the following:
A. REMOVE the remaining F/D from service.
B. ISOLATE the following[PR 9708031031:
- CLEAN UP DEMIN FILTER INLET.
- CLEAN UP FILTER DEMIN. 'A' DISCH
- CLEAN UP FILTER DEMIN. 'B' DISCH 5.8.8 STOP B(A)P221, B(A) RWCU PUMP. [CD-937B]
5.8.9 IF Reactor Vessel water temperature is > 212'F AND the pump is to be out-of-service for more than approximately 15 min, THEN PERFORM the following to isolate the pump: [CD-937B1 A. CLOSE I-BG-VO1O (1-BG-V006), B(A) RWCU Recirc Pmp Dsch Vlv.
B. ENSURE 1-BG-V210 (1-BG-V200), B(A) RWCU Recire Pmp Dsch Byp Vlv is closed.
C. CLOSE 1-BG-V008 (1-BG-V004), B(A) RWCU Recirc Pmp Suction Vlv.
5.8,10 CLOSE HV-F044, FLTR DEMIN BYPASS.
Hope Creek Page 38 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.BG-0001(Q)
NOTE 5.8.11 The following step need only be completed if RWCU System must be isolated.
5.8.11 IF RWCU System must be isolated, THEN CLOSE the following valves:
A. HV-FOOI, PMP SUCT CONT INBD ISOLATION VALVE B. HV-F004, PUMP SUCT CONT OUTBD ISOLATION VALVE C. HV-F039, RWCU RTN TO RPV ISOLATION VALVE NOTE 5.8.12 If a negative value for power loss is observed in Step 5.8.12, then a substitute value of 0.0 for Computer Point A196 RWCU FLOW (WCU) (Insert Value Function) will correct the heat balance discrepancy.
5.8.12 OBSERVE the Process Computer heat balance (OD-3d) value for power loss in the Cleanup Demineralizer System (QCU)
AND, as necessary, PLACE Computer Point A196 in MANUAL with a substitute value of 0.0 using Attachment 3 --Computer Point Al 96 Substitute Value Instructions, to correct the heat balance discrepancy.
Hope Creek Page 39 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.BG-001(Q)
NOTE 5.9 The Regenerative Heat Exchangers can only be bypassed in CONDITION 4, PR 5, OR Condition 2 when maintaining temperature < 2000F.
5.9 Bypassing the Regenerative Heat Exchangers 5.9.1 ENSURE all prerequisites of Section 2.9 are satisfied._
5.9.2 IF bypass of the Regenerative Heat Exchangers is required, THEN PERFORM the following:
A. UNLOCK AND OPEN V23 1, Bypass Valve.
NOTE 5.9.1.B System flow may have to be adjusted as V233 is opened.
B. UNLOCK AND OPEN V233, Bypass Valve, C. CLOSE V230, Hx Outlet Valve.
D. ADJUST system flowrate (for 2 pump operation) to approx. 300- 320 gpm.
(flow rate may change due to the difference in system resistance due to heat exchanger being removed from service. Flow adjustments should be made using LIV-F042.)
Continued next page Hope Creek Page 40 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.BG-0001(Q) 5.9 (continued) 5.9.3 IF partially bypass of the Regenerative Heat Exchangers is required, THEN PERFORM the following:
A. UNLOCK AND OPEN V233, Bypass Valve.
NOTE 5.9.3.B System flow may have to be adjusted as V231, Bypass Valve, is opened.
B. UNLOCK AND THROTTLE OPEN V231, Bypass Valve, as necessary to maintain desired RWCU temperature.
C. ADJUST system flowrate (for 2 pmp operation) to approx. 300 to 320 gpm.
(flow rate may change due to difference in system resistance due to Heat Exchanger being bypassed. Flow adjustments should be made using HV-F042).
Continued next page Hlope Creek Page 41 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.BG-0001(Q) 5.9 (continued)
NOTE 5.9.4 The following step is intended to be used during the performance HC.OP-IS.Z-0001 (Q),
Inservice System Leakage Test of the Reactor Coolant Pressure Boundary, as a temperature control method.
5.9.4 To control RWCU system outlet temperature, USE any combination of the following:
- THROTTLE BG-HV-F104, CLEANUP BYPASS -
OPEN to raise RWCU System outlet temperature (CRIDS A215)
OR CLOSED to lower RWCU System outlet temperature.
- THROTILE BG-HY-F042, HX RETURN TO VESSEL, as necessary, to maintain RWCU` OUTLET FLOW (CRIDS A2856) between 300 - 320 gpm.
OPEN to lower RWCU System outlet temperature (CRIDS A215)
OR CLOSED to raise RWCU System outlet temperature 5.9.5 WHEN RWCU system outlet temperature control is no longer required THEN PERFORM the following:
A. CLOSE BG-HV-F104, CLEANUP BYPASS B. OPEN BG-HV-F042, Hx Return to Vessel.
C. THROTTLE l-ED-V035 RWCU NRHx RACS RTN VLV to 43 degrees OPEN (JAW SAP WCM Blocking Point Information Page)
Hope Creek Page 42 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.BG-0001(Q)
.5.9.6 PERFORM the following to secure bypassing the Regenerative Heat Exchangers:
A. IF Regenerative Heat Exchanger was drained, THEN VERIFY Heat Exchanger is filled and vented.
B. ENSURE, V232, Hx Inlet Valve, open.
C. OPEN V230, Hx Outlet Valve.
D. CLOSE AND LOCK V23 1, Bypass Valve.
E. CLOSE AND LOCK V233, Bypass Valve.
F. ADJUST system flowrate as required (flow rate may change due to the difference in system resistance due to securing bypassing the heat exchanger).
Hope Creek Page 43 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.BG-0001(Q) 5.10 Placing the Regenerative. Heat Exchangers in Service CAUTION 5.10.1 Fill and vent Heat Exchangers slowly to avoid a RWCU Isolation.
5.10.1 IF the Regenerative Heat Exchanger is to be placed in-service, THEN PERFORM the following:
A. PERFORM the following to ensure Heat Exchangers are filled and vented:
- 1. THROTTLE OPEN BG-HV-F104 to maintain flow through the RWCU Pumps while closing BG-HV-F042, Hx Return to Vessel.
- 2. CLOSE BG-HV-F042, Hx Return to Vessel.
- 3. OPEN V230, I-x Outlet Valve.
- 4. CLOSE AND LOCK V231, Hx Bypass Valve, AND V233, Hx Bypass Valve.
- 5. OPEN V232, Hx Inlet Valve.
- 6. VENT using V066, Hx High Point Vent Valve, AND V067, Hx High Point Vent Valve.
B. OPEN BG-HV-F042, HX Return To Vessel.
C. CLOSE BG-HiV-F104.
D. ADJUST system flow to approximately 300 gpm.
Hope Creek Page 44 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BEATTACHED FOR FIELD USE 20030122 MS EATCE O IL S PSEG Internal Use Only H -PS HC.OP~SO.BG4JO01(Q)
X -0 1Q NOTE 5.11 A. The following steps can be used to for the Purpose of reducing Rad Levels.flush a RWCU Pump prior to maintenance Rnd Pro should be contacted to survey the pump after a 20 minute flush OS/CRS. OR as otherwise directed by the B. If the desired Rad levels are NOT achieved, repeated until a sufficient dose reduction then the following steps should be is achieved 5.11 FlushinaRWCU Pumpprior to Maintenance 5.11.1 ENSURE all prerequisites of Section 2.11 are satisfied.
CLAUTION 5.11.2 RWCU Pump cooldown should be limited to 265F/min.
5.1 1.2 IF flush of A RWCU Pump is required, THEN PERFORM the following:
A. CLOSE I-BG-V006, A RWCU Recirc Pmp Dsch VIv.
B. CLOSE l-BG-V200, A RWCU Recire Pmp Dsch Byp Vlv.
C. CLOSE 1-BG-V004, A RWCU Recirc Pmp Suction Vlv.
D. OPEN l-BG-V026, Seal Flush Vent,
-AND I-BG-V027, Seal Flush Vent.
E. OPEN l-BG-Vl94, Discharge Line Drain, AND l-BG-V]95, Discharge Line Drain.
F. CLOSE 1-BG-V024, Casing Drain Isolation Valve.
G. OPEN l-BG-V022, Casing Drain Vlv, AND I -BG-V023, Casing Drain Vlv.
Continued next page Hope Creek Page 45 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.BG-0001(Q) 5.11.2 (continued)
H. OPEN 1-AP-V142, Condensate Transfer Isolation Valve.
I. WHEN the pump has flushed for approximately 20 minutes, THEN CLOSEI 1-AP-V 142, Condensate Transfer Isolation Valve.
J. NOTIFY Radiation Protection to survey the RWCU Pump as necessary.
K. IF the desired rad levels have NOT been achieved, THEN REPEAT Steps 5.11.2 H through 5.11.2.J as necessary until desired rad levels are achieved.
5.11.3 WHEN flushing is complete, THEN PERFORM the following:
A, CLOSE l-AP-V142, Condensate Transfer Isolation Valve.
B. CLOSE 1-BG-V022, Casing Drain Vlv, AND 1-BG-V023 Casing Drain Vlv.
C. OPEN I-BG-V024, Casing Drain Isolation Valve.
D. CLOSE 1-BG-V194, Discharge Line Drain, AND 1-DO-V195, Discharge Line Drain.
E. CLOSE l-BG-V026, Seal Flush Vent, AN) 1-BG-V027, Seal Flush Vent.
5.11.4 IF flush of the B RWCU Pump is required, THEN PERFORM the following:
A. CLOSE 1-BG-V010, B RWCU Recire Pmp Dsch Vlv.
B. CLOSE l-BG-V210, B RWCU Recire Pmp Dsch-Byp Vlv.
Continued next page Hope Creek Page 46 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.BG-001(Q) 5.11.4 (continued)
C. CLOSE 1-BG-VO08, B RWCU Recirc Pmp Suction Vlv.
D. OPEN l-BG-V073, Seal Flush Vent, AND 1-BG-V074 Seal Flush Vent.
E. CLOSE 1-BO-V030, Casing Drain Isolation Valve.
F. OPEN l-BG-V028, Casing Drain Vlv, AND 1-BG-V029, Casing Drain Vlv.
G. OPEN 1-AP-V 143, Condensate Transfer Isolation Valve.
H. WHEN the pump has flushed for approximately 20 minutes, THEN CLOSE 1-AP-Vl43, Condensate Transfer Isolation Valve.
I. NOTIFY Radiation Protection to survey the RWCU Pump.
J. IF the desired rad levels have NOT been achieved, THEN REPEAT Steps 5.11.4. G through 5.11.4.1 as necessary until desired rad levels are achieved.
5.11.5 WHEN flushing is complete, THEN PERFORM the following:
A. CLOSE 1-AP-V143, Condensate Transfer Isolation Valve.
B. CLOSE 1-BG-V028, Casing Drain Vlv, AND I-BG-V029, Casing Drain Vlv.
C. OPEN 1-BG-V030, Casing Drain Isolation Valve.
D. CLOSE 1-BG-V073, Seal Flush Vent, AND 1-BG-V074 Seal Flush Vent.
Hop~e Creek Page 47 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.BG-0001(Q)
6.0 REFERENCES
6.1 P&IDTs M-25-1 M-44-1 M-45-1 M-43-1, Sht. 1 M-101 6.2 Logic Diagrams J-44-0 Sht. 1,2,3,4,5,6,7,8 6.3 Electrical Drawings E-0021-1 Sht. 1, 5 E0031-1 E- 0032-1 6.4 Vendor Manuals NI-G33-386 & 387 Ecodyne Corporation - RWCU F/D NL-G33-429-2 Union Pump Co. - RWCU Recirc Pumps Nl-A41-0045 (1) RWCU System 6.5 Panel Drawings J-0650-1 Sht. 9 J-065 1-1 Sht. 6 6.6 DITS D3.31 D5.14 6.7 GE Documents GEK 90300 Volume VI, Part 1 23A1 860, RWCU Pump Instructions G.E. Drawing 166B8227 Hope Creek Page 48 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Uie Only HC.OP-SO.BG-0001(Q) 6.8 Commitment Documents CD-886X (Q210.24)
CD-937B (AID 25-80)
CID-786D (AID 48-78)
CD-445D (SIL 258 SUPP 2)
CD-389E (SIL 436) 6.9 Other DEF # DEH-92-0008 1 6.10 Cross References HC.RE-SO.RJ-0010(Q), Process Computer Program Operating Instructions 6.11 Corrective Actions PR 970803103 PR 980515086 PR 980709244 CR971127121 RWCU Differential Flow setpoint 20004666 TS990418149 20018965 80007129 DCP 4EC-3192 Hope Creek Page 49 of 53 Rev. 33
( ( I.)>
or-('4 0>
PSEG Internal Use Only HC.OP-SO.BG-0001(Q) )-4 ATTACHMENT 1 M MAXIMUM RWCU RETURN TO FEEDIWATER FLOW - 2 PUMP OPERATION 0 z
-I4 I
Maximum RWCU Return to Feed Water Flow equivalent to Total RWCU F/D Bed Flow of 300 gpm @ 120"F with 2 pumps running 0 AI 370.0 C) a:
365.0 z 0
M 360.0
_Iii
__ I__ion _
U)
C
- 0. 355.0
-i so 350.0 _ - _ I,,_, ____ _
-i w 345.0 -4i 0 340.0 0
o 335.0 If, the RWCU Retum to FW Flow at the cment - - - -
u-Retumn to FW temp. is in this region, a 330.0 Then, theTotal IRWCU Flowthrough F/D bedsis -s 0 I. > 300 gpm at 120 degF.
- 325.0 a0 C (A
2 320.0 P1 o 315.0 . l - l l l J /l Good Region for RWCU EJ Flowki I If. the RWCU Retum to FW Flow at the current
=` 310.0 ___ - II 1
- _ lRetum to FW temp. is in this region, Then, the Total RWCU Flow through FID beds is a 305.0 . l1 1 1 1 . - - or=3Mgpmat120de9F.
300.0 295.0 70 90 110 130 150 170 190 210 230 250 270 290 310 330 350 370 390 410 430 450 470 RWCU Retum to Feedwater Flow Temp. Crids A215 (degF)
Hope Creek Page 50 of 53 Rev. 33
( (
( (AS 0>
PSEG Internal Use Only HC.OP-SO.BG-0001(Q)
ATTACHAENT 2 MAXIMUM RWCU RETURN TO FEEDWATER FLOW - 1 PUMP OPERATION .0 z
--4 P1i(I
-U Maximum RWCU Return to Feed Water Flow equivalent to Total RWCU FID Bed Flow 0
-4 of 160 gpm @ 120OF with one pump running 0 z
0 P1 185.0 U)
C E~ 181.0 IWC FI Be Flo To 1191 Region ll T i LU)
-_4
- 0901 __ Y__
-_4 co Return to FW ternp. Is in this region, -4 04 173.0 Then, the Total RWCUJ Flow through FID beds is
> 150 gprn at 120 degF.
- 7 /
0 LL 0
S-o
) 169.0 165.0 1 161.0 I,
1 III I!__ _
I.L1111E II II ,
0
-l I-0 C
Ui)
P1
, , I , I ) ,
01 i ,
Good Region for R!NCU FID Flow IL If, the RWCU Return to FW Flow at the current o 157.0 Return to FW temp. is in this region, Then, the Total RWCU Flow through F/D beds is a 153.0 .J.-44--i------I.-! 4 4 -+-4 I < or = 150 gpm at 120 degF.
11 I 1
I I I I 0 149.0 -, I I
-145.0 70 90 III I _. I 110 130 150 170 190 210 230 250 270 290 310 330 350 370 390 410 430 450 470 I__
RWCU Return to Feedwater Flow Temp. @ CridsA215 (degF)
Hope Creek Page 51 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030 122 PSEG Internal Use Only HC.OP-SO.BGO0001(Q)
ATTACHMENT 3 COMPUTER POINT A196 SUBSTITUTE VALUE INSTRUCTIONS (Page 1 of 2)
NOTE A196 (Cleanup System Flow) is placed in MANUAL with a value of "0.0" when taking RWCU out of service.
Al 96 (Cleanup System Flow) is placed in AUTOMATIC when returning RWCU to service.
AUTOMATIC The value of the computer point is updated based on field inputs and/or computer algorithims.
MANUAL The value of the computer point is frozen at the current value unless a different value is manually entered.
1.0 To swap computer point A196 between a) AUTOMATIC and b) MANUAL (with a value of 0.0)
PERFORM the following:
1.1 SELECT "SYS" on top menu bar.
1.2 SELECT "Change Env"' on pull down menu. _
1.3 SELECT "MaintEnv" on second pull down menu.
1.4 ENTER password "HCNSSS" using keypad THEN PRESS "ENTER" key.
1.5 SELECT "SELECT" on top menu bar.
1.6 ENSURE that an ""is in the 'CP NAMES SEARCH" blue box.
1.7 SELECT "AINMISC" on left of screen.
(It may be necessary to repeat Steps 1.5 and 1.6 to have the list of choices displayed.)
1.8 SELECT "A196" on right of screen.
1.9 VERIFY the expected "A" or "WMappears next to "MEAS" on right of screen.
("A" = AUTOMATIC, "M" = MANUAL)
IF already is desired state THEN PROCEED to step 1.13.
Continued Next Page Hope Creek Page 52 of 53 Rev. 33
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE HC.OP-AB.RPV-0009(Q) 20030122 IPSEG Internal Use Only H.PA~P-09Q SHUTDOWN COOLING
. APPROVED: _ _ _ __
Manager - Hope Creek Operations 94 Effective Date
'.j/4 ls.
Date.
CATEGORY II SHUTDOWN COOLING ALARMS
- RHR LOGIC A OUT OF SERVICE A6-Al
- RHR, LOGIC B OUT OF SERVICE A7 - Al
- COMPUTER PT IN ALARM A4 - F5
- APRM/RBM FLOW REF OFF NORMAL C6-El INDICATIONS
- Trip of RHR pump in Shutdown Cooling
- Isolation of Shutdown Cooling Flowpath
- Reduced or stopped RHR Shutdown Cooling flow to the Jet Pumps
- Lowering Core flow
- Rising Reactor coolant temperature/pressure
- Rising Recirc pump loop flow Hope Creek Page I of 45 Rev. 0
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122i internaI use unly HC.OP-AB.RPV-0009(Q)
SHUTDOWN COOLING ADDITIONAL INFORMATION:
Procedures:
- HC.OP-GP.SM-0001(Q) DEFEATING NSSSS ISOLATIONS FOR SHUTDOWN COOLING Valves:
- BC-HV-F008 SHUTDOWN COOLING OUTBD ISOLATION
- BC-HV-Foo9 SHUTDOWN COOLING INBD ISOLATION
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-AB.RPV-0009(Q)
.0 IMMEDIATE OPERATOR ACTIONS NONE AUTOMATIC ACTIONS Reactor Pressure > 82 psig The following valves cannot be opened from the Control Room OR their Remote Shutdown controls:
. HV-F008
. HV-F009
- HV-F015A
. HV-FO15B
- HV-F022
. HV-F023 Reactor Pressure > 82 psig The following valves will isolate:
OR . HV-FO08*
Reactor Level < 12.5" a HV-FOO9*
OR HVF1A Loss of EITHER RPS Bus . HV.F~l5A AND
- HV-FO15B*
RSP Takeover Switches in NORMAL . HV-F022
- HV-F023 RHR Pump in Shutdown Cooling RHR pump trips.
AND Closure of ANY of the following:
- HV-F008 HV-FOO9
- Associated HV-F006 If GP.SM-0001 has been performed, these isolations are bypassed.
Hope Creek Page 3 of 45 Rev. 0
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030 1Pafg Internal Use Only It HC.OP-AB.RPV0009(Q)
SHUTDOWN COOLING This Page Intentionally Left Blank Hope Creek Page 4 of 45 Rev. 0
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-AB;RPV-0009(Q)
SHUTDOWN COOLING LIST OF CONDITIONS A. Loss of the RHR system providing Shutdown Cooling ............................ ................. t. 7 B. Alternate Loop of RHR is required to restore Shutdown Cooling .7 C. RHR S/D Cooling CANNOT be established within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> .7 D. Loss of S/D Cooling AND RCS temp. < 2000 F AND RCS temp. is anticipated to reach > 2000 F....9 E. Forced Circulation CANNOT be established using preferred RHR loops or Reactor Recirculation. 11 F. RWCU is required for Alternate Decay Heat Removal .II G. Condensate Transfer is required for S/D cooling .13 H. RPV Temperature and Pressure CANNOT be maintained using Normal OR Alternate Decay Heat Rem oval............................................................................................................................................. 17 Hope Creek Page 5 of 45 Rev. 0
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 2003012-2I.f 'ugernai use Univ HC.OP-AB.RPV-0009(Q)
SHUTDOWN COOLING ADDITIONAL INFORMATION:
Procedures:
- HC.OP-SO.BC-00i D2 DECAY HEAT REMOVAL OPERATION.
- HC.OP-SO.BB-00i D2 REACTOR RECIRCULATION SYSTEM OPERATION.
Valves:
- BC-HV-F008 SHUTDOWN COOLING OUTBD ISOLATION
- BC-H V-F009 SHUTDOWN COOLING INBD ISOLATION FIGNRE 1 Total Loss of Heat Removal from Rx Vessel 1000 EFPD of Operations 5.000 4.000 R0 LL 3.000 a0 0
0 N0 2.000
+0 (D
E=
1.000 0.000 10 100 1000 Time from Rx Shutdown (hours)
Hope Creek Page 6 of 45 Rev. 0
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 fres, Lnlernai use Unily HC.OP-AB.RPV-0009(Q)
SHUTDOWN COOLING SUBSEQUENT OPERATOR ACTIONS
! I.. . i CONDITION ACTION A. Loss of the RHR system providing . A. 1 IF below 2000 F, Shutdown Cooling THEN PERFORM the following:
- a. ESTIMATE time to reach 2000 F IAW Figure 1.
Time: __ _ _ _ _ _
Li b. IF RCS temperature is expected to rise above 2000 F, THEN IMPLEMENT Condition D.
L A.2 IF the Shutdown Cooling suction line was Estimated time RCS isolated, will reach 2001F: THEN PERFORM the following:
L
- PRIOR to establishing the suction flow path from the vessel, FILL & VENT the suction line IAW SO.BC-0002. [CD-891D]
C
- EVALUATE the need to implement Condition C (Suction line venting may take more than one hour).
U A.3 IF necessary, dispatch operators to manually open HV-F008 and/or HV-F009. [CD-065X]
A.4 Restore the tripped RHR pump as follows:
o~ a. CLOSE FO15A(B).
o b. RESTART RHR Pump A(B).
Q c. IMMEDIATELY THROTTLE OPEN F015A(B) to establish Shutdown Cooling flow between 3000 gpm and 10,000 gpm.
B. Alternate Loop of RHR is required to 0 B.1 PLACE RHR loop A(B) in Shutdown Cooling restore Shutdown Cooling 1AW SO.BC-0002.
Time:
C. RHR S/D Cooling CANNOT be 0 C,,1 MONITOR Reactor Coolant temperature and established within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. pressure at least once per hour.
[T/S 3.4.9.1, 3.4.9.2] [3.4.9.1.b, 3.4.9.2.bJ IT/S 3.9.11.1, 3.9.11.2] - C.2 ENSURE forced circulation in the core Time: - utilizing Reactor Recirc 1AW SO.BB-0002 OR an alternate method.
Hope Creek Page 7 of 45 Rev. 0
200 30ACTIVE ALL ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 12 .2EG Internal Use Only HC.OP-AB.RPV-0009(Q)
SHUTDOWN COOLING ADDITIONAL INFORMATION:
Valves:
- 13B-HV-FOOI REACTOR HEAD VENT DRW INBD ISLN
- BB1-HV-F002 REACTOR HEAD VENT DRW OUTBD ISLN TABLE D.2 - REDUNDANT REACTOR VESSEL PRESSURE INDICATIONS NOMENCLATURE RANGE DESCRIPTION CONTROL ROOM PANEL 10-C-650 PI-5824A 0-50 LOW RANGE REACTOR PRESS PI-5824B 0- 50.. LOW RANGE REACTOR PRESS Pl-R605-C32 0- 1200 REACTOR PRESSURE PR-R623A-B21 0-1500 PAMS PR-R623B-B21 0- 1500 PAMS PI-3684A 0- 1500 PAMS P1-3684B 0- 1500 PAMS LOWER RELAY ROOM PANEL 10-C411 IFDPISL-N658AE41. 0 0-200 lHPCI TRIP UNIT IFDPISL-N658E-E41 00-200 lHPCI TRIP UNIT LOWER RELAY ROOM PANEL 10-C-641 IFDPISL-N658C-E,4t 0 - 200 HPCI TRIP UNIT IFD.PISL-N658G-E41 1 q - 200 HPCI TRIP UNIT LOWER RELAY ROOM PANEL 10-C-618
.IFCPISL-N658B.E5I 0 - 200 RCIC TRIP UNIT 1FCPISL-N658F-E5 . 0 - 200 RCIC TRIP UNIT LOWER RELAY ROOM PANEL 10-C-631 IFCPISL-N658D-E5 1 0-200 RCICTRIP UNIT IFCPISL-N658H-E51 0- 200 RCIC TRIP UNIT D69 o
Hope Creek Page 8 of 45 Rev. 0
FOR FIELD USE ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED ALL ACTIVE ON-T;HE-SPOT CaHANGES MUST BE ATTACHED FOR FIELD USE 20030122 P Internal 1EU Use Only HC.OP-AB.RPV4009(Q)
SHUTDOWN COOLING SUBSEQUENT OPERATOR AC1gIONS CONDITION ACTION D. Loss of S/D Cooling O D.1 EVALUATE the need to establish Primary AND AND RCS temp. < 200'F Secondary Containment.
AND RCS temp. is anticipated to reach U D.2 EVALUATE the following for indications of
> 2000F.
entry into OPCON 3:
IT/S 3.6.1.1, 3.6.5.11 U
- An increase in steam dome pressure could be indicative that boiling, to some degree, is Time: occurring in the Reactor Core. This parameter should be monitored using the redundant Reactor pressure indications given in Table D.2, particularly those with the lowest ranges such as Reactor Low Range Pressure (0- 50 psig on Panel I OC650A) or, the HPCI and RCIC trip units.
Z
- An increase in Reactor Head Vent temperature could be indicative of the onset 4 or verification of the presence of boiling in the vessel. This temperature is monitored by TE-N064 (when BB-HV-F00I and BB-HV-F002 are open), and can be read on the Control Room recorder B21-TRR614 point 24, Reactor Head Vent.
O
- An unexplained increase in Drywell leakage could be indicative of the presence of steam flow out of the vessel head and into the Drywell. This parameter is monitored at RMS and includes primarily the Drywell Equipment Drain flow, however, steaming into the Equipment Drain Sump could also be indicated by total Drywell leakage and Drywell Cooler condensate flow, therefore, all of these points should be monitored for unexplained increases.
Hope Creek Page 9 of 45 Rev. 0
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 200301223EG Internal Use Only HC.OP-AB.RPV-0009(Q)
SHUTDOWN COOLING CAUTIONS:
- 1. Apply temperature compensation as necessary. Main Steam Line flooding occurs at 118 inches.
NOTES:
- 1. IF in 10-0004,10-0005, or 10-0009, the associated attachment for "PLACING THE PLANT IN ALTERNATE DECAY HEAT REMOVAL MODE OF OPERATION" MAY identify an effective mode of Alternate Decay Heat Removal.
ADDITIONAL INFORMATION:
Procedures:
- HC.OP-IO.ZZ-0004(Q) SHUTDOWN FROM RATED POWER TO COLD SHUTDOWN
- HC.OP-IO.ZZ-0005(Q) COLD SHUTDOWN TO REFUELING
- HC.OP-IO.ZZ-0009(Q) REFUELING OPERATION
- HC.OP-DL.ZZ-0026(Q) SURVEILLANCE LOG
- HC.OP-SO.EC-000l(Q) FUEL POOL COOLING AND CLEANUP SYSTEM
- HC.OP-SO.BG-0001(Q) REACTOR WATER CLEANUP SYSTEM OPERATION Valves:
- 1-ED-V035 RWCU NRHX RACS RTN PLUG. (Rm 4504E).
Hope Creek Page 10 of 45 Rev. 0
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-AB.RPV-0009(Q)
SHUTDOWN COOLING SUBSEQUENT OPERATOR ACTIONS (continued)
CONDITION ACTION I 1 " I12 I .! -A -
rrsLI I ** **
A~ET L. rorcea UrcuiaUon LAiNNU I be Li NI lr_ I -
established using preferred RHR loops or Reactor Recirculation. Li E.1 MONITOR temperatures LAW DL-0026
[CD-693A, CD-178A, CD-973B, Attachment 3s.
CD-1OA, CD-076B, CD-06SX - °l
- CAUTION 1
LI E.3 IF RPV LVL reaches 90 inches, THEN CLOSE the MSIV's.
3 E.4 ENSURE T.S. cool down limits are not exceeded.
[T/S 3.4.6.1.bI E.5 EVALUATE the following systems for alternate decay heat removal:
Li
Li * "D" RHR (Attachment 2)
Li]
- CONDENSATE TRANSFER (Subsequent G)
El E.6 IF the vessel head is removed, AND the Reactor Cavity is flooded, THEN maximize Fuel Pool Cooling:
- ENSURE two Fuel Pool Cooling pumps are in service. (EC)
Li
- ENSURE SACS flow aligned through BOTH.Fuel Pool Cooling heat exchangers.
F. RWCU is required for Alternate Decay L F. 1 ENSURE RWCU is in service. (BG)
HeatRemo .l F.2 FULLY OPEN ED-V035.
[CD-900E]
Time: L- F.3 IF necessary, THEN Bypass the Regenerative heat exchanger to maximize decay heat removal.
(BG)
Hope Creek Page II of 45 Rtev. 0
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 200301223EG Internal Use Only HC.OP-AB.RPV-O009(Q)
SHUTDOWN COOLING ADDITIONAL INFORMATION:
Procedures:
- HC.OP-SO.AP-OOO1(Q) CONDENSATE TRANSFER SYSTEM OPERATION
- HC.OP-SO.BG-OOO1(Q) REACTOR WATER CLEANUP SYSTEM OPERATION Valves:
TABLE G: Condensate Transfer Injection Flowpaths SYSTEM CS XFR DISCH ISLN- OUTBD ISOL VLV INJECTION VALVE
'A' RHR 1-AP-VO44 (Rm. 4328) N/A BC-HV-FO17A
'C' RHR 1-AP-V047 (Rm. 4328) N/A BC.HV-FO17C
'B' RXR 1-AP-V056 (Rm 4322B) N/A BE-HV-FO17B
'D' RHR 1-AP-V059 (Rm. 4322B) N/A BE-HV-FO17D
'A' CORE SPRAY 1-AP-V041 (Rm. 4331) BE-HV-FO04A BE-HV-FOO5A
'B' CORE SPRAY 1-AP-V062 (Rm. 4322B) BE-HV-FO04B BE-HV-FOOSB 0 HPCI 1-AP-V038 (Rm. 4331) N/A BJ-HV-8278 RCIC I-AP-V052 (Rm. 4315) N/A BD-HV-F013 Hope Creek Page 12 of 45 Rev. 0
ALL ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-AB.RPV-0009(Q)
_ SUBSEQUENT OPERATOR ACTIONS (continued)
LCONDITION ACT IONl
- 0. Condensate Transfer is required for Cl G.1 ENSURE Condensate Transfer is in-service.
S/D cooling. (AP)
El G.2 ENSURE RWCU is in-service. (BG)
Time: LI G.3 REFER to Table G and align one of the
- Continued on Page 15 following flowpaths to feed the vessel from condensate transfer as follows:
U G04 IF an RHR injection line will be used, THEN PERFORM the following:
3 a. OPEN the desired loops INJECTION VALVE listed in Table G.
O b. THROTTLE OPEN the associated CS XFR DISCH ISLN listed in Table G to obtain-the desired injection rate.
O G.5 IF a Core Spray injection line will be used, THEN PERFORM the following:
4A C) a. CLOSE the desired loops OUTBD ISOL VLV listed in Table G.
O b. OPEN the associated INJECTION VALVE listed in Table G.
L c. RE-OPEN the OUTBD ISOL VLV.
0 d. THROTTLE OPEN the associated CS XFR DISCH ISLN listed in Table G to obtain the desired injection rate.
O *** Continued on Page 15
- 9 Hope Creek Page 13 of 45 Rev. 0
I ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE
- 2003012 2E G Internal Use Only HC.OP-AB.RPV-0009(Q)
SHUTDOWN COOLING NOTES:
- 2. Reactor pressure must be below the Low Pressure Isolation setpoint for the system to prevent auto-closure of the injection valve.
ADDITIONAL INFORMATION:
Procedures:
- HC.OP-SO.BG-0001(Q) REACTOR WATER CLEANUP SYSTEM OPERATION Valves:
- AE-HV-F032A FW INLET CHECK VALVE
- AE-HV-F032B FW INLET CHECK VALVE TABLE G: Condensate Transfer Injection Flowpaths SYSTEM CS XFR DISCH ISLN OUTBD ISOL VLV INJECTION VALVE
'A' RHR 1-AP-V044 (Rm. 4328) N/A BC-HV-FO17A
'C' RIHR
'B' RHR 1-AP-V047 (Rm. 4328) 1-AP-V056 (Rm 4322B)
N/A N/A BC-HV-FO17C BE-HV-FO17B 0
'D' RHR I-AP-V059 (Rm. 4322B) N/A BE-HV-FO17D
'A' CORE SPRAY 1-AP-V041 (Rm. 4331) BE-HV-FO04A BE-HV-FOO5A
'B' CORE SPRAY 1-AP-V062 (Rm. 4322B) BE-HV-F004B BE-HV-FO05B HPCI I-AP-V038 (Rm. 4331) N/A BJ-HV-8278 RCIC 1-AP-V052 (Rm. 4315) N/A BD-HV-F013 Hope Creek Page 14 of 45 Rev. O
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-AB.RPV-0009(Q)
SHUTDOWN COOLING SUBSEQUENT OPERATOR ACTIQNS (cputiniued)
CONDITION ACTION
- Continued from Page 13 *** *** Continued from Page 13 ***
G. Condensate Transfer is required for 0 G.6 IF the RCIC injection line will be used, S/D cooling. THEN PERFORM the following:
i** NOTE 2**
E a. VERIFY reactor pressure < 64 psig 0 b. ENSURE the HV-F032B is open.
L c. PLACE the NORM/BYPASS keylock switch for the HV-F013 in BYPASS.
0 d. OPEN the HV-F013.
0 e. THROTTLE OPEN the I-AP-V052 to obtain the desired injection rate.
L G.? IF the HPCI injection line will be used, THEN PERFORM the following:
Li ** NOTE 2**
'II 0 a. VERIFY reactor pressure < 100 psig O b. ENSURE the HV-F032A is open.
0 c. PLACE the NORM/BYPASS keylock switch for the HV-8278 in BYPASS.
U d. OPEN the HV-8278.
0 e. THROTTLE OPEN the I-AP-V038 to obtain the desired injection rate.
U G.8 MAINTAIN RPV LVL using RWCU Blowdown. (BG) 9 Hope Creek Page 15 of 45 Rev. 0
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030 hk~IIi internal Use Linl HC.OP-AB.RPV-0009(Q)
SHUTDOWN COOLING NOTES:
- 3. -The goal of the following steps is to establish water flow through two SRVs with at least a 50# d/p. It is desirable to maintain less than a 160# dip across the SRV's to ensure a single LPCI or Core Spray pump can deliver sufficient flow to remove decay heat. Any injection source may be used to flood the vessel, but it is desirable to use the torus as a suction source for recirculation of water through the vessel and SRVs. This will prevent unnecessary water addition to the torus from outside sources.
ADDITIONAL INFORMATION:
Procedures:
- HC.OP-AB.ZZ-0001(Q) TRANSIENT PLANT CONDITIONS.
Valves:
- BB-HV-F001 REACTOR HEAD VENT DRW INBD ISLN
- BB-HV-F002 REACTOR HEAD VENT DRW OUTBD ISLN
- BB-HV-F005 REACTOR HEAD VENT STM LINE A
- AB-HV-F016 CTMT INBD STM LINE DRAIN HDR ISLN OUTBOARD MOV e AB-HV-F019 CTMT INBD STM LINE DRAIN HDR ISLN INBOARD MOV 0
- FC-HV-F007 RCIC STM INBD ISLN VLV
- FC-HV-F008 RCIC STM OUTBD ISLN VLV
- FC-HV-F076 RCIC STM WARMUP VLV Hope Creek Page 16 of 45 Rev. 0
ALL AC'IVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-AB.RPV-0009(Q)
SHUTDOWN COOLING SUBSEQUENT OPERATOR ACTIONS (continued).
CONDITION l ACTION I H. RPV Temperature and Pressure ** NOTE 3**
CANNOT be maintained using Normal H. I INITIATE Suppression Pool Cooling JAW OR Alternate Decay Heat Removal. AB-0001.
[CD-973B, CD-i1OE, CD-950B1
- Continued on Page 19 *** - H.2 ENSURE the following Valves are closed.
- RPV Head Vents.
- MSIV's.
Time:
- Main Steam Line Drain valves.
- HPCI Steam Isolations.
- RCIC Steam Isolations.
o H.3 PLACE the control switches for two SRV's to OPEN (SRVs will not open until a 50# d/p is established).
HA.4 SLOWLY RAISE RPV water level to establish a flow path through the OPEN SRV's.
1 H.5SECURE all injection into the RPV except from CRD.
o3 H.6 START one Core Spray Subsystem or one LPCI Pump with suction from the Suppression Pool.
LI H.7 RAISE Core Spray OR LPCI injection into the RPV to maximum.
Q H.8 IF RPV pressure does not stabilize at least 50 psig above suppression chamber pressure, OR two SRVs are NOT open, THEN START and additional Core Spray Subsystem or LPCI pump AND continue to RAISE injection flow to establish stated conditions.
u H.9 IF RPV pressure stabilizes at more than 160 psig above Suppression Chamber pressure, THEN OPEN another SRV.
El *** Continued on page 19 ***
Hope Creek Page 17 of 45 Rev. 0
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SHUTDOWN COOLING CAUTIONS:
- 2. Maintain at least 50 psig above Suppression Chamber pressure with at least two SRV's open.
Hope Creek Page 18 of 45 Rev. 0
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 rJSE Internal Use Only HC.OP-AB.RPV-0009(Q)
SHUTDOWN COOLING SUBSEQUENT OPERATOR ACTIONS
. CONDITION ACTION
- Continued from Page 17 *** *** Continued from Page 17 ***
H. RPV Temperature and Pressure Q
- CAUTION 2
- CANNOT be maintained using Normal Ej H. 1O IF the cooldown rate exceeds 90'F/hr, OR Alternate Decay Heat Removal. THEN REDUCE Core Spray or LPCI injection into the RPV until EITHER of the
- -following occurs:
Li
- The cooldown rate drops below 90 'F/hr.
)
- RPV pressure decreases to within 50 psig of Suppression Chamber pressure.
Ei H. I I CONTROL Suppression Pool temperature to maintain RPV water temperature above 790 F.
fT/S 3.4.6.1.d]
Hope Creek Page 19 of 45 Rev. 0
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SHUTDOWN COOLING This Page Intentionally Left Blank Hope Creek Page 20 of 45 Rev. 0
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-AB.RPV-0009(Q)
SHUTDOWN COOLING ATTACHMENT 1 ALTERNATE DECAY HEAT REMOVAL USING C TO A CROSS-TIE (Page I of 6)
S NOTE 1.0 Operation of the C to A Cross-Tie is restricted to conditions when reactor coolant temperature is < 3000 F (67 psia). [PR 970602179, PR 960927120]
1.0 Establishing Alternate Decay Heat Removal Using the C to A Cross-tie ICD-609G]
1.1 ENSURE the AP System is available providing keepfill for all A Loop ECCS Systems required for operability. (I-AP-V041, CS Xfrto A Core Spray Dsch (Rm. 4331) 1.2 ENSURE that the Jockey Pump CP228 is secured AND tagged IAW NC.NA-AP.ZZ-001 5(Q); Safety Tagging Program.
(Breaker 52-232074) 1.3 CLOSE lBC-V203 ECCS Jock Pmp C Suct Vlv (Rm. 4114C)
AND TAG IAW NC.NA-AP.ZZ-0015(Q).
1.4 CLOSE the following valves:
HV-FO04A RHR PMP A SUPP POOL SUCT MOV S
HV-FO04C RHR PMP C SUPP POOL SUCT MOV 1.5 TAG the following IAW NC.NA-AP.ZZ-0015(Q):
S HV-FO04A RHR PMP A SUPP POOL SUCT MOV (52-21203 1)
S HV-FO04C RHR PMP C SUPP POOL SUCT MOV (52-232031)
CAUTION 1.6 Manual or automatic opening of HV-F007 A(C) RHR PMP A(C) MIN FL MOV will drain the Reactor Vessel to the Suppression Pool.
1.6 ENSURE the following valves are closed:
Hope Creek Page 21 of 45 Rev. 0
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ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-AB.RPV-0009(Q)
SHUTDOWN COOLING ATTACHMENT 1 ALTERNATE DECAY HEAT REMOVAL USING C TO A CROSS-TIE (Page 2 of 6) 1.7 VERIFY the following LPCI Injection Valves are closed, /
THEN DE-ENERGIZE AND TAG their power sources to ensure these valves do not open if a LPCI signal is received during cross-tie operating mode:
- HV-F027A RHR LOOP A SUPP CHAMBER SPRAY HDR ISLN MOV (52-212083) 1.9 Fully OPEN IBC-V133 RHR Pmp C Suct Frm Recir Loop B (Rm 4227E)
AND TAG in the open position lAW NC.NA-AP.ZZ-0015(Q).
4 1.10 ENSURE F077 RECIRC LOOP B TO RHR SUP MAN VLV is open.
1.11 IF the Shutdown Cooling suction line was isolated, THEN PERFORM a fill and vent lAW HC.OP-SO.BC-0002(Q),
Decay Heat Removal Operation.
1.12 ENSURE the following valves are open: °
- HV-F008 SHUTDOWN COOLING OUTBD ISLN MOV
- HV-F009 SHUTDOWN COOLING INBD ISLN MOV.
1.13 UNLOCK AND OPEN lBC-V571 RHR Cross-Tie Isolation Valve for C Loop BC-HV-11673. (Rmn4114A) 1.14 OPEN the following valves until a solid stream of water issues, THEN CLOSE (Local):
1BC-V578 AND IBC-V579 RHR Vent Valves (Rm. 4113A) lB* 1C-V580 AND IBC-V581 RHR Vent Valves (Rm. 4114A)
Hope Creek Page 23 of 45 Rev. 0
ALL AC71VE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 2003012 i-3 internal Use Unly HC.OP-AB.RPV-0009(Q)
SHUTDOWN COOLING This Page Intentionally Left Blank
-.Hope Creek Page 24 of 45 Rev. 0
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-AB.RPV-0009(Q)
SHUTDOWN COOLING ATTACHMENT 1 ALTERNATE DECAY HEAT REMOVAL USING C TO A CROSS-TIE (Page 3 of 6) 1.15 OPEN l BC-V570 RHR Cross-Tie Isolation Valve for A Loop (Rm. 411 3A)
NOTE 1.16 A. The interlock override will allow C RHR Pump to operate when the pump is aligned to the alternate suction from the RPV, when and if required.
B. In the cross-tie mode, C RHR Pump will not be automatically protected against the loss of suction from the RPV.
1 16 OBTAIN key for the I-BC-HS-1 1496 Keylock Switch from Work Control key cabinet.
1.17 At Panel I0C641 perform the following:
A. INSERT the key in the 1-BC-HS-1 1496 Keylock Switch.
B. OVERRIDE the HV-FO04C Valve/Pump C Interlock using the 1-BC-HS-11496 Keylock Switch.
C. LOG in CRS Log the position of the Keylock Switch.
1.18 IF during the cross-tie operation mode, the HV-F008 or HV-F009 close (e.g., on RPV Low Level 3 signal), then immediately STOP the C RHR Pump AND TAKE corrective action.
1.19 IF HV-FO15A RHR LOOP A RET TO RECIRC LOOP A ISLNMOV does NOT open immediately to establish flow, THEN SECURE the RHR Pump.
9 Hope Creek Page 25 of 45 Rev. 0
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SHUTDOWN COOLING This Page Intentionally Left Blank Hope Creek Page 26 of 45 Rev. 0
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-AB.RPV-0009(Q)
SHUTDOWN COOLING ATTACHMENT 1 ALTERNATE DECAY HEAT REMOVAL USING C TO A CROSS-TIE (Page 4 of 6)
CAUTION 1.20 Manual or automatic opening of HV-FO07A(C) RHR PMP A(C) MIN FL MOV will drain the Reactor Vessel to the Suppression Pool.
1.20 START RHR PUMP CP202 and immediately THROTTLE OPEN HIV-FOI 5A RHR LOOP A RET TO RECIRC LOOP A ISLN MOV until FI-R603C LOOP C FLOW indicates 3000 gpm.
- OBSERVE AI-6358C PUMP C MOT AMPS.
- MAINTAIN flow of 3000 gpm for at least 10 minutes.
1.21 OPEN HV-FOI5A RHR LOOP A RET TO RECIRC LOOP A ISLN MOV until FI-R603C LOOP C FLOW indicates 10,000 gpm.
<-0 Hope Creek Page 27 of 45 Rev. 0
ALL ACfIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 2 0 0 3 0 10 2 L- icrniueui HC.OP-AB.RPV-OOO9(Q)
SHUTDOWN COOLING This Page Intentionally Left Blank Hope Creek Page 28 of 45 Rev. 0
ALL AC4 IVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-AB.RPV-0009(Q)
SHUTDOWN COOLING ATTACHMENT 1 ALTERNATE DECAY HEAT REMOVAL USING C TO A CROSS-TIE (Page 5 of 6) 2.0 Securing Alternate Decay Heat Removal When C to A Cross-tie was used.
2.1 CLOSE HV-FO15A RHR LOOP A RET TO RECIRC LOOP A ISLN MOV.
2.2 WHEN the HV-FO15A RHR LOOP A RET TO RECIRC LOOP A ISLN MOV is closed, THEN STOP the C RHR Pump CP202.
2.3 REMOVE 1-BC-HS-1 1496 Keylock Switch from the OVERRIDE position.
A. REMOVE the key fron I -BC-HS- 11496 Keylock Switch AND RETURN the key to the Work Control key cabinet.
B. LOG in CRS Log the position of the keylock switch.
2.4 CLOSE IBC-V570 RHR Cross-Tie Isolation Valve for A Loop (Rm. 4113A).
2.5 CLOSE AND)LOCK IBC-V571 RHR Cross-Tie Isolation Valve for C Loop BC-HV-1 1673. (Rm 4114A) 2.6 RELEASE tags from IBC-V203 ECCS Jock Pmp C Suct Vlv (Rm. 4114C)
AND OPEN valve.
2.7 RELEASE tags from Jockey Pump CP228.
2.8 RELEASE tags from IBC-V133 RHR Pmp C Suc Frm Recir Loop B (Rm 4227E) 2.9 CLOSE AND LOCK IBC-V133 RHR Pmp C Suc Frm Recir Loop B (Rm 4227E) 2.10 CLOSE the following valves:
- HV-FOO8 SHUTDOWN COOLING OUTBD ISLN MOV
- HV-F009 SHUTDOWN COOLING INBD ISLN MOV Hope Creek Page 29 of 45 Rev.O0 1
ALL AC0IVE 1 ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030 122' internal USe LUnly HC.OP-AB.RPV-OOO9(Q)
SHUTDOWN COOLING This Page Intentionally Left Blank Hope Creek Page 30 of 45 Rev. 0
ALL AC"IVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE HC.OP-AB.RPV0009(Q) 20030122 nternai use u.nwyH.PAP-09Q iL.
SHUTDOWN COOLING ATTACHMENT 1 ALTERNATE DECAY HEAT REMOVAL USING C TO A CROSS-TIE (Page 6 of 6) 2.11 RELEASE the tags from the following valves:
- HV-F027A RHR LOOP A SUPP CHAMBER SPRAY HDR ISLN MOV 2.12 RELEASE tags from HV-FO04A AND HV-FO04C RHR PMP SUPP POOL SUCT MOVs.
2.13 ALIGN system as plant conditions require.
9 Hope Creek Page 31 of 45 Rev. 0
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SHUTDOWN COOLING This Page Intentionally Left Blank 0
Hope Creek Page 32 of 45 Rev. 0
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-ABRPV-0009(Q)
SHUTDOWN COOLING ATTACHMENT 2 ALTERNATE DECAY HEAT REMOVAL USING D TO B CROSS-TIE (Page I of 7)
NOTE 1.0 Operation of the D to B Cross-Tie is restricted to conditions when reactor coolant temperature is < 300'F (67 psia). [PR 970602179, PR 960927120]
1.0 Establishing Alternate Decay Heat Removal Using the D to B Cross-tie
[CD-609G]
1.1 ENSURE the AP System is available providing keepfill for all B Loop ECCS Systems required for operability. (1-AP-V062 CS Xfr to B Core Spray Dsch IsIn
[Rm. 4322B])
1.2 ENSURE that the Jockey Pump DP228 is secured AND tagged 1AW NC.NA-AP.ZZ-0015(Q); Safety Tagging Program.
(Breaker 52-242074) 1.3 CLOSE 1BC-V261 ECCS Jockey Pump D Suction Valve II AND TAG 1AW NC.NA-AP.ZZ-00I5(Q).
1.4 CLOSE the following valves:
ALL ACT'VE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 J'1L ELl CLiY HC.OP-AB.RPV.0009(Q)
SHUTDOWN COOLING This Page Intentionally Left Blank 0
Hope Creek Page 34 of 45 Rev. 0
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Onby HC.OP-AB.RPV-0009(Q)
SHUTDOWN COOLING ATTACHMENT 2 ALTERNATE DECAY HEAT REMOVAL USING D TO B CROSS-TIE (Page 2 of 7)
CAUTION 1.6 Manual or automatic opening of HV-FO07B(D) RHR PMP B(D) MIN FL MOV will drain the Reactor Vessel to the Suppression Pool.
1.6 ENSURE the following valves are closed:
1.7 VERIFY the following LPCI Injection Valves are closed, THEN DE-ENERGIZE AND TAG their power sources to ensure these valves do not open if a LPCI signal is received during cross-tie operating mode:
- HV-F027B =RHR LOOP B SUPP CHAMBER SPRAY HDR ISLN MOV (52-222083) 1.9 FULLY OPEN 1BC-y043 RHR Pmp D Suc Frn Recir Loop B (Rm. 4227D; Az 150 above catwalk)
AND TAG in the open position IAW NC.NA-AP.ZZ-0015(Q).
1.10 ENSURE F077 RECIRC LOOP B TO RHR SUP MAN VLV is open.
Hope Creek Page 35 of 45 Rev. 0
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SHUTDOWN COOLING This Page Intentionally Left Blank Hope Creek Page 36 of 45 Rev. 0
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE H.PA.P-09Q 2003%9122 PSEG Internal Use Only HC.0P-AB.RPV-0009(Q)
SHUTDOWN COOLING ATTACHMENT 2 ALTERNATE DECAY HEAT REMOVAL USING D TO B CROSS-TIE (Page 3 of 7) 1.11 IF the Shutdown Cooling suction line was isolated, THEN PERFORM a fill and vent IAW HC.OP-SO.BC-0002(Q),
Decay Heat Removal Operation.
1.12 ENSURE the following valves are open:
- HV-F008 SHUTDOWN COOLING OUTBD ISLN MOV
- HV-F009 SHUTDOWN COOLING INBD ISLN MOV.
1.13 UNLOCK AND OPEN lBC-V601 RHR Crosstie Iso Vlv B LOOP BC-ffV-11680 MOV (Rm. 4107A) 1.14 OPEN the following valves until a solid stream of water issues, THEN CLOSE (Local).
- IBC-V610 and lBC-V611 RHR B&D Loop X-Tie Vent Vlvs (Rm. 4107A)
- IBC-V608 and 1BC-V609 RHR B&D Loop X-Tie Vent Vlvs (Rm. 4107A) 1.15 CRACK OPEN IBC-V600 RHR X-Tie Iso Vlv Loops B&D. (Rm. 4107A) 1.16 OPEN IBC-V608 and IBC-V609 RHR B&D Loop X-Tie Vent Vlvs until a solid stream of water issues, THEN CLOSE (RrriA4107A)
- 1.17 OPEN IBC-V600 RHRX-Tie Iso Vlv Loops B&D. (Rm. 4107A) 9 Hope Creek Page 37 of 45 Rev. 0
ALL ACTNVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 1
2003U12YM Iternal Use Pnly HC.OP-AB.RPV-0009(Q)
SHUTDOWN COOLING This Page Intentionally Left Blank Hope Creek Page 38 of 45 Rev. 0
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-AB.RPV-0009(Q)
SHUTDOWN COOLING ATTACHMENT 2 ALTERNATE DECAY HEAT REMOVAL USING D TO B CROSS-TIE (Page 4 of 7)
NOTE 1.18 A. The interlock override will allow D RHR Pump to operate when the pump is aligned to the alternate suction from the RPV, when and if required.
B. In the cross-tie mode, D RHR Pump will not be automatically protected against the loss of suction from the RPV.
1.18 OBTAIN key to the l-BC-HS-1 1682 Keylock Switch from Work Control key cabinet.
1.19 PERFORM the following at Panel 10C640:
A. INSERT the key in the 1-BC-HS-1 1682 Keylock Switch.
B. OVERRIDE the HV-FO04D Valve/Pump D Interlock using the I-BC-HS-1 1682 Keylock Switch.
C. LOG in CRS Log the position of the Keylock Switch.
1.20 IF during the cross-tie operation mode, the HV-F008 or HIV-F009 close (e.g., on RPV Low Level 3 signal), then immediately STOP the D RHR Pump AND TAKE corrective action.
1.21 IF HV-F01 5B RHR LOOP B RET TO RECIRC LOOP B ISLN MOV does not open immediately to establish flow, THEN SECURE the RHR Pump.
Page 39 of 45 Rev. 0 Hope Creek
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 2003G122-3F IaKernal use Univ HC.OP-AB.RPV-0009(Q)
SHUTDOWN COOLING This Page Intentionally Left Blank Is 0
.0 Hope Creek Page 40 of 45 Rev. 0
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE HC.OP-AB.RPV-0009(Q) 2003(?122 PSEG Intern tal Use OnlY H.PA.P-09Q SHUTDOWN COOLING ATTACHMENT 2 ALTERNATE DECAY HEAT REMOVAL USING D TO B CROSS-TIE (Page 5 of 7)
CAUTION 1.22 Manual or automatic opening of HV-F007B(D) RHR PMP B(D) MIN FL MOV will drain the Reactor Vessel to the Suppression Pool.
1.22 START RHR PUMP DP202 and immediately THROTTLE OPEN HV-F0l 5B RHR LOOP B RET TO RECIRC LOOP B ISLN MOV UNTIL FI-R603D LOOP D FLOW indicates 3000 GPM.
.0 OBSERVE AI-6358D PUMP D MOT AMPS.
. MAINTAIN flow of 3000 gpm for at least 10 minutes.
1.23 OPEN HV-FO15B RHR LOOP B RET TO RECIRC LOOP B ISLN MOV UNTIL FI-R603D LOOP D FLOW indicates 10,000 gpm.
Hope Creek Page 41 of 45 - Rev. 0
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SHUTDOWN COOLING This Page Intentionally Left Blank Hope Creek Page 42 of 45 Rev. 0
ALL ACTWE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030-22 This Pl'&yv' HC.OP-AB.RPV.0009(Q)
SHUTDOWN COOLING This Page Intentionally Left Blank Hope Creek Page 44 of 45 Rev. 0
ALL ACTTWE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030Y22 £ LYJ".£USV11 ant VW J1113 HC.OP-AB.RPV-0009(Q)
SHUTDOWN COOLING ATTACHMENT 2 ALTERNATE DECAY HEAT REMOVAL USING D TO B CROSS-TIE (Page 7 of 7) 2.11 RELEASE the tags from the following valves:
.2.12 RELEASE tags from HV-FO04B AND HV-FO04D RHR PMP SUPP POOL SUCT MOV.
2.13 ALIGN system as plant conditions require.
9 Hope Creek Page 45 of 45 Rev. 0 N
UU
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-AB;RPV-0009(Q)
SHUTDOWN COOLING REVISION
SUMMARY
Rev. 0 This procedure has been re-formatted into a two-column format as part of the Hope Creek-Abnormal Operating Procedure upgrade project. This procedure supercedes HC.OP-AB.ZZ-0142(Q). The sequence of steps have been re-arranged to provide better flow of the steps. The information previously contained in the discussion section has been moved to the Bases Document for this procedure. Revision bars have been omitted from this revision due to the number of changes that have been made.
The following list of Editorial changes has been made to this procedure:
- 1. Added new Alarms and Indications which are indicative of an RHR pump trip, shutdown cooling suction Line isolation, and shutdown cooling flow bypass event.
- 2. Added Automatic Actions for Shutdown Cooling valves.
- 3. Incorporated former Attachment 1 into the body of the procedure.
- 4. Deleted former Note 4.8. The intent ofthis note is satisfied by the Condition statement for this section.
- 5. Reworded sub-steps of former step 4.8 and added a note for clarity.(80023233)
- 6. Changed "Alternate Shutdown Cooling" in Attachments 1 and 2 to "Alternate Decay Heat Removal" IAW SQR Reviewer comments.
The following list of Non-Editorial changes has beenrmade to this procedure:
- 1. Changed former Note 4.0 to indicate the respective Integrating Operating procedure may identify which mode of Alternate Decay Heat Removal would be effective as determined by Engineering.
Reference to HC.OP-SO.BC-0002(Q) was deleted. The abnormal action steps direct the operators to this procedure at the appropriate times.
- 2. Deleted former step 4.1. The CRS will determine when conditions are appropriate for exiting the abnormal.
- 3. Former step 4.4 was expanded to specific corrective actions throughout the abnormal.
- 4. Former step 4.5 was modified to include a one hour time limit. This is consistent with T/S 3.9.11.1 actionb.
- 5. Added guidance to bypass the regenerative heat exchanger IAW SOP if necessary to provide additional decay heat removal.
- 6. Expanded guidance on using Condensate Transfer for feed and bleed cooling. Existing guidance was inadequate and required entry into High Radiation areas to manually throttle MOVs.
- 7. Deleted former step 4.7.c to use head spray. For Hope Creek, head spray operation depends on having an RHR pump in Shutdown Cooling. If I have an RHR pump operating in Shutdown Cooling, I would not be in this abnormal. Additionally, head spray injects into the steam dome.
Hope Creek Core Spray and RHR inject inside the core shroud, which is more effective at providing core circulation and cooling.
- 8. Former step 4.8.12 was deleted.
- 9. Based on 50.59 reviewer input, the maximum RPV to torus d/p when performing Alternate Shutdown Cooling lAW Condition 'H' was raised from 140 to 160 psi.
____ e Hope Creek Page I of 1 Rev. 0
NC.TQ-WB.ZZ-031 0(Z)
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: HOPE CREEK SYSTEM: 234000 Fuel Handling Equipment TASK: Bent Mast IAW HC.OP-SO.KE-0001 (Q) Attachment 2 (Alternate Path)
TASK NUMBER: N2340040104 JPM NUMBER: 2003-NRC-S3 ALTERNATE PATH: 3 K/A NUMBER: 234000 A2.03 APPLICABILITY: IMPORTANCE FACTOR: 2.8 3.1 EO = RO = SRO 3 LSRO 3 RO SRO EVALUATION SETTING/METHOD: REFUELING PLATFORM - PERFORM / SIMULATE
REFERENCES:
HC.OP-SO.KE-0001 Rev.,,2HC.RE-FR.ZZ-0001 Attachment 1 TOOLS AND EQUIPMENT: Refueling Platform, Dummy Bundle, Move Sheet VALIDATED JPM COMPLETION 10 min.
TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A APPROVED: _ ,i N/A Q0 BARGAINING UNIT REPRESENTATIVE CAUTION: No plant equipment shall be operated during the performance of a JPM without the following:
- 1. Permission from the OS or Unit CRS,
- 2. Direct oversight by a qualified individual (determined by the individual granting permission based on plant conditions).
- 3. Verification of the "as left" condition by a qualified individual.
ACTUAL JPM COMPLETION TIME: min.
ACTUAL TIME CRITICAL COMPLETION TIME: N/A min.
JPM PERFORMED BY: GRADE: F SAT _I UNSAT REASON, IF UNSATISFACTORY:
EVALUATOR'S SIGNATURE: DATE:
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NC.TQ-WB.ZZ-031 0(Z)
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:
DATE:
SYSTEM: 234000 Fuel Handling Equipment TASK: Bent Mast IAW HC.OP-SO.KE-0001(Q) Attachment 2 (Alternate Path)
TASK N2340040104 INITIAL CONDITIONS:
- You are the Refueling Bridge operator.
- The Reactor is in Operational Condition 4 preparing for refueling.
- The Refuel Platform is in a standby lineup, powered up, and warmed up > 1/2 hour.
- A Spotter and Refueling SRO are standing by.
- The Dummy bundle is being used to simulate an irradiated fuel bundle.
- The Dummy bundle is full up on the Main Hoist being moved IAW Move Sheet Step #02.
- You are to continue HC.OP-SO.KE-0001 at step 5.8.16.
INITIATING CUE:
Place the bundle in its designated storage location IAW the move sheet step #2.
Successful Completion Criteria:
- 1. All critical steps completed.
- 2. All sequential steps completed in order.
- 3. All time-critical steps completed within allotted time.
- 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made (and NRC concurrence is obtained).
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OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: 234000 Fuel Handling Equipment TASK: Bent Mast IAW HC.OP-SO.KE-0001(Q) Attachment 2 (Alternate Path)
STEP STEP COMMENTS
- NO. (*Denotes a Critical Step) STANDARD EVAL (Required for UNSAT
(#Denotes a Sequential Step) ll_l S/U evaluation)
Operator obtains procedure HC.OP-SO.KE- Operator obtains the correct procedure.
0001.
Operator reviews prerequisites, precautions Operator reviews prerequisites, and limitations. precautions and limitations.
Examiner Cue: If excessive time is taken reviewing prerequisites, precautions and limitations, inform operator that all are satisfied.
Operator determines beginning step of the Operator determines correct beginning step procedure. to be 5.8.16 of HC.OP-SO.KE-0001(Q)
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OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: 234000 Fuel Handling Equipment TASK: Bent Mast lAW HC.OP-SO.KE-0001 (Q) Attachment 2 (Alternate Path)
STEP STEP COMMENTS
- NO. (*Denotes a Critical Step) STANDARD EVAL (Required for UNSAT ll_l_(#Denotes a Sequential Step) l_l SIU evaluation) 5.8 Fuel/Blade Guide Movement - Within Spent Examiner Note: All operations for this Fuel Storage Pool (other than Refuel Mode) JPM are performed on the Refueling in Manual, Platform.
Initialing steps is not critical A generic Fuel Movement sheet is provided where MOVE Step #1 is the DUMMY BUNDLE from the normal storage location to an empty spare Fuel Pool location.
Move Step #2 is from the spare location back to the normal storage location.
Examiners Cues proceeded by a $ are given ONLY if the evolution is SIMULATED.
The operator may log on to the Refuel Platform Computer but it is not necessary when operating in Manual Mode.
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NC.TQ-WB.ZZ-031 0(Z)
OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: 234000 Fuel Handling Equipment TASK: Bent Mast lAW HC.OP-SO.KE-0001(Q) Attachment 2 (Alternate Path)
P _ _ _
STEP I EVAL COMMENTS (Required for UNSAT
- Denotes a Critical Stei STANDARD SIU evaluation) 0.0. 10 START TIME: Operator uses the PLATFORM AND TROLLEY control operators to maneuver USE the Refuel Platform AND Trolley the Fuel Grapple using position indication cameras so that it is positioned over Fuel Position Controls AND Position Indicating Pool location AD-28 in accordance to the System to maneuver the Fuel Grapple to the fuel movement sheet.
target location listed on the Fuel Movement Sheet(s). $ Examiner Cue: "The controls respond to the directions stated."
$ Examiner Cue: "The grapple is positioned over the location stated."
5.8.17 ENSURE the Fuel Grapple is at the correct Operator ensures the grapple is positioned Core OR Fuel Pool Coordinates. over Fuel Pool location AD-28 in (REFER TO Note 5.8) accordance to the fuel movement sheet.
$ Examiner Cue: "The grapple is positioned over the location stated."
- 5.8.18 ROTATE the Fuel Grapple AND attached Operator rotates the Fuel Grapple and fuel assembly/blade guide to attain direct attached fuel assembly to attain direct alignment AND orientation with the target alignment and orientation with the target location, location.
[CD-396Y] $ Examiner Cue: "The grapple and fuel assembly are oriented and aligned over the location stated."
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NC.TQ-WB.ZZ-031 0(Z)
OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: 234000 Fuel Handling Equipment TASK: Bent Mast lAW HC.OP-SO.KE-0001(Q) Attachment 2 (Alternate Path)
STEP STEP COMMENTS
- NO. (*Denotes a Critical Step) STANDARD EVAL (Required for UNSAT llll___(#Denotes a Sequential Step) S/U evaluation)
- 5.8.19 Slowly LOWER the fuel assembly/blade
- Operator lowers the Fuel Grapple and guide into the target location using the Fuel Dummy bundle using the Fuel Grapple Grapple hoist position control in the LOWER Hoist control in the LOWER position.
position. $ Examiner Cue: "The grapple is lowering; the GRAPPLE NORMAL UP light is off."
SRO / Examiner Cue: Wait 5 seconds or until Z reading of 30 and cue...
"Stop Hoist Travel"
- The operator stops hoist movement.
Examiner Cue: After the hoist is stopped...
"The grapple has stopped suddenly.
The SLACK CABLE light is lit with the hoist at Z Position 39. The load cell is reading 25 pounds. The spotter saw the cable go slack and it remains slack."
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OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: 234000 Fuel Handling Equipment TASK: Bent Mast lAW HC.OP-SO.KE-0001(Q) Attachment 2 (Alternate Path)
- STEP STEP l COMMENTS
(*Denotes a Critical Step) STANDARD EVAL (Required for UNSAT
- NO.
I (#Denotes a Sequential Step) l_l S/U evaluation)
- Operator notifies Refueling SRO or CRS/OS.
- Operator determines the mast is bent or binding by the valid SLACK CABLE light on with the grapple loaded and not in contact with any structure.
Examiner Note: Allow the operator reasonable time to determine cause.
I I4-HC.OP- Operator determines correct procedure is SO.KE- HC.OP-SO.KE-0001 Attachment 2 0001 beginning step to be 2.0 Bent Mast.
Attach-ment 2 2.0 Bent Mast (or Precaution 3.1.7) Examiner Note: Operator may use Precaution 3.1.7 which provides the same guidance. The action taken would also be the same.
Note 2.0 DO NOT attempt to lower or release the Operator reads Note 2.0 bundle without SRO approval if a bent Mast is encountered.
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OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: 234000 Fuel Handling Equipment TASK: Bent Mast lAW HC.OP-SO.KE-0001 (Q) Attachment 2 (Alternate Path)
STEP STEP COMMENTS
- NO. (*Denotes a Critical Step) STANDARD EVAL (Required for UNSAT
(#Denotes a Sequential Step) S/U evaluation)
Operator reads step 2.0
- ... IF while lowering the mast, an Examiner Note: If permission is requested unexpected slack cable or pre-mature to raise the hoist, then Cue: "Permission weight transfer occurs, stop lowering, raise is given.
the load to clear the slack cable (if one Operator raises main fuel hoist to clear exists), and notify the cognizant Refuel SRO SLACK CABLE light using the Fuel Grapple or OS/CRS before attempting any corrective Hoist control in the RAISE position.
action.
Examiner Cue: SLACK CABLE light is off.
Operator notifies Refueling SRO and/or CRS/OS to initiate a Notification.
Examiner Cue: Acknowledge the request for corrective action.
STOP TIME: Termination Cue: This JPM is complete.
A different refueling crew will troubleshoot the Mast problem.
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JOB PERFORMANCE MEASURE INITIAL CONDITIONS:
- You are the Refueling Bridge operator.
- The Reactor is in Operational Condition 4 preparing for refueling.
- The Refuel Platform is in a standby lineup, powered up, and warmed up > 1/
2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
- A Spotter and Refueling SRO are standing by.
- The Dummy bundle is being used to simulate an irradiated fuel bundle.
- The Dummy bundle is full up on the Main Hoist being moved IAW Move Sheet Step #2.
- You are to continue HC.OP-SO.KE-0001 at step 5.8.16.
INITIATING CUE:
Place the bundle in its designated storage location IAW the move sheet step #2.
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HC.RE-FR.ZZ-OOU i(Q)
ATTACHMENT 1 FUEL MOVEMENT SHEET REFUEL NO. IN/A SHEET NO. 1 CONTINUED ON SHEET N/A Step I.D. FROM Time TO Time Operator Verified By Number Number Location Orientation Date Location Orientation Date Initials Initials 01 DUMMY SFP ANY SFP NE AD - 28 AH - 50 02 DUMMY SFP NE SFP NW AH - 50 AD - 28 (Lk Le raL, Prepared By Q4a.L a5PEZe7L PCoz fLrC(a, LLk id(
Date Independently Verified By Date Hope Creek Page 18 of 23 Rev. 20
NC.TQ-WB.ZZ-0310(Z)
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: HOPE CREEK SYSTEM: Refueling Platform JPM NUMBER: 2003-NRC-S4 TASK: Perform the Monorail Auxiliary Hoist Controls Functional Test TASK NUMBER: N2340010204 ALTERNATE PATH: N/A K/A NUMBER: 234000 A3.01 IMPORTANCE FACTOR: 2.6 3.6 RO SRO APPLICABILITY: EO F ROD2 STA :] SRO F LSROFX EVALUATION SETTING/METHOD: Walkthrough/Simulate (Perform)
REFERENCES:
HC.OP-FT.KE-0001(Q), Rev. 16 TOOLS AND EQUIPMENT: Refueling Platform/None VALIDATED JPM COMPLETION TIME: 20 Min.
TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Min.
APPROVAL: N/A L iL 2PE IONS BARGAINING UNIT TRAINING SUPERVISOR AGnR REPRESENTATIVE or De ee CAUTION: No plant equipment shall be operated during the performance of a JPM without the following:
- 1. Permission from the OS or Unit CRS;
- 2. Direct oversight by a qualified individual (determined by the individual granting permission based on plant conditions).
- 3. Verification of the "as left" condition by a qualified individual.
ACTUAL JPM COMPLETION TIME: Min.
ACTUAL TIME CRITICAL COMPLETION TIME: N/A Min.
JPM PERFORMED BY: GRADE: FI SAT [I1 UNSAT REASON, IF UNSATISFACTORY:
EVALUATOR'S SIGNATURE: DATE:
Rev. 0 Nuclear Common Page 1 Page 1 ofl2 of 12 Rev. 0
NC.TQ-WB.ZZ-031 0(Z)
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:
DATE:
SYSTEM: Refueling Platform JPM NUMBER: 2003-NRC-S4 TASK: Perform the Monorail Auxiliary Hoist Controls Functional Test TASK NUMBER: N2340010204 INITIAL CONDITIONS:
- HC.OP-FT.KE-0001 is in progress.
INITIATING CUE:
Perform the Monorail Auxiliary Hoist Controls Functional Test lAW HC.OP-FT.KE-0001.
Successful Completion Criteria:
All critical steps completed.
All sequential steps completed in order.
All time-critical steps completed within allotted time.
JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
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JPM NUMBER: 2003-NRC-S4 OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: Refueling Platform TASK: Perform the Monorail Auxiliary Hoist Controls Functional Test IAW HC.OP-FT.KE-0001.
NO. (*Denotes a Critical Step) STANDARD (Required for UNSAT L (#Denotes a Sequential Step) S evaluation)
Examiner Note:
Provide operator with marked up copy of HC.OP-FT.KE-0001.
The operator may log onto the Refuel Bridge Computer. This is not required for Monorail Hoisi operation.
Examiners Cues proceeded by a $ are given ONLY if the evolution is SIMULATED.
Operator reviews precautions and limitations Operator reviews precautions and limitations.
Examiner Cue:
If excessive time is taken reviewing precautions and limitations, inform operator that all are satisfied.
Operator determines beginning step of The operator determines the correct beginning procedure step of the procedure to be 5.4.1.
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JPM NUMBER: 2003-NRC-S4 OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: Refueling Platform TASK: Perform the Monorail Auxiliary Hoist Controls Functional Test IAW HC.OP-FT.KE-0001.
STPSTEP EVLCOMMENTS
- STEP (*Denotes a Critical Step) STANDARD EVA (Required for UNSAT
_ NO. (#Denotes a Sequential Step) l evaluation)
NOTE 5.4. IF defective or inoperative equipment is discovered while conducting Operator reads Note.
this test, a Notification should be generated which directs equipment repair.
CAUTION 5.4 During movement of the Refuel Platform ensure that the Fuel Grapple Operator reads Caution.
is not damaged by impact with the Fuel Pool walls or underwater obstructions.
- 5.4.1 START TIME Examiner Note: Initialing Attachment 2 in At the Start/Stop Station, the following steps is not critical.
TURN the CONSOLE SELECT switch to Operator turns the Start/ Stop Station MONO. CONSOLE SELECT switch to MONO.
$ Examiner Cue: The switch that you indicated is in the position stated.
- 5.4.2 On the Monorail Pendant, Operator moves the Monorail Pendant PRESS the BRIDGE FORWARD joystick. BRIDGE joystick to the FORWARD position VERIFY the following to maneuver the Refueling Platform.
AND INITIAL Attachment 2. $ Examiner Cues: The control indicated is in the position stated.
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JPM NUMBER: 2003-NRC-S4 OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: Refueling Platform
-r A ' [Z. ODrfnrm thn KAnnnrnil Ailt;Iiarv Hnikt Cnntrnl Fuinrtional Test 1AW HC-OP-FT.KE-0001.,
I - ;r :* t, I I l AUAIIII.A I . IVIM t,. t411 . , , , , -_.
ITEPSTEP lV lLCOMMENTS STEP (*Denotes a Critical Step) STANDARD S/U (Required for UNSAT
- NO. (#Denotes a Sequential Step) llevaluation)_l
_ A. Refuel Platform moves North Refuel Platform moves in direction indicated.
B. Speed control is smooth and continuous. Speed control is smooth and continuous.
C. Refuel Platform movement alarm is Refuel Platform movement alarm is sounding AND the warning beacon is sounding and the indicating beacon is illuminated. illuminated.
D. VERIFY Bridge motion from only this Operator observes other control stations station. are not in use.
- 5.4.3 RELEASE the BRIDGE FORWARD joystick., Operator releases BRIDGE joystick.
VERIFY the following AND INITIAL Attachment 2.
$ Examiner Cues:
A. Refuel Platform movement stops. Bridge stops.
B. Refuel Platform movement alarm is silent Alarm is quiet and warning beacon is and warning beacon is extinguished. extinguished.
- 5.4.4 PRESS the BRIDGE REVERSE joystick Operator moves the Monorail Pendant VERIFY the following BRIDGE joystick to the REVERSE position.
AND INITIAL Attachment 2. $ Examiner Cues: The control indicated is in the position stated.
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JPM NUMBER: 2003-NRC-S4 OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: Refueling Platform TASK: Perform the Monorail Auxiliary Hoist Controls Functional Test IAW HC.OP-FT.KE-0001.
- STEP STEPEVLCM NT NO (*Denotes a Critical Step) STANDARD EA ( COMMENTS NO. (#Denotes a Sequential Step) S/Uevaluation)
A. Refuel Platform moves south. Refuel Platform moves in direction indicated.
B. Speed control is smooth and continuous. Speed control is smooth and continuous.
C. Refuel Platform movement alarm is Refuel Platform movement alarm is sounding AND the warning beacon is sounding and the warning beacon is illuminated. illuminated.
- 5.4.5 RELEASE the BRIDGE REVERSE joystick Operator releases the BRIDGE joystick.
VERIFY the following $ Examiner Cues: The control indicated is AND INITIAL Attachment 2. in the position stated.
A. Refuel Platform motion stops. Refuel Platform motion stops.
B. Refuel Platform movement alarm is silent Refuel Platform movement alarm is silent and warning beacon is extinguished. warning beacon is extinguished.
- 5.4.6 PRESS the TROLLEY RIGHT pushbutton, Operator presses the TROLLEY RIGHT VERIFY the following pushbutton.
AND INITIAL Attachment 2. $ Examiner Cues: The pushbutton indicated is in the position stated.
A. Trolley moves west. Monorail Trolley moves in direction indicated.
B. Speed control is smooth and continuous. Speed control is smooth and continuous.
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NC.TQ-WB.ZZ-031 0(Z)
JPM NUMBER: 2003-NRC-S4 OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: Refueling Platform TASK: Perform the Monorail Auxiliary Hoist Controls Functional Test IAW HC.OP-FT.KE-0001.
STEP I COMMENTS STEP (*Denotes a Critical Step) STANDARD EVAL (Required for UNSAT
. (#Denotes a Sequential Step) ___evaluation)
- 5.4.7 RELEASE the TROLLEY RIGHT pushbutton, Operator releases the TROLLEY RIGHT VERIFY the Trolley motion stops pushbutton.
AND INITIAL Attachment 2. $ Examiner Cue:
Trolley motion stops.
- 5.4.8 PRESS the TROLLEY LEFT pushbutton, Operator presses the TROLLEY LEFT VERIFY the following pushbutton.
AND INITIAL Attachment 2. $ Examiner Cues: The pushbutton indicated is in the position stated.
A. Trolley moves east. Monorail Trolley moves in direction indicated.
B. Speed control is smooth and continuous. Speed control is smooth and continuous.
- 5.4.9 RELEASE the TROLLEY LEFT pushbutton, Operator releases the TROLLEY LEFT VERIFY the Trolley motion stops pushbutton.
AND INITIAL Attachment 2. $ Examiner Cue: Trolley motion stops Nuclear Common Page 7 of 13 Rev. 0
NC.TQ-WB.ZZ-031 0(Z)
JPM NUMBER: 2003-NRC-S4 OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: Refueling Platform TASK: Perform the Monorail Auxiliary Hoist Controls Functional Test IAW HC.OP-FT.KE-0001.
- STEP STEP EVAL COMMENTS NO (*Denotes a Critical Step) STANDARD (Required for UNSAT N (#Denotes a Sequential Step) evaluation)
_ 5.4.10 PRESS the HOIST LOWER pushbutton, Examiner Cue: Simulate remaining Hoist AND LOWER the grapple to greater than 7 steps.
feet below the surface of the water to clear Operator presses the HOIST LOWER the hoist override. pushbutton.
VERIFY the following The hoist cable moves downward at least 6 AND INITIAL Attachment 2 inches below the Normal Up stop.
$ Examiner Cues: The pushbutton indicated is in the position stated.
A. Monorail Hoist cable moves downward. Monorail Hoist cable moves in the direction indicated.
B. Speed control has high and low speed and Speed control has high and low speed is smooth and continuous. and is smooth and continuous.
- A slight depression on the pushbutton will Hoist runs slow.
produce a slow speed.
- A full depression on the pushbutton will Hoist runs slow then fast.
produce a slow speed for a short period of time then switch to fast speed.
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NC.TQ-WB.ZZ-031 0(Z)
JPM NUMBER: 2003-NRC-S4 OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: Refueling Platform TASK Perform the Monorail Auxiliary Hoist Controls Functional Test IAW HC.OP-FT.KE-0001.
S P STEP IVL COMMENTS
- NO. (*Denotes a Critical Step) STANDARD EVAL (Required for UNSAT NO. (#Denotes a Sequential Step) evaluation)
- 5.4.11 RELEASE the HOIST LOWER pushbutton, Operator releases HOIST LOWER VERIFY the hoist cable motion stops pushbutton.
AND INITIAL Attachment 2. $ Examiner Cue:
Hoist cable motion stops.
- 5.4.12 PRESS the HOIST RAISE pushbutton, Operator presses HOIST RAISE pushbutton.
VERIFY the following $ Examiner Cues: The pushbutton AND INITIAL Attachment 2. indicated is in the position stated.
A. Monorail Hoist cable moves upward. Monorail Hoist cable moves in direction indicated.
B. Speed control has high and low speed and Speed control has high and low speed is smooth and continuous and is smooth and continuous.
- A slight depression on the pushbutton will Hoist moves at a slow speed.
produce a slow speed.
- A full depression on the pushbutton will Hoist moves at a slow speed for a short produce a slow speed for a short period period of time then switch to fast speed.
of time then switch to fast speed.
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JPM NUMBER: 2003-NRC-S4 OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: Refueling Platform TASK: Perform the Monorail Auxiliary Hoist Controls Functional Test IAW HC.OP-FT.KE-0001.
STEP COMMENTS STEP (*Denotes a Critical Step) STANDARD E L RevuatioN)SA NO. (#Denotes a Sequential Step) (Req evaluation)SA 5.4.13 RELEASE the HOIST RAISE pushbutton Operator releases HOIST RAISE pushbutton before it reaches the Normal Up Rotary before the hoist reaches the Normal Up stop.
electrical stop, $ Examiner Cue:
VERIFY the hoist cable motion stops Hoist cable motion stops below the AND INITIAL Attachment 2. Normal Up stop.
- 5.4.14 PRESS the HOIST RAISE pushbutton to Operator presses HOIST RAISE pushbutton raise the hoist cable to the Normal Up Rotary until hoist automatically stops.
electrical stop. $ Examiner Cue: The pushbutton VERIFY the hoist cable motion automatically indicated is in the position stated.
stops Hoist cable rises until automatically AND INITIAL Attachment 2. stops.
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JPM NUMBER: 2003-NRC-S4 OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: Refueling Platform TASK: Perform the Monorail Auxiliary Hoist Controls Functional Test IAW HC.OP-FT.KE-0001.
- STEP STEP EVLCOMMENTS N (*Denotes a Critical Step) STANDARD S/U (Required for UNSAT
(#Denotes a Sequential Step) evaluation)
NOTE 5.4.15 Operator reads Note.
The Mechanical Jam Stop may be moved down on the cable to check the MAX UP Examiner Cue: Moving the Mechanical ROTARY Switch. HC.OP-SO.KE-0001(Q) Jam Stop is not required.
should be referred to for stop setup.
Examiner Note: Depending where the Mechanical Jam Stop is positioned, simulation of step 5.4.15 may be required.
- 5.4.15 Simultaneously PRESS the HOIST LIMIT Operator simultaneously presses the HOIST OVERRIDE LIMIT OVERRIDE and HOIST RAISE AND HOIST RAISE pushbuttons. pushbutton until hoist automatically stops.
VERIFY the Monorail Hoist cable moves $ Examiner Cue: The pushbutton upward indicated is in the position stated. The Hoist cable rises until automatically AND automatically stop at the Maximum Up stops.
Rotary limit switch cut-out Examiner Cue:
AND INITIAL Attachment 2. Another refueling crew will finish the remaining steps of the procedure.
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JPM NUMBER: 2003-NRC-S4 OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: Refueling Platform TASK: Perform the Monorail Auxiliary Hoist Controls Functional Test lAW HC.OP-FT.KE-0001.
U p-STEP I COMMENTS
(*Denotes a Critical Ste EVAL (Required for UNSAT STANDARD SWu evaluation)
STOP TIME: Terminating Cue: Repeat back message from the operator on the status of the JPM, and then state "This JPM is complete".
I __________________________________ L ____ I _____________________
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JOB PERFORMANCE MEASURE STUDENT INFO SHEET INITIAL CONDITIONS:
- HC.OP-FT.KE-0001 is in progress.
INITIATING CUE:
Perform the Monorail Auxiliary Hoist Controls Functional Test IAW HC.OP-FT.KE-0001.
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PSEG Internal Use Only Page 1 of l PSEG NUCLEAR L.L.C. CCO4T RtL GQPY#
HOPE CREEK GENERATING STATIC N
- 0-70't-HC.OP-FT.KE-0001(Q) - Rev. 17 REFUELING PLATFORM AND FUEL GRAPPLE OPERABILITY TEST - REFUELING USE CATEGORY: I A. Biennial Review performed Yes No N/A B. Change Package(s) and Affected Document Number(s) incorporated into this revision.
- OTSC No(s) or None V REVISION
SUMMARY
- 1. The following changes have been incorporated based on DCP 80047191:
- 5.1.7 has been revised to indicate the verification performed is visual.
- Steps 5.2.1.D - TOUCH the SELECT MANUAL on the Touch Screen has been deleted, function does not exist..
- Steps 5.2.1.E - ENSURE the MANUAL OPERATION ACTIVE button is being displayed has been deleted, function does not exist..
- Step 5.2.2.D.5 and 5.2.2.F.5 - have been revised to indicate the readout increases in the negative direction.
- Step 5.2.2.H.3 has been revised to replace " increases in negative numbers"
- Step 5.2.2.J.3 has been revised to replace " decreases in negative numbers"
- Step 5.2.3.M and 5.2.3.R have been revised to correct step referenced.
- Step 5.2.3.U hasd been revised to indicate the TRAVEL OVERRIDE PB is also required to be pressed.
IMPLEMENTATION REQUIREMENTS Effective date 3- 2 0$tf I APPROVED: - s _ _ , _
3I2*7e3 Manager - Hope Cycf1k Operations Date
PSEG Internal Use Only HC.OP-FT.KE-OOOl(Q)
REFUEL PLATFORM AND FUEL GRAPPLE OPERABILITY TEST - REFUELING TABLE OF CONTENTS Section Title Page 1.0 PURPOSE .2 2.0 PREREQUISITES .2 3.0 PRECAUTIONS & LIMITATIONS .
4.0 EQUIPMENT REQUIRED .5 6
5.0 PROCEDURE ...........
5.1 Refuel Platform General Visual Inspection. 6 Fuel Grapple Controls and Grapple Hoist Functional Test. 8 5.2 5.3 Frame Auxiliary Hoist Controls Functional Test ................................... 20 25 5.4 Monorail Auxiliary Hoist Controls Functional Test ................................
5.5 Procedure Completion Instructions ................................... 30 6.0 RECORDS .32
7.0 REFERENCES
.33 ATTACHMENTS Attachment 1 Data Sheet - Deficiency Summary .34 Attachment 2 Functional Test - Check Sheet .36
)
Page 1 of 40 Rev. 17 Hope Creek
PSEG Internal Use Only HC.OP-FT.KE-0001(Q)
REFUEL PLATFORM AND FUEL GRAPPLE OPERABILITY TEST - REFUELING 1.0 PURPOSE This procedure provides detailed instructions for insuring the operational readiness of the Refuel Platform and Fuel Grapple. This procedure should be performed after Refuel Platform and Fuel Grapple related maintenance has been completed and prior to the refueling outage.
[CD-182C, CD-281C]
2.0 PREREQUISITES 2.1 Permission to perform this procedure has been obtained from the OS/CRS as indicating by a signature on Attachment 1 of this procedure.
2.2 No testing, maintenance or other activity is in progress on the Refuel Platform or in the Spent Fuel Pool, New Fuel Vault or Shipping Cask Pit which would impede the movement of the Refuel Platform is in progress.
2.3 ENSURE that AC power is available to the Refuel Platform by verifying that Breaker 52-254061 closed. Breaker 52-254061 should be closed to ensure adequate warm up prior to performing this procedure (the minimum warm up time is l/2 hour).
The Control Panels have heaters that require power to prevent condensation between periods of use (outages).
2.4 OBTAIN the Fuel Pool Storage location for the Dummy Bundle from Reactor Engineering.
2.5 VERIFY the Fuel Grapple Mast Stowage Clamp has been removed prior to moving the Fuel Grapple.
2.6 HC.MD-PM.KE-0003(Q); Refueling Platform Operational Check and HC.OP-ST.KE-000I(Q), Refuel Interlock Operability Functional Test - Section 5.4 fl have been completed. _
2.7 INITIAL Attachment 2 signifying all prerequisites listed above are satisfied. L Hope Creek Page 2 of 40 Rev. 17
HC.OP-FT.KE-0001(Q)
PSEG Internal Use Only 3.0 PRECAUTIONS AND LIMITATIONS 3.1 Precautions 3.1.1 NO fuel assemblies are to be grappled this procedure.
OR moved while conducting Fuel Grapple 3.1.2 Prior to moving the Refuel Platform, OR Monorail Hoist:
A. IDENTIFY OR REPOSITION underwater obstructions cables B. REMOVE all hoses, ropes, electrical Platform tracks OR other equipment from the Refuel cables C. ENSURE all hoses, ropes, electrical to the Refuel Platform OR other equipment are not secured Refuel Platform (Bridge), Trolley in a manner that would restrict OR Monorail Hoist movement.
D. ENSURE the Jib Cranes positioned AND Fuel Channeling Boom are with Refuel Platform (Bridge) so they will not interfere OR Trolley motion.
of the Refuel Platform 3.1.3 The Spent Fuel Pool and portions material.
are contaminated with radioactive requirements listed OBTAIN AND FOLLOW the on the Radiation Work Permit.
lamps 3.1.4 To prevent damage to underwater fully submerged ENSURE that the lamps remain while they are energized.
(Bridge), Trolley 3.1.5 Operation of the Refuel Platform speed control operators should OR Fuel Grapple with the variable and decelerations, be accomplished by gradual accelerations of the operators.
rather than full on and full off deflections control.
the equipment and better operator This will produce less wear on the NEVER be left unattended with 3.1.6 The Refueling Platform should Station).
the STOP light on the Start/Stop "POWER ON" (as indicated by accord.
electrical failure could cause the platform to move on its own An the for short durations while the operator leaves Turning off the powerstandard practice.
platform should be a Rev. 17 Page 3 of 40 BApe r Hlope qtg-rme
HC.OP-FT.KE-0001(Q)
PSEG Internal Use Only 3.1.7 Abnormalities that may occur during operation, such as spurious high load readings OR audible indications should not be ignored.
Such occurrences must be investigated AND the cause ascertained to prevent possible subsequent damage to the platform or handled fuel.
3.1.8 Should an emergency stop occur during lowering of auxiliary delay OR monorail hoists, the safety brake of that hoist will set without AND take the hoist load on its ratchet-pawl arrangement.
Prior to attempting to releasing the brake, the cause of the emergency stop should be understood.
IF possible, the grapple should be moved away from irradiated fuel prior to performing the release.
stop, In the case where a full load is being lowered at the time of the this load may prevent the safety brake from immediately releasing to raise on a subsequent hoist operation, unless the hoist is commanded brake.
as an initial operation, thereby taking the load off the safety it will emit IF the brake does not release because of a lowering command, In most a loud chattering noise, alerting the operator to raise the load.
not following this cases, no harm will occur as the result of an operator prevent procedure. The only consequence is that the safety brake will the hoist from lowering.
Hoist, 3.1.9 Should an emergency stop occur during the lowering of the Main load.
the hoist safety brake will set without delay and take the hoist Prior to attempting to release the brake, the cause of the emergency stop should be understood.
IF possible, the grapple should be moved away from irradiated fuel prior to performing the release.
stop, In the case where a full load is being loaded at the time of the on a this load may prevent the safety brake from immediately releasing raise as subsequent hoist operation, unless the hoist is commanded to an initial operation, thereby taking the load off the safety brake.
In most cases, no harm will IF the brake does not release because of a lowering command, The only occur as the result of an operator not following this procedure.
lowering.
consequence is that the safety brake will prevent the hoist from fAft ID,--A-T WA Rev. 17 Xdr,%; vv Hope Creek
PSEG Internal Use Only HC.OP-FT.KE-0001(Q) 3.2 Limitations 3.2.1 During movement of the Refuel Platform (Bridge),
Trolley and Fuel Grapple ENSURE that the Fuel Grapple is not damaged by impact WITH the Spent Fuel Pool walls or underwater obstructions.
3.2.2 While slowly removing submerged tools OR equipment from the Spent Fuel Pool water, MONITOR radiation levels to assure personnel safety and radiation exposure is minimized. [CD-217B]
3.2.3 USE established procedures to prevent the spread of radioactive materials WHEN removing contaminated equipment from the Spent Fuel Pool water.
3.2.4 A designated "spotter" is required for all bridge activities which require any grapple to be loaded.
3.2.5 NO individual should perform bridge activities for greater than six consecutive hours.
4.0 EQUIPMENT REQUIRED
- Underwater flood lamp
- Dummy bundle a Clipboard and pencil with rope tethers
- Binoculars
- Plexiglass viewing aid with rope tethers
- Jet Pump Grapple and/or General Purpose Grapple
- Actuating Poles with General Purpose Grapple Manipulator
- Test Weight - (located at V-47 and is 550 lbs including Refuel Mast).
Page 5 of 40 Rev. 17 Hope Creek
HC.OP-FT.KE-0001(Q)
PSEG Internal Use Only 5.0 PROCEDURE 5.1 Refuel Platform General Visual Inspection ICD-444X NOTE 5.1 this inspection, IF defective or inoperative equipment is discovered while conducting a Notification should be generated which directs equipment repair 5.1.1 Visually INSPECT the Refuel Bridge for the following AND INITIAL Attachment 2: A L Excessive leaking oil or grease from gearboxes or couplings drips pans are in place (as required).
4, CAUTION with Fuel Grapple, Auxiliary Frame and Monorail Hoists are contaminated procedure radioactive materials. Implement established Radiological Protection to prevent personnel contamination.
- All pneumatic hoses for integrity.
- Integrity of all electrical cable.
. Integrity of all hoist lifting cables.
. Security of all fasteners using either safety wire, lock tight or tack welded.
- Security of all coupling and fasteners.
- Foreign material exclusion requirements
- Damage or deterioration of any part or sub-assembly.
- Fuel Grapple gimbal pins are properly installed and show no visible deterioration. [CD-950A]
-- I ^Jn-Rev. ' P°P 17 W VJL -Vu Hope Creek ragw
HC.OP-FT.KE-0001(Q)
PSEG Internal Use Only 5.1.2 At the West end of the Refuel Platform VERIFY the following AND INITIAL Attachment 2.
A. Main Power Disconnect Switch is in the CLOSED position.
B. Monorail Hoist Disconnect Switch is in the CLOSED position.
C. Air Compressor Disconnect Switch is in the CLOSED position.
5.1.3 At the West end of the Refuel Platform (Bridge),
VERIFY the Main Hoist Air Isolation Valve AND Monorail Hoist Air Isolation Valve are full OPEN AND INITIAL Attachment 2.
5.1.4 At the Refuel Platform Air Compressor Receiver, VERIFY the following AND INITIAL Attachment 2.
A. Air Compressor stops automatically psig).
WHEN the receiver pressure is equal to 110 psig (105 - 115 B. Air Receiver Relief Valve is not leaking.
aD 5.1.5 OPEN the Air Receiver Drain Valve AND VERIFY the Air Compressor automatically starts before Receiver air pressure decreases to 70 psig AND INITIAL Attachment 2.
5.1.6 CLOSE the Air Receiver Drain Valve.
5.1.7 Visually VERIFY the Refuel Platform (Bridge) I AND Trolley Position Indication System cog wheels are placed correctly in the tracking rack AND INITIAL Attachment 2.
,3 Page 7 of 40 Rev. 17 Hope Creek
HC.OP-FT.KE-0001(Q)
PSEG Internal Use Only 5.2 Fuel Grapple Controls and Grapple Hoist Functional Test NOTE 5.2 while conducting this IF defective or inoperable equipment or indications are discovered repair.
test, a Notification should be generated which directs equipment NOTE 5.2.1 files required for operation.
The computer takes approximately one minute to load all the 5.2.1 PERFORM the following to activate AND log on to the Refuel Bridge Computer:
A. TURN all circuit breakers for the Control System to the ON position. [Located on top of Bridge]
B. PRESS the START PB on the START/STOP Station mounted in the Main Trolley Cab.
AND the following will occur.
INITIAL Attachment 2.
- STOP PB illuminates
- Heater circuits to the motors and cabinets are automatically disconnected when power is turned on.
C. PERFORM the following to log on to the system:
- 1. VERIFY the Log On Screen is on.
- 2. SELECT LOG ON icon, on the Touch Screen, AND VERIFY that the Keypad screen is visible.
- 3. TYPE your name THEN TOUCH the ENTER icon.
- 4. IF incorrect name was entered, TOUCH the CHANGE NAME icon THEN TYPE your name icon.
THEN TOUCH the ENTER Continued next page a f AII Rev. 17
-- a-Hope Creek Jr abuse;. %y Ul -
HC.OP-FT.KE-0001(Q)
PSEG Internal Use Only 5.1 .2.C (continued) 4 52 5. TOUCH the ENTER PASSWORD icon.
- 6. TYPE password THEN TOUCH the ENTER icon.
- 7. SELECT LIGHT TEST icon on the Touch Screen.
NOTE 5.2.1.C.8 for Computer The Computer Override Light will not illuminate unless the keyswitch Override is used.
VERIFY all lamps on the Status Display Panel I 8.
AND on the right and left hand controllers are illuminated. ___4_
- 9. SELECT LIGHT TEST icon on the Touch Screen to end the lamp test.
- 10. OBSERVE the "IS CASK GATE INSTALLED?"
prompt on the screen, Touch Screen.
AND ANSWER by pressing YES or NO on the
- 11. OBSERVE the "IS REACTOR GATE INSTALLED?"
prompt on the screen, AND ANSWER by pressing YES or NO on the Touch Screen.
- 12. VERIFY that the Log On Screen reappears.
- 13. TOUCH the PRESS FOR OPERATION icon to begin operation of the system. A/
-- An^f Rev. 17 Hope Creek r-age X VI wU
TT4'r Idn Iv'1 T"V An~al 1"n PSEG Internal Use Only ni..r-r & I
/S 5.2.2 Fuel Grapple Controls Functional Test N/1
-Ip, A. CHECK the PLATFORM, TROLLEY AND GRAPPLE Control Operators are in the NEUTRAL position AND the Control SELECT Switch is placed to the CONSOLE position.
B. PRESS the STOP PB on the Start/Stop Station.
VERIFY the Red STOP pushbutton light is off II~
AND INITIAL Attachment 2.
C. PRESS the START PB on the Start/Stop Station to restart Refuel Platform electrical equipment.
CAUTION 5.2.2.D thru 5.2.2.N A. During movement of the Refuel Platform (Bridge), Trolley and Fuel Grapple ensure that the Fuel Grapple is not damaged by impact with the Fuel Pool walls or underwater obstructions.
B. Operation of the Refuel Platform (Bridge), Trolley or Fuel Grapple with the variable speed controllers should be accomplished by gradual accelerations and decelerations, rather than full on and full off deflection of the controls.
D. PLACE the PLATFORM Control Operator to the FORWARD position, VERIFY the following (A AND INITIAL Attachment 2. /
- 1. Refuel Platform moves North (away from the Core).
- 2. Speed Control is variable, continuous and smooth.
- 3. Platform is not "crabbing" (moving unsteadily) down the rails.
- 4. Bridge motion warning alarm AND the warning beacon are operating.
- 5. Bridge Readout increases in the negative direction. VI Continued on next page 4)
Page 10 of 40 Rev. 17 Hope Creek
PSEG Internal Use Only HC.OP-FT.KE-0001(Q) 5.2.2 (continued)
E. RETURN the PLATFORM Control Operator to the NEUTRAL position, VERIFY the following AND INITIAL Attachment 2.
- 1. Refuel Platform motion stops.
- 2. Bridge motion warning alarm AND the warning beacon stops.
F. PLACE the PLATFORM Control Operator to the REVERSE position, VERIFY the following AND INITIAL Attachment 2.
- 1. Refuel Platform moves South. (towards the Core)
- 2. Speed control is variable, continuous and smooth.
- 3. Platform is NOT "crabbing" (moving unsteadily) down the rails.
- 4. Bridge motion warning alarm AND the warning beacon are operating.
- 5. Bridge Readout will decrease in the negative direction (becomes a smaller negative number).
G. RETURN the PLATFORM Control Operator to the NEUTRAL position, VERIFY the following AND INITIAL Attachment 2.
- 1. Refuel Platform motion stops.
- 2. Bridge motion warnings alarm AND the warning beacon are stop.
Continued on next page Hope Creek Page 11 of 40 Rev. 17
PSEG Internal Use Only HC.OP-FT.KE-0001(Q) 5.2.2 (continued)
H. PLACE the TROLLEY Control Operator to the RIGHT position, VERIFY the following AND INITIAL Attachment 2. ___
- 1. Trolley moves East. (as the operator faces the Mast)
- 2. Speed control is variable, continuous and smooth.
- 3. Trolley Readout numbers increase.
I. RETURN the TROLLEY Control Operator to the NEUTRAL position, VERIFY that Trolley motion stops AND INITIAL Attachment 2.
J. PLACE the TROLLEY Control Operator to the LEFT position, VERIFY the following AND INITIAL Attachment 2.
- 1. Trolley moves West. (as the operator faces the Mast)
- 2. Speed control is variable, continuous and smooth.
- 3. Trolley Readout numbers decrease.
K. RETURN the TROLLEY Control Operator to the NEUTRAL position, VERIFY that Trolley motion stops AND INITIAL Attachment 2.
L. PLACE the GRAPPLE Control Operator to the LOWER position, VERIFY the following AND INITIAL Attachment 2.
- 1. GRAPPLE NORMAL UP light goes out.
- 2. Fuel Grapple Telescopic Mast extends without binding as the Fuel Grapple is lowered. __L Continued on next page Hope Creek Page 12 of 40 Rev. 17
yydfs d-%_T kale'V age int uUULW PSEG Internal Use Only XI.%r-r i..A 5.2.2 (continued)
M. PLACE the GRAPPLE Control Operator to the RAISE position, VERIFY the following AND INITIAL Attachment 2. /___
- 1. Fuel Grapple Mast Telescopes inward without binding as the Fuel Grapple is raised.
- 2. Fuel Grapple automatically stops WHEN it reaches the full up position.
- 3. Green GRAPPLE NORMAL UP light is on.
N. IF required, POSITION the Plexiglass Viewing Aid so that the Fuel Grapple hooks can be observed.
- 0. VERIFY grapple camera AND monitor are functioning.
P. VERIFY that the protective cover over the GRAPPLE ENGAGE/RELEASE Switch on the Right Hand Controller is in place AND INITIAL Attachment 2. [CD-978A, CD-736D]
Q. UTILIZE the grapple monitor and/or binoculars and IF required, the Plexiglass Viewing Aid to facilitate observation of the Fuel Grapple hooks Continued on next page Page 13 of 40 Rev. 17 Hope Creek
PSEG Internal Use Only HC.OP-FT.KE-0001(Q) 5.2.2 (continued) 7). .
NOTE 5.2.2.R and 5.2.2.S Fuel Grapple hooks should actuate in approximately one second. Sluggish hook operation is indicative of binding operating cylinders or water filled air lines.
R. PLACE the GRAPPLE ENGAGE/RELEASE Switch on the Right Hand Controller to the ENGAGE position, VERIFY the following AND INITIAL Attachment 2. __/____
- 1. Fuel Grapple hooks move to the ENGAGED position.
- 2. Grapple ENGAGE light is on.
- 3. No air bubbles escape from the air hoses OR hook operating cylinder.
S. PLACE the GRAPPLE ENGAGE/RELEASE Switch on the Right Hand Controller to the RELEASE position,
- 2) VERIFY the following AND INITIAL Attachment 2.
- 1. Fuel Grapple hooks move to the RELEASED position.
- 2. Grapple ENGAGE light is off.
- 3. No air bubbles escape from the air hoses or hook operating cylinder.
T. PERFORM the following to check the fail safe position of the grapple hook AND INITIAL Attachment 2 [CD-986F].
- 1. PLACE the GRAPPLE ENGAGE/RELEASE Switch on the Right Hand Controller in the RELEASE position to open the grapple hooks.
- 2. CUT power to the Bridge by pressing the STOP PB on the Start/Stop Station.
) Continued on next page Hope Creek Page 14 of 40 Rev. 17
-T 1 ] l; . A T.
T7 k nA l IAn \
PSEG Internal Use Only rlL.ur-r i .rJl-UUUlkv) 5.2.2.T (continued)
- 3. Visually VERIFY the Grapple hooks CLOSE automatically. ______
- 4. RESTORE power by pressing the START PB on the Start/Stop Station. _
NOTE 5.2.3 A. During movement of the Refuel Platform (Bridge), Trolley and Fuel Grapple ensure that the Fuel Grapple is not damaged by impact with the fuel pool walls or underwater obstructions.
B Operation of the Refuel Platform (Bridge), Trolley or Fuel Grapple with the variable speed controllers should be accomplished by gradual accelerations and decelerations, rather than full on and full off deflection of the controls.
5.2.3 Fuel Grapple Hoist Functional Test [CD-736D] /1-A. Using the PLATFORM AND TROLLEY Control Operators, MANEUVER the Fuel Grapple so that it is positioned approximately over the Dummy Bundle.
CAUTION 5.2.3.B To prevent damage to underwater lamps ensure that the lamps remain fully submerged while they are energized. [CD-673D]
B. SUBMERGE, POSITION AND ENERGIZE an underwater lamp to illuminate A//A the lifting handle of the Dummy Bundle.
C. POSITION the Fuel Grapple directly over the Dummy Bundle by using the Refuel Platform Traverse Toggle (fine positioning, 4-way) control switch.
VERIFY the Traverse Toggle FORWARD and REVERSE and LEFT and RIGHT Position Controls function successfully AND INITIAL Attachment 2.
) Continued on next page Hope Creek Page 15 of 40 Rev. 17
PSEG Internal Use Only HC.OP-FT.KE-0001(Q) 5.2.3 (continued)
D. Using the GRAPPLE control operator, LOWER the Fuel Grapple UNTIL it is approximately /
one foot above the handle of the Dummy Bundle. X114 E. ROTATE the Fuel Grapple into alignment WITH the Dummy Bundle handle.
F. PLACE the GRAPPLE ENGAGE/RELEASE Switch to the RELEASE position to ensure the Fuel Grapple hooks are open.
OBSERVE the grapple ENGAGE light off.
G. Using the GRAPPLE Control Operator, slowly LOWER the Fuel Grapple onto the Dummy Bundle.
H. WHEN the Fuel Grapple is fully lowered on the Dummy Bundle, VERIFY the following AND INITIAL Attachment 2.
- 1. Fuel Grapple downward motion automatically stops.
- 2. SLACK CABLE light is on.
CAUTION 5.2.3.1 No fuel assemblies are to be grappled or moved while conducting this procedure.
I. PLACE the GRAPPLE ENGAGE/RELEASE Switch to the ENGAGE position.
CHECK the grapple ENGAGED light is on.
J. RECORD the initial Refuel Platform (Bridge), Trolley AND Fuel Grapple values from the digital position indicators on Attachment 2.
Continued on next page Hope Creek Page 16 of 40 Rev. 17
Irl dND WT1 IL' nfA I {n'l PSEG Internal Use Only II.IM-E .
5.2.3 (continued)
K. RAISE the Fuel Grapple with attached Dummy Bundle using the GRAPPLE Control Operator in the RAISE position, UNTIL the Fuel Grapple is fully raised.
VERIFY the following AND INITIAL Attachment 2.
- 1. Fuel Grapple automatically stops without driving into its Overtravel Limit Switch.
- 2. GRAPPLE NORMAL UP light is on. __/
CAUTION 5.2.3.L To prevent damage to the Dummy Bundle or other submerged equipment, avoid collisions with the loaded Fuel Grapple and the Spent Fuel Pool walls or submerged equipment.
L. Using the PLATFORM AND TROLLEY Control Operators, MANEUVER the loaded Fuel Grapple to a Spent Fuel Pool location away from the Dummy Bundle storage location. _____
M. Using the PLATFORM AND TROLLEY Control Operators, MANEUVER the loaded Fuel Grapple to the coordinates listed in procedure Step 5.2.3.J.
N. ROTATE the Fuel Grapple to align the Durmmy Bundle WITH its storage location.
- 0. Slowly LOWER the Dummy Bundle by using the GRAPPLE Control Operator in the LOWER position.
ADJUST Refuel Platform position with the Traverse Toggle Control Switch to fine tune alignment IF required.
VERIFY the GRAPPLE NORMAL UP light is off AND INITIAL Attachment 2.
Continued on next page Page 17 of 40 Rev. 17 Hope Creek
PSEG Internal Use Only HC.OP-FT.KE-0001(Q) 5.2.3 (continued)
P. WHEN the Dummy Bundle is fully seated in its storage location, VERIFY the following AND INITIAL Attachment 2. ____
- 1. Fuel Grapple automatically stops lowering.
- 2. SLACK CABLE light is on.
- 3. Load cell indicates less than 50 pounds.
Q. RECORD the final Refuel Platform (Bridge), Trolley AND Fuel Grapple values from the digital position indicators on Attachment 2.
R. VERIFY the position indication values obtained in procedure Steps 5.2.3.J and 5.2.3.Q are within +/- 0.50 AND INITIAL Attachment 2.
S. PLACE the GRAPPLE ENGAGE/RELEASE Switch to the RELEASE position.
T. RAISE the Fuel Grapple UNTIL the GRAPPLE NORMAL UP light is on AND the upward motion automatically stops.
U. Simultaneously PRESS the HOIST OVERRIDE pushbutton AND TRAVEL OVERRIDE pushbutton AND PLACE the GRAPPLE Control Operator to the RAISE position.
Slowly RAISE the Grapple until the BACK UP HOIST LIMIT light is illuminated on the Interlock Status Display Module.
VERIFY the Hoisting motion automatically stops AND the hoist can NOT be raised above this point.
INITIAL Attachment 2. [CD-124B]
V. RETURN the Fuel Grapple to the GRAPPLE NORMAL UP position by using the GRAPPLE Control Operator.
VERIFY the BACK UP HOIST LIMIT light is off. _
Continued on next page Hope Creek Page 18 of 40 Rev. 17
PSEG Internal Use Only HC.OP-FT.KE-0001(Q) 5.2.3 (continued)
CAUTION 5.2.3.W To prevent damage to underwater lamps, ensure that the lamps remain fully submerged while they are energized.
W. Using the CONSOLE LIGHTS Toggle Switch, TURN on the Fuel Grapple lamps.
VERIFY both lamps are operable
/fJ/'4 AND INITIAL Attachment 2.
X. TURN off the Fuel Grapple lights.
Hope Creek Page 19 of 40 Rev. 17
yyg 4-%," Y.11ir 117T11 WhAl id'%N PSEG Internal Use Only nL.-.r-r L.rz1ri-uuuIy) 5.3 Frame Auxiliary Hoist Controls Functional Test NOTE 5.3 IF defective or inoperative equipment is discovered while conducting this test, a Notification should be generated which directs equipment repair.
CAUTION 5.3 During movement of the Refuel Platform (Bridge) or Trolley ensure that the Fuel Grapple is not damaged by impact with the Spent Fuel Pool walls or underwater obstructions.
5.3.1 At the Start/Stop Station, TURN the CONSOLE SELECT Switch to FRAME. ___
NOTE 5.3.2 through 5.3.29 All remaining steps for the Auxiliary Hoist Functional Test are performed using the Auxiliary Hoist (Frame) pendant controls.
5.3.2 On the Frame Pendant, PRESS the BRIDGE FORWARD joystick, VERIFY the following AND INITIAL Attachment 2.
A. Refuel Platform moves North.
B. Speed control is smooth and continuous.
C. Refuel Platform movement alarm is sounding AND the warning beacon is illuminated.
D. VERIFY Bridge motion from only this station.
_ n nf4Af o _P Rev. 17 ST__
Hope Creek JL "r X -
PSEG Internal Use Only HC.OP-FT.KE-0001(Q) 5.3.3 RELEASE the BRIDGE FORWARD joystick, VERIFY the following AND INITIAL Attachment 2.
A. Refuel Platform movement stops.
B. Refuel Platform movement alarm is silent AND the warning beacon is off.
5.3.4 PRESS the BRIDGE REVERSE joystick, VERIFY the following AND INITIAL Attachment 2.
A. Refuel Platform moves south.
B. Speed control is smooth and continuous.
C. Refuel Platform movement alarm is sounding AND the warning beacon is illuminated.
5.3.5 RELEASE the BRIDGE REVERSE joystick, VERIFY the following AND INITIAL Attachment 2.
A. Refuel Platform motion stops.
B. Refuel Platform movement alarm is silent AND the warning beacon is off.
5.3.6 PRESS the TROLLEY RIGHT pushbutton, VERIFY the following AND INITIAL Attachment 2.
A. Trolley moves east.
B. Speed control is smooth and continuous.
5.3.7 RELEASE the TROLLEY RIGHT pushbutton, VERIFY the Trolley motion stops AND INITIAL Attachment 2.
Hope Creek Page 21 of 40 Rev. 17
PSEG Internal Use Only HC.OP-FT.KE-0001(Q) 5.3.8 PRESS the TROLLEY LEFT pushbutton, VERIFY the following ,AJ4 AND INITIAL Attachment 2.
A. Trolley moves west.
B. Speed control is smooth and continuous.
5.3.9 RELEASE the TROLLEY LEFT pushbutton, VERIFY the Trolley motion stops AND INITIAL Attachment 2.
5.3.10 PRESS the HOIST LOWER pushbutton, VERIFY the following AND INITIAL Attachment 2.
A. Auxiliary Hoist cable moves downward.
B. Speed Control has high and low speed and is smooth and continuous.
A slight depression on the pushbutton will produce a slow speed.
A)
- A full depression on the pushbutton will produce a slow speed for a short period of time then switch to fast speed.
5.3.11 RELEASE the HOIST LOWER pushbutton, VERIFY the hoist cable motion stops AND INITIAL Attachment 2.
5.3.12 PRESS the HOIST RAISE pushbutton, VERIFY the following AND INITIAL Attachment 2.
A. Auxiliary Hoist cable moves upward.
B. Speed control has high and low speed and is smooth and continuous.
- A slight depression on the pushbutton will produce a slow speed.
A full depression on the pushbutton will produce a slow speed for a short period of time then switch to fast speed.
I)
Page 22 of 40 Rev. 17 Hope Creek
S__s Or _r CAN_ and wars PSEG Internal Use Only HC.UV-YI.KE-0001(Q) 5.3.13 RELEASE the HOIST RAISE pushbutton before it reaches the Normal Up Rotary electrical stop, VERIFY the hoist cable motion stops AND INITIAL Attachment 2. /__
5.3.14 PRESS the HOIST RAISE pushbutton to raise the hoist cable to the Normal Up Rotary electrical stop.
VERIFY the hoist cable motion automatically stops AND INITIAL Attachment 2.
NOTE 5.3.15 The Mechanical Jam Stop may be moved down on the cable to check the MAX UP ROTARY Switch. HC.OP-SO.KE-0001(Q) should be referred to for stop setup.
5.3.15 Simultaneously PRESS the HOIST LIMIT OVERRIDE AND the HOIST RAISE pushbuttons.
VERIFY the Frame Hoist cable moves upward and automatically stops at the Maximum Up Rotary Switch AND INITIAL Attachment 2. AJl NOTE 6.3.16 This tool is used for load cell operability testing in this procedure. The Dummy Bundle will only be relocated with the Fuel Grapple.
5.3.16 ATTACH the Jet Pump Grapple to the Frame Auxiliary Hoist cable in accordance with HC.OP-SO.KE-0001(Q).
TIGHTEN the locking nut on the cable terminal to prevent inadvertent separation of the grapple from the cable. [CD-949A] / fr A. ATTACH Quick Disconnect Air fittings and hose to the Grapple AND ACTUATE the grapple open and closed.
B. VERIFY correct operation WHEN the correct button is pressed.
5.3.17 SUBMERGE the Jet Pump Grapple in the Spent Fuel Pool water taking care to avoid splashing.
5.3.18 Using the Refuel Platform (Bridge and Trolley) position controls, MANEUVER the Jet Pump Grapple over the test weight located at V-47.
Hope Creek Page 23 of 40 Rev. 17
PSEG Internal Use Only HC.OP-FT.KE-0001(Q) 5.3.19 LOWER the Jet Pump Grapple to the level of the Test Weight Handle.
NOTE 5.3.20 No fuel assemblies are to be grappled or moved while conducting this procedure.
5.3.20 ATTACH the Jet Pump Grapple to the Test Weight Handle. (( /fF NOTE 5.3.21 Hoist Load Cell should indicate approximately 200 lbs. plus the weight of the stop block and tool.
5.3.21 RAISE the test weight only high enough to VERIFY the Auxiliary Hoist Load Cell indication operability AND INITIAL Attachment 2. /4 5.3.22 LOWER the test weight until the Auxiliary Hoist cable is slack.
5.3.23 REMOVE the Jet Pump Grapple from the Test Weight Handle.
5.3.24 VERIFY that NO fuel assemblies OR other equipment have been inadvertently grappled AND INITIAL Attachment 2.
5.3.25 Using the HOIST RAISE pushbutton, RAISE the Jet Pump Grapple to the Auxiliary Hoist Maximum limit.
Hope Creek Page 24 of 40 Rev. 17
PSEG Internal Use Only HC.OP-FT.KE-0001(Q) 5.4 Monorail Auxiliary Hoist Controls Functional Test NOTE 5.4 IF defective or inoperative equipment is discovered while conducting this test a Notification should be generated which directs equipment repair.
CAUTION 5.4 During movement of the Refuel Platform ensure that the Fuel Grapple is not damaged by impact with the Fuel Pool walls or underwater obstructions.
5.4.1 At the Start/Stop Station, TURN the CONSOLE SELECT Switch to MONO.
NOTE 5.4.2 through 5.4.29 Aq1 All remaining steps for the Monorail Hoist Functional Test are performed using the Monorail Hoist (Monorail) pendant controls 5.4.2 On the Monorail Pendant, PRESS the BRIDGE FORWARD joystick, VERIFY the following AND INITIAL Attachment 2.
A. Refuel Platform moves North.
B. Speed control is smooth and continuous.
C. Refuel Platform movement alarm is sounding AND the warning beacon is illuminated.
D. VERIFY Bridge motion from only this station.
Hope Creek Page 25 of 40 Rev. 17
PSEG Internal Use Only HC.OP-FT.KE-0001(Q) 5.4.3 RELEASE the BRIDGE FORWARD joystick, VERIFY the following AND INITIAL Attachment 2.
A. Refuel Platform movement stops.
B. Refuel Platform movement alarm is silent AND the warning beacon is off.
5.4.4 PRESS the BRIDGE REVERSE joystick, VERIFY the following AND INITIAL Attachment 2.
A. Refuel Platform moves south.
B. Speed control is smooth and continuous.
C. Refuel Platform movement alarm is sounding AND the warning beacon is illuminated.
5.4.5 RELEASE the BRIDGE REVERSE joystick, VERIFY the following AND INITIAL Attachment 2.
A. Refuel Platform motion stops.
B. Refuel Platform movement alarm is silent AND the warning beacon is off.
5.4.6 PRESS the TROLLEY RIGHT pushbutton, VERIFY the following AND INITIAL Attachment 2.
A. Trolley moves west.
B. Speed control is smooth and continuous.
5.4.7 RELEASE the TROLLEY RIGHT pushbutton, VERIFY the Trolley motion stops AND INITIAL Attachment 2.
Hope Creek Page 26 of 40 Rev. 17
PSEG Internal Use Only HC.OP-FT.KE-0001(Q) 5.4.8 PRESS the TROLLEY LEFT pushbutton, VERIFY the following AND INITIAL Attachment 2.
A. Trolley moves east.
B. Speed control is smooth and continuous.
5.4.9 RELEASE the TROLLEY LEFT pushbutton, VERIFY the Trolley motion stops AND INITIAL Attachment 2.
5.4.10 PRESS the HOIST LOWER pushbutton, AND LOWER the grapple to greater than 7 feet below the surface of the water to clear the hoist override.
VERIFY the following AND INITIAL Attachment 2.
A. Monorail Hoist cable moves downward.
B. Speed control has high and low speed and is smooth and continuous.
- A slight depression on the pushbutton will produce a slow speed.
- A full depression on the pushbutton will produce a slow speed for a short period of time then switch to fast speed.
5.4.11 RELEASE the HOIST LOWER pushbutton, VERIFY the hoist cable motion stops AND INITIAL Attachment 2.
5.4.12 PRESS the HOIST RAISE pushbutton, VERIFY the following AND INITIAL Attachment 2.
A. Monorail Hoist cable moves upward.
B. Speed control has high and low speed and is smooth and continuous
- A slight depression on the pushbutton will produce a slow speed.
- A full depression on the pushbutton will produce a slow speed for a short period of time then switch to fast speed.
Hope Creek Page 27 of 40 Rev. 17
PSEG Internal Use Only HC.OP-FT.KE-0001(Q) 5.4.13 RELEASE the HOIST RAISE pushbutton before it reaches the Normal Up Rotary electrical stop, VERIFY the hoist cable motion stops AND INITIAL Attachment 2.
5.4.14 PRESS the HOIST RAISE pushbutton to raise the hoist cable to the Normal Up Rotary electrical stop.
VERIFY the hoist cable motion automatically stops AND INITIAL Attachment 2.
NOTE 5.4.15 The Mechanical Jam Stop may be moved down on the cable to check the MAX UP ROTARY Switch. HC.OP-SO.KE-0001(Q) should be referred to for stop setup.
5.4.15 Simultaneously PRESS the HOIST LIMIT OVERRIDE AND HOIST RAISE pushbuttons.
VERIFY the Monorail Hoist cable moves upward AND automatically stop at the Maximum Up Rotary limit switch cut-out AND INITIAL Attachment 2.
CAUTION 5.4.16 A. Equipment submerged in the Spent Fuel Pool water may be highly radioactive. Tools and equipment should be monitored for radiation as they are slowly removed from the water. [CD-217B]
B. Equipment submerged in the Spent Fuel Pool is highly contaminated with radioactive materials. Established procedures should be followed to prevent the spread of radioactive contamination.
5.4.16 REMOVE the Jet Pump Grapple from the Spent Fuel Pool water taking care to avoid splashing.
REMOVE the Jet Pump Grapple from the Frame Auxiliary Hoist cable, IF not previously removed.
A. ATTACH Mono Aux Hoist Quick Disconnect air fittings and hose to the Grapple AND ACTUATE the grapple open and closed.
B. VERIFY correct operation when the correct button is pressed.
Hope Creek Page 28 of 40 Rev. 17
PSEG Internal Use Only HC.OP-FT.KE-0001(Q)
NOTE 5.4.17 This tool is used for load cell operability testing in this procedure. The Dummy Bundle will only be relocated with the Fuel Grapple.
5.4.17 ATTACH the Jet Pump Grapple to the Monorail Hoist cable in accordance with HC.OP-SO.KE-000I(Q).
TIGHTEN the locking nut on the cable terminal to prevent inadvertent separation of the grapple from the cable. [CD-949A]
5.4.18 SUBMERGE the Jet Pump Grapple in the Fuel Pool water taking care to avoid splashing.
5.4.19 Using the Refuel Platform (Bridge and Trolley) position controls, MANEUVER the Jet Pump Grapple over the test weight located at V-47.
5.4.20 LOWER the Jet Pump Grapple to the level of the Test Weight Handle.
CAUTION 5.4.21 NO fuel assemblies are to be grappled OR moved while conducting this procedure.
5.4.21 ATTACH the Jet Pump Grapple to the Test Weight Handle.
5.4.22 RAISE the test weight only high enough to VERIFY the Monorail Hoist Load Cell indication operability AND INITIAL Attachment 2.
5.4.23 LOWER the test weight until the Monorail Hoist cable is slack.
I) 5.4.24 REMOVE the Jet Pump Grapple from the test weight handle.
Hope Creek Page 29 of 40 Rev. 17
PSEG Internal Use Only HC.OP-FT.KE-0001(Q) 5.4.25 VERIFY that NO fuel assemblies OR other equipment have been inadvertently grappled AND INITIAL Attachment 2.
5.4.26 Using the HOIST RAISE pushbutton, RAISE the Jet Pump Grapple to the Monorail Hoist Maximum Up limit.
5.5 Procedure Completion Instructions CAUTION 5.5.1 A. Equipment submerged in the Spent Fuel Pool water may be highly radioactive. Tools and equipment should be monitored for radiation as they are slowly removed from the water.
B. Equipment submerged in the Spent Fuel Pool is highly contaminated with radioactive materials. Established procedures should be followed to prevent the spread of radioactive contaminated.
5.5.1 REMOVE the Jet Pump Grapple from the Spent Fuel Pool water.
5.5.2 DISCONNECT the Monorail Hoist Cable from the Jet Pump Grapple.
DISCONNECT the Quick Disconnect Air fitting I
AND hose from the Jet Pump Grapple.
5.5.3 DE-ENERGIZE the underwater lamp.
5.5.4 REMOVE the underwater lamp from the Spent Fuel Pool water.
5.5.5 REMOVE the Plexiglass viewing aid from the water.
5.5.6 RINSE Jet Pump Grapple, underwater lamp and Plexiglass Viewing Aid.
WRAP all equipment in individual polyethylene bags for storage.
5.5.7 RETURN all equipment to the designated contaminated storage location AND INITIAL Attachment 2.
Hope Creek Page 30 of 40 Rev. 17
ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE
-20030327 PSEG Internal Use Only HC.OP-FT.KE-0001(Q) 5.5.8 IF no further testing is required, PERFORM the following to log off AND shut-off the Refuel Bridge Computer:
A. TOUCH the SHOW MENU icon on the Touch Screen.
B. TOUCH the LOG OFF icon.
C. TOUCH the YES/LOG OFF icon to verify system log off, log off is now complete.
D. PRESS the SHUT DOWN icon on the touch screen.
E. PRESS the YES / SHUT DOWN icon to verify system shutdown, F. ENSURE the SAFE SHUTDOWN message is displayed on the touch screen prior to securing power to the refueling platform. Failure to following this sequence could corrupt the database in Microsoft Access, resulting in loss of Automatic and Semi-Automatic operation.
NOTE 5.5.9 Portions of the Refuel Platform Hoists and equipment unaffected by noted deficiencies may still be considered operable.
5.5.9 SUMMARIZE on Attachment 1 the procedure steps where deficiencies were noted.
INCLUDE the number of the Notification that was submitted to correct the noted deficiencies.
RETURN the procedure and Attachment 1 to the OS/CRS for review.
DESCRIBE the operational limitations and restrictions on the Refuel Platform hoists and equipment.
5.5.9 WHEN Station Maintenance has been implemented to correct noted deficiencies.
PERFORM a retest using the applicable portions of this procedure. -
Hope Creek Page 31 of 40 Rev. 17
PSEG Internal Use Only HC.OP-FT.KE-0001(Q) 5.5.10 WHEN a retest proves satisfactory SIGN off the appropriate procedure step AND NOTE the date of completion on Attachment 1.
Otherwise REQUEST additional maintenance.
5.5.11 IF equipment deficiencies were not discovered while conducting this functional test, INDICATE that on Attachment 1 AND RETURN this procedure to the OS/CRS for review.
6.0 RECORDS 6.1 RETAIN the following lAW NC.NA-AP.ZZ-001 1(Q); Records Management Program:
Attachment 1 - Refueling Platform And Fuel Grapple Operability Test - Refueling Data sheet - Deficiency Summary Attachment 2 - Refueling Platform And Fuel Grapple Operability Test - Refueling Functional Test - Check Sheet Hope Creek Page 32 of 40 Rev. 17
PSEG Internal Use Only HC.OP-FT.KE-0001(Q)
7.0 REFERENCES
3 7.1 HCGS Equipment Location P-0047-1 7.2 Instruction Manuals:
GEK-75563 Vol. I & II, Refuel Platform Equipment Assembly (TDR No. N1-A41-52(l & 2))
GEK-75578 Local Area Underwater Light (TDR No. N1-A41-41(2))
GEK-33087B Viewing Aid (TDRNo. N1-A41-41(2) 7.3 HCGS FSAR Section 9.1.4.2.7.1 7.4 Commitment Documents CD-949A GE SIL No. 82 CD-182C NRC CIRC 77-12 CD-950A GE SIL No. 87 CD-281C INPO SER 28-84 CD-978A GE SIL No. 298 CD-673D INPO OE 1239 CD-124B CD-736D NRC INFO 85-12 CD-217B INPOO+MRIIl CD-444X FSAR CD-986F GE SIL No. 533 7.5 Procedures HC.MD-ST-KE-000I(Q) Refuel Platform 7 - Day Operational Check HC.MD-PM-KE-0003(Q) Refuel Platform Operational Check HC.OP-SO.KE-0001(Q) Refueling Platform and Fuel Grapple Operation 7.6 Other Documents ECA 4HE-0021 Disconnected the Load Float function DCP 80047191 Hope Creek Page 33 of 40 Rev. 17
PSEG Internal Use Only HC-0P-FT.KE-000l(Q)
ATTACHMENT 1 Page I of 2 0* REFUELING PLATFORM AND FUEL GRAPPLE OPERABILITY TEST - REFUELING DATA SHEET - DEFICIENCY
SUMMARY
Procedure NotificationI Description Retest SAT Step Number Number __Date Hope Creek Page 34 of 40 Rev. 17
PSEG Internal Use Only HC.OP-FT.KE-0001(Q)
ATTACHMENT 1 Page 2 of 2 01 REFUELING PLATFORM AND FUEL GRAPPLE OPERABILITY TEST - REFUELING DATA SHEET - DEFICIENCY
SUMMARY
Procedure Notification Description Retest SAT Step Number Number Date I--
Permission to test: /
OS/CRS DATE-TIME Performed by: I NAME DATE-TIME Equipment returned to proper stowage location: /
NAME DATE-TIME Review by: /
OS/CRS DATE-TIME Order Number: DR. NO.
Hope Creek Page 35 of 40 Rev. 17
HC.OP-FT.KE-0001(Q)
PSEG Internal Use Only ATTACHMENT 2 Page 1 of 5 TEST - REFUELING
- 7) REFUELING PLATFORM AND FUEL GRAPPLE OPERABILITY FUNCTIONAL TEST - CHECK SHEET TITLE INITIALS STEP I f\.
I 2.7 Procedure prerequisites have been completed _k
.- . f i . ._ ._ TE-- fe1an__
No excessive leaking oil or grease. Drip, pans are in place kas} Y/ _
required).
Pneumatic hose integrity Electrical cable integrity I Hoist cable integrity All fasteners are secure 5.1.1 All couplings, gearbox and safety covers are secure.
Foreign Material Exclusion requirements satisfied. t _
No damage or deterioration of any part or sub-assembly I I
Fuel Grapple gimbal pin integrity I_ I Main Power, Air Compressor and Monorail Hoist Disconnect 5.1.2 Switches CLOSED Main Hoist Air Isolation Valve and Monorail Hoist Air Isolation 5.1.3 Valves OPEN 5.1.4 Air Compressor receiver pressure & integrity 5.1.5 Air Compressor auto start 5.1 7 Refuel Platform (Bridge) and Trolley position cog wheels in the I e
.1. tracking rack Page 36 of 40 Rev. 17 Hope Creek
PSEG Internal Use Only HC.OP-FT.KE-0001(Q)
ATTACHMENT 2 Page 2 of 5 REFUELING PLATFORM AND FUEL GRAPPLE OPERABILITY TEST - REFUELING FUNCTIONAL TEST - CHECK SHEET STEP TITLE INITIALS 5.2.1 .B Refuel Platform START pushbutton check (Start/Stop Station) ,,y 4 5.2.2.B Refuel Platform STOP pushbutton check (Start/Stop Station) 5.2.2.D PLATFORM position control FORWARD checks (Console) 5.2.2.E PLATFORM position control in NEUTRAL checks (Console) 5.2.2.F PLATFORM position control REVERSE checks (Console) 5.2.2.G PLATFORM position control in NEUTRAL checks (Console) 5.2.2.H TROLLEY position control RIGHT checks (Console) 5.2.2.1 TROLLEY position control in NEUTRAL check (Console) 5.2.2.J TROLLEY position control LEFT checks (Console) 5.2.2.K TROLLEY position control in NEUTRAL check (Console) 5.2.2.L GRAPPLE position control LOWER checks (Console) 5.2.2.M GRAPPLE position control RAISE checks (Console) 5.2.2.P HOIST GRAPPLE ENGAGE/RELEASE switch cover in place
___ ____ ___ (Console)_ _ _
5.2.2.R. HOIST GRAPPLE ENGAGE/RELEASE switch ENGAGE 5.2.2.R checks (Console)
Hope Creek Page 37 of 40 Rev. 17
thkni fry rt-..r-r TOT ETA lent~ T7r.,
PSEG Internal Use Only .l-UUUIt' q)
ATTACHMENT 2 Page 3 of 5 t 1 REFUELING PLATFORM AND FUEL GRAPPLE OPERABILITY TEST - REFUELING FUNCTIONAL TEST - CHECK SHEET PROCEDURE TITLE INITIALS STEP HOIST GRAPPLE ENGAGE/RELEASE switch RELEASE /,//,4 5.2.2.S checks (Console) 5.2.2.T Fail Safe Position Check of GRAPPLE HOOK [CD-986F]
5.2.3.C Refuel Platform Traverse Toggle Switch checks (Console) 5.2.01H Automatic down travel stop and SLACK CABLE light checks (Console)
Initial position indication coordinates 5.2.3.J Bridge Trolley _ _ Hoist
.2.3.K Automatic up travel stop and GRAPPLE NORMAL UP light 5.2.3.K checks (Console) 5.2.3.0 GRAPPLE NORMAL UP light off check (Console) 5.2.3.P Dummy Bundle seated checks (Console)
Final position indication coordinates 5.2.3.Q Bridge Trolley _ _ Hoist 5.2.3.R Position indication system values + 0.50 5.2.3.U HOIST OVERRIDE pushbutton check (Console) 5.2.3.W Fuel Grapple lights (both) operability check 5.3.2 Refuel Platform FORWARD control checks (Frame) 5.3.3 Refuel Platform forward motion stop checks (Frame)
Hope Creek Page 38 of 40 Rev. 17
PSEG Internal Use Only HC.OP-FT.KE-0001(Q)
ATTACHMENT 2 Page 4 of 5 PeREFUELING GRAPPLE ANDFUEL OPERABILITY PLATFORM TEST - REFUELING FUNCTIONAL TEST - CHECK SHEET PROCEDURE TITLE INITIALS STEP 5.3.4 Refuel Platform REVERSE control checks (Frame) 5.3.5 Refuel Platform reverse motion stop checks (Frame) 5.3.6 Trolley RIGHT control checks (Frame) 5.3.7 Trolley right motion stop check (Frame) 5.3.8 Trolley LEFT control checks (Frame) 5.3.9 Trolley left motion stop check (Frame) l 5.3.10 Auxiliary Hoist LOWER control checks (Frame) = _=
5.3.11 Auxiliary Hoist cable motion stop (Frame) 5.3.12 Auxiliary Hoist RAISE control checks (Frame) 5.3.13 Auxiliary Hoist cable motion stop (Frame) 5.3.14 Auxiliary Hoist NORMAL UP ROTARY limit auto stop (Frame) 5.3.15 Auxiliary Hoist MAXIMUM UP ROTARY limit auto stop (Frame) 5.3.21 Auxiliary Hoist Load Cell operability test (Frame) _ _ _
5.3.24 Auxiliary Hoist free of fuel assemblies or other equipment Xll__
5.4.2 Refuel Platform FORWARD control checks (Monorail) 5.4.3 Refuel Platform forward motion stop checks (Monorail) 5.4.4 Refuel Platform REVERSE control checks (Monorail)
Hope Creek Page 39 of 40 Rev. 17
PSEG Internal Use Only HC.OP-FT.KE-0001(Q)
ATTACHMENT 2 Page 5 of 5 Av\ REFUELING PLATFORM AND FUEL GRAPPLE OPERABILITY TEST - REFUELING FUNCTIONAL TEST - CHECK SHEET PROCEDURE TITLE INITIALS STEP 5.4.5 Refuel Platform reverse motion stop checks (Monorail) 5.4.6 Trolley RIGHT control checks (Monorail) 5.4.7 Trolley right motion stop check (Monorail) 5.4.8 Trolley LEFT control checks (Monorail) 5.4.9 Trolley left motion stop check (Monorail) 5.4.10 Monorail Hoist LOWER control checks (Monorail) 5.4.11 Monorail Hoist cable motion stop (Monorail) 5.4.12 Monorail Hoist RAISE control checks (Monorail) 5.4.13 Monorail Hoist cable motion stop (Monorail) 5.4.14 Monorail Hoist NORMAL UP ROTARY limit auto stop
.4.1 (Monorail) 5.4.15 Monorail Hoist MAXIMUM UP ROTARY limit auto stop (Monorail) 5.4.22 Monorail Hoist Load Cell operability test (Monorail) 5.4.25 Monorail Hoist free of fuel assemblies and other equipment 5.5.7 Equipment decontaminated and returned to designated storage location Reviewed and Accepted by:
OS/CRS Hope Creek Page 40 of 40 Rev. 17
NC.TQ-WB.ZZ-0310(Z)
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: HOPE CREEK SYSTEM: Refueling Platform JPM NUMBER: 2003-NRC-S5 TASK: Perform Semi-Automatic Fuel Transfer within the Spent Fuel Pool.
TASK NUMBER: 234000A302 N/A K/A NUMBER: 234000 A3.02 ALTERNATE PATH:
IMPORTANCE FACTOR: 3.1 3.7 RO SRO APPLICABILITY: EO D] RODCo STA Cl SROFi LSRO FX EVALUATION SETTING/METHOD: Walkthrough/Simulate (Perform)
REFERENCES:
HC.OP-SO.KE-0001(Q), Rev. 30 TOOLS AND EQUIPMENT: Refueling Platform/None VALIDATED JPM COMPLETION TIME: 20 Min.
TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Min.
APPROVAL: N/A _ _ _ _
BARGAINING UNIT TRAINING SUPERVISOR YANASER REPRESENTATIVE or Designee CAUTION: No plant equipment shall be operated during the performance of a JPM without the following:
- 1. Permission from the OS or Unit CRS;
- 2. Direct oversight by a qualified individual (determined by the individual granting permission based on plant conditions).
- 3. Verification of the "as left" condition by a qualified individual.
ACTUAL JPM COMPLETION TIME: Min.
ACTUAL TIME CRITICAL COMPLETION TIME: N/A Min.
JPM PERFORMED BY: GRADE: F SAT R UNSAT REASON, IF UNSATISFACTORY:
EVALUATOR'S SIGNATURE: DATE:
Nuclear Common Page 1 of 23 Rev. 0
NC.TQ-WB.ZZ-031 0(Z)
OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:
DATE:
SYSTEM: Refueling Platform JPM NUMBER: 2003-NRC-S5 TASK: Perform Semi-Automatic Fuel Transfer within the Spent Fuel Pool.
TASK NUMBER: 234000A302 INITIAL CONDITIONS:
- There are NO irradiated components grappled to any refueling platform hoist.
- Auxiliary hoists are fully raised with attached tooling clear of obstructions.
- HC.OP-ST.KE-0001 and HC.OP-FT.KE-0001 has been completed for the Refueling Platform.
- The Refuel platform is in a standby lineup.
- Main Hoist Grapple is RELEASED.
- Primary and Redundant encoders are selected for Bridge, Trolley and Hoist travel.
- An approved FUEL MOVEMENT SHEET for transfer of the dummy bundle has been obtained from Reactor Engineering. The Spent fuel rack locations specified on the FUEL MOVEMENT SHEET are within the Secure Travel Zone.
- Prerequisites for dummy bundle transfer within the Spent Fuel Pool are completed per HC.OP-SO.KE-0001.
INITIATING CUE:
Perform transfer of the dummy bundle within the spent fuel storage racks using Semi-Automatic XY mode of refueling platform operation, in accordance with the attached Fuel Movement Sheet step # 01.
Successful Completion Criteria:
All critical steps completed.
All sequential steps completed in order.
All time-critical steps completed within allotted time.
JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Nuclear Common Page 2 of 23 Rev. 0
NC.TQ-WB.ZZ-0310(Z)
JPM NUMBER: 2003-NRC-S5 OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: Refueling Platform TASK: Perform Semi-Automatic Fuel Transfer within the Spent Fuel Pool.
STEP L COMMENTS
- STEP NO. (*Denotes a Critical Step) STANDARD EVAL (Required for UNSAT
(#Denotes a Sequential Step) S/Uevaluation)
Examiner Note: Provide operator with marked up copy of HC.OP-SO.KE-0001.
Operator reviews precautions and limitations Operator reviews precautions and limitations.
Examiner Cue:
If excessive time is taken reviewing precautions and limitations, inform operator that all are satisfied.
Operator determines beginning step of The operator determines the correct beginning procedure. step of the procedure to be 5.10.
Examiner Note:
5.1 .3.C. PERFORM the following to log on to the The operator will need to log in to the Refuel system: Platform Computer to perform this JP\M. Login procedure is as follows:
5.1.3.C.1. VERIFY the Log On Screen is on. Verifies Log On Screen is on Nuclear Common Page 3 of 23 Rev. 0
NC.TQ-WB.ZZ-031 0(Z)
JPM NUMBER: 2003-N RC-S5 OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: Refueling Platform TASK: Perform Semi-Automatic Fuel Transfer within the Spent Fuel Pool.
STEP NO. STEP l COMMENTS
(*Denotes a Critical Step) STANDARD ESV/AUL (Required for UNSAT
(#Denotes a Sequential Step) S evaluation) 5.1 .3.C.2. SELECT LOG ON icon, on the Touch Screen, Operator selects LOG ON ICON on the Touch AND VERIFY that the Keypad screen is visible. Screen and verifies Keypad Screen is visible.
- 5.1.3.C.3. TYPE your name Operator types name on Keypad on Touch THEN TOUCH the ENTER icon. Screen.
5.1.3.C.4. IF incorrect name was entered, If necessary, re-enters name then touches Enter TOUCH the CHANGE NAME icon icon.
THEN TYPE your name THEN TOUCH the ENTER icon.
- 5.1.3.C.5. TOUCH the ENTER PASSWORD icon. Operator touches Enter Password icon.
- 5.1.3.C.6. icon. password THEN TOUCH the ENTER TYPE Operator types password on Keypad on Touch
- o. Screen.
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NC.TQ-WB.ZZ-031 0(Z)
JPM NUMBER: 2003-NRC-S5 OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: Refueling Platform TASK: Perform Semi-Automatic Fuel Transfer within the Spent Fuel Pool.
l N STEP COMMENTS
- STEP NO. (*Denotes a Critical Step) STANDARD EVAL (Required for UNSAT
- (#Denotes a Sequential Step) S evaluation) 5.1.3.C.7. SELECT LIGHT TEST icon on the Touch Operator selects LIGHT TEST icon on the Touc Screen. Screen.
NOTE The Computer Override Light will not illuminate Operator reads NOTE.
5.1.3.C.8 unless the keyswitch for Computer Override is used.
5.1.3.C.8. VERIFY all lamps on the Status Display Panel Operator verifies all lamps on the Status Display AND on the right and left hand controllers are Panel and the Right and Left Hand Controllers illuminated. are illuminated.
5.1 .3.C.9. SELECT LIGHT TEST icon on the Touch Operator touches Light Test icon on the Touch Screen to end the lamp test. Screen to end lamp test.
- 5.1.3.C.10. OBSERVE the "IS CASK GATE INSTALLED?" Operator Presses YES on Touch Screen.
prompt on the screen, AND ANSWER by pressing YES or NO on the Touch Screen.
Nuclear Common Page 5 of 23 Rev. 0
NC.TQ-WB.ZZ-031 0(Z)
V JPM NUMBER: 2003-NRC-S5 OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: Refueling Platform TASK: Perform Semi-Automatic Fuel Transfer within the Spent Fuel Pool.
STEP IV lLCOMMENTS
- STEP NO. (*Denotes a Critical Step) STANDARD EVAL (Required for UNSAT
_ _ (#Denotes a Sequential Step) S/U evaluation)
- 5.1.3.C.11. OBSERVE the "IS REACTOR GATE Operator presses YES on Touch Screen.
INSTALLED?"
prompt on the screen, AND ANSWER by pressing YES or NO on the Touch Screen.
5.1 .3.C.12. VERIFY that the Log On Screen reappears.
- 5.1.3.C.13. TOUCH the PRESS FOR OPERATION icon to Operator presses PRESS FOR OPERATION begin operation of the system. icon on the Touch Screen.
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NC.TQ-WB.ZZ-031 0(Z)
JPM NUMBER: 2003-NRC-S5 OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: Refueling Platform TASK Perform Semi-Auto matic Fuel Transfer within the Spent Fuel Pool.
l _ STEP IVAL COMMENTS
- STEP NO. (*Denotes a Critical Step) STANDARD EVAL (Required for UNSAT
(#Denotes a Sequential Step) S/U evaluation) 5.10NOTE 5.10 Operator reads Note 5.10 All irradiated fuel moves or core alterations must be directly supervised by a licensed SRO or SRO limited to fuel-handling. Non-irradiated fuel handling not involving core alterations and blade guide movement do not require direct supervision by an SRO and can be annotated by the spotter directly involved with the evolution. [CD-168A]
This procedure Section describes any combination of fuel/blade guide in Spent Fuel Storage Pool movements between any of the following fuel storage locations:
- Fuel storage racks
- Fuel preparation machines
- Fuel sipping canisters
- Special test and measurement devices Nuclear Common Page 7 of 23 Rev. 0
NC.TQ-WB.ZZ-0310(Z).
JPM NUMBER: 2003-NRC-S5 OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: Refueling Platform TASK: Perform Semi-Automatic Fuel Transfer within the Spent Fuel Pool.
_ I STEP IVl COMMENTS
- STEP NO. (*Denotes a Critical Step) STANDARD ESVALl (Required for UNSAT L (#Denotes a Sequential Step) S evaluation)
Note 5.10 (cont.) Operator reads note.
This Section uses the term "source" location (from location) as the location where a fuel/blade guide assembly is initially grappled and "target" location (to location) as the destination of the fuel/blade guide assembly.
Fuel Assembly channel fastener orientation and location must be accomplished and documented in accordance with the Fuel Movement Sheets.
ENSURE that all prerequisites have been Operator checks prerequisites are satisfied.
5.10.1 satisfied IAW Section 2.10 of this procedure.
5.10.2 Switch on the Start/Stop Station is set to Operator checks the MONO/FRAME/CONSOLE CONSOLE. Switch on the Start/Stop Station is set to CONSOLE. If not, the operator places it in CONSOLE.
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NC.TQ-WB.ZZ-031 0(Z)
JPM NUMBER: 2003-NRC-S5 OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: Refueling Platform TASK Perform Semi-Autcomatic Fuel Transfer within the Spent Fuel Pool.
STEP
- STEP NO. (*Denotes a Critical Step) STANDARD
________(#Denotes a Sequential Step) lL
- 5.10.3 TOUCH the Show Menu icon Operator touches SHOW MENU touch AND SELECT XY MODE ACTIVE icon. screen button.
Operator selects XY MODE ACTIVE.
- 5.10.4 PRESS the PRESS FOR OPERATION Operator presses the PRESS FOR button. OPERTION button.
5.10.5 TOUCH the SELECT AUTO on the Touch Operator uses SELECT AUTO button to Screen. ensure SELECT AUTO is selected.
5.10.6 ENSURE the MANUAL OPERATION Operator ensures MANUAL OPERATION ACTIVE button ACTIVE button is being displayed.
is being displayed.
5.10.7 Operator touches REQUEST on touch
. TOUCH REQUEST on the Auto screen screen. Operator verifies that the keypad is AND VERIFY that the keypad is displayed. displayed.
Page 9of 23 Rev. 0 Nuclear Common
NC.TQ-WB.ZZ-031 0(Z).
I JPM NUMBER: 2003-N RC-S5 OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: Refueling Platform TASK: Perform Semi-Automatic Fuel Transfer within the Spent Fuel Pool.
.STEP COMMENTS
- (*Denotes a Critical Step) STANDARD S/U (Required for UNSAT
(#Denotes a Sequential Step) evaluation)
- 5.10.8 In accordance with the Fuel Movement Operator enters location for Source Location Sheet(s), as AD-28 using the keypad on the Touch ENTER the location via the alphanumeric Screen.
keypad displayed on the Touch Screen.
- 5.10.9 After visually verifying the Bridge Position, Operator visually verifies the Bridge Position, Trolley position AND the requested location, Trolley position AND the requested location PRESS the VERIFY button. *Operator Presses the VERIFY button.
- 5.10.10 PRESS AUTO RUN icon on the touch Examiner Note: Pressing AUTO RUN will screen to initiate Refuel Platform movement. cause the platform to move automatically from the current position to location AD-28.
Operator presses AUTO RUN icon on the touch screen.
5.10.11 VERIFY that the bridge and trolley have Operator observes platform, trolley, and hoist moved to the requested position movement to Source Location AD-28 in the AND the message AUTO SEQUENCE Spent Fuel Pool over the Dummy Bundle.
COMPLETE is displayed on the Touch Operator verifies AUTO SEQUENCE Screen. COMPLETE is displayed on the Touch Screen.
Nuclear Common Page 10 of 23 Rev. 0
NC.TQ-WB.ZZ-031 0(Z).
JPM NUMBER: 2003-NRC-S5 OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: Refueling Platform TASK Perform Semi-Automatic Fuel Transfer within the Spent Fuel Pool.
STEP
- STEP NO. (*Denotes a Critical Step) STANDARD L_____ _ l(#Denotes a Sequential Step) 5.10.12 ENSURE the Fuel Grapple is at the correct Operator verifies location with Fuel Fuel Pool Coordinates. Movement sheet FROM Location AD-28.
(REFER TO NOTE 5.10)
- 5.10.13 LOWER the Fuel Grapple to approximately *Operator uses the Hoist LOWER control to one foot above the fuel assembly/blade lower the Fuel Grapple to approximately one guide to be removed by using the Fuel foot above the DUMMY Bundle.
Grapple Hoist control in the LOWER position Operator observes Grapple NORMAL UP AND OBSERVE the GRAPPLE NORMAL light extinguished.
UP light off
- 5.10.14 ROTATE the Fuel Grapple so that the *Operator rotates the Fuel Grapple in line grapple hooks are in line with Dummy Bundle handle.
with the fuel assembly/blade guide handle.
5.10.15 IF possible Operator verifies "DUMMY" marked on WHEN fuel is being moved, SRO should handle of Dummy Bundle using the Main visually ENSURE correct serial number of Grapple camera.
Fuel Assembly.
(REFER TO NOTE 5.10)
Nuclear Common Page 11 of 23 Rev. 0
NC.TQ-WB.ZZ-031 0(Z).
JPM NUMBER: 2003-NRC-S5 OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: Refueling Platform TASK: Perform Semi-Automatic Fuel Transfer within the Spent Fuel Pool.
- S STEP COMMENTS
- (*Denotes a Critical Step) STANDARD EVAL (Required for UNSAT
__ _ (#Denotes a Sequential Step) S evaluation) 5.10.16 PLACE the GRAPPLE ENGAGE/RELEASE Operator ensures the GRAPPLE Switch to the RELEASE position to ensure ENGAGE/RELEASE Switch to the RELEASE the Fuel Grapple hooks are open, position to ensure the Fuel Grapple hooks OBSERVE the ENGAGE light off. are open, Operator observes the ENGAGE light off.
Examiner Note: The grapple may already be open.
- 5.10.17 Slowly LOWER the Fuel Grapple UNTIL the Operator slowly lowers the Fuel Grapple until Fuel Grapple is resting on the fuel the Fuel Grapple is resting on the fuel assembly/blade guide handle. Grapple may assembly/blade guide handle. The grapple be gently twisted to seat on handle. may be gently twisted to seat on handle.
5.10.17.A OBSERVE Fuel Grapple downward motion Operator observes Fuel Grapple downward automatically stops. motion automatically stops.
5.10.17.B OBSERVE the SLACK CABLE light on. Operator observes the SLACK CABLE light on.
Nuclear Common Page 12 of 23 Rev. 0
NC.TQ-WB.ZZ-031 0(Z)
JPM NUMBER: 2003-NRC-S5 OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: Refueling Platform TASK: Perform Semi-Automatic Fuel Transfer within the Spent Fuel Pool.
S STEP COMMENTS
(*Denotes a Critical Step) STANDARD EVAL (Required for UNSAT L _l ___(#Denotes a Sequential Step) S evaluation)
-6.iG.iG. ENSURE Fuel Grapple is at required depth Operator observes HOIST GRAPPLE
. to. 17.C by observing ELEVATION Digital Readout at -215.
HOIST GRAPPLE ELEVATION Digital Readout.
- i44-6.46' ROTATE grapple in both directions. [CD- Operator gently rotates the grapple in both G. o. 17. D 739F] directions to ensure grapple is seated.
- -.46--7 PLACE the GRAPPLE ENGAGE/RELEASE Operator places the GRAPPLE s.to, ij Switch in the ENGAGE position to grapple ENGAGE/RELEASE Switch in the ENGAGE the fuel assembly/blade guide. position to grapple the fuel assembly/blade guide.
-5+6-1T-A OBSERVE the grapple ENGAGE light on. Operator observes the grapple ENGAGE 5 ,i. 18. A light on.
Operator Initials the Fuel Movement sheet FROM position time and date.
Page,14('of 25 Rev. 0 Nuclear Common 11
NC.TQ-WB.ZZ-031 0(Z)
JPM NUMBER: 2003-NRC-S5 OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: Refueling Platform TASK: Perform Semi-Automatic Fuel Transfer within the Spent Fuel Pool.
STEP NO. STEP I COMMENTS
- (*Denotes a Critical Step) STANDARD ESV/AUL (Required for UNSAT
_ _ _ (#Denotes a Sequential Step) S evaluation)
- 5.10.18.B ROTATE grapple in both directions to Operator rotates the grapple in both ensure proper directions to ensure grapple is seated.
engagement. [CD-739F]
- 5.10.19 Slowly RAISE the grappled fuel Operator uses the Fuel Grapple hoist control assembly/blade guide using the in the RAISE position.
Fuel Grapple hoist control in the RAISE position.
5.10.19.A OBSERVE the SLACK CABLE light off Operator checks the SLACK CABLE light is extinguished.
5.10.19.B OBSERVE the HOIST LOADED light: Operator checks the HOIST LOADED light
- Light ON for Fuel Assembly ON.
- Light OFF for Blade Guide 5.10.19. C OBSERVE the Load Cell Indicator to ensure Operator verifies the Load Cell reading the assembly has been grappled. consistent with Dummy Bundle weight.
Nuclear Common Page 14 of 23 Rev. 0
NC.TQ-WB.ZZ-031 0(Z)
JPM NUMBER: 2003-NRC-S5 OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: Refueling Platform TASK: Perform Semi-Automatic Fuel Transfer within the Spent Fuel Pool.
STEP IVI LCOMMENTS
- (*Denotes a Critical Step) STANDARD EVAL (Required for UNSAT L____(#Denotes a Sequential Step) l evaluation) 5.10.19.D Visually VERIFY assembly/blade guide is Operator verifies Dummy Bundle being being lifted. raised.
CAUTION 5.10.20 Operator reads Caution 5.10.20
- 5.10.20 RAISE AND CONTINUOUSLY OBSERVE Operator uses the Fuel Grapple hoist control the fuel assembly/blade in the RAISE position.
guide during its upward travel. Operator verifies Dummy Bundle being raised.
5.10.21 ENSURE hose and cable reels are taking Operator monitors hose and cable reels.
up slack by observing cables and air hoses remain taught within the grapple.
CAUTION 5.10.22 Operator reads caution.
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NC.TQ-WB.ZZ-031 0(Z)
JPM NUMBER: 2003-NRC-S5 OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: Refueling Platform TASK: Perform Semi-Automatic Fuel Transfer within the Spent Fuel Pool.
STEP IVI l COMMENTS
- (*Denotes a Critical Step) STANDARD EVAL (Required for UNSAT
_ _ _ (#Denotes a Sequential Step) S evaluation)
- 5.10.22 WHEN the fuel assembly/blade guide has Operator releases Raise control.
reached its upper limit:
5.10.22.A OBSERVE the GRAPPLE NORMAL UP OBSERVE the GRAPPLE NORMAL UP light light on. on.
5.10.22.B Fuel Grapple upward motion automatically Operator observes Fuel Grapple upward stops. motion automatically stops.
- 5.10.23 TOUCH the SELECT AUTO on the Touch Operator presses the SELECT AUTO icon on Screen. the Touch Screen.
5.10.24 ENSURE the MANUAL OPERATION Operator ensures the MANUAL OPERATION ACTIVE button ACTIVE button is being displayed.
is being displayed.
- 5.10.25 TOUCH REQUEST on the Auto screen Operator Touches "REQUEST" on touch AND VERIFY that the keypad is displayed. screen. Operator verifies that the keypad is displayed.
Page 16 of 23 Rev. 0 Nuclear Common
NC.TQ-WB.ZZ-0310(Z)
JPM NUMBER: 2003-NRC-S5 OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: Refueling Platform TASK: Perform Semi-Automatic Fuel Transfer within the Spent Fuel Pool.
STEP
- STEP NO. (*Denotes a Critical Step) STANDARD
_(#Denotes a Sequential Step) l_.
- 5.10.26 In accordance with the Fuel Movement Operator enters location for Target Location Sheet(s), as AH-50 using the keypad on the Touch ENTER the location via the alphanumeric Screen.
keypad displayed on the Touch Screen.
5.10.27 After visually verifying the Bridge position, Operator visually verifies the Bridge Position, Trolley position, AND the requested Trolley position AND the requested location location, *Operator Presses the VERIFY button.
PRESS the VERIFY button.
- 5.10.28 PRESS AUTO RUN icon on the touch Operator presses AUTO RUN icon on the screen Touch Screen.
to initiate Refuel Platform movement.
5.10.29 VERIFY that the bridge and trolley have Operator verifies that the bridge, trolley, and moved to the requested position hoist have moved to the requested position AND the display message AUTO (AH-50) AND the display message AUTO SEQUENCE COMPLETE is displayed SEQUENCE COMPLETE is displayed on the on the Touch Screen. Touch Screen.
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NC.TQ-WB.ZZ-031 0(Z) X JPM NUMBER: 2003-NRC-S5 OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: Refueling Platform TASK: Perform Semi-Automatic Fuel Transfer within the Spent Fuel Pool.
l STEP COMMENTS
- STEP NO. (*Denotes a Critical Step) STANDARD EVAL (Required for UNSAT
- (#Denotes a Sequential Step) / evaluation) 5.10.30 ENSURE the Fuel Grapple is at the correct Operator ensures the Fuel Grapple with Core Dummy Bundle is above Target Location AH-OR Fuel Pool Coordinates. 50.
(REFER TO Note 5.10)
- 5.10.31 ROTATE the Fuel Grapple Operator rotates the dummy bundle into NE AND attached fuel assembly/blade guide to orientation in accordance with the Fuel attain direct alignment Movement Sheet AND orientation with the target location.
[CD-396Y]
5.10.32 CAUTION 5.10.32 Operator reads CAUTION 5.10.32
- 5.10.32 Slowly LOWER the fuel assembly/blade Operator uses the Fuel Grapple hoist guide into the target location position control in the LOWER position to using the Fuel Grapple hoist position control slowly lower the bundle into the Target in the LOWER position. Location AH-50.
Nuclear Common Page 18 of 23 Rev. 0
NC.TQ-WB.ZZ-031 0(Z)
JPM NUMBER: 2003-NRC-S5 OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: Refueling Platform TASK: Perform Semi-Automatic Fuel Transfer within the Spent Fuel Pool.
. STEP IVl l COMMENTS
- STEP NO. (*Denotes a Critical Step) STANDARD ESV/AL (Required for UNSAT L (#Denotes a Sequential Step) S evaluation)
- 5.10.33 WHEN the fuel assembly/blade guide Operator releases the LOWER control when is fully seated in the target location the Dummy Bundle is fully seated.
AND:
5.10.33.A OBSERVE the SLACK CABLE light on. Operator observes the SLACK CABLE light on.
5.10.33.B1 OBSERVE the HOIST LOADED light off. Operator observes the HOIST LOADED light off.
5.10.33.C OBSERVE no load indicated (< 60 Ibs) on Operator observes no load indicated (< 60 the load cell indicator. Ibs) on the load cell indicator.
5.10.33.D OBSERVE Fuel Grapple downward motion Operator observes Fuel Grapple downward automatically stops. motion automatically stops.
Page 19 of 23 Rev. 0 Nuclear Common
NC.TQ-WB.ZZ-0310(Z)
JPM NUMBER: 2003-N RC-S5 OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: Refueling Platform TASK: Perform Semi-Automatic Fuel Transfer within the Spent Fuel Pool.
STEP IV ILCOMMENTS
- STEP NO. (*Denotes a Critical Step) STANDARD EVAL (Required for UNSAT
= (#Denotes a Sequential Step) S/ evaluation) 5.10.33.E ENSURE Fuel Grapple is at required depth Operator observes the Fuel Grapple is at by observing HOIST GRAPPLE required depth by observing HOIST ELEVATION Digital Readout GRAPPLE ELEVATION Digital Readout reading -215
- 5.10.34 PLACE the GRAPPLE ENGAGE/RELEASE Operator places the GRAPPLE Switch to the RELEASE position ENGAGE/RELEASE Switch to the RELEASE AND OBSERVE the grapple ENGAGE light position.
off. Operator observes the grapple ENGAGE light off.
- 5.10.35 Slowly RAISE the Fuel Grapple by using the Operator uses the hoist position control in the hoist position RAISE position.
control in the RAISE position.
5.10.35.A OBSERVE the SLACK CABLE light off. Operator observes the SLACK CABLE light off.
Nuclear Common Page 20 of 23 Rev. 0
NC.TQ-WB.ZZ-031 0(Z)
JPM NUMBER: 2003-NRC-S5 OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: Refueling Platform TASK: Perform Semi-Automatic Fuel Transfer within the Spent Fuel Pool.
STEP NO. STEP COMMENTS
(*Denotes a Critical Step) STANDARD EVAL (Required for UNSAT
(#Denotes a Sequential Step) l _ l _ _ _ _ _evaluation) 5.10.35.B OBSERVE the HOIST LOADED light Operator observes the HOIST LOADED light remains off. remains off.
5.10.35.C OBSERVE the Load Cell Indicator to ensure Operator observes the Load Cell Indicator to that no load has been inadvertently ensure that no load has been inadvertently grappled. [CD-442A] grappled.
- 5.10.36 RAISE the Fuel Grapple fully to avoid Operator raises Fuel Grapple at least one collision with any underwater obstructions. foot above racks and releases the RAISE IF next Fuel Assembly OR blade guide to be moved is nearby, control.
RAISE the Fuel Grapple at least one foot.
5.10.37 ENSURE hose and cable reels are taking Operator observes hose and cable reels for up slack by observing slack.
cables and air hoses remain taught within the grapple.
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NC.TQ-WB.ZZ-031 0(Z)
JPM NUMBER: 2003-NRC-S5 OPERATOR TRAINING PROGRAM NAME:
JOB PERFORMANCE MEASURE DATE:
SYSTEM: Refueling Platform TASK: Perform Semi-Automatic Fuel Transfer within the Spent Fuel Pool.
STEP NO. STEP l COMMENTS
- (*Denotes a Critical Step) STANDARD ESVAL (Required for UNSAT L _l ___(#Denotes a Sequential Step) S evaluation) 5.10.38 IF Fuel Assemblies were moved, Operator Initials the Fuel Movement sheet INITIAL the appropriate box on the Fuel TO position time and date.
Movement Sheet(s) indicating the fuel transfer has been completed.
5.10.39 NOTIFY the Control Room that the fuel Operator notifies Control Room that fuel transfer has been completed. transfer is completed.
Terminating Cue: Repeat back message STOP TIME: from the operator on the status of the JPM, and then state "This JPM is complete".
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NC.TQ-WRZ.Z-031 0(Z)
JOB PERFORMANCE MEASURE OPERATOR INFO SHEET INITIAL CONDITIONS:
- There are NO irradiated components grappled to any refueling platform hoist.
- Auxiliary hoists are fully raised with attached tooling clear of obstructions.
- HC.OP-ST.KE-0001 and HC.OP-FT.KE-0001 has been completed for the Refueling Platform.
- The Refuel platform is in a standby lineup.
- Main Hoist Grapple is RELEASED.
- Primary and Redundant encoders are selected for Bridge, Trolley and Hoist travel.
- An approved FUEL MOVEMENT SHEET for transfer of the dummy bundle has been obtained from Reactor Engineering. The Spent fuel rack locations specified on the FUEL MOVEMENT SHEET are within the Secure Travel Zone.
- Prerequisites for dummy bundle transfer within the Spent Fuel Pool are completed per HC.OP-SO.KE-0001.
INITIATING CUE:
Perform transfer of the Dummy Bundle within the spent fuel storage racks using Semi-Automatic XY mode of refueling platform operation, in accordance with the attached Fuel Movement Sheet step # 01.
Nuclear Common Page 23 of 23 Rev. 0
HC.RE-FR.ZZ-OOU ,(Q)
ATTACHMENT 1 FUEL MOVEMENT SHEET REFUEL NO. N/A SHEET NO. 1 CONTINUED ON SHEET _ N/A Step I.D. FROM Time TO Time Operator Verified By Number Number Location Orientation Date Location Orientation Date Initials Initials 01 DUMMY SFP ANY SFP NE AD - 28 AH - 50 02 DUMMY SFP NE SFP NW AH - 50 AD - 28 C*RLL-t5K HL PCR EL at' LL__d______
Prepared By Date Independently Verified By Date Hope Creek Page 18 of 23 Rev. 20
PSEG Internal Use Onlv Page 1 of 1 PSEG NUCLEAR L.L.C.
HOPE CREEK GENERATING STATION HC.OP-SO.KE-0001(Q) - Rev. 30 REFUELING PLATFORM AND FUEL GRAPPLE OPERATION USE CATEGORY: II A. Biennial Review performed Yes No N/A v B. Change Package(s) and Affected Document Number(s) incorporated into this revision.
- OTSC No(s) or None V REVISION
SUMMARY
- 1. The following changes have been incorporated based on DCP 80047191 Added Sections 2.10 and 5. 10 - Fuel/Blade Guide Movement - Within Spent Fuel Storage Pool (other than Refuel Mode) in Semi-Automatic Mode
- 2. CAUTION 5.8 has been revised to indicated the "source" location is the "from location" on the Fuel Movement Sheets and the "target" location is the "to location" on the Fuel Movement Sheets. Editorial IMPLEMENTATION REQUIREMENTS Effective date 3 21 Ox APPROVED: 3 /?? /3 Manager - Hop ek Operations Date
PSEG Internal Use Onlv HC.OP-SO.KE-0001(Q)
REFUELING PLATFORM AND FUEL GRAPPLE OPERATION TABLE OF CONTENTS Section Title Page 1.0 PURPOSE ......................... 3 2.0 PREREQUISITES ....................... 3 3.0 PRECAUTIONS & LIMITATIONS .......... ............... 23 4.0 EQUIPMENT REQUIRED ........................ 29 5.0 PROCEDURE ......................... 30 5.1 Refuel Platform Start-up and Shutdown ............................................. 30 5.2 Fuel Transfer - Reactor Core to Spent Fuel Storage Pool ........................ 34 5.3 Fuel Transfer - Spent Fuel Storage Pool to Reactor Core ........................ 40 5.4 Blade Guide Transfer - Spent Fuel Storage Pool to Reactor Core ........... 46 5.5 Blade Guide Transfer - Reactor Core to Spent Fuel Storage Pool ........... 49 5.6 Fuel Movement - Within Reactor Vessel ............................................. 53 5.7 Blade Guide Movement - Within Reactor Vessel .................................... 57 5.8 Fuel/Blade Guide Movement - Within Spent Fuel Storage Pool (other than Refuel Mode) in Manual .................................. 62 5.9 Auxiliary Hoist Tool Installation .................................. 67 5.10 Fuel/Blade Guide Movement - Within Spent Fuel Storage Pool (other than Refuel Mode) in Semi-Automatic Mode ............................... 80
6.0 REFERENCES
............................................ . 87 Hope Creek Page I of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO.KE-0001(Q)
REFUELING PLATFORM AND FUEL GRAPPLE OPERATION TABLE OF CONTENTS Section Title Page ATTACHMENTS ANALYZED LOADS Permitted Over IRRADIATED FUEL Not Requiring SECONDARY CONTAINMENT INTEGRITY ............. 89 Instructions for Manually Lowering a Fuel Bundle ................................. 90 Refueling Platform Interlocks ............... ............................. 94 Hope Creek Page 2 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO.KE-0001(Q)
REFUELING PLATFORM AND FUEL GRAPPLE OPERATION
- 1.0 PURPOSE 1.1 This procedure provides detailed instructions to accomplish the following Refueling tasks:
1.1.1 Transfer fuel to and from the Spent Fuel Storage Pool and Reactor Core. [CD-736D].
1.1.2 Transfer blade guides to and from the Spent Fuel Storage Pool and Reactor Core.
1.1.3 Transfer fuel within Reactor Vessel.
1.1.4 Transfer blade guides within Reactor Vessel.
1.1.5 Transfer Fuel and Blade Guides within the Spent Fuel Storage Pool (other than Refuel Mode). [CD-736D]
1.1.6 Install necessary tools on Refueling Platform Auxiliary Hoists.
1.2 In addition this procedure provides the prerequisites, precautions and limitations required to maintain fuel integrity during Refueling Operations.
2.0 PREREQUISITES 2.1 Refuel Platform Start-up and Shutdown 2.1.1 Breaker 52-254061 is closed to provide power to Refuel Platform.
2.1.2 Applicable Precautions and Limitations have been reviewed by each procedure user.
2.2 Fuel Transfer - Reactor Core to Spent Fuel Storage Pool 2.2.1 The Reactor Building Secondary Containment Ventilation System RBVS & FRVS automatic isolation dampers shall be operable IAW T.S. 3.6.5.2.
2.2.2 Reactor Building integrity shall be maintained IAW T.S. 3.6.5. .b.
2.2.3 The Fuel Grapple Hoist shall be verified operable LAW USFAR 9.1.4.2.12.3 by performing procedure HC.OP-ST.KE-000I(Q), Refuel Interlock Operability Functional Test - Section 5.4.
Hope Creek Page 3 of 94 Rev. 30
PSEG Interins al Use Only HC.OP-SO.KE-0001(Q) 2.2.4 At least 23 feet of water shall be maintained over the top of irradiated Fuel Assemblies seated in the Spent Fuel Storage Racks IAW T.S. 3.9.9.
2.2.5 The Filtration, Recirculation and Ventilation System shall be operable IAW T.S. 3.6.5.3.
2.2.6 Procedure HC.OP-ST.KE-0001(Q); Refuel Interlock Operability Test must be performed prior to CORE ALTERATIONS, IAW T.S. 3.9.1.
[CD-182C]
2.2.7 The Reactor Mode Switch shall be operable AND locked in the REFUEL OR the SHUTDOWN position IAW T.S. 3.9.1.
2.2.8 At least two Source Range Monitors (SRM) shall be operable AND inserted to the normal operating level IAW T.S. 3.9.2 AND:
A. Annunciation and continuous visual indication of these monitors is available in the Control Room.
B. One of the required SRM detectors is located in the Reactor Core quadrant where CORE ALTERATIONS are being performed AND the other SRM detector shall be located in an adjacent quadrant.
2.2.9 All control rods are fully inserted IAW T.S. 3.9.3.
2.2.10 The Reactor shall be subcritical for a minimum of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
[ UFSAR 9.1.4.2.12.1.
2.2.11 Establish and maintain direct communication between the Control Room and Refueling Floor personnel [UFSAR 9.1.4.2.12.2.]
2.2.12 At least 22 feet 2 inches of water shall be maintained over the top of the Reactor Pressure Vessel flange IAW T.S. 3.9.8.
2.2.13 All CORE ALTERATIONS shall be observed AND directly supervised by either a Senior Reactor Operator OR a Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation IAW T.S. 6.2.2.C.
2.2.14 Breaker 52-254061 is closed to provide power to Refuel Platform.
Hope Creek Page 4 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 2.2.15 Prior to moving the Refueling Platform ensure the following conditions exist:
A. Refuel Platform tracks are clear of equipment or materials which would impede platform motion.
B. Cables, ropes or other devices are not tied to the Refuel Platform or Trolley.
C. The Jib Cranes and Channel Handling Boom have been positioned to prevent collisions with the Refuel Platform.
D. The Fuel Grapple, Monorail Hoist and Auxiliary Hoist are not carrying any loads.
E. Underwater obstructions which may interfere with fuel transfer are identified and repositioned IF possible. CD-396Y F. PERFORM HC.OP-FT.KE-000l(Q);
Refuel Platform and Fuel Grapple Operability Test - Refueling:
- 1. IF maintenance has been completed on the Refueling Platform and/or Hoists.
- 2. Monthly during fuel handling operations.
G. PERFORM HC.OP-FT.KE-0002(Q);
Fuel Grapple Full Down Travel Functional Test - Refueling IF not performed within 30 days of starting fuel handling operations.
2.2.16 No testing, maintenance or other activity is in progress on the Refuel Platform, Spent Fuel Storage Pool, New Fuel Vault, Reactor Cavity or Shipping Cask Area which would impede the movement of the Refuel Platform.
2.2.17 Permission to move irradiated nuclear fuel OR PERFORM CORE ALTERATIONS has been granted by the OS/CRS.
2.2.18 OBTAIN the Fuel Movement Sheet(s) developed by Reactor Engineering IAW HC.RE-FR.ZZ-000I(Q).
2.2.19 All personnel that will operate the Refuel Platform and Fuel Grapple have completed training and are qualified. [CD-124B]
Page 5 of 94 Rev. 30 Hope Creek
PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 2.2.20 WHEN transferring irradiated fuel, or any other irradiated Reactor internal, between Reactor Vessel and Spent Fuel Storage Pool the Shielded Fuel Transfer Chute shall be installed.
2.2.21 NOTIFY the Radiation Protection Department prior to starting any fuel transfer operation. The Radiation Protection Department shall ensure that personnel leave the upper level of the Drywell prior to fuel transfer. [CD-069A]
2.2.22 Power to Refuel Platform Control Console energized.
2.2.23 Position indication cameras for the Main Hoist are selected for display.
2.2.24 No equipment or tools, with the exception of; the Refueling Platform, the Polar Crane or any ANALYZED LOADS (ANALYZED LOADS are listed in Attachment 1), SHALL be moved over IRRADIATED FUEL UNLESS SECONDARY CONTAINMENT INTEGRITY is in effect lAW T.S. 1.39.
2.2.25 During fuel movement and control blade movement, the Service Pole Caddy is to be locked in its storage position on the East end of the rail using the two locking brakes to the handrail provided on the pole caddy.
2.2.26 Applicable Precautions and Limitations have been reviewed by each procedure user.
2.2.27 Underwater lights have been installed in the Reactor Vessel and Cavity and energized as necessary to support Refueling activities.
Hope Creek Page 6 of 94 Rev. 30
1- dN T7li ~fi1 Idfh PSEG Internal Use Only ULM 2.3 Fuel Transfer - Spent Fuel Storage Pool to Reactor Core 2.3.1 The Reactor Building Secondary Containment Ventilation System RBVS & FRVS automatic isolation dampers shall be operable IAW T.S. 3.6.5.2.
2.3.2 Reactor Building integrity shall be maintained IAW T.S. 3.6.5.1.b.
2.3.3 The Fuel Grapple Hoist shall be verified operable IAW UFSAR. 9.1.4.2.12.3 by performing procedure HC.OP-ST.KE-0001(Q),
Refuel Interlock Operability Functional Test - Section 5.4.
2.3.4 At least 23 feet of water shall be maintained over the top of irradiated Fuel Assemblies seated in the Spent Fuel Storage Racks IAW T.S. 3.9.9.
2.3.5 The Filtration, Recirculation and Ventilation System shall be operable IAW T.S. 3.6.5.3.
2.3.6 Procedure HC.OP-ST.KE-000l(Q); Refuel Interlock Operability Test must be performed prior to CORE ALTERATIONS IAW T.S. 3.9.1. [CD-182C]
2.3.7 The Reactor Mode Switch shall be operable AND locked in the REFUEL OR the SHUTDOWN position IAW T.S. 3.9.1.
2.3.8 At least two Source Range Monitors (SRM) shall be operable AND inserted to the normal operating level IAW T.S. 3.9.2 AND:
A. Annunciation AND continuous visual indication of these monitors is available in the Control Room.
B. One of the required SRM detectors is located in the Reactor core quadrant where CORE ALTERATIONS are being performed AND the other SRM detector shall be located in an adjacent quadrant.
2.3.9 All control rods are fully inserted IAW T.S. 3.9.3.
2.3.10 The Reactor shall be subcritical for a minimum of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
[UFSAR 9.1.4.2.12.1].
2.3.11 Establish and maintain direct communication between the Control Room and Refueling Floor personnel [UFSAR 9.1.4.2.12.21.
Hope Creek Page 7 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 2.3.12 At least 22 feet 2 inches of water shall be maintained over the top of the Reactor Pressure Vessel flange IAW T.S. 3.9.8.
2.3.13 All CORE ALTERATIONS shall be observed AND directly supervised by either a Senior Reactor Operator OR a Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation IAW T.S. 6.2.2.c.
2.3.14 Breaker 52-254061 is closed to provide power to Refuel Platform.
2.3.15 Prior to moving the Refueling Platform ensure the following conditions exist:
A. Refuel Platform tracks are clear of equipment or materials which would impede platform motion.
B. Cables, ropes or other devices are not tied to the Refuel Platform or Trolley.
C. The Jib Cranes and Channel Handling Boom have been positioned to prevent collisions with the Refuel Platform.
D. The Fuel Grapple, Monorail Hoist and Auxiliary Hoist are not carrying any loads.
E. Underwater obstructions which may interfere with fuel transfer are identified and repositioned IF possible. [CD-396Y1 F. PERFORM HC.OP-FT.KE-0001(Q);
Refuel Platform and Fuel Grapple Operability Test - Refueling:
- 1. IF maintenance has been completed on the Refueling Platform and/or Hoists.
- 2. Monthly during fuel handling operations.
G. PERFORM HC.OP-FT.KE-0002(Q);
Fuel Grapple Full Down Travel Functional Test - Refueling IF not performed within 30 days of starting fuel handling operations.
Hope Creek Page 8 of 94 Rev. 30
HC.OP-SO.KE-OOO1(Q)
PSEG Internal Use Only 2.3.16 No testing, maintenance or other activity is in progress on the Refuel Platform, Spent Fuel Storage Pool, New Fuel Vault, Reactor Cavity or Shipping Cask Area which would impede the movement of the Refuel Platform.
2.3.17 Permission to move irradiated nuclear fuel OR perform CORE ALTERATIONS has been granted by the OS/CRS.
2.3.18 OBTAIN the Fuel Movement Sheet(s) developed by Reactor Engineering IAW HC.RE-FR.ZZ-0001(Q).
2.3.19 All personnel that will operate the Refuel Platform and Fuel Grapple have completed training and are qualified. [CD-124B]
2.3.20 WHEN transferring irradiated fuel, or any other irradiated Reactor internal, between Reactor Vessel and Spent Fuel Storage Pool the Shielded Fuel Transfer Chute shall be installed.
2.3.21 NOTIFY the Radiation Protection Department prior to starting any fuel transfer operation. The Radiation Protection Department shall ensure that personnel leave the upper level of the Drywell prior to fuel transfer. [CD-069A1 2.3.22 Power to Refuel Platform Control Console energized.
2.3.23 Position indication cameras for the Main Hoist are selected for display.
2.3.24 No equipment or tools, with the exception of; the Refueling Platform, the Polar Crane or any ANALYZED LOADS (ANALYZED LOADS are listed in Attachment 1), SHALL be moved over IRRADIATED FUEL UNLESS SECONDARY CONTAINMENT INTEGRITY is in effect IAW T.S. 1.39.
2.3.25 During fuel movement and control blade movement, the Service Pole Caddy is to be locked in its storage position on the East end of the rail using the two locking brakes to the handrail provided on the paddy caddy.
2.3.26 Applicable Precautions and Limitations have been reviewed by each procedure user.
2.3.27 Underwater lights have been installed in the Reactor Vessel and Cavity and energized as necessary to support Refueling activities.
Hope Creek Page 9 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 2.4 Blade Guide Transfer - Spent Fuel Storage Pool to Reactor Core 2.4.1 The Fuel Grapple Hoist shall be verified operable IAW UFSAR 9.1.4.2.12.3 by performing procedure HC.OP-ST.KE-0001(Q), Refuel Interlock Operability Functional Test - Section 5.4.
2.4.2 At least 23 feet of water shall be maintained over the top of irradiated Fuel Assemblies seated in the Spent Fuel Storage Racks IAW T.S. 3.9.9.
2.4.3 Procedure HC.OP-ST.KE-0001(Q); Refuel Interlock Operability Test must be performed prior to CORE ALTERATIONS IAW T.S. 3.9.1.
[CD-182C]
2.4.4 The Reactor Mode Switch shall be operable AND locked in the REFUEL OR the SHUTDOWN position IAW T.S. 3.9.1.
2.4.5 The Reactor shall be subcritical for a minimum of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
[UFSAR 9.1.4.2.12.1].
2.4.6 At least 22 feet 2 inches of water shall be maintained over the top of the Reactor Pressure Vessel flange IAW T.S. 3.9.8.
2.4.7 Breaker 52-254061 is closed to provide power to Refuel Platform.
2.4.8 Prior to moving the Refueling Platform ensure the following conditions exist:
A. Refuel Platform tracks are clear of equipment or materials which would impede platform motion.
B. Cables, ropes or other devices are not tied to the Refuel Platform OR Trolley.
C. The Jib Cranes and Channel Handling Boom have been positioned to prevent collisions with the Refuel Platform.
D. The Fuel Grapple, Monorail Hoist and Auxiliary Hoist are not carrying any loads.
Continued next page Hope Creek Page 10 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 2.4.8 (continued)
E. Underwater obstructions which may interfere with fuel transfer are identified and repositioned IF possible. [CD-396YJ F. PERFORM HC.OP-FT.KE-0001(Q); Refuel Platform and Fuel Grapple Operability Test - Refueling:
- 1. IF maintenance has been completed on the Refueling Platform and/or Hoists.
- 2. Monthly during fuel handling operations.
G. PERFORM HC.OP-FT.KE-0002(Q);
Fuel Grapple Full Down Travel Functional Test - Refueling IF not performed within 30 days of starting fuel handling operations.
2.4.9 No testing, maintenance or other activity is in progress on the Refuel Platform, Spent Fuel Storage Pool, New Fuel Vault, Reactor Cavity or Shipping Cask Area which would impede the movement of the Refuel Platform.
2.4.10 OBTAIN the Fuel Movement Sheet(s) developed by Reactor Engineering IAW HC.RE-FR.ZZ-000 1(Q).
2.4.11 All personnel that will operate the Refuel Platform and Fuel Grapple have completed training and are qualified. [CD-124B]
2.4.12 NOTIFY the Radiation Protection Department prior to starting any fuel transfer operation. The Radiation Protection Department shall ensure that personnel leave the upper level of the Drywell prior to fuel transfer. [CD-069A]
2.4.13 Power to Refuel Platform Control Console energized.
2.4.14 Position indication cameras for the Main Hoist are selected for display.
2.4.15 No equipment or tools, with the exception of; the Refueling Platform, the Polar Crane or any ANALYZED LOADS (ANALYZED LOADS are listed in Attachment 1), SHALL be moved over IRRADIATED FUEL UNLESS SECONDARY CONTAINMENT INTEGRITY is in effect IAW T.S. 1.39. _
2.4.16 During fuel movement and control blade movement, the Service Pole Caddy is to be locked in its storage position on the East end of the rail using the two locking brakes to the handrail provided on the paddy caddy.
Hope Creek Page 11 of 94 Rev. 30
PSEG Internal Use Only HC.op-So.KE-0001(Q) 2.4.17 Applicable Precautions and Limitations have been reviewed by each procedure user.
2.4.18 Underwater lights have been installed in the Reactor Vessel and Cavity and energized as necessary to support Refueling activities.
2.5 Blade Guide Transfer - Reactor Core to Spent Fuel Storage Pool 2.5.1 The Fuel Grapple Hoist shall be verified operable IAW UFSAR 9.1.4.2.12.3 by performing procedure HC.OP-ST.KE-0001(Q), Refuel Interlock Operability Functional Test - Section 5.4.
2.5.2 At least 23 feet of water shall be maintained over the top of irradiated Fuel Assemblies seated in Spent Fuel Storage Racks IAW T.S. 3.9.9.
2.5.3 Procedure HC.OP-ST.KE-000l(Q); Refuel Interlock Operability Test must be performed prior to CORE ALTERATIONS IAW T.S. 3.9.1. ICD-182C]
2.5.4 The Reactor Mode Switch shall be operable AND locked in the REFUEL OR the SHUTDOWN position IAW T.S. 3.9.1.
2.5.5 The Reactor shall be subcritical for a minimum of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
[UFSAR 9.1.4.2.12.11 2.5.6 At least 22 feet 2 inches of water shall be maintained over the top of the Reactor Pressure Vessel flange IAW T.S. 3.9.8.
2.5.7 Breaker 52-254061 is closed to provide power to Refuel Platform.
Rev. 30 ID- - of OA lv12 Hope CreeK JL nr,, L,& VJL -,
PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 2.5.8 Prior to moving the Refueling Platform ensure the following conditions exist:
A. Refuel Platform tracks are clear of equipment or materials which would impede platform motion.
B. Cables, ropes or other devices are not tied to the Refuel Platform or Trolley.
C. The Jib Cranes and Channel Handling Boom have been positioned to prevent collisions with the Refuel Platform.
D. The Fuel Grapple, Monorail Hoist AND Auxiliary Hoist are not carrying any loads.
E. Underwater obstructions which may interfere with fuel transfer are identified AND repositioned IF possible. [CD-396Y]
F. PERFORM HC.OP-FT.KE-0001(Q);
Refuel Platform and Fuel Grapple Operability Test - Refueling:
- 1. IF maintenance has been completed on the Refueling Platform and/or Hoists.
- 2. Monthly during fuel handling operations.
G. PERFORM HC.OP-FT.KE-0002(Q);
Fuel Grapple Full Down Travel Functional Test - Refueling IF not performed within 30 days of starting fuel handling operations.
2.5.9 No testing, maintenance or other activity is in progress on the Refuel Platform, Spent Fuel Storage Pool, New Fuel Vault, Reactor Cavity or Shipping Cask Area which would impede the movement of the Refuel Platform.
2.5.10 OBTAIN the Fuel Movement Sheet(s) developed by Reactor Engineering IAW HC.RE-FR.ZZ-0001(Q).
2.5.11 All personnel that will operate the Refuel Platform and Fuel Grapple have completed training and are qualified. [CD-124B]
Hope Creek Page 13 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 2.5.12 NOTIFY the Radiation Protection Department prior to starting any fuel transfer operation. The Radiation Protection Department shall ensure that personnel leave the upper level of the Drywell prior to fuel transfer. [CD-069A]
2.5.13 Power to Refuel Platform Control Console energized.
2.5.14 Position indication cameras for the Main Hoist are selected for display.
2.5.15 No equipment or tools, with the exception of; the Refueling Platform, the Polar Crane or any ANALYZED LOADS (ANALYZED LOADS are listed in Attachment 1), SHALL be moved over IRRADIATED FUEL UNLESS SECONDARY CONTAINMENT INTEGRITY is in effect IAW T.S. 1.39.
2.5.16 During fuel movement and control blade.movement, the Service Pole Caddy is to be locked in its storage position on the East end of the rail using the two locking brakes to the handrail provided on the paddy caddy.
2.5.17 Applicable Precautions and Limitations have been reviewed by each procedure user.
2.5.18 Underwater lights have been installed in the Reactor Vessel and Cavity and energized as necessary to support Refueling activities.
2.6 Fuel Movement - Within Reactor Vessel 2.6.1 The Reactor Building Secondary Containment Ventilation System RBVS & FRVS automatic isolation dampers shall be operable IAW T.S. 3.6.5.2.
2.6.2 Reactor Building integrity shall be maintained IAW T.S. 3.6.5.1.b.
2.6.3 The Fuel Grapple Hoist shall be verified operable IAW UFSAR 9.1.4.2.12.3 by performing procedure HC.OP-ST.KE-OOO1(Q), Refuel Interlock Operability Functional Test - Section 5.4.
2.6.4 At least 23 feet of water shall be maintained over the top of irradiated Fuel Assemblies seated in the Spent Fuel Storage Racks IAW T.S. 3.9.9.
2.6.5 The Filtration, Recirculation and Ventilation System shall be operable IAW T.S. 3.6.5.3.
2.6.6 Procedure HC.OP-ST.KE-0001(Q); Refuel Interlock Operability Test must be performed prior to CORE ALTERATIONS IAW T.S. 3.9.1. [CD-182C] _
Hope Creek Page 14 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 2.6.7 The Reactor Mode Switch shall be operable AND locked in the REFUEL OR SHUTDOWN position IAW T.S. 3.9.1.
2.6.8 At least two Source Range Monitors (SRM) shall be operable AND inserted to the normal operating level IAW T.S. 3.9.2 AND:
A. Annunciation AND continuous visual indication of these monitors is available in the Control Room.
B. One of the required SRM detectors is located in the Reactor Core quadrant where CORE ALTERATIONS are being performed AND the other SRM detector shall be located in an adjacent quadrant.
2.6.9 All control rods are fully inserted IAW T.S. 3.9.3.
2.6.10 The Reactor shall be subcritical for a rninimum of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
[UFSAR 9.1.4.2.12.1].
2.6.11 Establish and maintain direct communication between the Control Room and Refueling Floor personnel [UFSAR 9.1.4.2.12.2].
2.6.12 At least 22 feet 2 inches of water shall be maintained over the top of the Reactor Pressure Vessel flange IAW T.S. 3.9.8.
2.6.13 All CORE ALTERATIONS shall be observed AND directly supervised by either a Senior Reactor Operator OR a Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation IAW T.S. 6.2.2.c.
2.6.14 Breaker 52-254061 is closed to provide power to Refuel Platform.
Hope Creek Page 15 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 2.6.15 Prior to moving the Refueling Platform ensure the following conditions exist:
A. Refuel Platform tracks are clear of equipment or materials which would impede platform motion.
B. Cables, ropes or other devices are not tied to the Refuel Platform or Trolley.
C. The Jib Cranes and Channel Handling Boom have been positioned to prevent collisions with the Refuel Platform.
D. The Fuel Grapple, Monorail Hoist and Auxiliary Hoist are not carrying any loads.
E. Underwater obstructions which may interfere with fuel transfer are identified and repositioned IF possible. [CD-396Y3 F. PERFORM HC.OP-FT.KE-0001(Q);
Refuel Platform and Fuel Grapple Operability Test - Refueling:
- 1. IF maintenance has been completed on the Refueling Platform and/or Hoists.
- 2. Monthly during fuel handling operations.
G. PERFORM HC.OP-FT.KE-0002(Q);
Fuel Grapple Full Down Travel Functional Test - Refueling IF not performed within 30 days of starting fuel handling operations.
2.6.16 No testing, maintenance or other activity is in progress on the Refuel Platform, Spent Fuel Storage Pool, New Fuel Vault, Reactor Cavity or Shipping Cask Area which would impede the movement of the Refuel Platform.
2.6.17 Permission to move irradiated nuclear fuel or perform CORE ALTERATIONS has been granted by the OS/CRS.
2.6.18 OBTAIN the Fuel Movement Sheet(s) developed by Reactor Engineering IAW HC.RE-FR.ZZ-000I(Q).
2.6.19 All personnel that will operate the Refuel Platform and Fuel Grapple have completed training and are qualified. [CD-124B]
Hope Creek Page 16 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 2.6.20 NOTIFY the Radiation Protection Department prior to starting any fuel transfer operation. The Radiation Protection Department shall ensure that personnel leave the upper level of the Drywell prior to fuel transfer. [CD-069A]
2.6.21 Power to Refuel Platform Control Console energized.
2.6.22 Position indication cameras for the Main Hoist are selected for display.
2.6.23 No equipment or tools, with the exception of; the Refueling Platform, the Polar Crane or any ANALYZED LOADS (ANALYZED LOADS are listed in Attachment 1), SHALL be moved over IRRADIATED FUEL UNLESS SECONDARY CONTAINMENT INTEGRITY is in effect IAW Tech Spec 1.39.
2.6.24 During fuel movement and control blade movement, the Service Pole Caddy is to be locked in its storage position on the East end of the rail using the two locking brakes to the handrail provided on the paddy caddy.
2.6.25 Applicable Precautions and Limitations have been reviewed by each procedure user.
2.6.26 Underwater lights have been installed in the Reactor Vessel and Cavity and energized as necessary to support Refueling activities.
2.7 Blade Guide Movement - Within Reactor Vessel 2.7.1 The Fuel Grapple Hoist shall be verified operable IAW UFSAR 9.1.4.2.12.3 by performing procedure HC.OP-ST.KE-0001(Q), Refuel Interlock Operability Functional Test - Section 5.4.
2.7.2 At least 23 feet of water shall be maintained over the top of irradiated Fuel Assemblies seated in the Spent Fuel Storage Racks IAW T.S. 3.9.9.
2.7.3 Procedure HC.OP-ST.KE-0001(Q); Refuel Interlock Operability Test must be performed prior to CORE ALTERATIONS IAW T.S. 3.9.1.
[CD-182C]
2.7.4 The Reactor Mode Switch shall be operable AND locked in the REFUEL OR the SHUTDOWN position IAW T.S. 3.9.1.
2.7.5 The Reactor shall be subcritical for a minimum of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
[ITFSAR 9.1.4.2.12.11 Hope Creek Page 17 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 2.7.6 At least 22 feet 2 inches of water shall be maintained over the top of the Reactor Pressure Vessel flange IAW T.S. 3.9.8.
2.7.7 Breaker 52-254061 is closed to provide power to Refuel Platform.
2.7.8 Prior to moving the Refueling Platform ensure the following conditions exist:
A. Refuel Platform tracks are clear of equipment or materials which would impede platform motion.
B. Cables, ropes or other devices are not tied to the Refuel Platform or Trolley.
C. The Jib Cranes and Channel Handling Boom have been positioned to prevent collisions with the Refuel Platform.
D. The Fuel Grapple, Monorail Hoist and Auxiliary Hoist are not carrying any loads.
E. Underwater obstructions which may interfere with fuel transfer are identified and repositioned IF possible. [CD-396Y]
F. Perform HC.OP-FT.KE-0001(Q); Refuel Platform and Fuel Grapple Operability Test - Refueling:
- 1. IF maintenance has been completed on the Refueling Platform and/or Hoists.
- 2. Monthly during fuel handling operations.
G. PERFORM HC.OP-FT.KE-0002(Q);
Fuel Grapple Full Down Travel Functional Test - Refueling IF not performed within 30 days of starting fuel handling operations.
2.7.9 No testing, maintenance or other activity is in progress on the Refuel Platform, Spent Fuel Storage Pool, New Fuel Vault, Reactor Cavity or Shipping Cask Area which would impede the movement of the Refuel Platform.
2.7.10 OBTAIN the Fuel Movement Sheet(s) developed by Reactor Engineering IAW HC.RE-FR.ZZ-0001(Q).
Hope Creek Page 18 of 94 Rev. 30
PSEG Internal Use OnlyH HC.OP-SO.KE-0001(Q) 2.7.11 All personnel that will operate the Refuel Platform and Fuel Grapple have completed training and are qualified. [CD-124B]
2.7.12 NOTIFY the Radiation Protection Department prior to starting any fuel transfer operation. The Radiation Protection Department shall ensure that personnel leave the upper level of the Drywell prior to fuel transfer. [CD-069A]
2.7.13 Power to Refuel Platform Control Console energized.
2.7.14 Position indication cameras for the Main Hoist are selected for display.
2.7.15 An SRO shall be on the Refuel Bridge to ensure no CORE ALTERATIONS take place.
2.7.16 No equipment or tools, with the exception of; the Refueling Platform, the Polar Crane or any ANALYZED LOADS (ANALYZED LOADS are listed in Attachment 1), SHALL be moved over IRRADIATED FUEL UNLESS SECONDARY CONTAINMENT INTEGRITY is in effect IAW Tech Spec 1.39.
2.7.17 During fuel movement and control blade movement, the Service Pole Caddy is to be locked in its storage position on the East end of the rail using the two locking brakes to the handrail provided on the paddy caddy.
2.7.18 Applicable Precautions and Limitations have been reviewed by each procedure user.
2.7.19 Underwater lights have been installed in the Reactor Vessel and Cavity and energized as necessary to support Refueling activities.
2.8 Fuel/Blade Guide Movement - Within Spent Fuel Storage Pool (other than Refuel Mode) in Manual 2.8.1 The Reactor Building Secondary Containment Ventilation System RBVS & FRVS automatic isolation dampers shall be operable IAW T.S. 3.6.5.2.
2.8.2 Reactor Building integrity shall be maintained IAW T.S. 3.6.5.1.b.
2.8.3 The Fuel Grapple Hoist shall be verified operable by performing procedure HC.OP-ST.KE-000I(Q), Refuel Interlock Operability Functional Test - Section 5.4. [UFSAR 9.1.4.2.12.3, CD-178H1]
2.8.4 At least 23 feet of water shall be maintained over the top of irradiated Fuel Assemblies seated in spent Fuel Storage Racks IAW T.S. 3.9.9.
Hope Creek Page 19 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO-KE-0001(Q) 2.8.5 The Filtration, Recirculation and Ventilation System shall be operable IAW T.S. 3.6.5.3.
2.8.6 Procedure HC.OP-FT.KE-0001(Q); Refuel Platform and Fuel Grapple Operability Test - Refueling has been completed. [CD-182C]
2.8.7 Procedure HC.OP-ST.KE-000 1(Q), Refuel Interlock Operability Functional Test - Section 5.4); has been completed to demonstrate Refuel Platform load cell setpoint. [UFSAR 9.1.4.2.12.3, CD-178H]
2.8.8 The Refuel Platform is in a standby line up.
2.8.9 Breaker 52-254061 is closed to provide power to Refuel Platform.
2.8.10 Prior to moving the Refueling Platform ensure the following conditions exist:
A. Refuel Platform tracks are clear of equipment or materials which would impede platform motion.
B. Cables, ropes or other devices are not tied to the Refuel Platform or Trolley.
C. The Jib Cranes and Channel Handling Boom have been positioned to prevent collisions with the Refuel Platform.
D. The Fuel Grapple, Monorail Hoist and Auxiliary Hoist are not carrying any loads.
E. Underwater obstructions which may interfere with fuel transfer are identified and repositioned IF possible.
2.8.11 Irradiated Fuel movements in Spent Fuel Storage Pool shall be observed AND directly supervised by either a Senior Reactor Operator OR a Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation. This is required since the SRO may have to evacuate Refuel floor IAW HC.OP-AB.CONT-0005(Q), Irradiated Fuel Damage, in the event a fuel bundle is dropped and radiation levels increase. [CD-168A]
2.8.12 Permission to move irradiated nuclear fuel has been granted by the OS/CRS.
2.8.13 OBTAIN the Fuel Movement Sheet(s) developed by Reactor Engineering IAW HC.RE-FR.ZZ-000 1(Q).
Hope Creek Page 20 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 2.8.14 All personnel that will operate the Refuel Platform and Fuel Grapple have completed training and are qualified. [CD-124B]
2.8.15 NOTIFY the Radiation Protection Department prior to starting any fuel transfer operation.
2.8.16 Power to Refuel Platform Control Console energized.
2.8.17 Spent Fuel Pool gates are verified installed per HC.MD-FR.KE-0013(Q),
Refuel Floor-Shield and Pool Plugs Removal and Replacement.
2.8.18 No equipment or tools, with the exception of; the Refueling Platform, the Polar Crane or any ANALYZED LOADS (ANALYZED LOADS are listed in Attachment 1), SHALL be moved over IRRADIATED FUEL UNLESS SECONDARY CONTAINMENT INTEGRITY is in effect 1AW T/S 1.39.
2.8.19 During fuel movement and control blade movement, the Service Pole Caddy is to be locked in its storage position on the East end of the rail using the two locking brakes to the handrail provided on the paddy caddy.
2.8.20 Applicable Precautions and Limitations have been reviewed by each procedure user.
2.9 Auxiliary Hoist Tool Installation Applicable Precautions and Limitations have been reviewed by each procedure user.
2.10 Fuel/Blade Guide Movement - Within Spent Fuel Storage Pool (other than Refuel Mode) in Semi-Automatic Mode 2.10.1 The Reactor Building Secondary Containment Ventilation System RBVS & FRVS automatic isolation dampers shall be operable IAW T.S. 3.6.5.2.
2.10.2 Reactor Building integrity shall be maintained IAW T.S. 3.6.5.l.b.
2.10.3 The Fuel Grapple Hoist shall be verified operable by performing procedure HC.OP-ST.KE-000l(Q), Refuel Interlock Operability Functional Test - Section 5.4. [UFSAR 9.1.4.2.12.3, CD-178H]
2.10.4 At least 23 feet of water shall be maintained over the top of irradiated Fuel Assemblies seated in spent Fuel Storage Racks IAW T.S. 3.9.9.
Hope Creek Page 21 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 2.10.5 The Filtration, Recirculation and Ventilation System shall be operable IAW T.S. 3.6.5.3.
2.10.6 Procedure HC.OP-FT.KE-0001(Q); Refuel Platform and Fuel Grapple Operability Test - Refueling has been completed. [CD-182C]
2.10.7 Procedure HC.OP-ST.KE-000 1(Q), Refuel Interlock Operability Functional Test - Section 5.4); has been completed to demonstrate Refuel Platform load cell setpoint. [UFSAR 9.1.4.2.12.3, CD-178H11 2.10.8 The Refuel Platform is in a standby line up.
2.10.9 Breaker 52-254061 is closed to provide power to Refuel Platform.
2.10.10 Prior to moving the Refueling Platform ENSURE the following conditions exist:
A. Refuel Platform tracks are clear of equipment or materials which would impede platform motion.
B. Cables, ropes or other devices are not tied to the Refuel Platform or Trolley.
C. The Jib Cranes and Channel Handling Boom have been positioned to prevent collisions with the Refuel Platform.
D. The Fuel Grapple, Monorail Hoist and Auxiliary Hoist are not carrying any loads.
E. Underwater obstructions which may interfere with fuel transfer are identified and repositioned IF possible.
2.10.11 Irradiated Fuel movements in Spent Fuel Storage Pool shall be observed AND directly supervised by either a Senior Reactor Operator OR a Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation. This is required since the SRO may have to evacuate Refuel floor in accordance with HC.OP-AB.CONT-0005(Q), Irradiated Fuel Damage, in the event a fuel bundle is dropped and radiation levels increase. [CD-168A1 2.10.12 Permission to move irradiated nuclear fuel has been granted by the OS/CRS.
2.10.13 OBTAIN the Fuel Movement Sheet(s) developed by Reactor Engineering IAW HC.RE-FR.ZZ-0001(Q).
Hope Creek Page 22 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 2.10.14 All personnel that will operate the Refuel Platform and Fuel Grapple have completed training and are qualified. [CD-124B]
2.10.15 NOTIFY the Radiation Protection Department prior to starting any fuel transfer operation.
2.10.16 Power to Refuel Platform Control Console energized.
2.10.17 Spent Fuel Pool gates are verified installed per HC.MD-FR.KE-0013(Q),
Refuel Floor-Shield and Pool Plugs Removal and Replacement.
2.10.18 No equipment or tools, with the exception of; the Refueling Platform, the Polar Crane or any ANALYZED LOADS (ANALYZED LOADS are listed in Attachment 1), SHALL be moved over IRRADIATED FUEL UNLESS SECONDARY CONTAINMENT INTEGRITY is in effect IAW T/S 1.39.
2.10.19 During fuel movement and control blade movement, the Service Pole Caddy is to be locked in its storage position on the East end of the rail using the two locking brakes to the handrail provided on the paddy caddy.
2.10.20 Applicable Precautions and Limitations have been reviewed by each procedure user.
3.0 PRECAUTIONS AND LIMITATIONS 3.1 Precautions 3.1.1 The normal up stop on Refueling Platform Main Hoist shall NOT be bypassed when handling Fuel Assemblies. The normal up stop on the Refueling Platform Auxiliary Hoist shall not be bypassed when handling irradiated components. (UFSAR 9.1.4.2.12.3) 3.1.2 To prevent damage to Fuel Assemblies:
A. DO NOT attempt to release a grappled Fuel Assembly UNTIL it is fully seated in a storage OR Reactor Core location. [CD-736D, CD-123E, CD-182C]
B. DO NOT reposition the Refuel Platform or Trolley while the Fuel Assembly is grappled and not fully withdrawn from the storage or Reactor Core location.
C. DO NOT twist a grappled Fuel Assembly while it is held fast in a storage or Reactor Core location.
Hope Creek Page 23 of 94 Rev. 30
PSEG Internal Use Oniy HC.OP-SO.KE-0001(Q) 3.1.3 WHEN transferring irradiated fuel between the Reactor Cavity AND Spent Fuel Pool.
A. Minimize the time the fuel is in the Drywell Bellows Area.
[CD-612X, CD-069A]
B. Restrict fuel transfer to most direct path between the Reactor Vessel AND Spent Fuel Pool. [CD-612X]
3.1.4 While positioning irradiated fuel in the Reactor Vessel or Spent Fuel Pool, maximize the amount of water shielding between the Fuel Assembly AND Reactor Vessel wall or Spent Fuel Pool wall. [CD-069A, CD-612X, CD-719A1 _
3.1.5 DO NOT remove a blade guide from its Reactor Core location IF the respective control rod will be left unsupported.
3.1.6 The Service Pole Caddy which rides on the same rail as the Monorail Auxiliary Hoist is for the removal and installation of the Moisture Separator and miscellaneous in vessel work. During the use of this procedure for fuel movement and control blade movement it is to be locked in its storage position on the East end of the rail using the two locking brakes to the handrail provided on the paddy caddy.
REFER to procedures HC.MD-FR.KE-0006(Q)
AND HC.MD-FR.KE-0026(Q) for operation of the Pole Caddy.
3.1.7 Any of the Refueling Bridge Mast Sections (10", 7", or 5"), can bind while being extended or retracted. The Encoder readout (distance traveled), used in conjunction with the Load Cell readout (weight on main mast cable), can be used to effectively verify whether binding is occurring. For example, IF you start from a full up position (10", 7", and 5" sections fully retracted), and start lowering the mast sections while observing the Encoder and Load Cell indications, the weight of the 10" section should transfer from the main mast cable to the 12" section at approximately 180" on the Encoder reading (the Load Cell indication will decrease by approximately 105#). Continuing down, the weight of the 7" section should transfer from the main mast cable to the 10" section at approximately 380" on the Encoder reading (the Load Cell indication will decrease by approximately 88#). This methodology can also be applied for use in the opposite direction. IF while lowering the mast, an unexpected slack cable OR pre-mature weight transfer occurs, stop lowering, raise the load to clear the slack cable (if one exists), and notify the cognizant Refuel SRO OR OS/CRS before attempting any corrective action. [CD-619G]
Hope Creek Page 24 of 94 Rev. 30
PSEG Internal Use OnlhE HC.0P-S0.KE-0001(Q) 3.1.8 WHEN handling fuel out of the Fuel Prep Machine VERIFY the channel fastener is clearly visible and not enclosed by the grapple head. This is the only place that the operator can see the channel fastener while grabbing a fuel bundle. [CD-739F]
3.1.9 To prevent damage to underwater lamps ensure that the lamps remain fully submerged while they are energized. ICD-673D]
3.1.10 Operation of the Refuel Platform (Bridge), Trolley or Fuel Grapple with the variable speed control operators should be accomplished by gradual accelerations and decelerations, rather than full on and full off deflections of the operators. This will produce less wear on the equipment and better operator control.
3.1.11 The Refueling Platform should never be left unattended with the "POWER ON" (as indicated by the STOP light on the Left Hand Controller). An electrical failure could cause the platform to move on its own accord. Turning off the power for short durations while the operator leaves the platform should be a standard practice.
3.1.12 Abnormalities that may occur during operation, such as spurious high load readings or audible indications should not be ignored. Such occurrences must be investigated and the cause ascertained to prevent possible subsequent damage to the platform or handled fuel.
3.1.13 Should an emergency stop occur during lowering of auxiliary or monorail hoists, the safety brake of that hoist will set without delay and take the hoist load on its ratchet-pawl arrangement.
- Prior to attempting to releasing the brake, the cause of the emergency stop should be understood.
IF possible, the grapple should be moved away from irradiated fuel prior to performing the release.
- In the case where a full load is being lowered at the time of the stop, this load may prevent the safety brake from immediately releasing on a subsequent hoist operation, unless the hoist is commanded to raise as an initial operation, thereby taking the load off the safety brake.
- IF the brake does not release because of a lowering command, it will emit a loud chattering noise, alerting the operator to raise the load. In most cases, no harm will occur as the result of an operator not following this procedure. The only consequence is that the safety brake will prevent the hoist from lowering.
Hope Creek Page 25 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 3.1.14 Should an emergency stop occur during the lowering of the Main Hoist, the hoist safety brake will set without delay and take the hoist load.
- Prior to attempting to release the brake, the cause of the emergency stop should be understood.
IF possible, the grapple should be moved away from irradiated fuel prior to performing the release.
- In the case where a full load is being loaded at the time of the stop, this load may prevent the safety brake from immediately releasing on a subsequent hoist operation, unless the hoist is commanded to raise as an initial operation, thereby taking the load off the safety brake.
- In most cases, IF the brake does not release because of a lowering command, no harm will occur as the result of an operator not following this procedure. The only consequence is that the safety brake will prevent the hoist from lowering.
3.1.15 An indication that the Grapple has missed completely is a Full Grapple Down Light ON with NO Slack Cable Light.
3.2 Limitations 3.2.1 Operate the Refuel Platform, Trolley and Fuel Grapple Hoist variable speed controls in a manner which results in gradual accelerations or decelerations.
3.2.2 The Fuel Grapple is the only hoist used to transfer Fuel Assemblies in the Spent Fuel Pool and Reactor Cavity.
3.2.3 The fuel may be transferred only to those devices and storage locations specified on the Fuel Movement Sheet(s) developed by Reactor Engineering IAWHC.RE-FR.ZZ-0001(Q). [CD-719A]
3.2.4 DO NOT move a Fuel Assembly within one foot of any assembly stored in a fuel preparation machine, shipping canister or special test fixture. [CD-719A]
3.2.5 A designated "spotter" is required for all bridge activities which require any grapple to be loaded.
3.2.6 No individual should perform bridge activities for greater than six consecutive hours.
Hope Creek Page 26 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 3.2.7 IF the Technical Specification requirements listed in Section 2.0 of this procedure cannot be maintained:
A. COMPLETE the transfer of any fuel loaded on the Fuel Grapple OR RETURN the fuel to its original location.
B. TERMINATE all further fuel transfers AND CORE ALTERATIONS UNTIL the conditions specified in the Technical Specification requirements listed in Section 2.0 are restored.
3.2.8 IF Refuel Platform or Fuel Grapple hoist equipment failure occurs while fuel is loaded on the Fuel Grapple: [CD-736D, CD-442A]
A. PERFORM corrective actions IAW Attachment 2.
B. REPORT the nature and extent of the equipment damage to the Refuel Floor Supervisor or Operations Superintendent.
3.2.9 IF underwater lights are used for illumination ensure the lamps are de-energized prior to removing them from the water. [CD-673D]
3.2.10 The Radiation Protection Department should be notified when fuel transfers are completed or are to be delayed for greater than one hour.
3.2.11 Operate the Refuel Platform, Trolley and Fuel Grapple in a manner to avoid collisions with underwater obstructions that can not be repositioned.
3.2.12 At the discretion of the Refuel Bridge SRO, and, with concurrence from Station Management, operation of the bridge and mast in concurrent multiple directions is permissible (e.g., moving the mast up/down with bridge motion, etc.). Individual responsibilities (SRO and spotter) regarding collision-avoidance should be briefed prior to any multiple dimensional fuel moves. [700079211 3.2.13 WHEN inserting and removing Fuel Assemblies in the Reactor Core prevent contact between the Fuel Assembly and incore detectors and installed neutron sources. ICD-365D]
3.2.14 ENSURE the Refuel Bridge handrails remain in place whenever the camera cart is on the bridge. [CD-711F]
3.2.15 Pre-operational assembly requirements for the Fuel Support Grapple is dependent upon the configuration of the control rod and drive assembly at the site of the fuel support.
Hope Creek Page 27 of 94 R~ev. 30
PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 3.2.16 The control blade grapple, the combined CRB/FSP grapple and the jet pump grapple are the only grapples to be used to handle control blades within the reactor pressure vessel.
3.2.17 All torque wrenches used in the performance of this procedure should be of the appropriate range to read the reference value or the last recorded torque value between 20% and 100% of range.
[PR 960128076]
3.2.18 IF alternate RHR-FPCC assist mode is in service, up to 9000 gpm may flow through the spent fuel pool to the reactor well. This will cause increased drag loads on the refuel mast when a load is transported through the fuel pool gates. It may be necessary to reduce bridge speed, when passing through the gate, to control vertical swing on the mast.
3.2.19 The refueling mast should not be permitted to swing against the trolley.
This may cause bending or damage to the mast.
3.3 Interlocks NOTE 3.3.1 Main hoist loaded relays actuate at 535 pounds and 550 pounds.
3.3.1 The following conditions will cause a Rod Block:
A. Main Hoist loaded, the Refuel Bridge over the Reactor Core, AND Mode Switch in REFUEL.
B. The Refuel Bridge over the Reactor Core AND Mode Switch in STARTUP.
3.3.2 The following conditions will prevent the Refueling Bridge from traveling in the reverse direction:
A. Main Hoist loaded, the Refuel Bridge over the Core,.
and any control rod withdrawn.
B. Refuel Bridge over the Core AND Mode Switch in STARTUP.
Hope Creek Page 28 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO.KE-OOO1(Q) 3.3.3 The following conditions will prevent Main Hoist up motion:
A. Normal up stop (can be bypassed).
B. Backup hoist limit.
C. Hoist jammed as indicated by 1200 pounds load.
D. Grapple not closed and the Main Hoist weight over 550 lbs.
E. Fuel Hoist Interlock:
- Rod out signal from Control Room
- RS 1 Limit Switch actuated
- Main Hoist Loaded 3.3.4 The following conditions will prevent Main Hoist down motion:
A. Slack cable as indicated by ( < 60 lbs ) and the Slack Cable Light on. (Actual weight indication will vary between Fuel Pool and In Core operation due to the length of cable used and the weight of that cable).
B. Full down limit reached at approximately 4 inches below the elevation of a fuel bundle in the core (as indicated by the Full Grapple Down Light on).
C. Fuel Hoist Interlock:
- Rod out signal from Control Room
- RS 1 Limit Switch actuated
3.3.6 Reference Attachment 3 for Interlock drawing.
4.0 EQUIPMENT REQUIRED
- Thread Sealant Loctite 2432 or 5772.
Hope Creek Page 29 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 5.0 PROCEDURE NOTE 6.0 All movements of the Refuel Platform, Trolley and Fuel Grapple hoist described in this procedure are performed at the Fuel Grapple Operator's Console. WHEN moving the auxiliary hoist(s) to set the mechanical jam, the hoist is operated from the applicable hoist pendant.
5.1 Refuel Platform Start-up and Shutdown 5.1.1 ENSURE that all prerequisites have been satisfied IAW Section 2.1.
NOTE 5.1.2 IF the AC power to the Refuel Platform was open, the Refuel Platform should be warmed up for a minimum of 1/2 hour prior to use.
5.1.2 Refuel Platform Start-up Instructions A. At the West end of the Refuel Platform VERIFY the following:
- 1. The Main Power Disconnect Switch is in the CLOSED position.
- 2. The Monorail Hoist Disconnect Switch is in the CLOSED position.
B. At the West end of the Refuel Platform (Bridge),
VERIFY the Main Hoist Air Isolation Valve AND Monorail Hoist Air Isolation Valve are open.
C. At the West end of the Refuel Platform PLACE the Air Compressor Disconnect Switch is in the CLOSED position.
Hope Creek Page 30 of 94 Rev. 30
- -- C.d,~ Vr. nifklf Id-Vt PSEG Internal Use Only UUvtkv)
NOTE 5.1.3 The computer takes approximately one minute to load all the files required for opern 5.1.3 PERFORM the following to activate the Refuel Bridge Computer:
A. TURN all circuit breakers for the Control System to the ON position. [Located on top of Bridge]
B. PRESS the START PB on the START/STOP Station mounted in the Main Trolley Cab.
AND the following will occur:
- STOP PB illuminates
- Heater circuits to the motors and cabinets are automatically disconnected when power is turned on.
C. PERFORM the following to log on to the system:
- 1. VERIFY the Log On Screen is on.
- 2. SELECT LOG ON icon, on the Touch Screen, AND VERIFY that the Keypad screen is visible.
- 3. TYPE your name THEN TOUCH the ENTER icon.
- 4. IF incorrect name was entered, TOUCH the CHANGE NAME icon THEN TYPE your name THEN TOUCH the ENTER icon.
- 5. TOUCH the ENTER PASSWORD icon.
- 6. TYPE password THEN TOUCH the ENTER icon.
- 7. SELECT LIGHT TEST icon on the Touch Screen.
Continued next page Hope Creek Page 31 of 94 Rev.30
PSEG Internal Use On - HC.OP-SO.KE-0001(Q) 5.1.3.C (continued)
NOTE 5.1.3.C.8 The Computer Override Light will not illuminate unless the keyswitch for Computer Override is used.
- 8. VERIFY all lamps on the Status Display Panel AND on the right and left hand controllers are illuminated.
- 9. SELECT LIGHT TEST icon on the Touch Screen to end the lamp test.
- 10. OBSERVE the "IS CASK GATE INSTALLED?"
prompt on the screen, AND ANSWER by pressing YES or NO on the Touch Screen.
- 11. OBSERVE the "IS REACTOR GATE INSTALLED?"
prompt on the screen, AND ANSWER by pressing YES or NO on the Touch Screen.
- 12. VERIFY that the Log On Screen reappears.
- 13. TOUCH the PRESS FOR OPERATION icon to begin operation of the system.
Hope Creek Page 32 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO.KE-0001(Q)
NOTE 5.1.4 AC power should remain available to the Refuel Plafform. Breaker 52-254061 should remain closed to ensure adequate warm-up prior to use. The Control Panels heaters are required to be energized to prevent condensation between periods of use (outages).
5.1.4 Refuel Platform Shutdown/Standby Instructions A. PRESS the Refuel Platform STOP pushbutton AND VERIFY the red STOP pushbutton light is off.
B. PERFORM the following to log off the Refuel Bridge Computer:
- 1. TOUCH the SHOW MENU icon on the Touch Screen.
- 2. TOUCH the LOG OFF icon.
- 3. TOUCH the YES/LOG OFF icon to verify system log off, log off is now complete.
C. PLACE the Air Compressor Disconnect Switch is in the OPEN position at the West end of the Refuel Platform.
D. ENSURE the Main Power Disconnect Switch AND the Monorail Hoist Disconnect Switch remain in the CLOSED position until maintenance is to be performed.
5.1.5 PERFORM the following to shut-off the system:
A. PRESS the SHUT DOWN icon on the touch screen.
B. PRESS the YES I SHUT DOWN icon to verify system shutdown.
C. ENSURE the SAFE SHUTDOWN message is displayed on the touch screen prior to securing power to the refueling platform. Failure to following this sequence could corrupt the database in Microsoft Access, resulting in loss of Automatic and Semi-Automatic operation.
Hope Creek Page 33 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 5.2 Fuel Transfer - Reactor Core to Spent Fuel Storage Pool 5.2.1 ENSURE that all prerequisites have been satisfied IAW Section 2.2 of this procedure.
5.2.2 USE the Trolley position control to position the Fuel Grapple to attain direct alignment with the center of the fuel transfer path. [CD-396y]
5.2.3 USE the Refuel Platform position control in the REVERSE position to maneuver the Refuel Platform over the Reactor Core.
5.2.4 Using the Refuel Platform AND Trolley position controls AND position indication system MANEUVER the Fuel Grapple to the coordinates listed on the Fuel Movement Sheet(s).
5.2.5 LOWER the Fuel Grapple to approximately one foot above the Fuel Assembly to be removed by using the Fuel Grapple Hoist control in the LOWER position.
5.2.6 ROTATE the Fuel Grapple so that the grapple hooks are in line with the Fuel Assembly handle.
5.2.7 PLACE the GRAPPLE ENGAGE/RELEASE Switch to the RELEASE position to ensure the Fuel Grapple hooks are open.
OBSERVE the grapple ENGAGE light off.
5.2.8 Slowly LOWER the Fuel Grapple until the Fuel Grapple is resting on the Fuel Assembly handle. Grapple may be gently twisted to seat on handle.
A. OBSERVE Fuel Grapple Hoist downward motion automatically stops.
B. OBSERVE the SLACK CABLE light on. [CD-736D]
C. ENSURE Fuel Grapple is at required depth by observing HOIST GRAPPLE ELEVATION Digital Readout.
D. ROTATE grapple in both directions. [CD-739F]
5.2.9 ENSURE the Fuel Grapple is at the correct Core Coordinates.
(SRO)
Hope Creek Page 34 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 5.2.10 PLACE the GRAPPLE ENGAGE/RELEASE Switch in the ENGAGE position to grapple the Fuel Assembly.
A. OBSERVE the grapple ENGAGE light is on.
B. ROTATE grapple in both directions to ensure proper engagement.
[CD-739F]
5.2.11 NOTIFY Control Room that assembly is being removed from Core AND that the SRM's should be observed UNTIL assembly is out of the core.
5.2.12 Slowly RAISE the grappled Fuel Assembly using the Fuel Grapple Hoist Control in the RAISE position.
A. OBSERVE the SLACK CABLE light off.
B. OBSERVE the HOIST LOADED light on. [CD-736D]
C. OBSERVE the load cell indicator to ensure the assembly has been grappled.
D. Visually VERIFY assembly is being lifted.
Hope Creek Page 35 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO.KE-0001(Q)
CAUTION 5.2.13 A. DO NOT attempt to release the Fuel Assembly unless it is fully seated in a storage or Reactor Core location. [CD-123E, CD-736D, CD-182C]
B. DO NOT reposition the Refuel Platform or Trolley while the Fuel Assembly is grappled and not fully withdrawn from the storage or Reactor Core location.
C. DO NOT twist a grappled fuel assembly while it is held fast in a Storage or Reactor Core location.
D. While positioning irradiated fuel in the Reactor Vessel or Spent Fuel Pool maximize the amount of water shielding between the Fuel Assembly and Reactor Vessel or Fuel Pool wall. [CD-612X, CD-069A]
5.2.13 RAISE AND CONTINUOUSLY OBSERVE the Fuel Assembly during its upward travel.
NOTIFY Control Room when assembly is out of the Core.
5.2.14 ENSURE hose and cable reels are taking up slack by observing cables and air hoses remain taught within the grapple.
CAUTION 5.2.15 DO NOT bypass the Main Hoist normal up stop when handling Fuel Assemblies or control rod blades in order to comply with UFSAR 9.1.4.2.12.3.
5.2.15 WHEN the Fuel Assembly has reached its upward limit:
A. OBSERVE the GRAPPLE NORMAL UP light on. [CD-736D]
B. Fuel Grapple upward motion automatically stops.
Hope Creek Page 36 of 94 Rev. 30
PSEG Internal Use On-IOO HC.OP-SO.KE-0001(Q)
CAUTION 5.2.16 A. Minimize the time the fuel is in the Drywell Bellows Area.
[CD-612X, CD-069A]
B. Restrict fuel transfer to the most direct path between the Reactor Vessel and Spent Fuel Pool. [CD-612X]
J~
5.2.16 USE the Trolley position control to position the Fuel Grapple to attain direct alignment with the center of the fuel transfer path to the Fuel Storage Pool. [CD-396Y]
5.2.17 ENSURE the Refuel Platform position control is in the FORWARD position to maneuver the Refuel Platform to the Spent Fuel Pool.
5.2.18 USE the Refuel Platform and Trolley position controls to maneuver the Fuel Grapple to the Spent Fuel Pool Storage Rack location listed on the Fuel Movement Sheet(s).
5.2.19 ROTATE the Fuel Grapple AND attached Fuel Assembly to attain direct alignment and correct orientation with the Fuel Storage Rack location.
Hope Creek Page 37 of 94 Rev. 30
PSEG internal Use Only HC.UY-bU.-UUUiV)
CAUTION 5.2.20 A. DO NOT attempt to release the Fuel Assembly unless it is fully seated in a storage or Reactor Core location. [CD-123E, CD-736D, CD-182C]
B. DO NOT reposition the Refuel Platform or Trolley while the Fuel Assembly is grappled and not fully withdrawn from the storage or Reactor Core location.
C. DO NOT twist a grappled fuel assembly while it is held fast in a Storage or Reactor Core location.
D. While positioning irradiated fuel in the Reactor Vessel or Spent Fuel Pool maximize the amount of water shielding between the Fuel Assembly and Reactor Vessel or Fuel Pool wall. [CD-612X, CD-069A]
5.2.20 ENSURE the Fuel Grapple is at the correct Core or Fuel Pool Coordinates.
SRO 5.2.21 Slowly LOWER the Fuel Assembly into the storage rack location using the Fuel Grapple Hoist position control in the LOWER position.
5.2.22 WHEN the SRO has ensured that the Fuel Assembly is fully seated in the correct Fuel Storage Rack location:
A. OBSERVE the SLACK CABLE light on. [CD-736D]
B. OBSERVE the HOIST LOADED light off. ICD-736D]
C. OBSERVE no load indicated (< 60 lbs) on the load indicator.
D. OBSERVE Fuel Grapple downward motion automatically stops E. ENSURE Fuel Grapple is at required depth by observing HOIST GRAPPLE ELEVATION Digital Readout.
5.2.23 PLACE the GRAPPLE ENGAGE/RELEASE Switch to the RELEASE position AND OBSERVE the grapple ENGAGE light off. [CD-736D]
Hope Creek Page 38 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 5.2.24 Slowly RAISE the Fuel Grapple by using the hoist position control in the RAISE position AND:
A. OBSERVE the SLACK CABLE light off. [CD-736D]
B. OBSERVE the HOIST LOADED light remains off. [CD-736D]
C. OBSERVE the load cell indicator to ensure that no load has been inadvertently grappled. ICD-442A]
D. ENSURE that hose and cable reels are taking up slack by observing air hoses remain taught within the Grapple.
5.2.25 RAISE the Fuel Grapple fully to avoid collision with any underwater obstructions. [CD-396Y1 5.2.26 INITLi1 the appropriate box on the Fuel Movement Sheet(s) indicating the fuel transfer has been completed.
5.2.27 NOTIFY the Control Room personnel that the fuel move has been completed.
5.2.28 Control Room personnel should update the fuel location tracking tool in use.
Hope Creek Page 39 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 5.3 Fuel Transfer - Spent Fuel Storage Pool to Reactor Core 5.3.1 ENSURE that all prerequisites have been satisfied IAW Section 2.3 of this procedure.
5.3.2 USE the Refuel Platform and Trolley position controls to maneuver the Fuel Grapple to the Spent Fuel Pool location listed on the Fuel Movement Sheets.
5.3.3 LOWER the Fuel Grapple to approximately one foot above the Fuel Assembly to be removed by using the Fuel Grapple Hoist control in the LOWER position.
5.3.4 IF possible, visually ENSURE correct serial number of Fuel Assembly.
SRO NOTE 5.3.5 The Fuel Assembly should be grappled in the Spent Fuel Pool so that the Fuel Assembly channel fastener is in the proper orientation for Fuel Assembly installation in the Reactor Core. The Fuel Movement Sheet(s) provides correct core channel fastener orientation.
5.3.5 ROTATE the Fuel Grapple so that the grapple hooks are in line with the Fuel Assembly handle.
5.3.6 PLACE the GRAPPLE ENGAGE/RELEASE Switch to the RELEASE position to ensure the Fuel Grapple hooks are open, OBSERVE the grapple ENGAGE light off.
5.3.7 Slowly LOWER the Fuel Grapple UNTIL the Fuel Grapple is resting on the Fuel Assembly handle. Grapple may be gently twisted to seat on handle AND:
A. OBSERVE Fuel Grapple downward motion automatically stops.
B. OBSERVE the SLACK CABLE light is on. [CD-736D]
C. ENSURE Fuel Grapple is at required depth by observing HOIST GRAPPLE ELEVATION Digital Readout.
D. ROTATE grapple in both directions. [CD-739F]
Hope Creek Page 40 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 5.3.8 ENSURE the Fuel Grapple is at the correct Core OR Fuel Pool Coordinates.
SRO 5.3.9 PLACE the GRAPPLE ENGAGE/RELEASE Switch in the ENGAGE position to grapple the Fuel Assembly.
A. OBSERVE the GRAPPLE ENGAGED light is on. [CD-736D]
B. ROTATE grapple in both directions to ensure proper engagement.
[CD-739F]
5.3.10 Slowly RAISE the grappled Fuel Assembly using the Fuel Grapple hoist control in the RAISE position.
A. OBSERVE the SLACK CABLE light is off. [CD-736D]
B. OBSERVE the HOIST LOADED light is on. [CD-736D]
C. OBSERVE the load cell indicator to ensure the assembly has been grappled.
D. Visually ENSURE assembly is being lifted.
E. ENSURE that hose and cable reels are taking up slack by observing air hoses remain taught within the Grapple.
Hope Creek Page 41 of 94 Rev. 30
PSEG Internal Use Only HC.0P.-S0-KE-0001(Q)
CAUTION 5.3.11 A. DO NOT attempt to release the Fuel Assembly unless it is fully seated in a Storage or Reactor Core location. [CD-123E, CD-736D, CD-182C]
B. DO NOT reposition the Refuel Platform or Trolley while the Fuel Assembly is grappled and not fully withdrawn from the storage or Reactor Core location.
C. DO NOT twist a grappled fuel assembly while it is held fast in a storage or Reactor Core location.
D. While positioning irradiated fuel in the Reactor Vessel or Spent Fuel Pool maximize the amount of water shielding between the Fuel Assembly and Reactor Vessel or Fuel Pool wall. [CD-612X, CD-069A]
5.3.11 RAISE AND CONTINUOUSLY OBSERVE the Fuel Assembly during its upward travel.
CAUTION 5.3.12 DO NOT bypass the Main Hoist normal up stop when Handling Fuel Assemblies or control rod blades in order to comply with UFSAR 9.1.4.2.12.3.
5.3.12 WHEN the Fuel Assembly has reached its upper limit of travel THEN OBSERVE:
A. GRAPPLE NORMAL UP light on. [CD-736D]
B. Fuel Grapple upward motion automatically stops.
Hope Creek Page 42 of 94 Rev. 30
PSEG Internal Use OnyE HC.OP-SO.KE-0001(Q)
CAUTION 5.3.13 A. Minimize the time the fuel is in the Drywell Bellows area.
[CD-612X, CD-069A]
B. Restrict fuel transfer to the most direct path between the Reactor Vessel and Spent Fuel Pool.
.~
5.3.13 USE the Trolley position control to position the Fuel Grapple in direct alignment with the center of the fuel transfer path to the Reactor Well. [CD-396Y]
5.3.14 USE the Refuel Platform Position Control in the REVERSE position to maneuver the Refuel Plafform to the Reactor Cavity area.
5.3.15 USE the Refuel Platform and Trolley Position Controls and Position Indication System to maneuver the Fuel Grapple to the Reactor Core location listed on the Fuel Movement Sheet(s).
5.3.16 NOTIFY Control Room that platform is moving over the Core.
5.3.17 ENSURE the Fuel Grapple is at the correct Core OR Fuel Pool Coordinates.
SRO 5.3.18 ROTATE the Fuel Grapple AND attached Fuel Assembly in direct alignment with the Reactor Core location and corresponding channel fastener orientation listed on the Fuel Movement Sheet(s).
5.3.19 NOTIFY the Control Room that the assembly is about to enter the Core and that SRM's must be observed until assembly is seated.
Hope Creek Page 43 of 94 Rev. 30
PSEG Internal Use OnlyH HC.OP-SO.KE-0001(Q)
CAUTION 5.3.20 A. DO NOT attempt to release the Fuel Assembly unless it is fully seated in a storage or Reactor Core location. [CD-1 23E, CD-736D, CD-1 82C]
B. DO NOT reposition the Refuel Platform or Trolley while the Fuel Assembly is grappled and not fully withdrawn from the storage or Reactor Core location.
C. DO NOT twist a grappled fuel assembly while it is held fast in a storage or Reactor Core location.
D. While positioning irradiated fuel in the Reactor Vessel or Spent Fuel Pool maximize the amount of water shielding between the Fuel Assembly and Reactor Vessel or Fuel Pool wall. [CD-612X, CD-069A]
5.3.20 Slowly LOWER the Fuel Assembly into the Reactor Core location using the Fuel Grapple Hoist Position Control in the LOWER position.
5.3.21 WHEN the SRO has ensured that the Fuel Assembly is fully seated in the correct Reactor Core location:
A. NOTIFY Control Room that assembly is seated in it proper Core location.
B. OBSERVE the SLACK CABLE light on. [CD-736D1 C. OBSERVE the HOIST LOADED light off. [CD-736D]
D. OBSERVE no load indicated (< 60 lbs) on the load cell indicator.
E. OBSERVE Fuel Grapple downward motion automatically stops.
F. ENSURE Fuel Grapple is at required depth by observing HOIST GRAPPLE ELEVATION Digital Readout.
5.3.22 PLACE the GRAPPLE ENGAGE/RELEASE Switch to the RELEASE position AND OBSERVE the grapple ENGAGE light off. [CD-736D]
Hope Creek Page 44 of 94 Rev.30
PSEG Internal Use Opnlly HC.OP-SO.KE-0001(Q) 5.3.23 Slowly RAISE the Fuel Grapple by using the Hoist Position Control in the RAISE position AND:
A. OBSERVE the SLACK CABLE light off. [CD-736D]
B. OBSERVE the HOIST LOADED light remains off. [CD-736D]
C. OBSERVE the Load Cell Indicator to ensure that no load has inadvertently been grappled. [CD442A]
5.3.24 ENSURE that hose and cable reels are taking up slack by observing air hoses remain taught within the Grapple.
5.3.25 RAISE the Fuel Grapple fully to avoid collision with any underwater obstructions. [CD-396Y]
5.3.26 INITIAL the appropriate box on the Fuel Movement Sheet(s) indicating the fuel transfer has been completed.
5.3.27 NOTIFY the Control Room personnel that the fuel move has been completed.
5.3.28 Control Room personnel should UPDATE the fuel location tracking tool in use.
Hope Creek Page 45 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 5.4 Blade Guide Transfer - Spent Fuel Storage Pool to Reactor Core 5.4.1 ENSURE that all prerequisites have been satisfied IAW Section 2.4 of this procedure.
5.4.2 USE the Refuel Platform and Trolley position controls to maneuver the unloaded Fuel Grapple to the blade guide location in the Spent Fuel Pool.
5.4.3 ENSURE the Fuel Grapple is at the correct Core OR Fuel Pool Coordinates.
SRO 5.4.4 LOWER the Fuel Grapple to approximately one foot above the blade guide to be grappled by using the Fuel Grapple Hoist Control in the LOWER position.
5.4.5 ROTATE the Fuel Grapple so that the grapple hooks are in line with the blade guide handle.
5.4.6 PLACE the GRAPPLE ENGAGE/RELEASE Switch to the RELEASE position to ensure the Fuel Grapple hooks are open, OBSERVE the grapple ENGAGE light off.
5.4.7 Slowly LOWER the Fuel Grapple UNTIL the Fuel Grapple is resting on the blade guide handle. Grapple may be gently twisted to seat on handle.
A. OBSERVE Fuel Grapple Hoist downward motion automatically stops.
B. OBSERVE the SLACK CABLE light on. [CD-736D]
C. ENSURE Fuel Grapple is at required depth by observing HOIST GRAPPLE ELEVATION Digital Readout.
5.4.8 PLACE the GRAPPLE ENGAGE/RELEASE Switch in the ENGAGE position to grapple the blade guide AND OBSERVE the GRAPPLE ENGAGE light on. [CD-736D]
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PSEG Internal Use Onlv HC.OP`-S0.KE-0001(Q) 5.4.9 Slowly RAISE the grappled blade guide using the Fuel Grapple hoist control in the RAISE position AND:
A. OBSERVE the SLACK CABLE light off. [CD-736D]
B. OBSERVE the Load Cell Indicator to ensure that blade guide has been grappled.
C. Visually VERIFY blade guide is being lifted.
5.4.10 RAISE AND CONTINUOUSLY OBSERVE the blade guide during its upward travel.
5.4.11 ENSURE hose and cable reels are taking up slack by observing cables and air hoses remain taught within the grapple.
NOTE 5.4.12 HOIST LOADED light may come on when hoist is almost full up.
5.4.12 WHEN the blade guide has reached its upper limit AND OBSERVE: _
A. GRAPPLE NORMAL UP light on. [CD-736D]
B. Fuel Grapple upward motion automatically stops.
5.4.13 USE the Trolley Position Control to position the Fuel Grapple in direct alignment with the center of the fuel transfer path to the Reactor Well. [CD-396Y]
5.4.14 USE the Refuel Platform Control in the Reverse position to maneuver the Refuel Platform to the Reactor Cavity area.
5.4.15 USE the Refuel Platform and Trolley Position Controls to maneuver the Fuel Grapple to the Reactor Core location listed on the Fuel Movement Sheet(s). Position Indication System should be used for single blade guides.
5.4.16 NOTIFY Control Room that platform is moving over the core.
Hope Creek Page 47 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 5.4.17 ENSURE the Fuel Grapple is at the correct Core OR Fuel Pool Coordinates.
SRO 5.4.18 ROTATE the Fuel Grapple AND attached blade guide in direct alignment with the Reactor Core location AND orientation listed on the Fuel Movement Sheet(s).
CAUTION 5.4.19 A. DO NOT attempt to release the blade guide unless it is fully seated in the Reactor Core location. [CD-123E]
B. DO NOT reposition the Refuel Platform or Trolley while the blade guide is grappled and not fully withdrawn from the Reactor Core location.
C. DO NOT twist a grappled blade guide while it is held fast in a Reactor Core location.
5.4.19 Slowly LOWER the blade guide into the Reactor Core location(s) using the Fuel Grapple hoist in the LOWER position.
5.4.20 WHEN the blade guide is fully seated in the Reactor Core location(s):
A. OBSERVE the SLACK CABLE light on.
B. OBSERVE the HOIST LOADED light off.
C. OBSERVE no load indicated (< 60 lbs) on the load cell indicator.
D. OBSERVE Fuel Grapple downward motion automatically stops E. ENSURE Fuel Grapple is at required depth by observing HOIST GRAPPLE ELEVATION Digital Readout.
5.4.21 NOTIFY the Control Room that the blade guides are in the Core location(s).
5.4.22 PLACE the GRAPPLE ENGAGE/RELEASE Switch to the RELEASE position AND OBSERVE the grapple ENGAGE light off.
Hope Creek Page 48 of 94 Rev. 30
PSEG Internal Use Ony-! HC.OP-SO.KE-0001(Q) 5.4.23 Slowly RAISE the Fuel Grapple by using the Hoist Position Control in the RAISE position.
A. OBSERVE the SLACK CABLE light off.
B. OBSERVE the HOIST LOADED light remains off.
C. OBSERVE the Load Cell Indicator to ensure that no load has been inadvertently been grappled. [CD-442A]
5.4.24 ENSURE that hose and cable reels are taking up slack by observing cables and air hoses remain taught within the grapple.
5.4.25 RAISE the Fuel Grapple fully to avoid collision with any underwater obstructions. ICD-396y]
5.4.26 INITIAL the appropriate box on the Fuel Movement Sheet(s) indicating the completion of the blade guide transfer step.
5.4.27 Control Room personnel should UPDATE the location tracking tool in use.
5.5 Blade Guide Transfer - Reactor Core to Spent Fuel Storage Pool 5.5.1 ENSURE that all prerequisites have been satisfied IAW Section 2.5 of this procedure.
5.5.2 USE the Refuel Platform and Trolley Position Controls to maneuver the Fuel Grapple to the coordinates listed on the Fuel Movement Sheet(s).
Digital Position Indication System should be used for single blade guides._
5.5.3 ENSURE the Fuel Grapple is at the correct Core OR Fuel Pool Coordinates.
SRO 5.5.4 LOWER the Fuel Grapple to approximately one foot above the blade guide to be removed by using the Fuel Grapple Hoist control in the LOWER position.
5.5.5 ROTATE the Fuel Grapple so that the grapple hooks are in line with the blade guide handle.
Hope Creek Page 49 of 94 Rev. 30
PSEG Internal Use OxH SK HC.0P-S0.KE-0001(Q) 5.5.6 PLACE the GRAPPLE ENGAGE/RELEASE Switch to the RELEASE to ensure the Fuel Grapple hooks are open, OBSERVE the grapple ENGAGE light off.
5.5.7 Slowly LOWER the Fuel Grapple UNTIL the Fuel Grapple is resting on the blade guide handle. Grapple may be gently twisted to seat on handle.
A. OBSERVE Fuel Grapple Hoist downward motion automatically stops.
B. OBSERVE the SLACK CABLE light on.
C. ENSURE Fuel Grapple is at required depth by observing HOIST GRAPPLE ELEVATION Digital Readout.
5.5.8 PLACE the GRAPPLE ENGAGE/RELEASE Switch in the ENGAGE position to grapple the blade guide AND OBSERVE the GRAPPLE ENGAGE light on.
CAUTION 5.5.9 DO NOT remove a blade guide from its Reactor Core location if the respective control rod will be left unsupported.
5.5.9 Slowly RAISE the grapple blade guide using the Fuel Grapple Hoist Control in the RAISE position.
A. OBSERVE the SLACK CABLE light off.
B. OBSERVE the load cell indicator to ensure the blade guide has been grappled.
C. Visually VERIFY blade guide is being lifted.
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PSEG Internal Use Only HC.0P-S0.KE-OO0l(Q)
CAUTION 5.5.10 A. DO NOT attempt to release the blade guide unless it is fully seated in the Reactor Core location. [CD-123E]
B. DO NOT reposition the Refuel Platform or Trolley while the blade guide is grappled and not fully withdrawn from the Reactor Core location.
C. DO NOT twist a grappled blade guide while it is held fast in a Reactor Core location.
5.5.10 RAISE AND CONTINUOUSLY OBSERVE the blade guide during its upward travel.
5.5.11 ENSURE that hose and cable reels are taking up slack by observing cables and air hoses remain taught within the grapple.
NOTE 5.5.12 HOIST LOADED light may come on when hoist is almost full up.
5.5.12 WHEN the blade guide has reached its upper limit THEN OBSERVE:
A. GRAPPLE NORMAL UP light on.
B. Fuel Grapple upward motion automatically stops.
5.5.13 NOTIFY the Control Room that blade guide is out of the core.
5.5.14 USE the Trolley position control to position the Fuel Grapple in direct alignment with the center of the fuel transfer path to the Fuel Pool. [CD-396Y]
5.5.15 USE the Refuel Platform position control in the FORWARD position to maneuver the Refuel Platform to the Spent Fuel Pool.
5.5.16 NOTIFY the Control Room that the platform is over the Fuel Pool.
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PSEG Internal Use Only HC-OP-SOXE-0001(Q) 5.5.17 USE the Refuel Platform AND Trolley Position Controls to maneuver the Fuel Grapple to an available blade guide storage location.
5.5.18 ENSURE the Fuel Grapple is at the correct Core OR Fuel Pool Coordinates.
SRO 5.5.19 ROTATE the Fuel Grapple AND attached blade guide so the blade guide cross beam is directly over the storage location support listed on the Fuel Movement Sheet(s).
5.5.20 Slowly LOWER the blade guide UNTIL it is fully seated on the support.
5.5.21 WHEN the blade guide is fully seated on the support THEN:
A. OBSERVE the SLACK CABLE light on.
B. OBSERVE the HOIST LOADED light off.
C. OBSERVE no load indicated (< 60 lbs) on the load cell indicator.
D. ENSURE Fuel Grapple is at required depth by observing HOIST GRAPPLE ELEVATION Digital Readout.
5.5.22 PLACE the GRAPPLE ENGAGE/RELEASE Switch to the RELEASE position AND OBSERVE the grapple ENGAGE light off.
5.5.23 Slowly RAISE the Fuel Grapple using the Hoist Control in the RAISE position.
A. OBSERVE the SLACK CABLE light off.
B. OBSERVE the HOIST LOADED light remains off.
C. OBSERVE the load cell indicator to verify that a load was not inadvertently grappled. [CD-442A1 D. ENSURE that hose and cable reels are taking up slack by observing air hoses remain taught within the Grapple.
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PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 5.5.24 RAISE the Fuel Grapple fully to avoid collision with any underwater obstructions. [CD-396Y1 5.5.25 INITIAL the appropriate block on the Fuel Movement Sheet(s) indicating that the blade guide transfer has been completed.
5.5.26 NOTIFY Control Room personnel that the blade guide transfer has been completed.
5.6 Fuel Movement - Within Reactor Vessel 5.6.1 ENSURE that all prerequisites have been satisfied IAW Section 2.6 of this procedure.
5.6.2 USE the Trolley Position Control to position the Fuel Grapple to attain direct alignment with the center of the fuel transfer path. [CD-396Y]
5.6.3 USE the Refuel Platform Position Control in the REVERSE position to maneuver the Refuel Platform over the Reactor Core.
5.6.4 Using the Refuel Platform and Trolley Position Controls AND Position Indication System, MANEUVER the Fuel Grapple to the coordinates listed on the Fuel Movement Sheet(s).
5.6.5 LOWER the Fuel Grapple to approximately one foot above the Fuel Assembly to be transferred by using the Fuel Grapple Hoist control in the LOWER position.
5.6.6 ENSURE the Fuel Grapple is at the correct Core Coordinates.
SRO 5.6.7 ROTATE the Fuel Grapple so that the grapple hooks are in line with the fuel assembly handle.
5.6.8 PLACE the GRAPPLE ENGAGE/RELEASE Switch to the RELEASE position to ensure the Fuel Grapple hooks are open, OBSERVE the grapple ENGAGE light off.
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PSEG Internal Use Oniy HC.OP-SO.KE-0001(Q) 5.6.9 Slowly LOWER the Fuel Grapple UNTIL the Fuel Grapple resting on the Fuel Assembly handle. Grapple may be gently twisted to seat on handle.
A. OBSERVE Fuel Grapple Hoist downward motion automatically stops.
B. OBSERVE the SLACK CABLE light on. [CD-736D]
C. ENSURE Fuel Grapple is at required depth by observing HOIST GRAPPLE ELEVATION Digital Readout.
D. ROTATE grapple in both directions. [CD-739F]
5.6.10 PLACE the GRAPPLE ENGAGE/RELEASE Switch in the ENGAGE position to grapple the fuel assembly AND:
A. OBSERVE the grapple ENGAGE light is on.
B. ROTATE grapple in both directions to ensure proper engagement. [CD-739F1 5.6.11 NOTIFY Control Room the assembly is being removed from Core AND that the SRM's should be observed until assembly is out of the Core.
5.6.12 Slowly RAISE the grappled Fuel Assembly using the Fuel Grapple Hoist Control in the RAISE position.
A. OBSERVE the SLACK CABLE light off.
B. OBSERVE the HOIST LOADED light on. [CD-736D]
C. OBSERVE the Load Cell Indicator to ensure the assembly has been grappled.
D. Visually VERIFY assembly is being lifted.
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PSEG Internal Use Only HC.OP-SO.KE-0001(Q)
CAUTION 5.6.13 A. DO NOT attempt to release the Fuel Assembly unless it is fully seated in a storage or Reactor Core location. [CD-123E, CD-736D, CD-182C]
B. DO NOT reposition the Refuel Platform or Trolley while the Fuel Assembly is grappled and not fully withdrawn from the storage or Reactor Core location.
C. DO NOT twist a grappled fuel assembly while it is held fast in a storage or Reactor Core location.
D. While positioning irradiated fuel in the Reactor Vessel or Spent Fuel Pool maximize the amount of water shielding between the Fuel Assembly and Reactor Vessel or Fuel Pool wall. [CD-612X, CD-069A]
5.6.13 RAISE AND CONTINUOUSLY OBSERVE the Fuel Assembly during its upward travel.
NOTIFY Control Room when assembly is out of the core.
5.6.14 ENSURE that hose and cable reels are taking up slack by observing cables and air hoses remain taught within the grapple.
NOTE 5.6.15 Safe working height is the height of the Fuel Assembly so that the top guide is cleared by approximately 5 feet.
5.6.15 WHEN the Fuel Assembly has reached its safe working height as indicated with a hoist grapple elevation digital readout (< 300 inches)
THEN NOTIFY Control Room that Fuel Assembly is out of its old core location.
5.6.16 USE the Refuel Platform AND Trolley Position Controls AND Digital Position Indication System to maneuver the Fuel Grapple to the Reactor Core location listed on the Fuel Movement Sheet(s).
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PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 5.6.17 NOTIFY Control Room that Fuel Assembly is over its new core location.
5.6.18 ENSURE the Fuel Grapple is at the correct Core OR Fuel Pool Coordinates.
SRO 5.6.19 ROTATE the Fuel Grapple AND attached Fuel Assembly in direct alignment with the Reactor Core location and corresponding channel fastener orientation listed on the Fuel Movement Sheet(s).
5.6.20 NOTIFY the Control Room that the assembly is about to enter the Core AND that SRM's must be observed until assembly is seated.
5.6.21 Slowly LOWER the Fuel Assembly into the Reactor Core location using the Fuel Grapple Hoist Position Control in the LOWER position.
5.6.22 WHEN the SRO has ensured that the Fuel Assembly is fully seated in the correct Reactor Core location:
A. NOTIFY Control Room that assembly is seated in its proper Core location.
B. OBSERVE the SLACK CABLE light on. [CD-736D]
C. OBSERVE the HOIST LOADED light off. [CD-736D]
D. OBSERVE no load (< 60 lbs) indicated on the load cell indicator.
E. OBSERVE Fuel Grapple downward motion automatically stops.
F. ENSURE Fuel Grapple is at required depth by observing HOIST GRAPPLE ELEVATION Digital Readout.
5.6.23 PLACE the GRAPPLE ENGAGE/RELEASE Switch to the RELEASE position AND OBSERVE the grapple ENGAGE light off. [CD-736D]
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PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 5.6.24 Slowly RAISE the Fuel Grapple by using the Hoist Position Control in the RAISE position.
A. OBSERVE the SLACK CABLE light off. ICD-736D_
B. OBSERVE the HOIST LOADED light remains off. [CD-736D1 C. OBSERVE the load cell indicator to ensure that no load has been inadvertently grappled. [CD-442A]
5.6.25 ENSURE that hose and cable reels are taking up slack by observing cables and air hoses remain taught within the grapple.
5.6.26 RAISE the Fuel Grapple fully to avoid collision with any underwater obstructions.
IF next Fuel Assembly to be handled is nearby, RAISE the Fuel Grapple at least one foot. [CD-396Y]
5.6.27 INITIAL the appropriate box on the Fuel Movement Sheet(s) indicating the fuel transfer has been completed.
5.6.28 NOTIFY the Control Room personnel that the fuel move has been completed.
5.6.29 Control Room personnel should UPDATE the fuel location tracking tool in use.
5.7 Blade Guide Movement - Within Reactor Vessel 5.7.1 ENSURE that all prerequisites have been satisfied IAW Section 2.7 of this procedure.
5.7.2 USE the Refuel Platform and Trolley Position Controls to maneuver the Fuel Grapple to the coordinates listed on the Fuel Movement Sheet(s).
Digital Position Indication System should be used for single blade guides.
5.7.3 ENSURE the Fuel Grapple is at the correct Core OR Fuel Pool Coordinates.
SRO 5.7.4 LOWER the Fuel Grapple to approximately one foot above the blade guide to be transferred by using the Fuel Grapple hoist control in the LOWER position.
5.7.5 ROTATE the Fuel Grapple so that the grapple hooks are in line with the blade guide handle.
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PSEG Internal Use Only HC.OP`-S0.KE-0001(Q) 5.7.6 PLACE the GRAPPLE ENGAGE/RELEASE Switch to the RELEASE position to ensure the Fuel Grapple hooks are open, OBSERVE the ENGAGE light off.
5.7.7 Slowly LOWER the Fuel Grapple UNTIL the Fuel Grapple is resting on the blade guide handle. Grapple may be gently twisted to seat on handle.
A. OBSERVE Fuel Grapple hoist downward motion automatically stops.
B. OBSERVE the SLACK CABLE light on.
C. ENSURE Fuel Grapple is at required depth by observing HOIST GRAPPLE ELEVATION Digital Readout.
5.7.8 PLACE the GRAPPLE ENGAGE/RELEASE Switch in the ENGAGE position to grapple the blade guide AND OBSERVE the GRAPPLE ENGAGE light on.
CAUTION 5.7.9 DO NOT remove a blade guide from its Reactor Core location if the respective control rod will be left unsupported.
5.7.9 Slowly RAISE the grapple blade guide using the Fuel Grapple Hoist Control in the RAISE position.
A. OBSERVE the SLACK CABLE light off.
B. OBSERVE the Load Cell Indicator to ensure that blade guide has been grappled.
C. Visually VERIFY blade guide is being lifted.
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PSEG internal Use Only-S HC.OP-SO.KE-0001(Q)
E CAUTION 5.7.10 A. DO NOT attempt to release the blade guide unless it is fully seated in the Reactor Core location. [CD-123E]
B. DO NOT reposition the Refuel Platform or Trolley while the blade guide is grappled and not fully withdrawn from the Reactor Core location.
C. DO NOT twist a grappled blade guide while it is held fast in a Reactor Core location.
5.7.10 RAISE AND CONTINUOUSLY OBSERVE the blade guide during its upward travel.
5.7.11 ENSURE hose and cable reels are taking up slack by observing cables and air hoses remain taught within the grapple.
NOTE 5.7.12 Safe working height is the height of the Fuel Assembly so that the top guide is cleared by approximately 5 feet.
5.7.12 WHEN the blade guide has reached its safe working height as indicated with a hoist grapple elevation digital readout (< 300 inches)
THEN NOTIFY Control Room that blade guide is out of the core.
5.7.13 USE the Refuel Platform AND Trolley position controls to maneuver the Fuel Grapple to the Reactor Core location listed on the Fuel Movement Sheet(s). Digital Position Indication System should be used for single blade guides.
5.7.14 NOTIFY Control Room that platform is moving to new location over the core.
5.7.15 ENSURE the Fuel Grapple is at the correct Core OR Fuel Pool Coordinates.
SRO Hope Creek Page 59 of 94 Rev. 30
PSEG Internal Use Onlx- HC.OP-SO.KE-0001(Q) 5.7.16 ROTATE the Fuel Grapple AND attached blade guide in direct alignment with the Reactor Core location AND orientation listed on the Fuel Movement Sheet(s).
CAUTION 6.7.17 A. DO NOT attempt to release the blade guide unless it is fully seated in the Reactor Core location. [CD-123EJ B. DO NOT reposition the Refuel Platform or Trolley while the blade guide is grappled and not fully withdrawn from the Reactor Core location.
C. DO NOT twist a grappled blade guide while it is held fast in a Reactor Core location.
5.7.17 Slowly LOWER the blade guide into the Reactor Core location(s) using the Fuel Grapple hoist in the LOWER position.
5.7.18 WHEN the blade guide is fully seated on the support THEN:
A. OBSERVE the SLACK CABLE light on.
B. OBSERVE the HOIST LOADED light off.
C. OBSERVE no load indicated (< 60 lbs) on the load cell indicator.
D. OBSERVE Fuel Grapple downward motion automatically stops.
E. ENSURE Fuel Grapple is at required depth by observing HOIST GRAPPLE ELEVATION Digital Readout.
5.7.19 NOTIFY the Control Room that the blade guides are in the core location(s).
5.7.20 PLACE the GRAPPLE ENGAGE/RELEASE Switch to the RELEASE position AND OBSERVE the grapple ENGAGE light off.
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PSEG Internal Use Only HC.OP-SO.K1 E-ooo1(Q) 5.7.21 Slowly RAISE the Fuel Grapple using the Hoist Position Control in the RAISE position AND:
A. OBSERVE the SLACK CABLE light off.
B. OBSERVE the HOIST LOADED light remains off.
C. OBSERVE the Load Cell Indicator to ensure that no load has been inadvertently been grappled. [CD-442A]
5.7.22 ENSURE that hose and cable reels are taking up slack by observing cables and air hoses remain taught within the grapple.
5.7.23 RAISE the Fuel Grapple fully to avoid collision with any underwater obstructions.
IF next blade guide to be handled is nearby RAISE the Fuel Grapple at least one foot. [CD-396Y]
5.7.24 INITIAL the appropriate box on the Fuel Movement Sheet(s) indicating the completion of the blade guide transfer step.
NOTE 5.7.25 Control Room personnel should update the location tracking tool in use 5.7.25 NOTIFY Control Room personnel that the blade guide transfer has been completed.
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PSEG Internal Use Only H(:.OP-SO.KE-0001(Q) 5.8 Fuel/Blade Guide Movement - Within Spent Fuel Storage Pool (other than Refuel Mode) in Manual NOTE 5.8 All irradiated fuel moves or core alterations must be directly supervised by a licensed SRO or SRO limited to fuel-handling. Non-irradiated fuel handling not involving core alterations and blade guide movement do not require direct supervision by an SRO and can be annotated by the spotter directly involved with the evolution. [CD-168A]
This procedure Section describes any combination of fuel/blade guide in Spent Fuel Storage Pool movements between any of the following fuel storage locations:
- Fuel storage racks
- Fuel preparation machines
- Fuel sipping canisters
- Special test and measurement devices This Section uses the term "source" location (from location) as the location where a fuel/blade guide assembly is initially grappled and "target" location (to location) as the I destination of the fuel/blade guide assembly.
Fuel Assembly channel fastener orientation and location must be accomplished and documented in accordance with the Fuel Movement Sheets.
5.8.1 ENSURE that all prerequisites have been satisfied IAW Section 2.8 of this procedure.
5.8.2 TOUCH the SELECT MANUAL on the Touch Screen.
5.8.3 ENSURE the MANUAL OPERATION ACTIVE button is being displayed.
5.8.4 Using the Refuel Platform AND Trolley Position Controls AND Position Indication System MANEUVER the Fuel Grapple to the coordinates listed for the source location on the Fuel Movement Sheet(s).
5.8.5 ENSURE the Fuel Grapple is at the correct Fuel Pool Coordinates.
(REFER TO Note 5.8)
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PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 5.8.6 LOWER the Fuel Grapple to approximately one foot above the fuel assembly/blade guide to be removed by using the Fuel Grapple Hoist control in the LOWER position AND OBSERVE the GRAPPLE NORMAL UP light off.
5.8.7 IF possible WHEN fuel is being moved, SRO should visually ENSURE correct serial number of Fuel Assembly.
(REFER TO Note 5.8) 5.8.8 ROTATE the Fuel Grapple so that the grapple hooks are in line with the fuel assembly/blade guide handle.
5.8.9 PLACE the GRAPPLE ENGAGE/RELEASE Switch to the RELEASE position to ensure the Fuel Grapple hooks are open, OBSERVE the ENGAGE light off.
5.8.10 Slowly LOWER the Fuel Grapple UNTIL the Fuel Grapple is resting on the fuel assembly/blade guide handle. Grapple may be gently twisted to seat on handle.
A. OBSERVE Fuel Grapple downward motion automatically stops.
B. OBSERVE the SLACK CABLE light on.
C. ENSURE Fuel Grapple is at required depth by observing HOIST GRAPPLE ELEVATION Digital Readout.
D. ROTATE grapple in both directions. [CD-739F]
5.8.10 PLACE the GRAPPLE ENGAGE/RELEASE Switch in the ENGAGE position to grapple the fuel assembly/blade guide.
A. OBSERVE the grapple ENGAGE light on.
B. ROTATE grapple in both directions to ensure proper engagement. [CD-739F]
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PSEG Internai Use On y HC.OP-SO.KE-0001(Q) 5.8.11 Slowly RAISE the grappled fuel assembly/blade guide using the Fuel Grapple hoist control in the RAISE position.
A. OBSERVE the SLACK CABLE light off B. OBSERVE the HOIST LOADED light:
- Light ON for Fuel Assembly
- Light OFF for Blade Guide C. OBSERVE the Load Cell Indicator to ensure the assembly has been grappled.
D. Visually VERIFY assembly/blade guide is being lifted.
CAUTION 5.8.12 A. DO NOT attempt to release the fuel assemblylblade guide unless it is fully seated in storage location. [CD-182C, CD-123E]
B. DO NOT reposition the Refuel Platform or Trolley while the fuel assembly/blade guide is grappled and not fully withdrawn from the storage location.
C. DO NOT twist a grappled fuel assembly/blade guide while it is held fast in a storage location. [CD-069A CD-612X]
D. While positioning irradiated fuel in the Spent Fuel Pool maximize the amount of water shielding between the Fuel Assembly and Fuel Pool wall.
5.8.13 RAISE AND CONTINUOUSLY OBSERVE the fuel assembly/blade guide during its upward travel.
5.8.14 ENSURE hose and cable reels are taking up slack by observing cables and air hoses remain taught within the grapple.
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PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 5.8.20 WHEN the fuel assembly/blade guide is fully seated in the target location AND:
A. OBSERVE the SLACK CABLE light on.
B. OBSERVE the HOIST LOADED light off.
C. OBSERVE no load indicated (< 60 lbs) on the load cell indicator.
D. OBSERVE Fuel Grapple downward motion automatically stops.
E. ENSURE Fuel Grapple is at required depth by observing HOIST GRAPPLE ELEVATION Digital Readout.
5.8.21 PLACE the GRAPPLE ENGAGE/RELEASE Switch to the RELEASE position AND OBSERVE the grapple ENGAGE light off.
5.8.22 Slowly RAISE the Fuel Grapple by using the hoist position control in the RAISE position.
A. OBSERVE the SLACK CABLE light off.
B. OBSERVE the HOIST LOADED light remains off.
C. OBSERVE the Load Cell Indicator to ensure that no load has been inadvertently grappled. [CD-442A]
5.8.23 RAISE the Fuel Grapple fully to avoid collision with any underwater obstructions.
IF next Fuel Assembly OR blade guide to be moved is nearby, RAISE the Fuel Grapple at least one foot.
5.8.24 ENSURE hose and cable reels are taking up slack by observing cables and air hoses remain taught within the grapple.
5.8.25 IF Fuel Assemblies were moved, INITIAL the appropriate box on the Fuel Movement Sheet(s) indicating the fuel transfer has been completed.
5.8.26 NOTIFY the Control Room that the fuel transfer has been completed.
5.8.27 Control Room personnel should UPDATE the fuel location tracking tool in use.
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PSEG Internal Use Only HC.OP-S0.KE-0001(Q) 5.9 Auxiliary Hoist Tool Installation ICD-117G]
NOTE 5.9 A. The installation steps in this section will be performed by a qualified Maintenance Technician under the direction of the operations department.
B. The fitting on the end of the auxiliary and monorail hoist cable has 1/2" -13 UNC threads. The Control Rod Grapple, Jet pump Grapple, Fuel Support Piece Grapple, Combined CRB/FSP Grapple and the General Purpose Grapple have 7/16" -14 UNC threads in the mounting stud (threaded hole on top of tool). Failure to use a cable terminal/adaptor, which threads between the hoists cable fitting and the tool mounting stud can cause failure due to thread mismatch. [CD-217E, CD-949A]
5.9.1 The following tools may be mounted to the Auxiliary Hoist's (Monorail OR Frame mounted) cable terminal, using the cable terminal/adaptor:
A. Jet Pump Grapple B. Control Rod Grapple C. Fuel Support Grapple D. Instrument Handling Tool E. General Purpose Grapple F. Combined CRB/FSP Grapple Hope Creek Page 67 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 5.9.2 CONNECT the Instrument Handling Tool to a Refueling Platform Auxiliary Hoist as follows:
NOTE 5.9.2.A To assure preload, thread sealant should NOT be used on the jam nuts at both ends of the cable terminal/adapter.
A. APPLY a thread sealant, either Loctite Thread Sealant 2432 or 5772, on both the male cable terminal threads and the female cable terminal/adaptor threads. [CD-949A]
B. THREAD the cable terminalladaptor onto the Auxiliary Hoist cable terminal. [CD-949A]
C. APPLY a thread sealant, either Loctite Thread Sealant 2432 or 5772, to the male cable terminal threads and the female mounting stud on top of the tool. [CD-949A]
D. SUPPORT the instrument handling tool in the vertical position AND THREAD the cable terminalladaptor into the top of the mounting stud.
E. VERIFY proper thread depth of insertion, both visually AND by point insertion at the sight hole in the square mounting stud. [CD-949A]
F. TIGHTEN the jam nuts, by torquing each jam nut to 25 - 30 ft-lbs
[CD-949A]. _
NOTE 5.9.2.G Radioactive water may be present in the air lines. Radiation Protection should monitor performance of Step 5.9.2.G.
G. Carefully BLEED Refuel Platform dual airlines into rag to remove any moisture, THEN ATTACH the air supply connections to the tool quick connect devices.
Continued next page Hope Creek Page 68 of 94 Rev. 30
-- - no-- nf aan tfla PSEG Internal Use Only HU.UVr-bU.h-L-U1 JUUlJ) 5.9.2 (continued)
H. IF the hoist must be removed from the water AND irradiated components are not being handled, LOOSEN the bolts on the mechanical jam AND SLIDE the jam toward the grapple to allow full withdrawal of the grapple.
TIGHTEN the bolts.
I. IF the hoist to be set is used for handling irradiated components, PERFORM the following: [CD451X]
NOTE 5.9.2.1.1 Performance of Step 5.9.2.1.1 will meet the requirements for the Instrument HandlirIg tool. [80033517]
- 1. VERIFY the electrical stops for the applicable Refueling Platform Auxiliary Hoist have been set 1AW HC.OP-ST.KE-000l(Q), Refuel Interlock Operability Functional Test - Section 5.4 for the Jet Pump Grapple.
- 2. LOWER the grapple to greater than 7 feet below the surface of the water to clear the hoist override.
- 3. RAISE the grapple to reach the electrical stops. (The mechanical jam may have to be lowered to allow this).
- 4. LOOSEN the bolts on the mechanical jam AND SLIDE the jam up UNTIL it just touches the limit switch LS4 (LS4 is a finger switch just below the mechanical jam entry point).
- 5. TIGHTEN the bolts.
Hope Creek Page 69 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 5.9.3 CONNECT a Control Rod Grapple to a Refueling Platform Auxiliary Hoist as follows:
NOTE 5.9.3.A To assure preload, thread sealant should NOT be used on the jam nuts at both ends of the cable terminal/adapter.
A. APPLY a thread sealant, either Loctite Thread Sealant 2432 or 5772, on both the male cable terminal threads and the female cable terminal/adaptor threads. [CD-949A]
B. THREAD the cable terminal/adaptor onto the Auxiliary Hoist cable terminal. [CD-949A]
C. APPLY a thread sealant, either Loctite Thread Sealant 2432 or 5772, to the male cable terminal threads and the female mounting stud on top of the tool. [CD-949A]
D. SUPPORT the Control Rod Grapple tool in the vertical position AND THREAD the cable terminal/adaptor into the top of the mounting stud.
E. VERIFY proper thread depth of insertion, both visually AND by point insertion at the sight hole in the square mounting stud. [CD-949A].
F. TIGHTEN the jam nuts, by torquing each jam nut to 25 -30 ft-lbs.
[CD-949A].
NOTE 5.9.3.G Radioactive water may be present in the air lines. Radiation Protection should monitor performance of Step 5.9.3.G.
G. Carefully BLEED Refuel Platform dual airlines into rag to remove any moisture, THEN ATTACH the air supply connections to the tool quick connect devices.
Continued next page Hope Creek Page 70 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 5.9.3 (continued)
H. IF the hoist must be removed from the water AND irradiated blades are not being handled, LOOSEN the bolts on the mechanical jam AND SLIDE the jam toward the grapple to allow full withdrawal of the grapple.
TIGHTEN the bolts.
I. IF the hoist is to be set to be used for handling irradiated blades, PERFORM the following: [CD-451X]
- 1. VERIFY the electrical stops for the applicable Refueling Platform Auxiliary Hoist have been set IAW HC.OP-ST.KE-000l(Q), Refuel Interlock Operability Functional Test - Section 5.4 for the Control Rod Grapple.
- 2. LOWER the grapple to greater than 7 feet below the surface of the water to clear the hoist override.
- 3. RAISE the grapple to reach the electrical stops. (The mechanical jam may have to be lowered to allow this).
- 4. LOOSEN the bolts on the mechanical jam AND SLIDE the jam up UNTIL it just touches the limit switch LS4 (LS4 is a finger switch just below the mechanical jam entry point).
- 5. TIGHTEN the bolts.
Hope Creek Page 71 of 94 Rev. 30
yyi', d-ir QC" XV1WInd11 £AM PSEG Internal Use Only r ,z -.- "=,c 5.9.4 CONNECT the Jet Pump Grapple to a Refueling Platform auxiliary hoist as follows:
NOTE 5.9.4.A at both ends To assure preload, thread sealant should NOT be used on the jam nuts of the cable terminal/adapter.
A. APPLY a thread sealant, either Loctite Thread Sealant 2432 or 5772, on both the male cable terminal threads and the female cable terminal/adaptor threads. [CD-949A]
B. THREAD the cable terminal/adaptor onto the Auxiliary Hoist cable terminal. [CD-949A].
C. APPLY a thread sealant, either Loctite Thread Sealant 2432 or 5772, to the male cable terminal threads and the female mounting stud on top of the tool. [CD-949A]
D. SUPPORT the Jet Pump Grapple in the vertical position AND THREAD the cable terminal/adaptor into the top of the mounting stud.
E. VERIFY proper thread depth of insertion, both visually AND by point insertion at the sight hole in the square mounting stud.
[CD-949A].
F. TIGHTEN the jam nuts, by torquing each jam nut to 25 - 30 ft-lbs.
[CD-949A].
NOTE 5.9.4.G monitor Radioactive water may be present in the air lines. Radiation Protection should performance of Step 5.9.4.G.
G. Carefully BLEED Refuel Platform dual airlines into rag to remove any moisture, THEN ATTACH the air supply connections to the tool quick connect devices.
Continued next page Page 72 of 94 Rev. 30 Hope Creek
PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 5.9.4 (continued)
H. PRESS the GRAPPLE RELEASE pushbutton AND VERIFY the keeper on the jet pump grapple hook is open.
I. PRESS the GRAPPLE ENGAGE pushbutton AND VERIFY the keeper closes over the grapple hook.
PRESS the GRAPPLE RELEASE pushbutton to open the keeper. _
J. IF the hoist must be removed from the water AND irradiated components are not being handled, LOOSEN the bolts on the mechanical jam AND SLIDE the jam toward the grapple to allow full withdrawal of the grapple.
TIGHTEN the bolts.
K. IF the hoist is to be set to be used for handling irradiated blades, PERFORM the following: [CD-451X]
- 1. VERIFY the electrical stops for the applicable Refueling Platform Auxiliary Hoist have been set IAW HC.OP-ST.KE-0001(Q), Refuel Interlock Operability Functional Test - Section 5.4
- 2. LOWER the grapple to greater than 7 feet below the surface of the water to clear the hoist override.
- 3. RAISE the grapple to reach the electrical stops. (The mechanical jam may have to be lowered to allow this).
- 4. LOOSEN the bolts on the mechanical jam AND SLIDE the jam up UNTIL it just touches the limit switch LS4 (LS4 is a finger switch just below the mechanical jam entry point).
- 5. TIGHTEN the bolts.
Hope Creek Page 73 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO.KE-0001(Q)
NOTE 5.9.5 IF the control rod is partially extended through the cruciform slot in the support, and the protrusion is observed to exceed the internal dimension of the slot in the grapple, the assembly is prepared using the two-legged top frame.
IF no obstructions are observed to exist, the grapple is assembled with the grid guide, a device provided to hold the grapple in proper orientation with respect to the top guide structure.
IF the location of the support is readily accessible, the hoist connection may be made directly to the stud and plate assembly.
5.9.5 CONNECT the Fuel Support Grapple to a Refueling Platform auxiliary hoist as follows:
A. IF necessary, INSTALL the top frame or the top guide.
B. REMOVE the lockwire from the 4 caps on the bolts AND SCREW out the bolts to take off the stud plate.
C. WITH the components supported to avoid torsional stress, BOLT the top assembly to the grapple top plate AND REWIRE the caps to specification.
NOTE 5.9.5.D To assure preload, thread sealant should NOT be used on the jam nuts at both ends of the cable terminal/adapter.
D. APPLY a thread sealant, either Loctite Thread Sealant 2432 or 5772, on both the male cable terminal threads and the female cable terminalladaptor threads. [CD-949A]
E. THREAD the cable terminal/adaptor onto the Auxiliary Hoist cable terminal. [CD-949A].
Continued next page Hope Creek Page 74 of 94 Rev. 30
TYJ'r £-%-n QI-% L'I 1AMIM(A PSEG Internal Use Oniy A1.111c 5.9.5 (continued)
F. APPLY a thread sealant, either Loctite Thread Sealant 2432 or 5772, to the male cable terminal threads and the female mounting stud on top of the tool. [CD-949A]
G. SUPPORT the Fuel Support Grapple in the vertical position AND THREAD the cable terminal/adaptor into the top of the mounting stud.
H. VERIFY proper thread depth of insertion, both visually AND by point insertion at the sight hole in the square mounting stud. [CD-949A].
I. TIGHTEN the jam nuts, by torquing each jam nut to 25 - 30 ft-lbs.
[CD-949A].
NOTE 5.9.5.J tor Radioactive water may be present in the air lines. Radiation Protection should moni performance of Step 5.9.5.J.
J. Carefully BLEED Refuel Platform dual airlines into rag to remove any moisture, THEN ATTACH the air supply connections to the tool quick connect devices.
K. IF the hoist must be removed from the water and fuel support pieces are NOT being handled, LOOSEN the bolts on the mechanical jam AND SLIDE the jam toward the grapple to allow full withdrawal of the grapple.
TIGHTEN the bolts.
Continued next page Page 75 of 94 Rev. 30 Hope Creek
PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 5.9.5 (continued)
L. IF the hoist is to be set to be used for handling fuel support pieces, PERFORM the following: [CD-451X]
NOTE 5.9.5.L.1 IF the electrical stops are set in accordance with Step 5.9.5.L.1, this will meet the requirement for the DEI or the GE Fuel Support Piece Grapple.
- 1. VERIFY the electrical stops for the applicable Refueling Platform Auxiliary Hoist have been set for either the Control Rod Grapple or the Jet Pump Grapple IAW HC.OP-ST.KE-000l(Q),
Refuel Interlock Operability Functional Test - Section 5.4
- 2. LOWER the grapple to greater than 7 feet below the surface of the water to clear the hoist override.
- 3. RAISE the grapple to reach the electrical stops. (The mechanical jam may have to be lowered to allow this).
- 4. LOOSEN the bolts on the mechanical jam AND SLIDE the jam up UNTIL it just touches the limit switch LS4 (LS4 is a finger switch just below the mechanical jam entry point).
- 5. TIGHTEN the bolts.
Hope Creek Page 76 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 5.9.6 CONNECT a Combined CRB/FSP Grapple to a Refueling Platform Auxiliary Hoist as follows:
NOTE 5.9.6.A To assure preload, thread sealant should NOT be used on the jam nuts at both ends of the cable terminal/adapter.
A. APPLY a thread sealant, either Loctite Thread Sealant 2432 or 5772, on both the male cable terminal threads and the female cable terminalladaptor threads. [CD-949A]
B. THREAD the cable terminal/adaptor onto the Auxiliary Hoist cable terminal. [CD-949A]
C. APPLY a thread sealant, either Loctite Thread Sealant 2432 or 5772, to the male cable terminal threads and the female mounting stud on top of the tool. [CD-949A]
D. SUPPORT the Combined CRB/FSP Grapple tool in the vertical position AND THREAD the cable terminalladaptor into the top of the mounting stud.
E. VERIFY proper thread depth of insertion, both visually AND by point insertion at the sight hole in the square mounting stud. [CD-949A].
F. TIGHTEN the jam nuts, by torquing each jam nut to 25 - 30 ft-lbs.
[CD-949A].
NOTE 5.9.6.G Radioactive water may be present in the air lines. Radiation Protection should monitor performance of Step 5.9.6.G.
G. Carefully BLEED Refuel Platform dual airlines into rag to remove any moisture, THEN ATTACH the air supply connections to the tool quick connect devices.
Continued next page Hope Creek Page 77 of 94 Rev. 30
PSEG Internal Use-Only HC.OP-SO.KE-00j01(Q) 5.9.6 (continued)
H. IF the hoist must be removed from the water AND irradiated blades are NOT being handled, LOOSEN the bolts on the mechanical jam AND SLIDE the jam toward the grapple to allow full withdrawal of the grapple.
TIGHTEN the bolts.
I. IF the hoist is to be set to be used for handling irradiated blades, PERFORM the following: [CD-451X]
- 1. VERIFY the electrical stops for the applicable Refueling Platform Auxiliary Hoist have been set IAW HC.OP-ST.KE-0001(Q), Refuel Interlock Operability Functional Test - Section 5.4 for the Combined CRB/FSP Grapple.
- 2. LOWER the grapple to greater than 7 feet below the surface of the water to clear the hoist override.
- 3. RAISE the grapple to reach the electrical stops. (The mechanical jam may have to be lowered to allow this).
- 4. LOOSEN the bolts on the mechanical jam AND SLIDE the jam up UNTIL it just touches the limit switch LS4 (LS4 is a finger switch just below the mechanical jam entry point).
- 5. TIGHTEN the bolts.
Continued next page Hope Creek Page 78 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SCIXKE-9OO1(Q) 5.9.6 (continued)
NOTE 5.9.6.J einstalled.
Overhead Crane should be used for lifting Combined Grapple with grid guide J. To install Combined Grapple Grid Guide PERFORM the following:
- 1. PLACE guide on mounts at top of grapple WITH the "L" latches pointing towards hoist cable.
- 2. SEAT guide on mounts AND while pushing down on T-handle, TURN each latch 900 (one turns clockwise and one turns counter clockwise).
- 3. LIFT-UP on guide to verify it is latched to grapple.
- 4. PLACE hoist cable within the rollers on the top of the guide THEN CLOSE AND PIN gate with ball lock pin.
Page 79 of 94 Rev. 30 Hope Creek
PSEG Internal Use onlyHE HC.OP-SO.KE-0001(Q) 5.10 Fuel/Blade Guide Movement - Within Spent Fuel Storage Pool (other than Refuel Mode) in Semi-Automatic Mode NOTE 5.10 All irradiated fuel moves or core alterations must be directly supervised by a licensed SRO or SRO limited to fuel-handling. Non-irradiated fuel handling not involving core alterations and blade guide movement do not require direct supervision by an SRO and can be annotated by the spotter directly involved with the evolution. [CD-1 68A]
This procedure Section describes any combination of fuel/blade guide in Spent Fuel Storage Pool movements between any of the following fuel storage locations:
- Fuel storage racks
- Fuel preparation machines
- Fuel sipping canisters
- Special test and measurement devices This Section uses the term "source" location (from location) as the location where a fuel/blade guide assembly is initially grappled and "target" location (to location) as the destination of the fuel/blade guide assembly.
Fuel Assembly channel fastener orientation and location must be accomplished and documented in accordance with the Fuel Movement Sheets.
5.10.1 ENSURE that all prerequisites have been satisfied IAW Section 2.10 of this procedure.
5.10.2 ENSURE the MONO/FRAME/CONSOLE Switch on the Start/Stop Station is set to CONSOLE.
5.10.3 TOUCH the Show Menu icon AND SELECT the XY MODE ACTIVE icon.
5.10.4 PRESS the PRESS FOR OPERATION button.
5.10.5 TOUCH the SELECT AUTO on the Touch Screen.
5.10.6 ENSURE the MANUAL OPERATION ACTIVE button is being displayed.
5.10.7 TOUCH REQUEST on the Auto screen AND VERIFY that the keypad is displayed.
Hope Creek Page 80 of 94 Rev. 30
PSEG Internal Use Only HC.OP-S0.KE-0001(Q) 5.10.8 In accordance with the Fuel Movement Sheet(s),
ENTER the source location via the alphanumeric keypad displayed on the Touch Screen.
5.10.9 After visually verifying the Bridge position, Trolley position AND the requested location, PRESS the VERIFY button.
5.10.10 PRESS AUTO RUN icon on the touch screen to initiate Refuel Platform movement.
5.10.11 VERIFY that the bridge and trolley have moved to the requested position AND the message AUTO SEQUENCE COMPLETE is displayed on the Touch Screen.
5.10.12 ENSURE the Fuel Grapple is at the correct Fuel Pool Coordinates.
(REFER TO NOTE 5.10) 5.10.13. LOWER the Fuel Grapple to approximately one foot above the fuel assembly/blade guide to be removed by using the Fuel Grapple Hoist control in the LOWER position AND OBSERVE the GRAPPLE NORMAL UP light off 5.10.14 ROTATE the Fuel Grapple so that the grapple hooks are in line with the fuel assembly/blade guide handle.
5.10.15 IF possible WHEN fuel is being moved, SRO should visually ENSURE correct serial number of Fuel Assembly.
(REFER TO NOTE 5.10) 5.10.16 PLACE the GRAPPLE ENGAGE/RELEASE Switch to the RELEASE position to ensure the Fuel Grapple hooks are open, OBSERVE the ENGAGE light off.
Hope Creek Page 81 of 94 Rev. 30
PSEG Internal Use OnHiy HC.OP-SO.KE-0001(Q) 5.10.17 Slowly LOWER the Fuel Grapple UNTIL the Fuel Grapple is resting on the fuel assembly/blade guide handle. Grapple may be gently twisted to seat on handle.
A. OBSERVE Fuel Grapple downward motion automatically stops.
B. OBSERVE the SLACK CABLE light on.
C. ENSURE Fuel Grapple is at required depth by observing HOIST GRAPPLE ELEVATION Digital Readout.
D. ROTATE grapple in both directions. [CD-739F]
5.10.18 PLACE the GRAPPLE ENGAGE/RELEASE Switch in the ENGAGE position to grapple the fuel assembly/blade guide.
A. OBSERVE the grapple ENGAGE light on.
B. ROTATE grapple in both directions to ensure proper engagement. [CD-739F]
5.10.19 Slowly RAISE the grappled fuel assembly/blade guide using the Fuel Grapple hoist control in the RAISE position.
A. OBSERVE the SLACK CABLE light off B. OBSERVE the HOIST LOADED light:
- Light ON for Fuel Assembly
- Light OFF for Blade Guide C. OBSERVE the Load Cell Indicator to ensure the assembly has been grappled.
D. Visually VERIFY assembly/blade guide is being lifted.
Hope Creek Page 82 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO.KE-0001(Q)
CAUTION 5.10.20 A. DO NOT attempt to release the fuel assemblylblade guide unless it is fully seated in storage location. [CD-182C, CD-123E]
B. DO NOT reposition the Refuel Platform or Trolley while the fuel assemblylblade guide is grappled and not fully withdrawn from the storage location.
C. DO NOT twist a grappled fuel assembly/blade guide while it is held fast in a storage location. [CD-069A CD-612X]
D. While positioning irradiated fuel in the Spent Fuel Pool maximize the amount of water shielding between the Fuel Assembly and Fuel Pool wall.
5.10.20 RAISE AND CONTINUOUSLY OBSERVE the fuel assembly/blade guide during its upward travel.
5.10.21 ENSURE hose and cable reels are taking up slack by observing cables and air hoses remain taught within the grapple.
CAUTION 5.10.22 DO NOT bypass the Main Hoist normal up stop when handling Fuel Assemblies or control rod blades.
5.10.22 WHEN the fuel assembly/blade guide has reached its upper limit:
A. OBSERVE the GRAPPLE NORMAL UP light on.
B. Fuel Grapple upward motion automatically stops.
5.10.23 TOUCH the SELECT AUTO on the Touch Screen.
5.10.24 ENSURE the MANUAL OPERATION ACTIVE button is being displayed.
Hope Creek Page 83 of 94 Rev. 30
PSEG Internai Use Only HC.OP-SO.Y.E-0001(Q) 5.10.25 TOUCH REQUEST on the Auto screen AND VERIFY that the keypad is displayed.
5.10.26 In accordance with the Fuel Movement Sheet(s),
ENTER the target location via the alphanumeric keypad displayed on the Touch Screen.
SRO 5.10.27 After visually verifying the Bridge position, Trolley position AND the requested location, PRESS the VERIFY button.
5.10.28 PRESS AUTO RUN icon on the touch screen to initiate Refuel Platform movement.
5.10.29 VERIFY that the bridge and trolley have moved to the requested position AND the display message AUTO SEQUENCE COMPLETE is displayed on the Touch Screen.
5.10.30 ENSURE the Fuel Grapple is at the correct Fuel Pool coordinates.
(REFER TO Note 5. 10) 5.10.31 ROTATE the Fuel Grapple AND attached fuel assembly/blade guide to attain direct alignment AND orientation with the target location. [CD-396Y_
CAUTION 5.10.32 A. DO NOT attempt to release the fuel assembly/blade guide unless it is fully seated in a storage location. [CD-182C, CD-123EJ B. DO NOT reposition the Refuel Platform or Trolley while the fuel assembly is grappled and not fully withdrawn from the storage or Reactor Core location.
C. DO NOT twist a grappled fuel assembly while it is held fast in a storage location. .. ,
Ii 5.10.32 Slowly LOWER the fuel assembly/blade guide into the target location using the Fuel Grapple hoist position control in the LOWER position.
Hope Creek Page 84 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 5.10.33 WHEN the fuel assembly/blade guide is fully seated in the target location AND:
A. OBSERVE the SLACK CABLE light on.
B. OBSERVE the HOIST LOADED light off.
C. OBSERVE no load indicated (< 60 lbs) on the load cell indicator.
D. OBSERVE Fuel Grapple downward motion automatically stops.
E. ENSURE Fuel Grapple is at required depth by observing HOIST GRAPPLE ELEVATION Digital Readout.
5.10.34 PLACE the GRAPPLE ENGAGE/RELEASE Switch to the RELEASE position AND OBSERVE the grapple ENGAGE light off.
5.10.35 Slowly RAISE the Fuel Grapple by using the hoist position control in the RAISE position.
A. OBSERVE the SLACK CABLE light off.
B. OBSERVE the HOIST LOADED light remains off.
C. OBSERVE the Load Cell Indicator to ensure that no load has been inadvertently grappled. [CD-442A]
5.10.36 RAISE the Fuel Grapple fully to avoid collision with any underwater obstructions.
IF next Fuel Assembly OR blade guide to be moved is nearby, RAISE the Fuel Grapple at least one foot.
5.10.37 ENSURE hose and cable reels are taking up slack by observing cables and air hoses remain taught within the grapple.
5.10.38 IF Fuel Assemblies were moved, INITIAL the appropriate box on the Fuel Movement Sheet(s) indicating the fuel transfer has been completed.
Hope Creek Page 85 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 5.10.39 NOTIFY the Control Room that the fuel transfer has been completed.
5.10.40 Control Room personnel should UPDATE the fuel location tracking tool in use.
5.10.41 IF additional fuel movement is required, GO TO Step 5.10.4.
Hope Creek Page 86 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO.KE-0001(Q)
6.0 REFERENCES
6.1 GE Documents:
GEK 75563, Refueling Platform Equipment Assembly GEK 33076A GEK 33147C GEK 33221A GEK 33143D GEK 33073B GEK 103853A 6.2 Commitment Documents CD-069A IE BULLETiN 78-08 CD-442A INPO SER 59.81 CD-719A GE SIL 152 CD-124B SER 31-83 CD-182C NRC C-77-12 CD-281C INPO SER 28-84 CD-365D GE SIL 409 CD-673D INPO OE 1239 CD-736D NRC IN 85-12 CD-789D GE AID 55 CD-123E INPO OE 1470 CD-71 IF H-1-KE-SEE-0332 CD-739F GE SIL 486 CD-443X F09-0025-00 CD-612X FO1-0091-01 CD-267Y FSAR Question 410.59 CD-396Y DSER 142 A&B CD-217E INPO OE 1556 CD-117G NHO INCI 354/91-166 CD-619G NHO INCI 354/94-049 CD-451X FSAR - Mechanical Jam, Stop Block - Backups to Normal Up Limit Section 9.1 CD-949A GE SIL 82 RI S1 CD-168A IE Cir 80-21 6.3 DCP No. 4-HM-0643 DCP 80016207 Continued next page Hope Creek Page 87 of 94 Rev. 30
PSEG internal Use Onlv HC.OP-SO.KE-0001(Q) 6.0 (continued) 6.4 Procedures HC.OP-ST.KE-0001(Q) - Refuel Interlock Operability Test HC.OP-FT.KE-0002(Q); Fuel Grapple Full Down Travel Functional Test - Refueling HC.OP-FT.KE-0001(Q) - Refuel Platform and Fuel Grapple Operability Test HC.RE-FR.ZZ-000I(Q) - Refuel Handling Controls HC.OP-AP.ZZ-0046(Q) - Radiological Access Control Program HC.OP-AB.CONT-0005(Q) - Irradiated Fuel Damage NC.NA-AP.ZZ-0049(Q) - Conduct of Fuel Handling 6.5 Letters HCGS-L-95-036 6.6 Other Documents PR 960821103 GE SIL 82 RI S1 PR 960128076 Order 70007921 Order 70006867 Hope Creek Page 88 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO-KE-0001(Q)
ATTACHMENT 1 Page 1 of 1 ANALYZED LOADS PERMITTED OVER IRRADIATED FUEL NOT REQUIRING SECONDARY CONTAINMENT INTEGRITY NOTE 70 feet relates to 17 feet above the surface of the water.
- 1. Fuels analysis is for an object < 117 lbs.
WITH a maximum distance of 70 ft from the load to the top of irradiated fuel in the Reactor Vessel.
REFERENCE:
NFS 2000-069 Calculation File T03.6-068, Light loads limits over irradiated fuel 14 Dec 1990 NFU-90-734 Hope Creek Page 89 of 94 Rev. 30
PSEG Internal Use Onlyv HC.OP-SO.KE-0001(Q)
CAUTION 5.8.15 DO NOT bypass the Main Hoist normal up stop when handling Fuel Assemblies or control rod blades in order to comply with UFSAR 9.1.4.2.12.3.
5.8.15 WHEN the fuel assembly/blade guide has reached its upper limit:
A. OBSERVE the GRAPPLE NORMAL UP light on.
B. Fuel Grapple upward motion automatically stops.
5.8.16 USE the Refuel Platform AND Trolley Position Controls AND Position Indicating System to maneuver the Fuel Grapple to the target location listed on the Fuel Movement Sheet(s).
5.8.17 ENSURE the Fuel Grapple is at the correct Core OR Fuel Pool Coordinates.
(REFER TO Note 5.8) 5.8.18 ROTATE the Fuel Grapple AND attached fuel assembly/blade guide to attain direct alignment AND orientation with the target location. [CD-396Y]
CAUTION 6.8.19 A. DO NOT attempt to release the fuel assembly/blade guide unless it is fully seated in a storage location. [CD-182C, CD-123E1 B. DO NOT reposition the Refuel Plafform or Trolley while the fuel assembly is grappled and not fully withdrawn from the storage or Reactor Core location.
C. DO NOT twist a grappled fuel assembly while it is held fast in a storage location.
5.8.19 Slowly LOWER the fuel assembly/blade guide into the target location using the Fuel Grapple hoist position control in the LOWER position.
Hope Creek Page 65 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO.KE-0001(Q)
ATTACHMENT 2 Page 1 of 4 INSTRUCTIONS FOR MANUALLY LOWERING A FUEL BUNDLE During fuel handling, various scenarios depict the need to lower a fuel bundle to a safe location in the Core or Fuel Pool. These scenarios may include the loss of power to the Bridge or malfunctions in other parts of the Bridge or the plant.
Except in emergency (evacuation, injury, etc.)
IF the Bridge malfunctions while fuel is grappled, NOTIFY the cognizant Refuel SRO OR OS/CRS before attempting any corrective action.
The purpose of this Attachment is to place the Fuel Assembly in the nearest appropriate storage location to allow the Bridge malfunction to be safely corrected. The cognizant SRO AND Reactor Engineer will determine the appropriate storage location.
1.0 In the event of a Loss of Power to the Bridge or Hoist Motor Malfunction (burnout, short) 1.1 IF the power is lost, the Hoist electric motor brake and emergency brake will engage.
NOTE 1.2 The Bridge/Trolley movement should be the minimum required to reach an appropriate location.
1.2 MOVE the Bridge/Trolley to an appropriate cell location using the handwheels provided for the Bridge Drive and Trolley Drive.
1.3 VERIFY the bundle is over an appropriate cell location.
NOTE 1.4 DO NOT drop the handwheel while installing it on the shaft.
1.4 ATTACH the handwheel on the West end of the Hoist Motor shaft AND SECURE it.
Hope Creek Page 90 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO.KE-0001(Q)
ATTACHMENT 2 Page 2 of 4 INSTRUCTIONS FOR MANUALLY LOWERING A FUEL BUNDLE 1.5 WITH one person holding the handwheel AND ready to lower the bundle, another person should release the emergency (safety) brake using the manual release on the brake 1.6 TAKE UP on the handwheel until the bundle starts to raise (approximately 3" bundle upward travel). This assures the handwheel has the load.
CAUTION 1.7 Step 1.7 will immediately transfer the bundle weight to the handwheel.
l-E 1.7 While holding the handwheel, release the motor brake by pushing the lever located inside the East end of the motor housing down and to the side. This permits lowering the bundle with the handwheel.
1.8 The cover is left off for the motor brake housing to preclude the need for tools in the case of an emergency.
Hope Creek Page 91 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO.KE-0001(Q)
ATTACHMENT 2 Page 3 of 4 INSTRUCTIONS FOR MANUALLY LOWERING A FUEL BUNDLE NOTE 2.0 DO NOT attempt to lower or release the bundle without SRO approval if a bent Mast is encountered.
2.0 Bent Mast IF the Mast is bent while it is loaded with a Fuel Bundle, its ability to extend and safely "put down" the Fuel Bundle may be impaired. Attempting to lower the load electrically may unspool the cable and allow an uncontrolled descent. A "slack cable" indication may also be received do to Mast Section(s) binding. Unless in the case of an emergency, SRO permission is required prior to attempting to move after binding the mast.
Any of the refueling bridge mast sections (10", 7", or 5"), can bind while being extended or retracted. The Encoder readout (distance traveled), used in conjunction with the Load Cell readout (weight on main mast cable), can be used to effectively verify whether binding is occurring. For example, IF you start from a full up position (10", 7", and 5" sections fully retracted), and start lowering the mast sections while observing the Encoder and Load Cell indications, the weight of the 1O" section should transfer from the main mast cable to the 12" section at approximately 180" on the Encoder reading (the Load Cell indication will decrease by approximately 105#). Continuing down, the weight of the 7" section should transfer from the main mast cable to the 10" section at approximately 380" on the Encoder reading (the Load Cell indication will decrease by approximately 88#). This methodology can also be applied for use in the opposite direction. IF while lowering the mast, an unexpected slack cable or pre-mature weight transfer occurs, stop lowering, raise the load to clear the slack cable (if one exists), and notify the cognizant Refuel SRO or OS/CRS before attempting any corrective action.
[CD-619G]
Hope Creek Page 92 of 94 Rev. 30
PSEG Internal Use Only HC.OP-SO.KE-0001(Q)
ATTACHMENT 2 Page 4 of 4 INSTRUCTIONS FOR MANUALLY LOWERING A FUEL BUNDLE NOTE 3.0 DO NOT attempt to lower or release the bundle without SRO approval if Platform failure is encountered.
3.0 Platform Failure A Platform failure includes Hoist Gear Train failure, Coupling failure or related structure failure.
As these components affect the ability to lower a Fuel Bundle (either electrically or manually),
unless in the case of an emergency, SRO approval is required prior to an attempt to move or lower the Fuel Bundle.
Hope Creek Page 93 of 94 Rev. 30
PSEG Internal Use Only HC.0P-S0.KE-OQO1(Q)
ATTACHMENT 3 Page 1 of 1 Refueling Platform Interlocks FUEL FUEL GRAPPLE GRAPPLE NOT LOADED FLLLYLOP NOTALL RODSIN K ELECTION REFUELING REFUELING FSECOND PLATFORM PLATFORM PLSTFORV ROD NEAROR NEAROR PLATFORM OVERCORE OVERCORE LOADED NOTALL NOTALL RODS IN ROOSIN OVERCORE STPSERVICE STOPFUELPLATFORM HOIST OPEATION OPERATION Hope Creek Page 94 of 94 Rev. 30