ML031130209

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Draft - Section B Operating
ML031130209
Person / Time
Site: Hope Creek PSEG icon.png
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
Download: ML031130209 (244)
v • d • e


Text

ES-301 Control Room Systems and Facility Walk-Through Test Outline Form-301-2 Facility: Hope Creek Date of Examination: 3/17/03 Exam Level: SRO(L) Operating Test No.: 1 B.1: Control Room Systems System JPM Description Code Safety S.1 215004 G2.1.23 (4.0) Ability to perform specific system and integrated D, L IC Source Range plant procedures during different modes of plant Monitor operation.

SRM/IRM Rod Block Bypassing during refueling operations IAW HC.OP-SO.SE-0001 Section 5.4.

Perform independent verification of installed jumpers. l S.2 204000 G2.1.20 (4.2) Ability to execute procedure steps. N, R, E, AUX/

RWCU L, A DHR Align RWCU for Alternate Heat Removal Alternate path for bypassing RHX for additional cooling.

S.3 234000 G2.2.28 (3.5) Knowledge of new and spent fuel movement N, R, A FHE Fuel Handling procedures.

Systems Manual transfer of dummy bundle within Spent Storage Pool. Unexpected Slack Cable / Bent Mast IAW HC.OP-SO.KE-0001 Attachment 2 (perform or simulate)

(JPM-KE-014 Modified for Alternate path due to unexpected Slack Cable.) l S.4 234000 A3.02 (3.7) Interlock operation N, R FHE Fuel Handling Systems Perform Monorail Aux Hoist Controls Functional Test HC.OP-FT.KE-0001 Section 5.4.1 through 5.4.15 (perform or simulate)

S.5 234000 A3.01 (3.6) Crane/refuel bridge movement. N, R FHE Fuel Handling Systems Automatic dummy bundle transfer in the Spent Fuel Pool (perform actual movement).

Draft based on Peach Bottom JPM.

B.2: Facility Walk-Through (Same as RO In-Plant Walkthrough) l NA NA NA NA NA Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol Room, (S)imulator, (L)ow-Power, (R)CA, (E)OP/AB G:/LSRO/03HCLSRONRCJPMOUTL 01106/03,11:47AM NUREG-1021, Revision 8

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 = SRO 3 LSRO W 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 rnin.

APPROVED:

N/A BARGAINING UNIT TRAINING SUPERVISOR OPERATIONS MANAGER RE:PRESENTATIVE 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: a SAT EJ 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.

a The CRS has directed l&C to bypass the SRM/IRM Rod Blocks lAW HC.OP-SO.SE-0001 Section 5.4.

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-S1

/ ( NC.Tt .ZZ-0310(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 r COMMENTS NO. (*Denotes a Critical Step) STANDARD EVAL (Required for I (#Denotes a Sequential Step) S/U UNSAT evaluation) 5.4.4 START TIME: Operator proceeds to panel 10C635, opens the Cabinet door and locates terminal strip PERFORM an independent verification of DD.

Operator locates terminals DD-19 and DD-the installed jumper from Step 5.4.3.

20.

INITIAL Attachment 1.

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.

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.

Nuclear Common Page 3 REV.: 0 I'll girls I crnyl- e.

( NC.TQ-.. .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 lAW 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)

  • 5.4.6 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: A jumper is installed on the terminals indicated.

Operator initials Attachment 1 as independent verifier.

Operator notifies Control Room that independent verification is complete.

STOP TIME: Terminating Cue: This JPM is complete.

Nuclear Common Page 4 REV.: 0

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.

  • The CRS has directed l&C to bypass the SRM/IRM Rod Blocks IAW HC.OP-SO.SE-0001 Section 5.4.

INITIATING CUE: Perform the Independent Verification requirements of steps 5.4.4 and 5.4.6 following l&C jumper installation IAW HC.OP-SO.SE-0001.

Nuclear Common Page 5 REV.: 0

CHANGES \A ST BE ATTACHED FOR FIELD USE D..-?-" -SPDT Page I of I PSEG Internal Use Only PSEG NUCLEAR L.L.C.

HOPE CREEK GENERATING STATION HC.OP-SO.SE-0001(Q) - Rev. 10 NUCLEAR INSTRUMENTATION SYSTEM OPERATION USE CATEGORY': I Yes No NoA /

Biennial Reviewv performed into this revision.

II. Chanige Package(s) and Affected Document Number(s) incorporated AD Rev. No. or Nione VI CP No. CP Rev. No. AD No.

C. OT SC(s) incorporated into this revision:

or None v/

OTSC No(s)

RFVISION

SUMMARY

80038788 the direction in steps 5.1.4 and Based on request made under Orders 70021956 and indication to the RBM or CMS is 5.3.5 was revised to include verification that proper bypass is cleared when the LPRM is returned observed when bypassing an l-PRM, and that this indication to service.

alphanumerical lists to bulleted lists

2. Based on writers review, several steps where changed from These changes are editorial in nature and since the steps did not require sequential performance.

5.1.2.B, 5.1.3.C. 5.1.5.B, and Note 5.3.

revision bars have been omitted. This affected steps 3.2.1, Document Management Program to Also, revised Step 6.1 by changing NC.NA-AP.ZZ-0003(Q),

This change is also editorial in nature as NC.NA-AP.ZZ-001 1(Q), Records Management Program.

5.3, which pointed out that described in NC.DM-AP.ZZ-0001(Q). Also, Notes 5.1 and The requirements stated in these compliance with a list of T/Ss was a requirement were removed.

information.

notes is currently stated as a limitation 3.2.1 making it redundant Effective date /)- 6 INIPLEINIFNTATION REQUIREMENTS None APP ROVED:

Manager - Hope Creek Operations Date

BE ATTACHED FOR HELD USE ALL ACTIVE ON-THE-SPOT CHANGES MUST 000 I (Q) 2C030 108HC.OP-SO.SE NUCLEAR INSTRUMENTATION SYSTEM OPERATION TABLE OF CONTENTS PAGE SECTION TITLE 2

1.0 PURPOSE.

2 2.0 PREREQUISITES.

3 3.0 PRECAUTIONS & LIMITATIONS 5

4.0 EQUIPMENT REQUIRED ...

6 5.0 PROCEDURE.

6 5.1 Placing the System in Service .

10 5.2 SRMIIRM Detector Drive Operation.....................................................

12 5.3 System Bypassing .

5.4 SRM/IRM Rod Block Bypassing during Refue'ng 17 operations (all Fuel Removed from Vessel)......................................

19 6.0 RECORDS.

19

7.0 REFERENCES

ATTACHMENTS 20 Attachment I Installation and Removal ofjumpers for SRM/IRM Rod Blocks............

Page 1 of 20 Rexv. 10 Hopse C reek

.f -3 7 CA\CLG-S S- B- A7TACHED FOR FIELD USE HC.OP-SO.SE-0()0 (Q)

NUCLEAR INSTRUMENTATION SYSTEM OPERATION 1.( PURPOSE This procedure outlines the steps necessary for the operation of the Nuclear Instrumentation Sy stem.

21) PREREQUISITES 2.1 Placing the System in Service 2.1.1 Reactor Protection System is in service to receive inputs from the Nuclear Instrumentation System.

2.1.2 Applicable Precautions and Limitations have been reviewed by each procedure user.

2.2 SRM/IRM Detector Drive Operation 2.2.1 Nuclear Instrumentation System is in service IAW Section 5.1 of this procedure.

2.2.2 Applicable Precautions and Limitations have been reviewed by each procedure user.

2.3 System Bypassing 2.3.1 Nuclear Instrumentation System is in service IAW Section 5.1 of this procedure.

2.3.2 Applicable Precautions and Limitations have been reviewed by each procedure user.

2.4 SR-M/IRM Rod Block Bypassing during Refueling Operations 2.4.1 Nuclear Instrumentation System is in service 1AW Section 5.1 of this procedure.

). 42 All Fuel is removed from Reactor Vessel.

2.4. 3 Applicable Precautions and Limitations have been reviewed by each procedure user.

Hope Creek Page 2 of 20 Revs. 10

-E-S37 .'" Ae\CS AUS' BE ATTACHED FOR FIELD USE HC.OP-SO.SrE-000 1(Q) 3.0 PRECAUTIONS AND LIMITATIONS

-I Precautions

3. 1.1 Control Rods shall not be moved when the SRM OR IRM Detectors are in motion.

3.1.2 An APRM Channel is nop IF < 2 IPRM inputs per level OR < 14 LPRM inputs per APRM Channel.

3.1.3 Before removing a joystick from Bypass, ensure bypassed Channel is reading approximately the same as the other Channels AND no HIGH or HIGH HIGHS exist on the bypassed Channel.

3.2 Limitations 3.2.i Ensure compliance with the following Technical Specifications:

  • I/S 3/4.2.2 APRM Setpoints
  • T/S 3/4.3.7.6 Source Range Monitors
  • T/S 3/4.9.2 Refueling Operations Instrumentation

[lope Creek Page 3 of 20 Rev. I1)

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030108 H-iC.OP-SO.SE-0001 (Q) 3.2.2 The signals listed in Table SE-00] will initiate a Control Rod block.

TABLE SE-001 PARAMETER SETPOINT BYPASSED SRM Downscale 3 cps IRM's 2 range 3 or Reactor Mode Switch in RUN SRM Upscale I X 105 cps IRM's 2 range 8 or Reactor Mode Switch in RUN.

a) Module unplugged IRM's > range 8 or Reactor SRM Inoperative b) Low Voltage c) Mode Switch out of Operate Mode Switch in RUN.

SRM Detector < 100 cps and Detectors not fully IRM's > range 3 or Reactor Wrong Position l inserted Mode Switch in RUN.

IRM's in range I position or IRM Downscale 5/125 of full scale Reactor Mode Switch in RUN.

IRM Upscale 108/] 25 of full scale Reactor Mode Switch in RUN a) Module unplugged Reactor Mode Switch IRM Inoperative b) Low Voltage in RUN.

c) Mode Switch out of Operate IRM Detector __ Reactor Mode Switch Wrong Position In RUN.

APRM Upscale .66(W-dW)+ 42%

  • FRTP Reactor Mode Switch not in Thermal Power 1FLDRN (Flow Biased) CMFLPD RUN.

APRM Downscale 4% of Rated Thermal Power R Mode Switch not in APRM Upscale 12% of Rated Thermal Powver R Mode Switch a) ** < 14 LPRM inputs APRM Inoperative b) Module unplugged None c) Mode Switch not in Operate Flow Unit Inoperative a) Module unplugged Reactor Mode Switch not in b) Mode Switch not in Operate RUN.

Flow Unit Upscale 11 1 % of Rated Flow Reactor Mode Switch not in 10% between Flow Unit outputs Reactor Mode Switch not in Comparator Trip RUN.

L

  • IF FRTP < I CMFLPD
    • < 2 1,PRM inputs per level is an Administrative limit imposed by Tech. Spec. Table 3.3.1-]

note (e). There are no automatic actions associated with this limit. Operator action is required to implement the appropriate response for an inoperable A PRM.

Hope Creek Page 4 of 20 Revs 10

CHr-ANES vk3SDE- ATTACHED FOR FHELD JSE IIC1.OP-SO.SE-000 I (Q) 3.2 .3 The signals listed in Table SE-002 vwill initiate a Reactor Scram.

TABLE SE-002 I

PARAM ETER SETPOINT BYPASSED SRMI Upscale 2 X 105 cps Shorting Links installed Reactor Mode Switch IRM Upscale 12D/125 of full scale in RUN a) Module unplugged l Reactor Mode Switch IRM Inoperative b) Low Voltage in RUN

__ c) Mode Switch not in Operate None lAPRIM Upscale 118% of Rated Thermal Power APRM Upscale

! 15% of Rated Thermal Power

~Reactor Mode Sxvitch in RUN.

APRMUpsale.66(W-dW)+ 5 1% -FRTP Thrmlo Power CMF LPD None Therinal Poer ] 113.5% maximum with high flow clamped a) **< 14 LPRM inputs APRMl Inoperative b) Module unplugged None c) Mode Switch not in Operate

  • IF FRTP < I CM FLPD
    • < 2 LPRRM inputs per level is an Administrative limit imposed by Tech. Spec. Table 3.3.1-1 note (e). There are no automatic actions associated with this limit. Operator action is required to implement the appropriate response for an inoperable APRM.

3.2.4 The signals listed in Table SE-003 will enable the Oscillation Power Range Monitor (OPRM):

TABLE SE-003 PARAMETER SETPOINT BYPASSED APRM POWER > 30% NONE' CORE: FLOW < 60% NONE 4.0 EQUIPMENT REQUIRED Non)

I lope C reek Page 5 of 20 Rev. I10

I. - JQ\---

- -3S7 CVHANGES MUST E ATTACHED FOR FIELD USE 11C.OP-SO.SE-OO0 I(Q)

NOTE 5.0 All operations are performed from 106C51C unless otherwise noted.

50o PROCEDURE

5. 1 Placing4jhe System in Service
5. 1.1 ENSURE all prerequisites have been satisfied IAW Section 21.I.

5.1.2 PLACE Source Range Monitors in service as follows:

A PLACE SRM A,BC & D MODE SWITCHES in OPERATE.

(I 0C635 & I 0C636)

13. OBSERVE the following annunciators are clear:
  • SRM UPSCALE OR INOPERATIVE
  • SRM DOWNSCALE C. OBSERVE all SOURCE RANGE NEUTRON MONITORING MONITOR STATUS lights are OFF.

D. OBSERVE STARTUP RANGE MONITOR RECORDERS A AND C AND B AND D indicate > 3 cps. (I 0C650C)

5. 1. PLACE Intermediate Range Monitors in service as follows:

A. PLACE IRM A,B,C,D,EF,G&H MODE SWITCHES in OPERATE. (I0C635 & 10C636)

B. PLACE CHANNEL A,B,C,DE,F.G&H IRM RANGE SELECT RANGE SWITCHES to 1.

C. OBSERVE the following annunciators are clear:

  • IRM A/B/E/F UPSCALE INOP/ TRIP
  • IRM C/D/G/H UPSCALE INOP/ TRIP (Continued Ne\xt Pace Hope Ci-eek Page 6 of 20 Revs. 10}

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030 108 HC.OP-SO.SE-OO I(Q) 5.1.3 (Continued)

D. OBSERVE IRM RPS TRI P CHANNELS A,B MN4ONITOR STATUS lights are OFF (except DNSC).

E. PRESS RECORDER INPUT R603 A,B,C&D IRM A, B, C, D, E,F. G&H PBs.

CAUTION 5.1.4 LPRM readings should be consistent with plant conditions before returning to service .

5.1.4 PLACE Local Power Range Monitors in service as follows:

A. VERIFY LPRM reading is consistent with plant conditions. l B. BYPASS APRM(s) in the affected cabinet. l C. At Panel 10C608, PLACE LOCAL POWER RANGE MONITOR Control Switch to OP THEN OBSERVE the LPRM BYPASS light is OFF. i D. OBSERVE APRM AND LPRM UPSCALE annunciator is clear.

E. At Panel 10C651, SELECT a control rod so that the LPRNM is displayed on the Four Rod Display THEN OBSERVE the following:

1. The associated BYPASS light on the Four Rod Display is OFF. I
2. The LPRM reading is consistent with plant conditions.,

F. At the CMS, SELECT OD-8 THEN OBSERVE that the LIPR\ is reading consistent with plant conditions.

G. VERIFY APRM GAFS are w ithin +/- 2% of rated CTP.

AND, IF necessary, ADJUST GAFS IAW HC.RE-S'F.SE-0002(Q). _-

Continued Next Page Hope Creek Page 7 of 20 Rev. IO

  • - S:C

-S> -A\_S AvST BE ATTAC~HED - FiELD USE IIC.OP-SO.SE-(001(Q) 1,.,4 (Conrtinaued)

Ii. UNBYPASS APRM(s) in the affected cabinet. ___

1. NOTIFY Reactor Engineer of l PRM placed in service.

S. i .5 PLACE Average Power Range Monitors in service as follows:

A. PLACE APRM A,B,C,D.E.F MODE SWITCHFS in OPERATE.

(IOC 608)

13. OBSERVE the following annunciators are clear:
  • APRM SYS A UPSCALE TRIP/INOP
  • APRM SYS B UPSCALE TRIP/INOP
  • APRM UPSCALE C. OBSERVE APRM RPS TRIP CHANNEL A.B MONITOR STATUS lights are OFF (except DNSC).

D. OBSERVE APRM DOWN SCALE annunciator is energized. __

5.1.6 PLACE Oscillation Power Range Monitor in service as followvs:

A. For the following Oscillation Power Range Monitors, PLACE the following OPRM MANUJAL BYPASS/AVUTO/OPRM MANUAL ENABLE Switch (S4) in the AUTO position (10C608):

1. OPRMA1
2. OPRMA2
3. OPRMBI
4. OPRMB2
5. OPRMC1
6. OPRMC2
7. OPRMDI
8. OPRMD2 Continued Next Page

[lop~e (Creeli Page 8 of 20 ReN. 10

-'-\ _  ? - CA- S ST BE ATTACHED FOR FIELD S_

.1 .6 ((iorntinued)

B. For the following Oscillation Power Range Monitors.

PLACE the OPERATE/TEST Key Switch in the OPERATE position. (10608):

I. OPRMA I I OPRMA2 OPRMBI

4. OPRMB2 OPRMC 1
6. OPRMC2
7. OPRMDI
8. OP RMD2 C. OBSERVE the following annunciator window is clear:

Window Box C3-F3 - OPRM TRIP BYP.P'INOP/TRBL

[). OBSERVE the local LED indicators for the following Oscillation Power Range Monitors are off (except READY). (I 0C608)

I. OPRMAI

2. OPRMA2
3. OPRMB1
4. OPRMB2
5. OPRMCI
6. OPRMC2
7. OPRMDI
8. OPRMD2 H~opeC Creck Page 9 of 20 Rev. II)

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030108 HC.OP-SO.SE-OOOl (Q) 5.2 SRM/IRM Detector Drive Operation 5.2.1 ENSURE all prerequisites have been satisfied lAW Section 2.2.

NOTE 5.2.2 A. When all IRM Range Switches are on range 3 OR above, SRM detectors may be fully withdrawn without causing a rod withdrawal block.

B. When Reactor Mode Switch is in RUN, IRM detectors may be fully withdrawn without causing a rod withdrawal block.

CAUTION 5.2.2 Control Rods shall not be moved when the SRM OR IRM Detectors are in motion.

5.2.2 WHEN desired, DRIVE OUT SRM (IRM) Detectors as followers:

A. PRESS DETECTOR DRIVE POWER ON/OFF PB POWER ON comes on.

NOTE 5.2.2.B Only one SRM Detector should be selected during drive out operation when SRM's are required to be operable.

B. PRESS required SRM (IRM) DETECTOR SELECT PBs.

Backlight comes on.

C. IF driving out SRM detectors. MAINTAIN STARTUP RANGE MONITOR RECORDERS A(C), B(D) (IOC650C) between 100 cps AND 105 cps.

D. PRESS AND HOLD DETIECTOR DRIVE OUT PB.

DRIVE OUT comes on.

Continued next page Hope Creek Page 10 of 20 Rev. IU

ANQES MUS7 BE A-TACHED FOR FIELD USE HC.OP-SO.SE-O0001(Q)

' .2. CzOfltifltl~ed)

E. WHEN STARTUP RANGE MONITOR RECORDERS (I0C650C) indicates desired level OR SRM (IRM) DETECTOR SELECT OUT is on.

RELEASE DETECTOR DRIVE OUT PB.

DRIVE OUT goes off.

F. PRESS selected SRM (IRM) DETECTOR SELECT PBs Backlight goes off.

G. WIlEN all SRM (IRM) DETECTOR SELECT OUT are on, PRESS DETECTOR DRIVE POWER ON/OFF PB.

OFF comes on.

WHEN desired, IDRIVE IN SRM (IRM) Detectors as follows:

A. PRESS DETECTOR DRIVE POWER ON/OFF PB.

POWER ON comes on.

B. PRESS required SRM (IRM) DETECTOR SELECT PBs.

Back-light comes on.

NOTE 5.2.3.C

'DRIVE IN"is a seal-in signal. All selected detectors will drive in until their respective

'DETECTOR SELECT IN" is on.

C. PRESS DETECTOR DRIVE IN PB. DRIVE IN AND DRIVING IN indicators come on.

D. WHEN all selected SRM (IRM) DETECTOR SELECT IN indicators are on, VERIFY DRIVING IN is off.

PRESS DETECTOR DRIVE IN PB. (DRIVE IN goes off).

E. PRESS selected SRM (IRM) DETECTOR SELECT PBs.

Backlight goes off.

F. PRESS DETECTOR DRIVE POWER ON/OF F PB.

OFF comes ON.

IIl o~e (Creek Page 11 of 20 Rev. If}

-- E-SDO CH-A\u; M\dS- BE ATTACHED FOR FIELD JSE I-C.0P-SO.SE-000 1(Q)

>j. .Sstem Bypassing

.3. I ENSURE all prerequisites have been satisfied 1AW Section -3_

5.3.2 T o bypass a Source Range Monitor.

PERFORM the following: __

NOTE 5.3.2.A If the Reactor Mode Switch is in the RUN position. the Source Range Neutron Monitoring Status Bypass light will NOT illuminate.

A. PLACE SOURCE RANGE NEUTRON MONITORING MONITOR BYPASS joystick to the SRM Channel position to be bypassed. OBSERVE associated SOURCE RANGE NEIUTRON MONITORING MONITOR STATUS BYPASS is on.

CAUTION 5.3.2.B

  • The bypassed Channel should be reading approximately the same as the other Channels.
  • No upscale alarm OR upscale trip exists on the bypassed Channel before removing a joystick from Bypass.
  • Placing a joystick to BYPASS defeats the MONITOR STATUS lights (except BYPASS) for the respective channel.
  • Status of upscale alarms and trips must be checked at local panel.

B. WHEN SRM bypass is no longer required, PLACE SOURCE RANGE NEUTRON MONITORING MONITOR BYPASS joystick to center position.

OBSERVE associated SOURCE RANGE NEUTRON MONITORING MONITOR STATUS BYPASS is off.

H~ope Creek Page 12 of 20 Rev. I 0

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHE- FOR FiELD USE 20030108 HC.OP-SO.SE-000 1(Q) 5.3.3 To bypass an Intermediate Range Monitor, PERFORM the following:

NOTE 5.3.3.A If the Reactor Mode Switch is in the RUN position, the Intermediate Range Neutron Monitoring Status Bypass light will NOT illuminate.

A. PLACE IRM RPS TRIP CHANNEL A(B) MONITOR BYPASS joystick to the IRM Channel position to be bypassed.

OBSERVE associated IRM RPS TRIP CHANNEL A(B)

MONITOR STATUS BYPASS is on.

CAUTION 5.3.3.B

  • The bypassed Channel should be reading approximately the same as the other Channels.

. No upscale alarm or upscale trip exists on the bypassed Channel before removing a joystick from Bypass.

  • Placing a joystick to BYPASS defeats the MVIOHNITOR STATUS lights (except BYPASS) for the respective channel.
  • Status of upscale alarms and trips must be checked at local panel.

B. WHEN IRM bypass is no longer requirc;.

PLACE IRM RPS TRIP CHANNEL A(B) MONITOR BYPASS joystick to center position.

OBSERVE associated IRM RPS TRIP CHANNEL A(B) MONITOR STATUS BYPASS is off.

Hope Creek Page 13 of 20 ev. IO

->  ;-HA\:-S MUS 3_ ATTACHED FOR FIELD USE H C.OP-SO.SE-000 1(Q) 5 3. To bypass an Average Power Range Monitor.

PERFORM the following:

A. PLACE APRM RPS TRIP CHANNEL A(B) MONITOR BYPASS joystick to the APRM Channel position to be bypassed THEN OBSERVE associated APRM RPS TRIP CHANNEL A(B)

MONITOR STATUS BYPASS is on.

I CAUTION 5.3.4.B

  • The bypassed Channel should be reading approximately the same as the other Channels.

a No upscale alarm or upscale trip exists on the bypassed Channel before removing a joystick from Bypass.

Placing a joystick to BYPASS defeats the MONITOR STATUS lights (except BYPASS) for the respective channel.

  • Status of upscale alarms and trips must be checked at local panel.

B. WINTEN APRM bypass is no longer required.

PLACE APRM RPS TRIP CHANNEL A(B) MONITOR BYPASS joystick to center position THEN OBSERVE associated APRM RPS TRIP CHANNEL A(B)

MONITOR STATUS BYPASS is off.

Hopse C reck Page 14 of 20 Rev. IO

L -s

\- -- SY CA\CGES MUST BE ATTACHED FOR FIELD USE HC.OP-SO.SE-0001(Q)

NOTE 5.3.5 A. An APRM Channel is inop IF < 2 LPRM inputs per level OR < 14 LPRM inputs per APRM Channel.

B. The Rod Block Monitor receives input from LPRMs. A RBM channel is considered administratively inoperable (for affected control rods)

IF < 50% of the LPRM inputs on a given LPRM level are available unless a situation specific evaluation has been performed. [70005801]

5.3.5 To bypass a Local Power Range Monitor, PERFORM the following:

A. IF LPRM is in an APRM, THEN, VERIFY operability lAW T/S Table 3.3.1-1 Note (e)

OR, DECLARE associated APRM INOP. __

B. VERIFY RBM Channel operability for the affected control rods lAW T/S 3.3.6.

C. BYPASS APRM(s) in the affected cabinet. l D. At Panel 10C608, PLACE LOCAL POWER RANGE MONITOR Control Switch to BY THEN OBSERVE the LPRM BYPASS light is ON.

E. At Panel I OC65 1, SELECT a control rod so that the LPRM is displayed on the Four Rod Display THEN OBSERVE that the associated BYPASS light on the Four Rod Display is ON.

F. At the CMS, SELECT OD-8 THEN OBSERVE that the LPRM is indicaling 3 in a RFDl field. _ l (3. VERIFY APRM GAFS are within - 2% of rated CTll AND. IF necessary, ADJUST GAFS lAW HC.RE-ST.SE-0002(Q).

Continued Next Pace Hope Creek Page 15 of 20R Revs. I 0

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 2003D 108 HC.OP-SO.SE-0001(Q) 5.3.5 (Continued)

H. UNBYPASS APRM(s) in the affected cabinet.

1. NOTIFY Reactor Engineer of LPRM bypassed.

J. WHEN LPRM bypass is no longer required, PLACE LPRM in service IAW step 5.1.4.

NOTE 5.3.6 Bypassing a Recirc Flow Unit with the joystick only removes it from the Comparator Circuit. To fully bypass unit requires I&C to bypass the unit at Panel 10C608 Pwr Range Neutron Mon Cab.

5.3.6 To bypass a Recirc Flow Unit from the Comparator Circuit, PERFORM the following:

A. PLACE RECIRC FLOW MONITORING RPS TRIP CHANNEL A(B)

MONITOR BYPASS joystick to required flow channel position.

OBSERVE associated RECIRC FLOW MONITORING RPS TRIP CHANNEL A(B) MONITOR STAk.TUS FLOW BYPASS is on.

B. WHEN Recirc Flow Unit bypass is no longer required, PLACE RECIRC FLOW MONITORING RPS TRIP CHANNEL A(B) MONITOR BYPASS joystick to t.outer position.

OBSERVE associated RECIRC FLOW MONITORING RPS TRIP CHANNEL A(B) MONITOR STATUS FLOW BYPASS is off.

Hope Creek Page 16 of 20 Rev. I10

- -,N--;-E-DOT CHAN\ES MJST BE ATTACHED FOR FIELD USE I-IC.OP-SO.SF-OO0 1(Q) 5.3.7 Io bypass (trip disable) an OPRM, PERFORM the following:

A. PLACE OPRM MANUAL BYPASS/AUTO/OPRvM MANUAL ENABLED Switch (S4) to the OPRM MANUAL BYPASS position. (10C608)

B. OBSERVE Annunciator Window Box C3-F3 -

TRIP BYP/INOP/TRBL is illuminated.

C. WHEN OPRNM 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/INOPrTRBL 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.

5.4.3 INSTALL a jumper in Panel 10C635 from DDl9 to DD20.

INITIAL Attachment 1.

5.4.4 PERFORM an independent verification of the installed jumper from Step 5.4.3.

INITIAL Attachment 1.

ti o1' e C.rc ki Page 17 of 20 Rev. I 0

'_ O-HE-PO-v- CHANGES MUST BE ATTACHED FOR FIELD USE HC.OP-SO.SE-0001 (Q) 5.4.5 INSTALL ajumper 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 DD19 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 10C636 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 SR-MIRM rod blocks are functioning AND) CLEAR the action statement log.

Ho(pe (Creck Page 18 of 20 Rev. I10

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030108 HC.OP-SO.SE-OOOI(Q) 6.0 RECORDS 6.1 RETAIN the following IAW NC.NA-AP.ZZ-00 I1(Q); Records Management Program:

a Procedure cover page 0 Attachment I - Installation and Removal of Jumpers for SRM/IRM Rod Blocks

7.0 REFERENCES

7.1 Panel Drawings: J-0651-1; Sht. 6, Sht. 7 7.2 GE Documents: GEK-90300, Vol. IV, Pt. 1, Sept. 1983 GEK-90300. Vol. IV, Pt. 3.

Sept. 1983 7.3 Procedures HC.RE-ST.SE-0002(Q) 7.4 Commitment Documents CD-849A CR 960911068 7.5 Other Documents DCP 4EC-3523 BP 970729283 70005801 Hope Creek Page 19 of 20 Rev. IO

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 2003T)108 HC.OP-SO.SE-OOOi (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 10C635 5.4.4 DD]9 TO DD20 I&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 5.4.11 AA35 TO AA36 _ _ _

Hop~e Creek Page 20 of 20 Rtev. I()

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: FE7 A A A 295( )21 X m AA AA1 U4 i

K/A NUMBER:

APPLICABILITY: IMPORTANCE FACTOR: 3.7 3.7 EO = RO = SRO 3 LSRO 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 TRAINING SUPERVISOR OPERATIONS MANAGER RFPRFSEFNTATIVE 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: GIRADE: F SAT F UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Nuclear Common Page 1 Rev. 0 2003-NRC-LSRO-S2

NC.TQ-WB.ZZ-0310(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM: 204000 RWCU System TASK: Align RVVCU for Alternate Decay Heat Removal lAW 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

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-N RC-LSRO-S2

( NC.TdQ .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) SIU UNSAT evaluation)

I l - l I I Operator obtains procedure HC.OP- 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.

. _I I Operator reviews AB-RPV-0009 List of Operator determines Section F of HC.OP-Conditions. AB.RPV-0009 is applicable.

I-I I Operator determines beginning step of the Operator determines correct beginning step procedure to be F.1

______________________ .4. -4 4 -4 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 I Operator verifies RWCU is in service from Cue sheet.

Examiner Note:

Initialing steps is not critical.

I__ _____ I __________________I_____________________

Page 3 REV.: 0 Nuclear Common

( NC .TQ NZ-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 evaluation)

  • 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 clockwise 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.

Page 4 REV.: 0 Nuclear Common

- - - I i C' I v- f I a AC>'

( NC.TQ- ,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

  • NO. (*Denotes a Critical Step) STANDARD

(#Denotes a Sequential Step)

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 Page 5 REV.: 0 Nuclear Common

(, NC.TQ .ZZ-0310(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

_______________________________ - I Y --

STEP (CMMEN TI

(*Denotes a Critical Step) STANDARD EVAL (Required for

(#Denotes a Sequential Step) SIU UNSAT evaluation)

I 5.9.1 ENSURE all prerequisites of Section 2.9 are Operator asks for permission to open the satisfied. Regen HX Bypass line.

Cue: OS/CRS permission has been obtained to open the Regen Hx bypass line.

If Operator asks if Full or Partial Bypass is required, Cue: Full bypass I. i i iI 5.9.2 IF bypass of the Regenerative Heat Exchangers is required, THEN PERFORM the following:

Nuclear Common Page 6 REV.: 0

( NCU.TI- .ZZ-0310(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 IS I, R STEP (.UMMEN I b

(*Denotes a Critical Step) STANDARD EVAL (Required for

(#Denotes a Sequential Step) SWu UNSAT evaluation)

I ____________

5.9.2.A UNLOCK AND OPEN V231, Bypass Valve. Examiners note: The following valves are located inside the Regen & Non-Regen HX room, which is a high radiation, contaminated area. Provide the operator with room map. Some valves are visible through the viewing window.

Operator simulates removal of locking device and rotates V231 handwheel in the Counter-clockwise 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-clockwise direction until the handwheel stops in the full open position.

Examiner Cue: The valve stated is in the position stated.

Nuclear Common Page 7 REV~: 0

( NC.TQ .ZZ-031,3(Z)

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: 204000 RWCU System TASK: 29502 AA1 .04 Align RWCU for Alternate Decay Heat Removal IAW Section F of HC.OP-AB.RPV-0009 STEP l COMMENTS

(*Denotes a Critical Step) STANDARD EVAL (Required for

(#Denotes a Sequential Step) SU UNSAT I _evaluation) l I 5.9.2.C CLOSE V230, Hx Outlet Valve. Operator simulates rotating the V230 handwheel in the Clockwise direction until the handwheel stops in the full closed position.

Examiner Cue: The valve stated is in the position stated.

I t 5.9.2.D ADJUST system flowrate (for 2 pump Operator should request the Control Room to adjust flow IAW 5.9.2.D operation) to approx. 300- 320 gpm.

(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

MWP I 450 AA O' NL a HAT 4I RoAS ryWp SRVW ,, Af cEtR 5P j AJ , A sNu Jo 4S T}

AiRSAM P' _ RESULTS. sc / cc < S~~ 1 S :vi?EVan EW a m p SUP=RSCR RellW s

SAIngoZ Y :tA'ih>Api/p-t/F£ SLR,,rEr, By

- II

JOS 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

Perform the required actions for Condition F of HC.OP-AB.iRV-0009.

Nuclear Common Page 9

ALL, ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only Page 1 of 1 PSEG NUCLEAR LL.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.

  • CP No. CP Rev. No. A)AD No. _ AD Rev. No. or None C. OTSC(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 UJFSAR section 5.2.3.2.2.2 (where the TIS direction was moved to). Editorial Change lAW NC.DM-AP.ZZ-0001(Q) allowances.

IMPLEMENTATION REQUIREMENTS Effective date lll 5 0 -/

Implementation of T/S Amendment 140 APPROVED: , A//42 Date Manager - Hope Ofek Operations

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 TABLE OF CONTENTS 4SECTION TITLE PAGE t

PURPOSE.. 2 L.0 I

PREREQUISITES.. 2

).0 PRECAUTIONS AND LIMITATIONS . 6 3o0 EQUIPMENT REQUIRED ............................................ 10 4.

4 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 REFERENCES.......................................................................................................... 48 6.0 ATTACHMENTS Attachment I - Maximum RWCU Return To Feedwater Flow - 2 Pump Operation ....................... 50 51 Attachment 2 - Maximum RWCU Return To Feedwater Flow - I Pump Operation .......................

52 Attachment 3 - Computer Point A196 Substitute Value Instructions ............................................

Hope Creek Page 1 of 53 R.ev. 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. I RWCU System Valves are aligned IAW applicable SAP/WCM operational mode.

2.1.2 RWCU Major Component Electrical lineup is complete IAW applicable SAP!WCM operational mode.

2.1.3 BB-HV-F023A, Reactor Recire Pumps Suction Valve, and/or BB-HV-F023B, Reactor Recire 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 andlor 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 lAW Section 5.1 of this procedure.

2.2.2 An idle RWCU Recirc pump shall be warmed up lAW Section 5.3, IF the temperature difference between the pump casing AND Reactor Vessel water is > 150iF AND Reactor water temperature is > 212 01. lCD-886XI 2.2.3 RWCU System Valves are aligned LAW applicable SAP/WCM operational mode.

2.2.4 RWCU Major Component Electrical lineup is complete IAW applicable SAP!WCM operational mode.

Page 2 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) 2.2.5 Chemistry Technician is available AND at least one RWCU Filter/Demin is ready for service (IF 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-F0l lA, Feedwater Inlet Valve, and/or AE-HV-F01 1B, 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),

AND FT-NO12A(D).

2.3 Warm-up of RWCU Recire Pumps 2.3.1 RWCU System Valves are aligned JAW 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.

2.36 BB-HV-F023A, Reactor Recirc Pump Suction Valve, and/or BE- HV-F023B, 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 1SKXR-l 1497 and I SKXR-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 JAW 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 Recirc Flow - Maximizing Bottom Head Drain Flow 2.5.1 RWCU System is in-service JAW 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 JAW 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 HC.OP-SO.BG-0001(Q) 2.8 Removing RWCU Pump/System from Service 2.8.1 RWCU System is in-service JAW 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 RWCU 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.

Page 5 of 53 Rev. 33 Hope Creek

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only 1C.OP-SO.BG--0001(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 0

between pump casing and Reactor Vessel water is > 150 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. [CD-786D]

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).

0 3.1.5 The rate of RWCU Pump warm-up shall NOT exceed 25 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-FOO1 AND BG-HV- F004 valves while venting RWCU delta transmitters (2.2.11). 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.

Page 6 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) 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 1SKXR-1 1497 OR 1SKXR-1 1499 (1OC609, 1OC61 1),

does NOT cause an automatic RWCU isolation for the associated inbd/otbd isol vlv (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).

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. 10), 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.

3.113 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 Aflow transmitters. [PR 9708031031 Page 7 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) 3.2 Limitations 3.231 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, 1-RC-V005, Three-way Diverting Valve, from Sample Panel 10C25 I 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 120WF.

3.2.6 Non-Regenerative Heat Exchanger maximum coolant (RACS) outlet temperature is limited to 180WF for Hot Standby, Startup, OR Blowdown conditions.

3.2.7 RWCU Pump Cooling Water (RACS) inlet temperature must NOT exceed 110F.

3.2.8 WHEN in Hot Standby Operation without Recirc 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 Demins.

Page 8 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) 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 Manuallyoperatedgatevalves 1-AE-V188 AND I-AErVI89, 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-FO0T, 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-Regenerative 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 (>1350 F)

OR RWCU Pump Rooms AND Heat Exchangers Rooms (>1400F)

D. Standby Liquid Control System actuation:

  • System A isolates HV-F001
  • System B isolates HV-F004 Continued next page Ho~pe 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-F00I, 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 6000 F or equivalent
  • Magnetic Thermocouple (Ensure compatibility between probe and box)

Page 10 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)

NOTE 5.0 All operations are performed from Panel 10C651C unless otherwise 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 IAW 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-F001 and BG-HV-F004 are CLOSED.

B. CLOSE l-BG-V024(1-BG-VO30O, A(B)RWCURecirc Pmp Csg Dmn Vlv.

C. OPEN the following valves:

1. l-BG-V022 (l-BG-V028), A(B) RWCU Recirc Pmp Csg Drn Vlv.
2. 1-BG-V023 (1-BG-V029), A(B) RWCU Recirc Pmp Csg Drn Vlv.

Continued next page Page 11 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-O00 1(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 1-AP-V142(1-AP-V143), Condensate and Storage Transfer to RWCU Recirc Pmp A(B) Seal Fill Isin 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-VO08, 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-1077(1076), A(B) RWCU Recirc Pump A(B) Vent sight glass (local):

A. 1-BG-V026, RWCU Recirc Pmp A Seal Flush Vent Vlv, AND 1-BG-V027, RWCU Recirc Pmp A Seal Flush Vent Vlv B, 1-BG-V073, RWCU Recire Pmp B Seal Flush Vent Vlv, AND 1-BG-V074, RWCU Recirc Pmp B Seal Flush Vent Vlv Page 12 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) 5.1.5 VENT using the following valves until piping is vented (Local):

A. 1-BG-V1 73, RWCU Pmp Suet Hdr Vent, (RM 4505)

AND 1-BG-V174, RWCU Pmp Suet Hdr Vent, (RM 4504D).

B. l-BG-V032, RHX Tube Side Inlet Hdr Vent, (RM 4508B)

AND l-BG-V033, RHX Tube Side Inlet Hdr Vent (RM 45063).

C. l-BG-V037, RHX BE207 Tube Side Vent, (RMI 4506B)

AND 1-BG-V038, RHX BE207 Tube Side Vent, (RM 4506B).

D. I-BG-V041, RHX AE207 Tube Side Vent, (RM 4506B)

AND 1-BG-V042, RHX AE207 Tube Side Vent, (RM 45063).

E. l-BG-V049, Non-REX AE208 Tube Side Vent, (RM 4506B)

AND 1-BG-VO50, Non-RHX AE208 Tube Side' Vent (RM 4506B).

F. 1-BO-V054, Non-REX Outlet Hdr Vent, (RM 4506C)

AND 1-BG-VO55, Non-RHX Outlet Hdr Vent, (RM 4506C).

G. 1-BG-V057, RHX AE207 Shell Side Vent, (RM 4506C)

AND 1-BG-VO58, RHX AE207 Shell Side Vent, (RM 4506C).

H. 1-BG-V062, RHX BE207 Shell Side Vent, (RM 4506B)

AND 1-BG-V063, RHX BE207 Shell Side Vent, (RM 4506B).

NOTE 5.1.5.1 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. l-BG-V066, RNX Shell Side Outlet Hdr Vent, (RM 4506A)

AND I-BG-V067, RHX Shell Side Outlet Hdr Vent, (RM 4508B).

-Hope Creek Page 13 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.BC-OOO1(Q) 5.1.6 IF opened in Step 5.1.3, THEN:

A. CLOSE 1-BG-V004, A RWCU Recire Pmp Suction Vlv ANDI 1-BG-V008, B RWCU Recirc Pmp Suction V1v.

B. CLOSE 1-BG-V200, A RWCU Recirc Pmp Dsch Byp Vlv AND 1-BG-V210, B RWCU Recirc Pmp Dsch Byp Vlv.

C. CLOSEiHV-F044, Fltr Demnin 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-VI43), Condensate and Storage Transfer to RWCU Recirc Pmp A(B)

Seal Fill Isln Vlv.

2. 1-BG-V022(1-BG-V028), A(B) RWCU Recirc Pmp Csg Drn Vlv.
3. l-BG-V023(1-BG-V029), A(B) RWCU Recirc Pmp Csg Drn Vlv.

B. OPEN 1-BG-V024(1-BG-V030), A(Bl)RWCU Recire Pmp Csg Din Vlv.

5.1.8 OPEN BG-HV-FOO1 and BG-HV-FOQ4.

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 H1C.OP-SO.BG-OOO1(Q)

NOTE 5.2 A. CRIDS points B2081 and A2856, OR NUMAC Drawers 1SKXR-1 1497 OR 1SKXR-11499 (100609, 1OC611) 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 A196 RWCU FLOW (WCU),

when the system was removed from service, THEN RETURN Computer Point A196 to AUTOMATIC using Attachment 3 - Computer Point Al96 Substitute Value Instructions.

1 Hope Creek Page 15 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-OOO1(Q) 5.2.3 IF in two pump operation, THEN PERFORM the following:

A. CLOSE HV-FO44, FLTR DEMIN BYPASS, by pressing the DECREASE push-button until CLOSE lamp is illuminated.

CAUTION 5.2.3.B RWCU Recirc Pumps trip on low flow c 70 gpm (after pump start time delay of 16 minutes). This trip will only occur If the common pump suction flowpath is c 70 gpm.

B. START A(B)P221, A(B) RWCU PUMP.

C. THROTTLE OPEN HV-FO44 FLTRDEMIN BYPASS UNTIL Computer point A2856 RWCU OUTLET FLOW indicates approximately 140 to 160 gpm.

CAUTION 5.2.3.D 3/4~- 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.

D. START B(A)P221, B(A) RWCU PUM.

E. THROITLE OPEN HV-F044, FLTR DEMIN BYPASS, UNTIL Computer Point A2856 RWCU OUTLET FLOW indicates approximately 300 to 320 gpm.

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 Hope Creek Page 16 of 53 Rev. 33

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Onl HC.OP-SO.RCG-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 B295 1 (B2952) FILTER DEMIN A(B) EFL FLOW indicates a maximum of 150 gpm AND has stabilized. [PR 980515086]

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.

1. MONITOR the following CLEANUP FILTER DEMINERALIZERS (10C650):
1. CR-R601-G33, INLET I/CONDUCTIVITY,

<1.0 MMHO/cm

2. CR-R603(Red), DEMINERALIZER A OUT CONDUCTIVITY, < 0,1 MMHO/.crn
3. CR-R603(Blue), DEMINIERALIZER 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-SOBG-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-NO15 A215 RWCU REGEN HX OUTLET TEMP TE.-N006 A2945 RWCU N-REGEN HX OUTLET TEMP TE-N019 A2944 RWCU REAC SUCT FLOW FT-N036A B2081 RWCU SYSTEM OUTLET FLOW TO FT-NO41A 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.

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.

D. WHEN RWCUI 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 Creeki 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 5.2.4.E During system operation with flow from the Reactor Bottom Head Drain ONLY, System flow should be maintained LESS THAN 136 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 B2951 (B2952) FILTER DEMIN A(B)

EFL FLOW indicates a maximum of 150 gpm and has stabilized.

NOTE 6.2.4.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, INLETH/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-4OO1(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-N015 A215 RWCU REGEN HX OUTLET TEMP TE-N006 A2945 RWCU N-REGEN HX OUTLET TEMP TE-N019 A2944 RWCU REAC SUCT FLOW FT-N036A B2081 RWCU SYSTEM OUTLET FLOW TO FDW FT-NO4lA 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 > 150WF and Reactor water temperature is > 2120F. [CD-886X1 B. All operations are performed locally unless noted otherwise.

CAUTION 5.3 The rate of RWCU Pump warm-up shall NOT exceed 265F per minute to prevent pump damage 5.3 Warm-up of RWCU Recirc Pumps WCD-937B, CD-445D]

5.3.1 ENSURE all prerequisites of Section 2.3 are satisfied.

~- Hope Creek 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(B3)P221, RWCU Pump, is necessary, THEN PERFORM the following:

A. ENSURE the following valves are CLOSED:

1. l-BG-V004 (VO08), A(B) RWCU Recirc Pmp Suction Vlv
2. 1-BG-V006 (V010), 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. 1-BG-V023 (V029), A(B) RWCU Recirc Pmp Csg Drm Vlv NOTE B.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 Pimp A(B) Seal Fill Isln Vlv.

Continued next page Hope Creek Page 21 of 53 Rev. 33 I

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:

  • 1-BG-V026 (V073), A(B) RWCU Recire Pmp Seal Flush Vent Vlv
  • 1-BG-V027 (V074), A(B) RWCU Recire Pmp Seal Flush Vent Vlv E. CLOSE the following valves:
1. I-AP-V142 (V143), Cond Stor and Xfr to A(B)

RWCU Recire Pmp Seal Fill Isln Vlv

2. 1-BG-V022 (V028), A(B) RWCU Recira Pmp Csg Drn Vlv
3. 1-BO-V023 (V029), A(B) RWCU Recire Pmp Csg Drn Vlv F. OPEN 1-BG-V024 (V030), RWCU Recirc Pmp A(B)

Csg Din Vlv.

5.3.3 PERFORM the following to warm-up the first RWCU Pump:

[CD-886X, CD-937B1 A. ENSURE l-BG-V003 (l-BG-V007), A(B) RWCU Recire Pmp Outbd Suction Vlv, is OPEN.

B. Slowly OPEN 1-BG-V004 (1-BG-V008), A(3) RWCU Recirc Pmp Suction Vlv.

Continued next page Hope 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 l-BG-V004 (1-BG-V008),

A(B) RWCU Recire Pmp Suction Vlv.

D. ENSURE the following valves are CLOSED: (PR 970803103]

  • HV-F042
  • HV-F044
  • IHV-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)P221, A(B) RWCU Recire Pump.

Continued next page 1- Hope Creek Page 23 of 53 Rev. 33 Il

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)

H. IF RWCU diff flow isolation signals alarm for >10 sec, in the following steps THEN THROTTLE back on HV-F044, HV-F104 OR 1BG-V200 (l-BG-V210). [PR 9708031031 I. WHEN A(B)P221, A(B) RWCU Recirc Pump, has operated approximately 10 seconds at a shutoff head, THEN slowly CRACK OPEN 1-BG-V200 (1-B3G-V210),

(1 0-4 turns) RWCU A(B) DISCH BYPASS VALVE, to pressurize system to F104 and F044. [PR970803103]

NOTE 5.3.3.J When opening HV-F044 use 10 seconds opening time initially, then 1 second intervals.

J J. 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 970803103]

1. Slowly THROTTLE OPEN HV-F104 OR
2. Slowly THROTTLE OPEN HV-F044 AND HV-F042 K. THROTTLE OPEN I-BG-V200 (1-BO-V210) RWCU "A" (B)

DISCH Bypass Valve and/or HV-F044 as necessary to establish a 25 0F/min. heat-up rate using pyrometer OR magnetic thennocouple, [PR 970803103]

L. Slowly OPEN 1-BG-V006 (1-BG-VOO), RWCU Pump A(B) Discharge Valve.

M. CLOSE I-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.BG-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-IO.ZZ-0003(Q), and/or HC.OP-lO.ZZ-0004(Q).

N. THROTTLE OPEN IV-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 (l-BG-V007), A(3) RWCU Recire 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.

OR

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 - (l00F + Ambient Rm Temp) = Warm up Time 100 /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-SO.BG-0001(Q) 5.3.4 (continued)

CAUTION 5.3.4.C 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 1-BG-V004 (l-BG-V008), A(B) RWCU Recirc Piup Suction Vlv.

D. WHEN fully open, THEN LOCK 1-BQ-V004 (1-BG-V008), A(B) RWCU Recirc Pmp Suction Vlv.

E. START A(B)P221, A(B) RWCU Recirc 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 Recirc 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 257F per minute. [PR 970803103]

Continued next page Page 26 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) 5.3.4 (continued)

NOTE 5.3A.G 0

Minimum pump to RWCU inlet differential temperature should be <1 00 F to complete warm-up.

_j

-G. WHEN casing temperature (as monitored using pyrometer OR thermocouple) is within 1000 F of Rx temperature5 OR WHEN warm-up time (as calculated in step 5.3.4.B.2) is up, THEN SLOWLY OPEN 1-BG-V006 (1-BG-V00),

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 V1v.

I. IF a first OR second FilterfDemin is to be placed in-service, THEN GO TO Step 5.2.3.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 HC.OP-SO.BG-0001(Q)

PSEG Internal Use Only NOTE 5.4 1SKXR-CRIDS points B2081 and A2856, OR NUMAC Drawers ISKXR-11497 OR flows.

11499 (10C609, 10C611) may be used to obtain temperature compensated CAUTION 5.4 runout.

Loss of a RWCU Pump, when in two pump operation, can cause pump FILTER DEMIN BYPASS, Flow must be reduced immediately by closing HV-F044, can remove (If open) OR throttling HV-F042, REGEN HX RTN ISLN, until Chemistry a Filter/Demin from service.

5.4 Blowdown Operation 5.4.1 ENSURE all prerequisites of Section 2.4 are satisfied.

CAUTION 5.4.2 Three Way Before opening HV-F034 (RWCU to the Main Condenser), 1-RC- V00, Diverting Valve, from Sample Panel 10C251 to the Condenser or CRW System, be (located on the 132' EL in the Reactor Bldg. outside of Room 4402) should turned 90° manually to the vertical position to divert flow to the CRW System.

vacuum This evolution is performed to reduce the risk of loosing Main Condenser during sample sink operation.

5.4.2 ENSURE that 1-RC-V005, Three Way Diverting Valve, is in the VERTICAL position.

Page 28 of 53 Rev. 33 Hope Creek

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 HC.OP-SO.BG-0001(Q)

PSEG Internal Use Only 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 c 130OF 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 Radwaste pIpIng.

C. HV-F033 valve auto closes on upstream pressure < 5 psig OR on downstream pressure > 140 pslg.

D. The system trips on RWCU Differential Flow ; 56 gpm for 45 seconds (time delay).

A gross failure of a differential pressure transmitter 1ISKXR-11497 OR K--

E.

ISKXR-11499 (10C609, 10C611), does NOT cause an automatic RWCU isolation for the associated Inbdlotbd isol vlv (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

> 66 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.

Page 29 of 53 Rev. 33 Hope Creek ENEEN

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.BG-OOO1(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 1SKXR-11497 indicates < 56 gpm (10C611, 1OC609).

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-F031, DRN FL ORF BYPASS.

5.4.8 IF NRHX outlet temperature approaches 130WF, 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 1-RC-V005, Three Way Diverting Valve, to the horizontal position.

n..a 21f SC Rev. 33 Hope Creek r agu ov vJ a

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO311G-OOQ1(Q)

NOTE 5.5 CRIDS points B2081 and A2856, OR NUMAC Drawers lSKXR-11497 OR 1SKXR-11499 (10C609, 10C611) may be used to obtain temperature compensated flows.

CAUTION 5.6 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, or throttling HV-F1104, CLEANUP .BYPASS.

5.5 Hot Standby Operation Without Reactor Recirc 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 1AW 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 Page 31 of 53 Rev. 33 Hope Creek

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030 122 PSEG Internal Use Only HC.OP-SO.BG-0001(Q) 5.5.3 (continued)'

CAUTION 5.5.3.B HV-F1 02, RECIRC LOOP SUCT HDR VALVE, should NOT be closed to the point where the RWCU -Recire 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-F102, RECIRC LOOP SUCT HDR, until Computer Point B2058 REAC BOTTOM HEAD DRAIN flow increases to between 115 and 125 gpm.

CAUTION 65.6.4 CLEANUP SYSTEM OUTLET TEMP must be maintained < 4340F to prevent thermal shock to the feedwater nozzles. [CD-389E3 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-F104, 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 Page 32 of 53 Rev. 33 Hope Creek l

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 HC.OP-SO.BG-0001(Q)

PSEG Internal Use Only 5.5.4 (continued)

D. WHEN CLEANUP SYSTEM OTLT TEMP (Computer Point A215) can be maintained *434 0 F WITH HV-F042 fully closed, THEN PERFORM the following:

1. CLOSE HV-F042, REGEN HX RTN ISLN.

AND

2. THROTTLE HV-F 104, 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 ISKXR-1 1497 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 FilterIDemin from service.

5.6 Blowdown During Refueling Operation 5.6.1 ENSURE all prerequisites of Section 2.6 are satisfied.

5.6.2 ENSURE that 1-RC-V005, Three Way Diverting Valve, is in the VERTICAL position.

Page 33 of 53 Rev. 33 Hope Creek

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEC Internal Use Only HC.OP-SO.BG-0001(Q) 5.6,3 IF blowdown required during Refuieling, THEN PERFORM the following:

CAUTION 6.6.3.A &B HV-F033, DRAIN FLOW CONTROL, valve auto closes on upstream pressure c5 psig QR 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, THEN 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 IX RTN ISLN, by pressing the DECREASE push-button AND THROTTLE OPEN HV-F033, MC 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, MC R606 DR FL COND. _

5.6.5 ENSURE the following valves arm closed:

  • HV-F034, RWCU RTN TO CNDSR
  • HV-F031, DRN FL ORF BYPASS Page 34 of 53 Rev. 33 Hope Creek

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE

.20030122 HC.OP-SO.BG-0001(Q)

PSEG Internal Use Only NOTE 5.6.6 then If I-RC-V005, Three Way Diverting Valve, is to be left in the vertical position, an OR "tagged for CS SAPINCM shoulId be updated to show the valve in 'off-normal" position.

5.6.6 IF NO additional blowdowns are anticipated, THEN RETURN l-RC-VO0S, Three Way Diverting Valve, to the horizontal position, for flow to Main Condenser.

CAUTION 5.7 runout.

Loss of a RWCU Pump, when In two pump operation, can cause pump HV-F044, FILTER DEMIN BYPASS, Flow must be reduced immediately by closing remove Chemistry can (If open) OR throttling HV-F042 REGEN HX RTN ISLN until US a FllterlDernin from service OR the flow is reduced through the two 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 5.7.3 and 5.7.4 the operator In the event HV-F044, FLTR DEMIN BYPASS, is unavailable or inoperable, A2081 to throWe may use HV-F104, CLEANUP BYPASS, AND Computer Point open/closed in order to bypass OR restore flow to Filter/Demins.

A, THROTTLE BG-HV-F042, REGEN HX 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.

Page 35 of 53 Rev. 33 Hope Creek wmnm

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 HC.OP-SO.BG-OOO1(Q)

PSEG Internal Use Only 5.7.3 WHEN flow is no longer required to be limited THEN THROTTLE BG-HV-F042, RECEN 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-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.

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.

Page 36 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) 5.8 Removing RWCU Pump/System from Service LCD-937B]

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 Denmins (F/D) are in-service, THEN REQUEST Chemistry to remove 1 FID from service OR reduce flow to maintain both Demins in-service AND flow between 140 - 160 gpm.

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.ICD-937B]

0 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 I-BG-V006 (1-BG-VO10), A(B) RWCU Recirc Pmp Dsch Vlv.

B. ENSURE I-BG-V200 (1-BG-V210), A(B) RWCU Recirc Pmp Dsch Byp Vlv is closed.

C. CLOSE 1-BG-V004 (1-BG-VOOS), A(B) RWCU Recire Pmp Suction Vlv.

Page 37 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)

NOTE 5.8.7 A. If only one RWCU Pump and FID 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

+1-20 gpni 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.

a CLEAN UP FILTER DEMIN. 'A' DISCH

  • CLEAN UP FILTER DEMIN. 'B' DISCH 5.8.8 STOP B(A)P221, B(A) RWCU PUMP. [CD-931B]

0 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-937B]

A. CLOSE 1-BG-VOlO (1-BG-V006), B(A) RWCU Recirc Pmp Dsch Vlv.

B. ENSURE I-BG-V210 (l-BG-V200), B(A) RWCU Recire Pmp Dsch Byp Vlv is closed.

C. CLOSE 1-BG-VO08 (1-BG-V004), B(A) RWCU Recirc Pmp Suction Vlv.

5.8.10 CLOSE HV-F044, FLTR DEMIN BYPASS.

Page 38 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-9001(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-FOOt, PMP SUCT CONT INBD ISOLATION VALVE B. HV-F004, PUMP SUCT CONT OUTBJD ISOLATION VALVE C. HV-FO39, 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 Al96 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, OR 5, OR Condition 2 when maintaining temperature < 2000 F.

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 5.9.1tB System flow may have to be adjusted as V233 Is opened.

B. UNLOCK AND OPEN V233, Bypass Valve, C. CLOSE V230, Bx 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 IIV-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 ANT) 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

>- Hope 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 6.9.4 The following step is intended to be used during the performance HC.OP-IS.ZZ-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) 8OR CLOSED to lower RWCU System outlet temperature.

  • THROTTLE BG-HV-F042, HX RETURN TO VESSEL, as necessary, to maintain RWCU OUTLET FLOW (CRIDS A2856) between 300 - 320 gpm.
  • THROTTLE 1-ED-V035 RWCU NRHx RACS RTN VLV -

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-H-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 (lAW 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).

Page 43 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) 5.10 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:

I. THROTTLE OPEN BG-HV-F104 to maintain flow through the RWCU Pumps while closing BG-HV-F042, Hix Return to Vessel.

2. CLOSE BG-HV-F042, Hx Return to Vessel.
3. OPEN V230, Hx 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-HV-F104.

D. ADJUST system flow to approximately 300 gpm.

Hope Creek Page 44 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 6.11 A. The following steps can be used to flush a RWCU Pump prior to maintenance for the purpose of reducing Rad Levels. Rad Pro should be contacted to survey the pump after a 20 minute flush OR as otherwise directed by the OS/CRS.

B. if the desired Rad levels are NOT achieved, then the following steps should be repeated until a sufficient dose reduction is achieved 5.11 Flushing a RWCU Pump prior to Maintenance 5.11.1 ENSURE all prerequisites of Section 2.11 are satisfied.

CAUTION 6.11.2 0

RWCU Pump cooldown should be limited to 25 F/min.

5.11.2 IF flush of A RWCU Pump is required, THEN PERFORM the following:

A. CLOSE 1-BG-V006, A RWCU Recirc Pmp Dsch Vlv.

B. CLOSE 1-BG-V200, A RWCU Recirc Pmp Dsch Byp Vlv.

C. CLOSE 1-BG-V004, A RWCU Recirc Pmp Suction Vlv.

D. OPEN 1-BG-V026, Seal Flush Vent, AND 1-BG-V027, Seal Flush Vent.

E. OPEN 1-BG-V194, Discharge Line Drain, AND 1-BG-V195, Discharge Line Drain.

F. CLOSE 1-BG-V024, Casing Drain Isolation Valve.

G. OPEN l-BG-V022, Casing Drain Vlv, AND 1-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-APV142, Condensate Transfer Isolation Valve.

I. WHEN the pump has flushed for approximately 20 minutes, THEN CLOSE l-AP-V142, 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 1-AP-V142, Condensate Transfer Isolation Valve.

B. CLOSE l-BG-V022, Casing Drain Vlv, AND 1-BG-V023 CasingDrainVlv.

C. OPEN 1-BG-V024, Casing Drain Isolation Valve.

D. CLOSE l-BG-V194, Discharge Line Drain, AND 1-BG-V195, Discharge Line Drain.

E. CLOSE l-BG-V026, Seal Flush Vent, AND 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-VO10, B RWCU Recire Pmp Dsch Vlv.

B. CLOSE 1-BG-V210, B RWCU Recirc Pmp Dsch-Byp Vlv.

Continued next page 1- Hope Creek Page 46 of 53 Rev. 33

USE ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD

- 20030122 HC.OP-SO.BG-001(Q)

PSEG Internal Use Only 1-C 11 A (rnntiniietll J,. 11.-T \ .w . ....

C. CLOSE 1-BG-V008, B RWCU Recire Pmp Suction Vlv.

D. OPEN 1-BG-V073, Seal Flush Vent,

-AND 1-BG-V074 SealFlushVent.

E. CLOSE 1-BG-V030, Casing Drain Isolation Valve.

F. OPEN 1-BO-V028, Casing Drain Vlv, AND 1-BG-V029, Casing Drain Vlv.

G. OPEN 1-AP-V143, Condensate Transfer Isolation Valve.

H. WHEN the pump has flushed for approximately 20 minutes, THEN CLOSE 1-AP-V 143, 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. Othrough 5.11.4.I 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 1-BG-V029, Casing Drain Vlv.

C. OPEN 1-BG-V030, Casing Drain Isolation Valve.

D. CLOSE l-BG-V073, Seal Flush Vent, AND l-BG-V074 Seal Flush Vent.

Page 47 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-O001(Q)

6.0 REFERENCES

6,1 P&ID's 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 E-0031-1 E- 0032-1 6.4 Vendor Manuals NI-G33-386 & 387 Ecodyne Corporation - RWCU F/D)

NI-033-429-2 Union Pump Co. - RWCU Recirc Pumps N1-A41-0045 (1) RWCU System 6.5 Panel Drawing J-0650-1 Sht. 9 J-0651-1 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 Ule Only HC.OP-SO.BG-0001(Q) 6.8 Commitment Documents CD-886X (Q210.24)

CD-937B (AID 25-S0)

CD-786D (AID 48-78)

CD-445D (SIL 258 SUPP 2)

CD-389E (SIL 436) 6.9 Other DEF # DEH-92-00081 6.10 Cross References HCRlE-SO.RJ-0010(Q), Process Computer Program Operating Instructions 6.11 Corrective Actions PR 970803103 PR 980515086 PR 980709244 CR;971127121 RWCU Differential Flow setpoint 20004666 TS990418149 20018965 80007129 DCP 4EC-3192 Page 49 of 53 Rev. 33 Hope Creek

K)>

PSEG Internal Use Only

( '

HC.OP-SO.BG-0001(Q)

( 0rI or0 oD 0 >

ATTACHMENT 1

'2 MAX1IMUM RWCU RETURN TO FEEDWATER FLOW - 2 PUMP OPERATION I r

z Maximum RWCU Return to Feed Water Flow equivalent to Total RWCU FID Bed Flow of 300 -II 0

gpm @ 120'F with 2 pumps running 370.0 I 0

365.0 C)

-4i wU 360.0 M D

-4

0. 355.0 D U)

(a 3500 C4.'

"c t 345.0 -I Cf) c2

-'-i o 340.0 RWU FIL) F(6wI0 ion1i m r

o 335.0 If, the RWCU Retum to FW Flow at the current - - - __ c a Return to FW temp. is inthis region, Then, the Total RWCU Flow through FID beds Is -- - - _ I-mr IL > 300 gpm at 120 degF. C 2 320.0 U) 0 a.. 325.0 - -' .- II- .- /

'j 315.0 - Ioo Rglon for RWCU Fo-lowF1N If.the RWCU Return to FW Flow at the cunent 310.0 ____ I - -_Retum to FW temp. is in this region, Then, the Total RWCU Flow through FID beds is 1 305.0 _ )z_or . 300gpm at 120 degF.

300.0 295.0 70 K 90

.111 110 130 150 170 190 210 230 250 270 290 310 330 350 370 390 410 430 450 470 RWCU Return to Feedwater Flow Temp. Crids A215 (degF)

Page 50 of 53 Rev. 33 Hope Creek

)>

Or-ooDII-

  • - G ( CA 0 >

PSEG Internal Use Only HC.OP-SO.BG-OOO1(Q) N)5-A ATTACIIMENT 2 <

.0 MAXMtUM RWCU RETURN TO FEEDWATER FLOW - 1 PUMP OPERATION ' z

-I m

I CV)

Maximum RWCU Return to Feed Water Flow equivalent to Total RWCU F/D Bed Flow i of 150 gpm i' 120°F with one pump running 0 D

z C

185.0 U)

E 181.0 K

-4 C.

RWCU FID Bed Flow Tooaig Region/ * -4i

<° 177.0 If, theRWCIJ Retum to FW Flow at the current _ - -

-4 Return to FW temp. Is in this region, C)

Then, the Total RWCU Flow through F/D beds is _ , I

> 150 gpmn at 120 degF. ma:

@1 169.0 0 IC 0

o 165.0 :_iI~II I~LVII 1~ /7

-- - - WI ;ti

-l I-0 C

V) s 161.0 II I I I;~ I I I I I I _0 II _ _J i M 0

C 0

t I I t I Good Region for RWVCU FID Flow If, the RWCU Return to FW Flow at the current oL 157.0 Return to FW temp. is in this region,

' 153.0 I I JIF Il Then, the Total RWCU Flow through FID beds is

< or = 150 gpm at 120 degF.

0 149.0 I I I I I I I 1-AS I ";J.u n

I

-r I I Ii I I

-t -

I i I I. I 4

I I

i I 1

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. @CridsA215 (degF)

Hope Creek Page 51 of 53 Rev. 33

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEC Internal Use Only HC.OP-SO.BC-0001(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.

A196 (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 "ChangeEnvt ' 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 "M" appears 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

-20030 122 PSEG Internal Use Only HC.OP-SO.BG-0001(Q)

ATTACHMENT 3 COMPUTER POINT A196 SUBSTITUTE VALUE INSTRUCTIONS (Page 2 of 2) 1.0. (Continued) 1.10 SELECT "AWM" block on bottom of screen to swap.

1.11 VERIFY the desired "A" or "M" appears next to "MEAS" on right of screen.

1.12 IF placing A196 in MANUAL with a value of 0.0 THEN PERFORM the following:

A. SELECT "PNT" on right side of screen and move mouse to the middle of the screen (current value will be outlined in a yellow box along with "PNT').

B. SELECT the space between the up and down arrows at bottom of the screen (a blue box will appear).

C. ENTER "0.0" in the blue box THEN PRESS "ENTER" key (box will turn gray).

D. VERIFY that "0.0" appears in the gray box.

1.13 SELECT "SYS" on top menu bar.

1414 SELECT "ChangeEnv" on pull down menu.

1.15 SELECT "OperEnv" on second pull down menu.

1.16 ENTER password "Operator" using keypad THEN PRESS "ENTER" key.

1.17 SELECT "DISP" on top menu bar followed by "OD_3d THEN VERIFY the following:

  • t"WCU" is colored blue (cyan) when in MANUAL
  • : '"WCU" shows a value of 0.0 when in MANUAL, with Al 96 set to "O.0".
  • "QCU" shows a value of 0.0 with Al96 set to "O.0".
  • "WCU" is colored black when in AUTOMATIC 1.18 IF placing A196 in MANUAL with a value of"O.0" THEN VERIFY that GRIDS point "B2081 " is in alarm (red), with a value of "O.0".

Hope Creek Page 53 of 53 Rev. 33

FOR FIELD USE I

lALL ACT1IVE ON-THE-SPOT CHANGES MUST BE ATTACHED HC.OP-AB.RPV-0009(Q) 20030122 PSEG Internal Use Only SHUTDOWN COOLING Effective Date Dae16 APPROVED:

Operations Date.

CATEGORY 1I SHUTDOWN COOLING ALARMS A6-Al

  • RHR LOGIC A OUT OF SERVICE A7 - Al A7-A1
  • RHR LOGIC B OUT OF SERVICE A6-B1
  • RHR HX CLG WTR OUTLET TEMP HI A4 - F5
  • COMPUTER PT IN ALARM C6-E1
  • APRM/RBM FLOW REF OFF NORMAL INDICATIONS
  • Lowering Core flow
  • Rising Recirc pump loop flow Rev. 0 K Hope Creek Page 1 of 45 I

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030 1 2,t internal use unly HC.OP-AB.RPV-0009(Q)

SHUTDOWN COOLING ADDITIONAL INFORMATION:

Procedures:

  • BC-HV-FO15A RHR LOOP A RET TO RECIRC
  • BC-HV-FO15B RHR LOOP B RET TO RECIRC
  • BC-HV-FO06A RHR PMP A SUCT FROM RECIRC
  • BC-HV-FO06B RHR PMP B SUCT FROM RECIRC Hope Creek Page 2 of 45 Rev. 0

Al IL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 2(J030122 PSEG Internal Use Only HC.OP-AB.RPV-0009(Q)

SHUTDOWN COOLING IMMEDIATE OPERATOR ACTIONS NONE AUTOMATIC ACTIONS T i .

Reactor Pressure > 82 psig The following valves cannot be opened from the Control Room OR their Remote Shutdown controls:

. HV-F008

. HV-F009

  • HV-FO15A
  • HV-FO15B
  • HV-F022
  • HV-F023 Reactor Pressure > 82 psig The following valves will isolate:

OR

  • HV-FO08*

Reactor Level < 12.5" . HV-FOO9*

OR

  • HV-FO15A*

Loss of EITHER RPS Bus

  • HV-FO15B*

AND a HV-F022 RSP Takeover Switches in NORMAL

. HV-F023 RHR Pump in Shutdown Cooling RHR pump trips.

AND Closure of ANY of the following:

  • HV-FOO8

. HV-FOO9

  • Associated HV-F006
  • If GPSM-ooo1 has been performed, these isolations are bypassed.

Page 3 of 45 Rev. 0 Hope Creek I

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 2 0 0 3 012--2hui internal Use Only HC.OP-AB.RPV-0009(Q)

SHUTDOWN COOLING This Page Intentionally Left Blank Hope Creek Page 4 of 45 Rev. 0

ALL ACZrIVE 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 ........................... ..................... 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 0

D. Loss of S/D Cooling AND RCS temp. < 200 F AND RCS temp. is anticipated to reach > 200 F....9 0

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 Removal.........................................................................................................1...................7.................. 17 Hope Creek Page 5 of 45 Rev. 0

ALL ACVIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 200301 2 b2Jui internal use unly HC.OP-AB.RPV-0009(Q)

SHUTDOWN COOLING ADDITIONAL INFORMATION:

Procedures:

  • HC.OP-SO.BB-00102 REACTOR RECIRCULATION SYSTEM OPERATION.

Valves:

  • BC-HV-FO15A RHR LOOP A RET TO RECIRC
  • BC-HV-FO1SB RHR LOOP B RET TO RECIRC
  • BC-HV-F009 SHUTDOWN COOLING INBD ISOLATION FIGURE 1 Total Loss of Heat Removal from Rx Vessel 1000 EFPD of Operations 5.000 4.000 0

U.

3.000 DI 0

0 0

0 c.s 0 2.000 40-E 1.000 0.000 10 100 1000 Time from Rx Shutdown (hours)

Hope Creek Page 6 of 45 Rev. o

ALL ACT1VE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 razky internal use unl HC.OP-AB.RPV-0009(Q)

SHUTDOWN COOLING SUBSEQUENT OPERATOR ACTIONS ,. D .. ! I -

CONDITION ACTION A. Loss of the RHR system providing O0 A. 1 IF below 200OF, Shutdown Cooling THEN PERFORM the following:

a. ESTIMATE time to reach 2000 F lAW Figure 1.
b. IF RCS temperature is expected to rise above 200F, THEN IMPLEMENT Condition D.

U A.2 IF the Shutdown Cooling suction line was Estimated time RCS isolated, will reach 2001F: .: THEN PERFORM the following:

Li

  • PRIOR to establishing the suction flow path from the vessel, FILL & VENT the suction line IAW SO.BC-0002. [CD-891D1 o
  • EVALUATE the need to implement Condition C (Suction line venting may take more than one hour).

O 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 FOSA(B).

o b. RESTART RHR Pump A(B).

C3 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.I PLACE RHR loop A(B) in Shutdown Cooling restore Shutdown Cooling lAW SO.BC-0002.

Time:

C. RHR S/D Cooling CANNOT be 0 C.I 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.

IT/S 3.4.9.1, 3.4.9.21 [3.4.9.1.b, 3.4.9.2.bJ ITIS 3.9.11.1, 3.9.11.21 O C.2 ENSURE forced circulation in the core utilizing Reactor Recirc JAW SO.BB-0002 Time: -OR an alternate method.

Hope Creek Page 7 of 45 Rev. 0

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 200 30 1 22EG Internal Use Only HC.OP-AB.RPV-0009(Q)

SHUTDOWN COOLING ADDITIONAL INFORMATION:

Valves:

  • BB-HV-F001 REACTOR HEAD VENT DRW INBD ISLN
  • BB-HVF1002 REACTOR HEAD VENT DRW OUTBD ISLN TABLE D.2 - REDUNDANT REACTOR VESSEL PRESSURE INDICATIONS NOMENCLATURE RANGE lDESCRIPTION CONTROL ROOM PANEL 10-C-650 PI-5824A 0 - 50 LOW RANGE REACTOR PRESS P1-S824B 0-50.S LOW RANGE REACTOR PRESS PI-R665-C32 0- 1200 REACTOR PRESSURE PR-R623A-B21 0- 1500 PAMS PR-R623BoB21 0- 1500 PAMS PI-3684A 0- 1500 PAMS PI-3684B 0- 1500 PAMS LOWER RELAY ROOM PANEL 10-C-617 1FDPISL-N65SA-,41. 1 - 200 lHPCI TRIP UNIT IFDPISL-N6$8E-E41 00-200 lHPCI TR1P UNIT LOWER RELAY ROOM PANEL 10-C-641 IFDPISL-N658C-E41 0-200 HPCI TRIP UNIT HPCI TRIP UNIT 0

IPDPISL-N658G-E41 0- 200 LOWER RELAY ROOM PANEL 10-C-618 IFCPISL-N658B-E5l 0-200 RCIC TRIP UNIT IFCPISLN658F-E51 0-200 RCIC TRIP UNIT LOWER RELAY ROOM PANEL 10-C-631 IFCPISL-N658D-E51 l 0-200 lRCICTRIP UNIT IFCPISL-N658H-E51 0- 200 RCIC TRIP UNIT Page 8 of 45 Rev. 0 Hope Creek

ALL ACfIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE ACTIV ALL012 ON-THE-SO CHAGES MsUST BE ATTACHED FOR FIELD USE HC.OP-AB.RPV-0009(Q) 20030122 SUBEQi Internal Use Only SHUTDOWN COOLING SUBSEQUENT OPERATOR ACTKIONS

4. ,

CONDITION ACTION D. Loss of SID Cooling a D.1 EVALUATE the need to establish Primary AND AND RCS temp. < 2000 F Secondary Containment.

AND U D.2 EVALUATE the following for indications of RCS temp. is anticipated to reach entry into OPCON 3:

> 200 0F.

[T/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 10C650A) or, the HPCI and RCIC trip units.

El

  • An increase in Reactor Head Vent temperature could be indicative of the onset or verification of the presence of boiling in the vessel. This temperature is monitored by TE-N064 (when BB-HY-FOO1 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 9of 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
  • I-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 E. Forced Circulation CANNOT be El NOTE 1**

established using preferred RHR loops 1 E.1 MONITOR temperatures lAW DL-0026 or Reactor Recirculation. A ttah entu3s0 ICD-693A, CD-178A, CD-973B, Attachment 3s.

CD-100A, CD-076B, CD-065X3

  • CAUTION 1
  • Time: 0 E.2 MAINTAIN RPV LVL > 80 inches, BUT < 90 inches.

LI E.3 IF RPV LVL reaches 90 inches, THEN CLOSE the MSIV's.

E3 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:

O

  • RWCU (Subsequent F) [CD-900E]

O * "C" RIHR (Attachment 1)

O * "D" RHR (Attachment 2) 1O

  • CONDENSATE TRANSFER (Subsequent G)

O E.6 IF the vessel head is removed, AND the Reactor Cavity is flooded, THEN maximize Fuel Pool Cooling:

O

  • ENSURE two Fuel Pool Cooling pumps are in service. (EC) 13
  • ENSURE SACS flow aligned through BOTH Fuel Pool Cooling heat exchangers.

F. RWCU is required for Alternate Decay 0 F.1 ENSURE RWCU is in service. (BG)

Heat Removal. L F.2 FULLY OPEN ED-V035.

O F.3 IF necessary, Time:THEN Bypass the Regenerative heat exchanger to maximize decay heat removal.

(BG)

V Hope Creek Page 11 of 45 Rev. 0 II

ALL ACFIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 200301223EG Internal Use Only HC.OP-AB.RPV-0009(Q)

SHUTDOWN COOLING ADDITIONAL INFORMATION:

Procedures:

  • HC.OP-SO.AP-0001(Q) CONDENSATE TRANSFER SYSTEM OPERATION

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' RHR I-AP-V047 (Rn. 4328) N/A BC-.HV-FO17C

'B' RH-IR I-AP-V056 (Rm 4322B) N/A BE-HV-FO17B

'D' RHR I-AP-VO59 (Rm. 4322B) N/A BE-HV-FO17D

'A' CORE SPRAY 1-AP-VO41 (Rm. 4331) BE-HV-FO04A BE-HV-FOO5A

'B' CORE SPRAY 1-AP-V062 (Rm. 4322B) BE-HV-FO04B BE-HV-FOO5B .

HPCI 1-AP-V038 (Rm. 4331) N/A BJ-HV-8278 RCIC I-AP-V052 (Rm. 4315) N/A BD-H4V-F013 Hope Creek Page 12 of 45 Rev. 0

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Ony HC.OP-AB.RPV-0009(Q)

SHUTDOWN COOLING SUBSEQUENT OPERATOR ACTIONS (continued).

CONDITION ACTION G. Condensate Transfer is required for U 0.1 ENSURE Condensate Transfer is in-service.

S/D cooling. (AP)

U G.2 ENSURE RWCU is in-service. (B1G)

Time: El G.3 REFER to Table G and align one of the

      • Continued on Page 15 *** feed the vessel from following flowpathsastofollows:

condensate transfer O G.4 IF an RHR injection line will be used, THEN PERFORM the following:

O a. OPEN the desired loops INJECTION VALVE listed in Table 0.

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:

O a. CLOSE the desired loops OUTBD ISOL VLV listed in Table G.

O b. OPEN the associated INJECTION VALVE listed in Table G.

U c. RE-OPEN the OUTBD ISOL VLV.

O d. THROTTLE OPEN the associated CS XFR DISCH ISLN listed in Table 0 to obtain the desired injection rate.

O

  • Continued on Page 15 ***

Hope Creek Page 13 of 45 Rev. 0

I ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 2003012-25LkSA 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:

  • AE-HV-F032B FW INLET CHECK VALVE TABLE G: Condensate Transfer Injection Flowpaths SYSTEM CS XFR DISCH ISLN OUTBD ISOL VLV INJECTION VALVE

'A' RIR 1-AP-V044 (Rra. 4328) N/A BC-HV-FO17A

'C' RUR 1-AP-V047 (Rm. 4328) N/A BC-HV-FO17C 0

'B' IH I-AP-V056 (Rm 4322B) N/A BE-HV-FO17B

'D'RHR I-AP-V059 (Rm. 4322B) N/A BE-HV-FO17D

'A' CORE SPRAY l1-AP-V041 (Rm. 4331) BE-HV-FO04A BE-HV-FOO5A

'B' CORE SPRAY 1-AP-V062 (Rm. 4322B) BE-HV-FO04B 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 ACN-VE 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 (cpntinued)

CONDITION ACTION

      • Continued from Page 13 *** la Continued from Page 13
  • G. Condensate Transfer is required for El G.6 IF the RCIC injection line will be used, SID cooling. THEN PERFORM the following:

LI **NOTE 2**

U a. VERIFY reactor pressure.< 64 psig C] b. ENSURE the HV-F032B is open.

Ca c. PLACE the NORM/BYPASS keylock switch for the HV-F013 in BYPASS.

C] d. OPEN the HV-F013.

C] e. THROTTLE OPEN the I -AP-V052 to obtain the desired injection rate.

C] G.7 IF the HPCI injection line will be used, THEN PERFORM the following:

C* NOTE 2**

LI a. VERIFYreactorpressure< 100psig C] b. ENSURE the HV-F032A is open.

C] c. PLACE the NORM/BYPASS keylock switch for the HV-8278 in BYPASS.

C d. OPEN the HV-8278.

LI e. THROTTLE OPEN the l-AP-V038 to obtain the desired injection rate.

C] G.8 MAINTAIN RPV LVL using RWCU Blowdown. (BG)

I II Hope Creek Page 15 of 45 Rev. 0

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SHUTDOWN COOLING NOTES:

3. -The goal of the following steps is to establish water flow through two SRV\s with at least a 50# d/p. It is desirable to maintain less than a 160# d/p 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

.0

ALL ACTiVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE ALL ACr-.IVE 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 ACT¶IQNS (continued) 5 , , .

0 CONDITION ACTION I H. RPV Temperature and Pressure ** NOTE 3**

CANNOT be maintained using Normal [ H. I INITIATE Suppression Pool Cooling LAW OR Alternate Decay Heat Removal. AB-000l.

[CD-973B, CD-11OE, CD-950B1

[] H.2 ENSURE the following Valves are closed.

      • Continued on Page 19 ***
  • RPV Head Vents.

Time: z0

  • HPCI Steam Isolations.

.0 L0I

  • RCIC Steam Isolations.

H.3 PLACE the control switches for two SRV's to OPEN (SRVs will not open until a 50# d/p is established).

o H.4 SLOWLY RAISE RPV water level to establish a flow path through the OPEN SRV's.

o H.5 SECURE all injection into the RPV except from CRD.

o H.6 START one Core Spray Subsystem or one LPCI Pump with suction from the Suppression Pool.

C H.7 RAISE Core Spray OR LPCI injection into the RPV to maximum.

U 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.

LI H.9 IF RPV pressure stabilizes at more than 160 psig above Suppression Chamber pressure, THEN OPEN another SRV.

El *** Continued on page 19

  • go Page 17 of 45 Rev. 0 Hope Creek

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122SEG Internal Use Only HC.OP-AB.RPV-0009(Q)

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

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SHUTDOWN COOLING SUBSEQUENT OPERATOR ACTIONS 0 CONDITION ACTION

      • Continued from Page 17 *** L Continued from Page 17 ***

H. RPV Temperature and Pressure -

  • CAUTION 2
  • CANNOT be maintained using Normal [3 H.10 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:

L

  • The cooldown rate drops below 90 'F/hr.

O

  • RPV pressure decreases to within 50 psig of Suppression Chamber pressure.

0 H. I I CONTROL Suppression Pool temperature to maintain RPV water temperature above 79 0F.

IT/S 3A.6.1.d Hope Creek Page 19 of 45 Rev. 0

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030o122SEG Internal Use Only HC.OP-AB.RPV-0009(Q)

SHUTDOWN COOLING 0

This Page Intentionally Left Blank Hope Creek Page 20 of 45 Rev. 0

ALL AC-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 1 of 6)

NOTE 1.0 Operation of the C to A 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 C to A Cross-tie [CD-609G]

1.1 ENSURE the AP System is available providing keepfill for all A Loop ECCS Systems required for operability. (1-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 LAW NCNA-AP.ZZ-0015(Q).

1.4 CLOSE the following valves:

  • HV-FO04C RHR PMP C SUPP POOL SUCT MOV 1.5 TAG the following IAW NC.NA-AP.ZZ-001 5(Q):

HV-FO04A RHR PMP A SUPP POOL SUCT MOV (52-21203 1)

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:

HV-FO07A RHR PMP A MIN FL VLV 40

Hope Creek Page 21 of 45 Rev. 0

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SHUTDOWN COOLING 0

This Page Intentionally Left Blank Hope Creek Page 22 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 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:

1.8 CLOSE AND TAG the following valves:

  • HV-F027A RHR LOOP A SUPP CHAMBER SPRAY HDR ISLN MOV (52-212083) 1.9 Fully OPEN IBC-V133 R1IR Pmp C Suet Frm Recir Loop B (Rm 4227E)

AND TAG in the open position IAW NC.NA-AP.ZZ-001 5(Q).

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 1AW HC.OP-SO.BC-0002(Q),

Decay Heat Removal Operation.

1.12 ENSURE the following valves are open:

1.13 UNLOCK AND OPEN IBC-V571 RHR Cross-Tie Isolation Valve for C Loop BC-HV-11673. (Rm4ll4A) 1.14 OPEN the following valves until a solid stream of water issues, THEN CLOSE (Local):

  • lBC-V578 AND IBC-V579 RHR Vent Valves (Rm. 4113A)
  • IBC-V580 AND lBC-V581 RHR Vent Valves (Rm. 4114A)

Hope Creek Page 23 of 45 Rev. 0

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SHUTDOWN COOLING This Page Intentionally Left Blank

~>Hope Creekc 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) 0 1.15 OPEN 1BC-V570 RHR Cross-Tie Isolation Valve for A Loop (Rm. 4113A)

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. Inthe cross-tie mode, C RHR Purnp will not be automatically protected against the loss of suction from the RPV.

1.16 OBTAIN key for the I-BC-HS- 11496 Keylock Switch from Work Control key cabinet.

1.17 At Panel 10C641 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-FOO9 close (e.g., on RPV Low Level 3 signal), then immediately STOP the C RHR Pump AND TAKE corrective action.

1.19 IF HV-F015A RHR LOOP A RET TO RECIRC LOOP A ISLN MOV does NOT open immediately to establish flow, THEN SECURE the RHR Pump.

Hope Creek Page 25 of 45 Rev. 0

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.xniernai use tin1W HC.OP-AB.RPV-0009(Q)

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 RV-FO15A 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-FO15A RHR LOOP A RET TO RECIRC LOOP A ISLN MOV until FI-R603C LOOP C FLOW indicates 10,000 gpm.

V Page 27 of 45 Rev. 0 Hope Creek

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SHUTDOWN COOLING Ts P This Page Intentionally Left Blank

"~ Hope Creek Page 28 of 45 Rev. 0

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE HCOP-ABRV009(Q) 20030122 PSEG Internal Use Only H.PA.P-09Q SHUTDOWN COOLING ATTACHMENT I 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-FOI 5A RHR LOOP A RET TO RECIRC LOOP A ISLN MOV.

2.2 WHEN the HV-FO15A RHRLOOPARETTORECIRC 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 frons l-BC-HS-1 1496 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 lBC-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-11673. (Rm4114A) 4114C) 2.6 RELEASE tags from IBC-V203 ECCS Jock Pmp C Suct Vlv (Rm.

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 (Rmr 4227E) 2.9 CLOSE AND LOCK IBC-V133 RHR Pmp C Suc Frm Recir Loop B (Rm 4227E) 2.10 CLOSE the following valves:

ALL AC71VE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 200301f22L"-- mnernal Use Unin HC.OP-AB.RPV-0009(Q)

SHUTDOWN COOLING This Page Intentionally Left Blank 0

Hope Creek Page 30 of 45 Rev. 0

ALL AC"IVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE HC.OP-ABRV0009(Q) 20030122 rainAJ Internat use umny H.PAP-09Q 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.

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-O0O9(Q)

SHUTDOWN COOLING ATTACHMENT 2 ALTERNATE DECAY HEAT REMOVAL USING D TO B CROSS-TIE (Page I of 7) 0 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 IAW NC.NA-AP.ZZ-O01 5(Q); Safety Tagging Program.

(Breaker 52-242074) 1.3 CLOSE 1BC-V261 ECCS Jockey Pump D Suction Valve AND TAG IAW NC.NA-AP.ZZ-0015(Q).

1.4 CLOSE the following valves:

  • HV-FO04D RHIR PMP D SUPP POOL SUCT MOV 1.5 TAG the following 1AW NC.NA-AP.ZZ-0015(Q):

0 HV-F004B RHR PMP B SUPP POOL SUCT MOV Breaker 52-222031 S HV-FO04D RRHR PMP D SUPP POOL SUCT MOV Breaker 52-242031 I

Page 33 of 45 Rev. 0 Hope Creek

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SHUTDOWN COOLING S

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 Only 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 B(D) MIN FL MOV will Manual or automatic opening of HV-FO07B(D) RHR PMP drain the Reactor Vessel to the Suppression Pool.

1.6 ENSURE the following valves are closed:

  • HV-FO07B RHR PUMP B MIN FLOW VLV
  • HV-FO07D RHR PUMP D MN FLOW VLV.

1.7 VERIFY the following LPCI Injection Valves are closed, valves do THEN DE-ENERGIZE AND TAG their power sources to ensure these not open if a LPCI signal is received during cross-tie operating mode:

  • HV-FO17D RHR LOOP D LPCI INJ MOV (52-242052) 1.8 CLOSE AND TAG the following valves:
  • HV-FO21B RHRLOOPBSPRAYISLNMOV (52-222062)
  • HV-F027B RHR LOOP B SUPP CHAMBER SPRAY HDR ISLN MOV (52-222083) 4227D; 1.9 FULLY OPEN 1BC-V043 RHR Pmp D Suc Frn Recir Loop B (Rm.

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.

1-f AC Rev. 0 Hope Creek ragev 0o uJI -r

ALL ACT-VE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 2OO3O122'- Sab f HC.OP-AH.RPV-0009(Q)

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 1 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 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 0 HV-FO9 SHUTDOWN COOLING INBD ISLN MOV.

1.13 UNLOCK AND OPEN IBC-V601 RHR Crosstie Iso Vlv B LOOP BC-HV-11680 MOV (Rm. 4107A) 1.14 OPEN the following valves until a solid stream of water issues, THEN CLOSE (Local).

IBC-V610 and IBC-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 lBC-V608 and lBC-V609 RHR B&D Loop X-Tie Vent Vlvs until a solid stream of water issues, THEN CLOSE (Rm. 4107A) 1.17 OPEN IBC-V600 RHR X-Tie iso Vlv Loops B&D. (Rm. 4107A)

I Page 37 of 45 Rev. 0 Hope Creek

ALL ACTiVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 2003GQ12Y-'31' lnrernal Use Unly HC.OP-AB.RPV-0009(Q)

SHUTDOWN COOLING This Page Intentionally Left Blank Hope Creek Page 38 of 45 Rev. O

ON-THE-' SPOT CHANGES MUST BE ATTACHE.D FOR FIELD USE HCOPABRPVO009(Q HPA.P-O9Q PSEG I unternal Use Only SHUTDOWN COOLING ATTACHMENT 2 B CROSS-TIE ALTERNATE DECAY HEAT REMOVAL USING D TO (Page 4 of 7)

NOTE 1.18 the pump is A The interlock override will allow D RHR Pump to operate when aligned to the alternate suction from the RPV, when and if required.

against E3. Inthe cross-tie mode, D RHR Pump will not be automatically protected the loss of suction from the RPV.

Control 1.18 OBTAIN key to the I-BC-HS-1 1682 Keylock Switch from Work key cabinet.

1.19 PERFORM the.following at Panel 10C640:

A. INSERT the key in the 1-BC-HS-1 1682 Keylock Switch.

the B. OVERRIDE the HV-FO04D Valve/Pump D Interlock using 1-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 HV-F009 close (e.g., on RPV Low Level 3 signal), then immediately STOP the D RHR Pump AND TAKE corrective action.

MOV does 1.21 IF HV-FO15B RHR LOOP B RET TO RECIRC LOOP B ISLN not open immediately to establish flow, THEN SECURE the RHR Pump.

-r A& Rev.O0 Hope Creek rage ay 0I 15

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SHUTDOWN COOLING This Page Intentionally Left Blank 0

0 Hope Creek Page 40 of 45 Rev. 0

ALL ACTAVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE IIC.OP-AB.RPV-0009(Q) 2003&122 PSEG Internal Use OnlY 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-FO07B(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.

. 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.

I Page 41 of 45 Rev. 0 Hope Creek

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SHUTDOWN COOLING This Page Intentionally Left Blank

,-' Hope Creek Page 42 of 45 Rev. 0

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SHUTDOWN COOLING ATTACHMENT 2 ALTERNATE DECAY HEAT REMOVAL USING D TO B CROSS-TIE (Page 6 of 7) 2.0 Securing Alternate Decay Heat Removal When D to B Cross-tie was used.

2.1 CLOSE HV-FO15B RHR LOOP B RET TO RECIRC LOOP B ISLN MOV.

2.2 WHEN the HV-F015B RHR LOOP B RET TO RECIRC LOOP B ISLN MOV is closed, THEN STOP the D RHR Pump DP202.

2.3 REMOVE 1-BC-HS-11682 Keylock Switch from the OVERRIDE position.

A. REMOVE the key from 1-BC-HS-11682 Keylock Switch AND RETURN to the Work Control key cabinet.

B. LOG in NSS Log the position of the Keylock Switch.

2.4 CLOSE 1BC-V600 RHR X-Tie Iso Vlv Loops B&D. (Rm. 4107A) 1680 2.5 CLOSE AND LOCK lBC-V601 RHR Crosstie Iso Vlv B LOOP BC-HV-1 MOV (Rm. 4107A) 2.6 RELEASE tags from 1BC-V261 ECCS Jockey Pmp D Suct Vlv (Rm. 4107D)

AND OPEN valve.

2.7 RELEASE tags from Jockey Pump DP228.

2.8 RELEASE tags from IBC-V043 RHR Pmp D Suc Frm Recir Loop B.

.(Rm. 4227D; Az 150 above catwalk) 2.9 CLOSE AND LOCK IBC-V043 RHR Pmp D Suc Frm Recir Loop B.

(Rm. 4227D; Az 150 above catwalk) 2.10 CLOSE the following valves:

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 200304i22 kl"tZ R111ILt RIMEJ uSc 'SILly HC.OP-AB.RPV-0009(Q)

SHUTDOWN COOLING This Page Intentionally Left Blank

" Hope Creek Page 44 of 45 Rev. 0

LL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE HC.OP-AB.RV-0009(Q)

I 0030122 A LYJLZ'J AUIVI "us Ubc 'lily H.PA.P-09Q 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:

  • HV-F027B RHR LOOP B SUPP CHAMBER SPRAY HDR ISLN MOV 2.12 RELEASE tags from HV-FO04B AND HV-FO04D RHR PMP SUPP POOL SUCT MOV.

2.13 ALIGN system as plant conditions require.

Hope Creek Page 45 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 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 I and 2 to 'Alternate Decay Heat Removal" IAW SQR Reviewer comments.

The following list of Non-Editorial changes has been made 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 1AW 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 1AW Condition 'H' was raised from 140 to 160 psi.

Hope Creek Page 1 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: 234000 A2.03 JPM NUMBER: 2003-NRC-S3 ALTERNATE PATH: E KIA NUMBER: 234000 A2.03 APPLICABILITY: IMPORTANCE FACTOR: 2.8 3.1 EO W RO W SRO W3 LSRO W RO SRO EVALUATION SETTING/METHOD: REFUELING PLATFORM - PERFORM I SIMULATE

REFERENCES:

HC.OP-SO.KE-0001 Rev. 28; HC.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:

N/A BARGAINING UNIT TRAINING SUPERVISOR OPERATIONS MANAGER 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: FISAT F1 UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Nuclear Common Page 1 Rev. 0 2003-NRC-LSRO-S3

NC.TQ-WB.ZZ-0310(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM: 234000 Fuel Handling Equipment TASK: Bent Mast lAW HC.OP-SO.KE-0001 (Q) Attachment 2 (Alternate Path)

TASK 234000 A2.03 INITIAL CONDITIONS:

  • You are the Refueling Bridge operator.
  • The Reactor is in Operational Condition 4 preparing for refueling.

1

  • The Refuel Platform is in a standby lineup, powered up, and warmed up > /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 #2.
  • You are to continue HC.OP-SO.KE-0001 at step 5.8.14.

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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( ( NC.Tc .ZZ-031 0(Z)

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) 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 5.8.14 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 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) S/U 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 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.

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( NC.Ti .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)

I I-STEP COMMENTS

(*Denotes a Critical Ste STANDARD EVAL (Required for UNSAT SIU evaluation)

I -r START TIME: Operator uses the PLATFORM AND TROLLEY control operators to maneuver USE the Refuel Platform AND Trolley the Fuel Grapple using position indication Position Controls AND Position Indicating cameras so that it is positioned over Fuel 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."

5.8.15 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."

  • 5.8.16 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.Tc~ .ZZ-0310(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 lll___(#Denotes a Sequential Step) ll__ S/U evaluation)
  • 5.8.17 LOWER the Fuel Grapple to approximately Operator lowers the Fuel Grapple using the one foot above the fuel assembly/blade Fuel Grapple Hoist control in the LOWER guide to be removed by using the Fuel position.

Grapple Hoist control in the LOWER position $ Examiner Cue: "The grapple is AND OBSERVE the GRAPPLE NORMAL lowering; the GRAPPLE NORMAL UP UP light off. light is off."

Examiner Cue: Wait 10 seconds and cue... "Stop Hoist Travel" Examiner Cue: After the hoist is stopped...

"The grapple has stopped suddenly.

The SLACK CABLE light is lit with the hoist at position 105. The load cell is reading 25 pounds."

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( NC.T4$ ZZ-0310(Z)

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 lll_(#Denotes a Sequential Step) ll_l S/U evaluation)

Operator notifies Refueling SRO or CRSIOS.

Operator recognizes 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.

If the operator does not recognize symptoms of a bent mast or diagnoses problem as a load cell malfunction, then Cue: "Carry out actions for a bent mast."

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 Nuclear Common Page 7 REV.: 0 2003-NRC-LSRO-S3

(

NC.T .ZZ-0310(Z).'.

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 l (#Denotes a Sequential Step) l__ __ SIU evaluation)

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.

Operator reads step 2.0 IF while lowering the mast, an Operator raises main fuel hoist to clear unexpected slack cable or pre-mature SLACK CABLE light using the Fuel Grapple weight transfer occurs, stop lowering, raise Hoist control in the RAISE position the load to clear the slack cable (if one exists), and notify the cognizant Refuel SRO Examiner Cue: SLACK CABLE light Is or OS/CRS before attempting any corrective action.

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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NC.TQ-WB.ZZ-031 0(Z)

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 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 lAW Move Sheet Step #2.
  • You are to continue HC.OP-SO.KE-0001 at step 5.8.14.

INITIATING CUE:

Place the bundle in its designated storage location IAW the move sheet step #2.

Nuclear Common Page 9 Rev. 0

AJ!.LACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE (SO3) 122 PSEG Internal Use Only Page 1 of 1 PSEG NUCLEAR L.L.C.

HOPE CREEK GENERATING STATION HC.OP-SO.KE-S001(Q) - Rev. 28 REFUELING PLATFORM AND FUEL GRAPPLE OPERATION USE CATEGORY: II A. Biennial Review performed Yes _ No _ N/A /

B. Change Package(s) and Affected Document Number(s) incorporated into this revision.

  • CP No. CP Rev. No. AD No. AD Rev. No. o_ None /

C. OTSC(s) incorporated into this revision:

  • OTSC No(s) or None Vf REVISION

SUMMARY

1. This following change is part of the Abnormal Upgrade Project. The following change involves renaming of the applicable abnormal and is editorial in nature:
  • Changed HC.OP-AB3.ZZ-0101(,Q) to HC.OP-AB.CONT-0005(Q) on pages 20 and 78.

L1~

IMPLEMENTATION REQUIREMENTS Effective date Implementation of HC.OP-AB.CONT-0005(Q)

APPROVED: _ - -- -

Manager - Hope Opterk Operations Date II V

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 23030122 PSEG Internal Use Only 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 .. 22 4.0 EQUIPMENT REQUIRED .. 28 5.0 PROCEDURE .. 29 5.1 Refuel Platform Start-up and Shutdown ............................................ 29 5.2 Fuel Transfer - Reactor Core to Spent Fuel Storage Pool ........................ 31 5.3 Fuel Transfer - Spent Fuel Storage Pool to Reactor Core ........................ 37 5.4 Blade Guide Transfer - Spent Fuel Storage Pool to Reactor Core ........... 43 5.5 Blade Guide Transfer - Reactor Core to Spent Fuel Storage Pool ........... 46 5.6 Fuel Movement - Within Reactor Vessel ............................................. 50 5.7 Blade Guide Movement - Within Reactor Vessel .................................... 54 5.8 Fuel/Blade Guide Movement - Within Spent Fuel Storage Pool (other than Refuel Mode) .......................... 59 5.9 Auxiliary Hoist Tool Installation .......................... 64

6.0 REFERENCES

.. 77 Hope Creek Page 1 of 84 Rev. 28

4 ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.KE-0001(Q)

REFUELING PLATFORM AND FUEL GRAPPLE OPERATION TABLE OF CONTENTS Section Title Page ATTACHMENTS Attachment 1 ANALYZED LOADS Permitted Over IRRADIATED FUEL Not Requiring SECONDARY CONTAINMENT INTEGRITY ............. 79 Attachment 2 Instructions for Manually Lowering a Fuel Bundle ........................... 0 0......

Attachment 3 Refueling Platform Interlocks .............. ............................. 84 I

V Hope Creek Page 2 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 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 1AW T.S. 3.6.5.1 .b.

2.2.3 The Fuel Grapple Hoist shall be verified operable IAW T.S. 3.9.6 by performing procedure HC.OP-ST.KE-0001(Q), Refuel Interlock Operability Functional Test - Section 5.4.

Hope Creek Page 3 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal 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 LAW 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 /> IAW T.S. 3.9.4.

2.2.11 Establish and maintain direct communication between the Control Room and Refueling Floor personnel IAW T.S. 3.9.5.

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 lAW 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 84 Rev. 28 II

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 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-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.

2.2.16 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-000 1(Q).

2.2.19 All personnel that will operate the Refuel Platform and Fuel Grapple have completed training and are qualified. [CD-124B]

Hope Creek Page 5 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 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 IAW 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 84 Rev. 28 I

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 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 LAW T.S. 3.6.5.2.

2.3.2 Reactor Building integrity shall be maintained IAW T.S. 3.6.5. .b.

2.3.3 The Fuel Grapple Hoist shall be verified operable IAW T.S. 3.9.6 by performing procedure HC.OP-ST.KE-000l(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 JAW T.S. 3.9.9.

2.3.5 The Filtration, Recirculation and Ventilation System shall be operable LAW T.S. 3.6.5.3.

2.3.6 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]

2.3.7 The Reactor Mode Switch shall be operable AND locked in the REFUEL OR the SHUTDOWN position JAW 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 /> IAW T.S. 3.9.4. _

2.3.11 Establish and maintain direct communication between the Control Room and Refueling Floor personnel 1AW T.S. 3.9.5.

Hope Creek Page 7 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 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 Platfonm.

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-000I(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 perfonned within 30 days of starting fuel handling operations.

Hope Creek Page 8 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 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 Sbipping 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 LAW 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-124BJ 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-069A]

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 LAW 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 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 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 T.S. 3.9.6 by performing procedure HC.OP-ST.KE-000 (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-000l(Q); Refuel Interlock Operability Test must be performed prior to CORE ALTERATIONS IAW T.S. 3.9.1.

ICD-182C1 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 /> IAW T.S. 3.9.4.

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 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 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. JCD-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.

2.4.9 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-0001(Q).

2.4.11 All personnel that will operate the Refuel Platform and Fuel Grapple have completed training and are qualified. fCD-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-069AJ 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 }), 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.

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ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 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 1AW T.S. 3.9.6 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 1AW T.S. 3.9.9.

2.5.3 Procedure HC.OP-ST.KE-0001(Q); Refuel Interlock Operability Test must be performed prior to CORE ALTERATIONS 1AW T.S. 3.9.1. [CD-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 /> LAW T.S. 3.9.4.

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.

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ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 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-396Y1 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.

2.5.9 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-000 1(Q).

2.5.11 All personnel that will operate the Refuel Platform and Fuel Grapple have completed training and are qualified. [CD-124BI Hope Creek Page 13 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OPSO.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-069AJ 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 lAW 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 T.S. 3.9.6 by performing procedure HC.OP-ST.KE-OOI(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 lAW 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]

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ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030 122 PSEC 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 JAW 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 LAW 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 minimum of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> LAW T.S. 3.9.4.

2.6.11 Establish and maintain direct communication between the Control Room and Refueling Floor personnel IAW T.S. 3.9.5.

2.6.12 At least 22 feet 2 inches of water shall be maintained over the top of the Reactor Pressure Vessel flange 1AW 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.

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ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 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-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.

2.6.16 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 lAW HC.RE-FR.ZZ-0001(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 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 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 T.S. 3.9.6 by performing procedure HC.OP-ST.KE-000I(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-000l(Q); Refuel Interlock Operability Test must be performed prior to CORE ALTERATIONS LAW 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 /> IAW T.S. 3.9.4.

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ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 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 lAW 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 lAW HC.RE-FR.ZZ-0001 (Q).

Hope Creek Page 18 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only ]C.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-124BJ 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. JCD-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) 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.l.b.

2.8.3 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. [CD-178H]

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.

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ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 2.8.5 The Filtration, Recirculation and Ventilation System shall be operable JAW 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-000l(Q), Refuel Interlock Operability Functional Test - Section 5.4); has been completed to demonstrate Refuel Platform load cell setpoint IAW T.S. 3.9.6. [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 lAW HC.RE-FR.ZZ-000l(Q).

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ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.KE-O001(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 Position indication cameras for the Main Hoist are selected for display.

2.8.18 Spent Fuel Pool gates are verified installed per HC.MD-FR.KE-0013(Q),

Refuel Floor-Shield and Pool Plugs Removal and Replacement.

2.8.19 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.

2.8.20 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.

2.8.21 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.

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ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.KE-OOO1(Q) 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. (T.S. 3.9.6) 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-182CJ 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.

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-719A]

3.1.5 DO NOT remove a blade guide from its Reactor Core location IF the respective control rod will be left unsupported.

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ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Intemal Use Only HC.OP-SO.KE-00G1(Q) 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 59), 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-619G1 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. [CD-673D1 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.

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ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.KE-O001(Q) 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.

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.

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ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 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 IAW HC.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.

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.

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ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only i RC.OP-SO.KE-0001(Q) 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-673D1 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 amanner 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. [CD-365D]

3.2.14 ENSURE the Refuel Bridge handrails remain in place whenever the camera cart is on the bridge. ICT)-711F1 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.

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 9601280761 Hope Creek Page 26 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 3.2.18 IF alternate RHR-FPCC assist mode i s in service, up to 9000 gpm may flow through the spent fuel pool 1to 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 beenecessary to reduce bridge speed, when passing through the gate, to con trol vertical swing on the mast.

3.2.19 The refueling mast should not be permitted to swing against the trolleyv.

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 27 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.KE-0001(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
  • 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
  • Main Hoist Loaded 3.3.5 Load Float function is disconnected per ECA 4HE-002 1.

3.3.6 Reference Attachment 3 for Interlock drawing.

4.0 EQUIPMENT REQUIRED

  • Thread Sealant Loctite 2432 or 5772.
  • Calibrated M&TE Torque Wrench (25 - 30 ft-lbs) for a 3/4" nut.

~< Hope Creek Page 28 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 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 perforrned 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.

- I 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.

Continued next page Hope Creek Page 29 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 5.1.2 (continued)

D. PRESS the ON pushbutton for each of the 5 position indication cameras (2 cameras overhead behind Trolley Cab, 3 cameras on the West End Truck ground level).

E. PLACE the position indication CRTs to the ON position in the Trolley Cab.

F. PLACE each of the 3 Digital Position Readout power supply toggle switches to the ON position in the Trolley Cab. West side.

NOTE 5.1.3 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).

5.1.3 Refuel Platform Shutdown/Standby Instructions A. PRESS the Refuel Platform STOP pushbutton AND VERIFY the red STOP pushbutton light is off.

B. PLACE the Air Compressor Disconnect Switch is in the OPEN position at the West end of the Refuel Platform.

C. ENSURE the Main Power Disconnect Switch AND the Monorail Hoist Disconnect Switch remain in the CLOSED position until maintenance is to be performed.

D. PRESS the OFF pushbutton for each of the 5 position indication cameras (2 cameras overhead behind Trolley Cab, 3 cameras on the West End Truck ground level).

E. PLACE the position indication CRTs to the OFF position in the Trolley Cab.

F. PLACE each of the 3 Digital Position Readout power supply toggle switches to the OFF position In the Trolley Cab. West side.

Hope Creek Page 30 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.KE-OOO1(Q) 5.2 Fuel Transfer - Reactor Core to Spent Fuel Storage Pool 5.2.1 ENSURE tat 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. ICD-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 31 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 5.2.10 PLACE the GRAPPLE ENGAGE/LEASE 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. ICD-736D1 C. OBSERVE the load cell indicator to ensure the assembly has been grappled.

D. Visually VERIFY assembly is being lifted.

V Hope Creek Page 32 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 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, CO-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 T.S. 3.9.6.

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 33 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only 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-612X1 I

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 34 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.KE-0001(Q)

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-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]

5.2.20 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-736D1 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-736D1 Hope Creek Page 35 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 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. [CD-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-396Y]

5.2.26 INITIAL 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 36 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 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 37 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 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-736D1)

B. OBSERVE the HOIST LOADED light is on. [CD-736D1 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 38 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.KE-OOO1(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-069A3 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 T.S. 3.9.6.

5.3.12 WHEN the Fuel Assembly has reached its upper limit of travel THEN OBSERVE:

A. GRAPPLE NORMAL UP light on. [CD-736DI B. Fuel Grapple upward motion automatically stops.

Hope Creek Page 39 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only 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.

I I 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 Platform 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 40 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 HC.OP-SO.KE-OOO1(Q)

PSEG Internal Use Only 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-123E, CD-736D, CD-182C]

B. DO NOT reposition the Refuel Platform or Trolley while the Fuel Assembly is grappled and not fully withdrawn fromithe 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. NOTIEFY 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 Ibs) 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 41 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only 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. [CD-442A]

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 42 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 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 JAW 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-736D1 H~ope Creek Page 43 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.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-396Y1 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 44 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 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 Plafform 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 ibs) 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 45 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030 122 PSEG Internal Use Only 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-442AJ 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. [CD-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 46 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.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.

Hope Creek Page 47 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.KE-0001(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-123EJ B. DO NOT reposition the Refuel Plafform 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 WHVEN 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.

Hope Clreek Page 48 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.KE-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.

x,-

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-442A]

D. ENSURE that hose and cable reels are taking up slack by observing air hoses remain taught within the Grapple.

Hope Creek Page 49 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SOJCE-0001(Q) 5.5.24 RAISE the Fuel Grapple fully to avoid collision with any underwater obstructions. [CD-396YJ 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 1AW 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.

Hope Creek Page 50 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 al Use Only PSEG Internm 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-739F]

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. ICD-736D1 C. OBSERVE the Load Cell Indicator to ensure the assembly has been grappled.

D. Visually VERIFY assembly is being lifted.

Hope Creek Page 51 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 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]

I 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).

' Hope Creek Page 52 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 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. ICD-736D]

Hope Creek Page 53 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 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. [CD-736D]

B. OBSERVE the HOIST LOADED light remains off. [CD-736DJ]

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 fuilly 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 LAW 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.

Hope Creeks Page 54 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.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.

Hope Creek Page 55 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.KE-0001(Q) lCAUTION 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 56 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 5.7.16 ROTATE the Fuel Grapple AND attached blade guide in direct a lignment with the Reactor Core location AND orientation listed on the Fuel Mmovement Sheet(s).

CAUTION 5.7.17 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.

5.7.17 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 Ibs) 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.

Hope Creek Page 57 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SOXKE-0001(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. [CD442A]

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 fiully 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.

Hope Creek Page 58 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 5.8 Fuel/Blade Guide Movement - Within Spent Fuel Storage Pool (other than Refuel Mode)

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 as the location where a fuel/blade guide assembly is initially grappled and "target' 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.

5.8.1 ENSURE that all prerequisites have been satisfied LAW Section 2.8 of this procedure.

5.8.2 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).

5.8.3 ENSURE the Fuel Grapple is at the correct Fuel Pool Coordinates.

(REFER TO Note 5.8) 5.8.4 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.

Hope Creek Page 59 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 5.8.5 IF possible WHEN fuel is being moved, SRO should visually ENSURE correct serial number of Fuel Assembly.

(REFER TO Note 5.8) 5.8.6 ROTATE the Fuel Grapple so that the grapple hooks are in line with the fuel assembly/blade guide handle.

5.8.7 PLACE the GRAPPLE ENGAGE/RELEASE Switch to the RELEASE position to ensure the Fuel Grapple hooks are open, OBSERVE the ENGAGE light off.

5.8.8 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-739FJ 5.8.9 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]

5.8.10 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 Continued next page Hope Creek Page 60 of 84 Rev. 28

IALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED 20030122 FOR FIELD USE PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 5.8.10 (continued)

C. OBSERVE the Load Cell Indicator to ensure the assembly has been grappled.

D. Visually VERIFY assembly/blade guide is being lifted.

CAUTION 5.8.11 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.

5.8.11 RAISE AND CONTINUOUSLY OBSERVE the fuel assembly/blade guide during its upward travel.

5.8.12 ENSURE hose and cable reels are taking up slack by observing cables and air hoses remain taught within the grapple.

CAUTION 5.8.13 DO NOT bypass the Main Hoist normal up stop when handling Fuel Assemblies or control rod blades in order to comply with T.S. 3.9.6.

5.8.13 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.

Hope Creek Page 61 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.KE-0001 (Q) 5.8.14 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).

5.8.15 ENSURE the Fuel Grapple is at the correct Core OR Fuel Pool Coordinates.

(REFER TO Note 5.8) 5.8.16 ROTATE the Fuel Grapple AND attached fuel assembly/blade guide to attain direct alignment AND orientation with the target location. [CD-396Y]

CAUTION 5.8.17 A. DO NOT attempt to release the fuel assemblylblade guide unless it is fully seated in a storage location. [CD-182C, CD-123E]

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.

5.8.17 Slowly LOWER the fuel assembly/blade guide into the target location using the Fuel Grapple hoist position control in the LOWER position.

5.8.18 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.

Hope Creek Page 62 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 5.8.19 PRES PLACE the GRAPPLE ENGAGE/RELEASE Switch to the RELEASE position AND OBSERVE the grapple ENGAGE light off.

5.8.20 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]

5.8.21 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.

5.8.22 ENSURE hose and cable reels are taking up slack by observing cables and air hoses remain taught within the grapple.

5.8.23 IF Fuel Assemblies were moved, INITIAL the appropriate box on the Fuel Movement Sheet(s) indicating the fuel transfer has been completed.

5.8.24 NOTIFY the Control Room that the fuel transfer has been completed.

5.8.25 Control Room personnel should UPDATE the fuel location tracking tool in use.

Hope Creek Page 63 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 5.9 Auxiliary Hoist Tool Installation [CD-117G1 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 fifting 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 Hoists (Monorail 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 64 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 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 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 instrument handling tool in the vertical position AND THREAD the cable terminal/adaptor into the top of the mounting stud.

E. VERIFY proper hread 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 Creelc Page 65 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 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 Handling tool. [80033517]

1. VERIFY the electrical stops for the applicable Refueling Platform Auxiliary Hoist have been set 1AW HC.OP-ST.KE-000I(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 66 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 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 terminaVadapter.

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 67 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HIC.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-0001(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 68 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 5.9.4 CONNECT the Jet Pump Grapple to a Refueling Platform auxiliary hoist as follows:

NOTE 5.9.4.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 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 Radioactive water may be present in the air lines. Radiation Protection should monitor 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 Hope Creek Page 69 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 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 ofthe 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 70 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use_ Onlv, 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 terminal/adaptor threads. [CD-949A]

E. THREAD the cable terminaUadaptor onto the Auxiliary Hoist cable terminal. [CD-949A].

Continued next page Hope Creek Page 71 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 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 6.9.5.J Radioactive water may be present in the air lines. Radiation Protection should monitor 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 Hope Creek Page 72 of 84 Rev. 28

WALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.KE-OOO1(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 6.9.5.L.1 IF the electrical stops are set in accordance with Step 5.9.5.L.11, this will meet the requirement for the DEI or the GE Fuel Support Piece Grapple.

I. 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-OOOI(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 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.KE-001(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 Loetite 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 terininal/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 terninal/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 6.9.6.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 74 of 84 Rev. 28

'ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.KE-0001(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 lAW 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 Creeks Page 75 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 5.9.6 (continued)

NOTE 5.9.6.J Overhead Crane should be used for lifting Combined Grapple with grid guide installed.

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 90° (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.

~> Hope Creek Page 76 of 84 Rev. 28

ALt ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use On]y 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 1F H-I-KE-SEE-0332 CD-739F GE SIL 486 CD-443X F09-0025-00 CD-612X FOI-0091-01 CD-267Y FSAR Question 410.59 CD-396Y DSER 142 A&B CD-217E INPO OE 1556 CD-I 17G 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 SI CD-I 68A IE Cir 80-21 6.3 DCP No. 4-HM-0643 DCP 80016207 Continued next page Hope Creek Page 77 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.KE-0001(Q) 6.0 (continued) 6.4 Procedures HC.OP-ST.KE-000 (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-0001(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-I-95-036 6.6 Other Documents PR 960821103 GE SIL 82 R1 S1 PR 960128076 Order 70007921 Order 70006867 Hope Creek Page 78 of 84 Rev. 28

rALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.KE-Ooo1(Q)

ATTACHMENT 1 Page I of I 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 S 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 79 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.KE-0001(Q)

ATTACHMENT 2 Page I 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 80 of 84 Rev. 28

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only , HC.OP-SO.KE-OO1(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 NOTE 1.6 The handwheel is marked with a direction indicator.

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 Stop 1.7 will Immediately transfer the bundle weight to the handwheel.

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 81 of 84 Rev. 28

XLL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.KE-00i(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 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-619GJ Hope Creek Page 82 of 84 Rev. 28

I ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 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 Platfonn 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 83 of 84 Rev. 28

._L ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20030122 PSEG Internal Use Only HC.OP-SO.KE-0001(Q)

ATTACHMENT 3 Page 1 of I Refueling Platform Interlocks NOTALL NOTALL ROOG t lI REFUEUNG PLATFORM EERVICE NEAROR PLATFORM OWER DORE HOIW LOADED FUEL ITO STOPOIT SRMAOE GRAPPLE PERAT IO OPERTN Hope Creek Page 84 of 84 Rev. 28

( ( HC.RE-FR.ZZ-000 ATTACHMENT I 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 AD - 28 AH - 50 02 DUMMY SFP ANY SFP AH - 50 AD - 28 4 .4 4 4 4 4 -I- 4 4 1 4 4 4 4 4 t 1 4 1 4 1 -t 4 4 I.- .1 I.

44. I.* I.4.

Prepared By Date Independently Verified By Date Hope Creek Page 18 of 23 Rev. 20

NC.TQ-WB.ZZ-031 0(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: HOPE CREEK

  • YSTEM: Refueling Platform JPM NUMBER: 2003-NRC-S4 TASK: Perform the Monorail Auxiliary Hoist Controls Functional Test TASK NUMBER: N2340010204 K/A NUMBER: 234000 A3.01 ALTERNATE PATH: N/A IMPORTANCE FACTOR: 2.6 3.6 RO SRO APPLICABILITY: Eo F ROD STAE I SROFi LSROFi EVALUATION SETTINGIMETHOD: Walkthrough/Simulate (Perform)

REFERENCES:

HC.OP-FT.KE-0001(Q), Rev. 15 TOOLS AND EQUIPMENT: Refueling Platform/None VALIDATED JPM COMPLETION TIME: 20 Min.

N/A Min.

-IME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS:

APPROVAL: N/A OPERATIONS SUPEVISnR MANAGER RARGAINING UNIT TDAIMIKIG INJI I VIIn I I.Ourar

. vl^,.

REPRESENTATIVE or Designee of a JPM without the CAUTION: No plant equipment shall be operated during the performance following:

1. Permission from the OS or Unit CRS; the individual granting
2. Direct oversight by a qualified individual (determined by permission based on plant conditions).
3. Verification of the "as left" condition by a qualified individual.

ACTUAL JPM COMPLETION TIME: Min.

N/A Min.

ACTUAL TIME CRITICAL COMPLETION TIME:

GRADE: SAT UNSAT IJPM PERFORMED BY:

REASON, IF UNSATISFACTORY:

cVALUATOR'S SIGNATURE: DATE:

Page 1 of 12 Rev. 0 Nuclear Common

NC.TQ-WB.ZZ-031 0(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME: -

DATE:

/ S;YSTEM: Refueling Platform JPM NUMBER: 2003-NRC-S4 Test TASK: Perform the Monorail Auxiliary Hoist Controls Functional TASK NUMBER: N2340010204 INITIAL CONDITIONS:

1. HC.OP-FT.KE-0001 is in progress.
2. Provide operator with marked up copy of HC.OP-FT.ZZ-0001.

INITIATING CUE:

Test IAW HC.OP-FT.KE-0001 Section 5.4.

Perform the Monorail Auxiliary Hoist Controls Functional Successful Completion Criteria:

All critical steps completed.

All sequential steps completed in order.

All time-critical steps completed within allotted time.

may exceed the validated time if satisfactory JPM completed within validated time. Completion time progress is being made.

Page 2 of 12 Rev. 0 Nuclear Common

! ( NC. X0 _-0310°(Z)

OPERATOR TRAINING PROGRAM NAME:

JPM NUMBER: 2003-NRC-S4 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Refueling Platform TAC'I,.

ItO . r\

DPrfnrm the MAornrail I,%.,IIII LII- blI' -' .

Aui ...iaif:rv Hoist Controls

- Functional

- _. . Test IAW HC.OP-FT.KE-0001.

[ ~STEP STANDARD STEP (*Denotes a Critical Step) evaluation)

  • NO. (#Denotes a Sequential Step)

Operator obtains/locates procedure Operator obtains the correc HC.OP-FT.KE-0001

. I Operator reviews precautions and limitations Operator views precautions and limitations Examiner Cue:

If excessive time is taken reviewing precautions and limitations, inform operator that all are satisfied.

I I i Operator determines beginning step of The operator determines the correct beginning procedure step of the procedure to be 5.4.1.

_ i.I i.

NOTE 5.4. IF defective or inoperative Operator reads Note.

equipment is discovered while conducting this test a Notification should be generated which directs equipment repair.

IJ_ _ _ _I_ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _

Page 3 of 12 Rev. 0 Nuclear Common

( ( NC.TQ-V. _-0310(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 COMMENTS

  1. (*Denotes a Critical Step) STANDARD EVAL (Required for UNSAT

(#Denotes a Sequential Step) l evaluation)

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 Right Hand Controller, the following steps is not critical.

TURN the CONSOLE SELECT switch to Operator turns the Right Hand Controller 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 presses the Monorail Pendant PRESS the BRIDGE FORWARD pushbutton, Bridge Forward pushbutton to maneuver the VERIFY the following Monorail Hoist.

AND INITIAL Attachment 2. $ Examiner Cues: The pushbutton indicated is in the position stated.

  • 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. sounding.

D. VERIFY Bridge motion from only this Bridge motion from only this station.

station.

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( ( NC.TQ-W( _-0310(Z)

OPERATOR TRAINING PROGRAM NAME:

JPM NUMBER: 2003-NRC-S4 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Refueling Platform

- An IPAr-.--I-; A lU-t r(nntrdco Minetinnnil TPst 1AW HC OP-FT.KE-0001.

TASK: reriorm Iri IVIUHIUIdI1 iUAXIIIdly I IUIOL .JJI ILIa USA u--. *, .' .-As STEP l COMMENTS STEP(*Denotes a Critical Step) STANDARD WU (Required for UNSAT

- evaluation)

Ll (#Denotes a Sequential Step) l 5.4.3 RELEASE the BRIDGE FORWARD Operator releases FORWARD pushbutton.

pushbutton, VERIFY the following AND INITIAL Attachment 2. $ Examiner Cues:

I I-A. Refuel Platform movement stops. Bridge stops. --7

_I B. Refuel Platform movement alarm is silent. I Alarm is quiet.

  • 5.4.4 PRESS the BRIDGE REVERSE pushbutton, Operator presses the Monorail Pendant VERIFY the following Bridge REVERSE pushbutton.

AND INITIAL Attachment 2. $ Examiner Cues: The pushbutton indicated is in the position stated.

I i A.- -Refuel

- . -Platform moves soutn.

--I Refuel Plafstfrm moves in direction indicated.

I I_

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. sounding.

I~ I -- I 5.4.5 RELEASE the BRIDGE REVERSE Operator releases REVERSE pushbutton.

pushbutton, $ Examiner Cues: The pushbutton VERIFY the following indicated is in the position stated.

AND INITIAL Attachment 2.

I Refuel Platform motion stops.

A. Refuel Platform motion stops.

I IJ-Page 5 of 12 Rev. 0 Nuclear Common

( ( NC.TQ-VtL --0310(Z)

JPM NUMBER: 2003-NRC-S4 OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM:

-A I C'I.

\fFUIIre L ant: IvIUfiIUI Refueling Platform VII i P)-,4-,

STPSTEP

+k- hA--il

(*Deotes Gll "UAIall Yv Ii vl:tw(Thntrnlrk Ai ivilir\/ -nict vl Test 1AW HC OP-FT.KE-0001.,\,..___

lluo Finrzirinn:I STANDARD EVLCOMMENTS EVAL (Required for UNSAT

  1. NO Step) a Critical

. (#Denotes a Sequential Step) evaluation)

B. Refuel Platform movement alarm is silent. Refuel Platform movement alarm is silent.

  • 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. Refuel Platform moves in direction indicated.

B. Speed control is smooth and continuous. Speed control is smooth and continuous.

  • 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. Ketuel FlatTorm moves in aireciluri indicated.

I______ __________________________________ ________I________________________

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( ( NC.TQ- 4 --0310(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.

STPSTEP EVLCOMMENTS N l (*Denotes a Critical Step) lSTANDARD S/U (Required for UNSAT

. (#Denotes a Sequential Step) evaluation)

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

  • 5.4.10 PRESS the HOIST LOWER pushbutton, Operator presses the HOIST LOWER AND LOWER the grapple to greater than 7 pushbutton.

feet below the surface of the water to clear The hoist cable moves downward at least 6 the hoist override. inches below the Normal Up stop.

VERIFY the following $ Examiner Cues: The pushbutton AND INITIAL Attachment 2 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-V4( -0310(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.

IT I STEP IL COMMENTS

  1. (*Denotes a Critical Step) STANDARD EVAL (Required for UNSAT l N (#Denotes a Sequential Step) l 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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I ( NC.TQ-Vj( Z-0310(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 lV l COMMENTS

  1. NO. (*Denotes a Critical Step) STANDARD S/U (Required for UNSAT

(#Denotes a Sequential Step) evaluation)

  • 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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( NC.TQ- 4 '-0310(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.

  1. STEP STEP EVLCOMMENTS NO (*Denotes a Critical Step) STANDARD El (Required for UNSAT

. (#Denotes a Sequential Step) S 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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I

( NCTQ-W( --0310(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.

  1. STEP STEP EVAL COMMENTS
  1. (*Denotes a Critical Step) STANDARD SW (Required for UNSAT NO. (#Denotes a Sequential Step) l evaluation)

STOP TIME: _ Terminating Cue: Repeat back message from the operator on the status of the JPM, and then state "This JPM is complete".

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NC.TQ-WB.ZZ-031 0(Z)

JOB PERFORMANCE MEASURE STUDENT INFO SHEET

'QIlTIAL CONDITIONS:

1. HC.OP-FT.KE-0001 is in progress.

INITIATING CUE:

Perform the Monorail Auxiliary Hoist Controls Functional Test IAW HC.OP-FT.KE-0001 Section 5.4.

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