ML110060144

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HC.OP-IO.ZZ-0005(Q), Rev. 30, Cold Shutdown to Refueling
ML110060144
Person / Time
Site: Salem, Hope Creek  PSEG icon.png
Issue date: 04/25/2009
From:
Public Service Enterprise Group
To:
Office of Nuclear Reactor Regulation
References
LR-N10-0355 HC.OP-IO.ZZ-0005(Q), Rev 30
Download: ML110060144 (38)
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Text

PSEG Internal Use Only PSEG NUCLEAR L.L.C.

Page 1 of 1 HOPE CREEK GENERATING STATION HC.OP-IO.ZZ-0005(Q) - Rev. 30 COLD SHUTDOWN TO REFUELING USE CATEGORY: I

  • Biennial Review Performed: Yes No NA 9
  • Packages and Affected Document Numbers incorporated into this revision:

CP No.

CP Rev.

AD No.

Rev No.

None 9

  • The following OTSCs were incorporated into this revision: None REVISION

SUMMARY

  • Incorporates CP 80095532 which removes LV-1754. Reference to LV-1754 as deleted in Step 5.4.39.B. This was reviewed by the CP and is editorial. (80095532-0440)

IMPLEMENTATION REQUIREMENTS Effective Date 4/25/09 None

HC.OP-IO.ZZ-0005(Q)

Hope Creek Page 1 of 37 Rev. 30 COLD SHUTDOWN TO REFUELING TABLE OF CONTENTS SECTION TITLE PAGE 1.0 PURPOSE.............................................................................................................2 2.0 PREREQUISITES.................................................................................................2 3.0 PRECAUTIONS AND LIMITATIONS....................................................................3 4.0 EQUIPMENT REQUIRED.....................................................................................5 5.0 PROCEDURE.......................................................................................................6 5.1 Administrative Requirements for Entering Operational Condition 5 -Refueling............................................................6 5.2 Reactor Pressure Vessel Filling..................................................................9 5.3 Raising Refuel Floor Exhaust High Radiation Setpoints...........................12 5.4 Reactor Vessel Preparation for Refueling................................................13 6.0 RECORDS..........................................................................................................23

7.0 REFERENCES

....................................................................................................23 ATTACHMENTS

, Entering OPERATIONAL CONDITION 5 Final Checks Mode of Operation.......25, Placing the Plant in Alternate Decay Heat Removal..........................................26, Vessel Level Instrumentation Temperature Compensation Curves...................28, Installation of Gaitronics Communication Cable to Refueling Bridge.................32, Cooldown Transient Boundaries........................................................................34, Operational Limitations Comment Page............................................................35, Raising Refuel Floor Exhaust High Radiation Setpoints....................................36

HC.OP-IO.ZZ-0005(Q)

Hope Creek Page 2 of 37 Rev. 30 COLD SHUTDOWN TO REFUELING START TIME DATE BY TERMINATION TIME ________________

DATE ______________

BY COMPLETION TIME ________________

DATE ______________

BY COMMENTS:

1.0 PURPOSE This procedure provides a sequence for placing the plant in a Refueling configuration (OPERATIONAL CONDITION 5) from Cold Shutdown (OPERATIONAL CONDITION 4).

This sequence ensures conformance with T/S requirements, integration of plant personnel refuel floor activities, personnel and equipment safety and compliance with the station ALARA Program.[CD-443X]

2.0 PREREQUISITES 2.1 Plant Initial Conditions 2.1.1.

Reactor is depressurized with Head Vents HV-F001 AND HV-F002 open. Reactor water temperature is 200 °F.

2.1.2.

Reactor water level has been established at 80 to 90 inches IAW HC.OP-IO.ZZ-0004(Q), Shutdown From Rated Power To Cold Shutdown.

2.1.3.

A cooldown of the Reactor Coolant System is in progress with a cooldown rate of 90o F / hr. IAW HC.OP-IO.ZZ-0004(Q),

Shutdown From Rated Power To Cold Shutdown.

2.1.4.

Reactor level is maintained by balancing Control Rod Drive System water addition AND Reactor Water Cleanup System (RWCU) drain to the Main Condenser via the RWCU blowdown line, IAW HC.OP-SO.BG-0001(Q), OR any other viable means of level control.

2.1.5.

All control rods are fully inserted in the Reactor, EXCEPT for control rods removed IAW T/S 3.9.10.1 OR 3.9.10.2.

2.1.6.

The Reactor Recirculation System has been shut down IAW HC.OP-SO.BB-0002(Q), Reactor Recirculation System Operation.

HC.OP-IO.ZZ-0005(Q)

Hope Creek Page 3 of 37 Rev. 30 2.1.7.

Drywell AND Torus de-inerting is in progress OR drywell atmosphere oxygen concentration is greater than 19.5%.

2.1.8.

The Reactor Mode Switch is locked in the REFUEL OR SHUTDOWN position. [CD-391H]

2.1.9.

CST Temperature should be greater than 55oF.

(CRIDS page 126, A2497 can be used) 3.0 PRECAUTIONS AND LIMITATIONS 3.1 IF this procedure is terminated prior to completion, the SM/CRS shall note the reason, time and date of termination on this procedure 3.2 DO NOT exceed a cooldown rate of 90°F/hr. This administrative limit will prevent exceeding the T/S limit of 100 °F/hr.

3.3 Reactor Vessel Flange Metal Temperature and Head Flange Metal Temperature shall not be permitted to drop to less than 79 °F while ANY of the vessel flange bolts are under tension. [T/S 3.4.6.1]

3.4 The Reactor Mode Switch may be placed in the REFUEL position at anytime all OPERATIONAL CONDITION 5 T/S are satisfied AND Reactor water temperature is less than 140 °F AND any vessel head closure bolts are less than fully tensioned.

3.5 The Reactor Mode switch should remain in the SHUTDOWN position, IF Reactor water temperature should exceed 140 °F OR IF any of the T/S required for remaining in OPERATIONAL CONDITION 5 are not maintained.

3.6 To enhance Reactor Vessel, Reactor Cavity and Spent Fuel Pool water cavity clarity, performance of the following activities should be evaluated:

  • Preventing system operations, which would inject sediment from, stagnant portions of auxiliary systems such as RWCU, RHR Shutdown Cooling OR Fuel Pool Cooling.
  • Thoroughly flushing the system selected to flood the Reactor Vessel, Reactor Cavity and equipment pool.

(The Condensate - Feedwater Systems should be considered clean.)

HC.OP-IO.ZZ-0005(Q)

Hope Creek Page 4 of 37 Rev. 30 3.7 Raising RPV level may cause a rise in RPV pressure due to steam generated by hot RPV metal. As long as Reactor Coolant System bulk coolant temperature is < 200o F, as recorded in HC.OP-DL.ZZ-0026, Attach 3s, this is not an OPERATIONAL CONDITION Mode Change.

3.8 To prevent personnel exposure to airborne radiation and steam discharge, Reactor Vessel water level should be slowly lowering while piping connected to the Reactor Vessel Head is being breached.

3.9 Drywell and Reactor Head removal and removal of Reactor internals has the potential for exposing personnel to smearable and airborne radioactive contamination and elevated radiation levels. Minimize personnel radiation exposure and personnel and equipment contamination by following the direction of Radiation Protection personnel.

3.10 Raising water level to > 200 in. to cover the Main Steam Dryer will significantly reduce radiation exposure and help with Reactor Vessel Flange Temperature control during RPV Head removal. Once visual verification is available on the refuel floor, the level may be raised to as close to the Reactor Vessel flange as possible without raising level to the Flange (218 in.).

3.11 To protect personnel from radiation overexposure, irradiated fuel should not be moved within 7 feet of the Fuel Pool Gates if Fuel Pool Shield Plugs are removed and the Reactor Cavity is not filled with water.

3.12 Caution should be exercised when the Main Steam Safety Relief Valve Pilots are removed from the header. A potential vessel drain path will exist from the body pilot tube through the valve to the Torus. This exists even with blind flanges installed.

HC.OP-IO.ZZ-0005(Q)

Hope Creek Page 5 of 37 Rev. 30 3.13 Operations with potential to drain the Reactor Pressure Vessel (OPDRV) and operations with potential to drain the Reactor Cavity (OPDRC) consists of any operation or task which has the potential to cause an unplanned lowering in Reactor Pressure Vessel level or Reactor Cavity level AND uncovering irradiated fuel. OPDRCs shall be of concern when Fuel Pool to Reactor Cavity Gates are removed, or CORE ALTERATIONS are in progress. All OPDRV shall be considered OPDRC. By definition, when the Reactor Pressure Vessel is completely de-fueled and the watertight gates between the Reactor Cavity and the Spent Fuel Pool are installed, an operation with potential to drain the Reactor Vessel/Cavity does not exist. All activities which could result in interconnected components being placed into abnormal configurations, penetrations being drained OR filled, OR connected piping systems being placed in off-normal flow paths, should be evaluated as OPDRVs. Each potential OPDRV should be reviewed on a case by case basis by a Senior Reactor Operator (SRO) licensed Operations Department personnel (SM/CRS/WCCS). Items considered in this evaluation should include but not be limited to the following: [CD-608G]

  • Driving force associated with any transfer of water.
  • Adequacy of procedures regulating performance of planned activity
  • Availability of sources of makeup water and their capacity.
  • Availability of redundant means of terminating the evolution.
  • Availability of automatic means of terminating drain down events.

After evaluation, if it is determined that an activity presents a minor risk of causing significant draining of the RPV/Cavity/Fuel Pool, the evolution may be assessed as not being a OPDRV. Manipulation of any penetration, which has two operable Barriers to prevent the inadvertent transfer of water need not be considered as a OPDRV. PRIOR TO performance of activities determined to be OPDRVs, an isolation contingency plan for sealing affected penetrations should be developed.

Personnel involved in performance of an evolution which could result in an OPDRV AND personnel required to support the contingency isolation plan, should be briefed on the contingency plan prior to the start of the evolution. All equipment required to execute the contingency plan should be pre-staged. Prior to performing any OPDRV, a briefing should be provided at the Outage Shift Turnover Meeting to ensure that critical plant personnel (Department Heads AND Senior Supervisors) are aware of the possible risks OR impact on other plant evolutions.

4.0 EQUIPMENT REQUIRED

  • Communications cable

HC.OP-IO.ZZ-0005(Q)

Hope Creek Page 6 of 37 Rev. 30 5.0 PROCEDURE NOTE The administrative requirements described in this section may be performed concurrently with the initial steps of Section 5.2. All administrative requirements must be completed prior to the start of Reactor Vessel Head de-tensioning.

Each step should be recorded upon completion.

5.1 Administrative Requirements for Entering Operational Condition 5 - Refueling 5.1.1.

REVIEW applicable T/S Surveillances required for entering Operational Condition 5, to determine if any Surveillances remain to be performed.

SM/CRS 5.1.2.

CHANGE WCM "Current Operating Mode" from Mode 4 to Mode 5 USING the Mode Dependent Tagging/Current Mode/Change function. GENERATE a "Components Off-Normal Position Report" USING the WCM Reports/Off Normal Report function.

SM/CRS 5.1.3.

COMPARE the systems and equipment required for service with the status of equipment in the Components in the Off-Normal Position Report as follows:

A.

IDENTIFY equipment / systems that are currently inoperable due to in-progress maintenance, OR equipment / system failures.

SM/CRS B.

POSITION all operable equipment to achieve the "Normal Position" OR to the required position as determined by SM/CRS.

SM/CRS C.

UPDATE WCM using the Mode/Dependent Tagging/Normal Positions/Change function.

SM/CRS 5.1.4.

PRIOR to entering CONDITION 5 ENSURE all current notifications are screened for operability. [70021851]

SM/CRS

HC.OP-IO.ZZ-0005(Q)

Hope Creek Page 7 of 37 Rev. 30 5.1.5.

COMPARE the active entries in the Temporary Modifications Log for entries, which could affect the operability of systems required for Mode Change.

SM/CRS 5.1.6.

DIRECT I&C to PERFORM the following:

A.

HC.IC-FT.SE-0001(Q), SRM Channel Functional Test, IF it has not been performed within the last 7 days,

[T/S 4.3.7.6.b.1, 4.9.2.b.2]

I&C Dept AND B.

HC.IC-FT.SE-0025(Q), SRM Fuel Loading Non-coincident Trips, as required IF shorting links are removed AND it has not been performed within the last 7 days.

[T/S 4.9.2.b.2]

I&C Dept 5.1.7.

INITIATE HC.OP-DL.ZZ-0026(Q) - Attachment 2 for those surveillance items applicable for entering Operational Condition 5 (i.e., Reactor Mode Switch position, all SRMs fully inserted with exception of items required for Core Alterations).

SM/CRS NOTE A Caution Tag should be placed on the Mode Switch Key, with the Key installed for surveillance testing in Mode 5. Upon completion of testing requiring Mode Key installation, the Mode Switch shall be locked in Shutdown or Refuel AND the key shall be removed.

[CD-391H]

5.1.8.

VERIFY Reactor Mode Switch Locked (Key Removed) in SHUTDOWN OR REFUEL position. [T/S 3.9.1]

SM/CRS 5.1.9.

RECORD the Time and Date on Section B of Attachment 1 WHEN the Reactor Mode Switch is placed in the SHUTDOWN position.

SM/CRS

HC.OP-IO.ZZ-0005(Q)

Hope Creek Page 8 of 37 Rev. 30 CAUTION Do not proceed with Reactor head de-tensioning UNTIL:

z ALL systems AND equipment required to enter Mode 5 are operable.

z RPV Metal Temps should be recorded on a 30 min. interval.

z ALL departments have signed Attachment 1 Section A.

5.1.10.

IF all systems requirements for entering Operational Condition 5 are satisfied, AND all departments have signed Attachment 1 Section A, THEN COMPLETE Section A of Attachment 1.

SM/CRS

HC.OP-IO.ZZ-0005(Q)

Hope Creek Page 9 of 37 Rev. 30 5.2 Reactor Pressure Vessel Filling NOTE If Shutdown Cooling becomes unavailable, the plant may be placed in the Alternate Decay Heat Removal Mode of operation using Attachment 2.

5.2.1.

CONTINUE the cooldown of the Reactor Vessel using the RHR System in the Shutdown Cooling Mode IAW HC.OP-SO.BC-0002 (Q), Decay Heat Removal Operation, AND the requirements of T/S 3.4.6.1.

SM/CRS 5.2.2.

VERIFY the following to ensure the RPV and associated systems are lined up to support raising level into the RPV Head:

  • Reactor coolant temperature is approximately 160 to 170 °F prior to raising RPV level over 90 inches.

SM/CRS

  • Adequate CST inventory and water quality to support Reactor Cavity flood-up. (Approximately 430,000 gal is required for Reactor Cavity and Equipment Pit flood up.)

SM/CRS

  • Condensate, Condensate Transfer, OR CRD Systems are available for RPV flood-up.

SM/CRS

SM/CRS

SM/CRS

  • Inboard AND Outboard MSIVs closed.

SM/CRS

  • RPV Head vents are open.

SM/CRS

  • HPCI AND RCIC steam supply lines isolated.

SM/CRS (continued on next page)

HC.OP-IO.ZZ-0005(Q)

Hope Creek Page 10 of 37 Rev. 30 5.2.2 (continued)

SM/CRS

SM/CRS 5.2.3.

RECORD RPV Head/Flange metal temperature at 30-minute intervals on HC.OP-DL.ZZ-0026 Att. 3s.when raising RPV level into the RPV head.

SM/CRS 5.2.4.

NOTIFY Radiation Protection at the Drywell Access that raising level in the RPV may cause steam to discharge through the RPV Head Vent Line into the Drywell Floor Drain Sump.

SM/CRS

HC.OP-IO.ZZ-0005(Q)

Hope Creek Page 11 of 37 Rev. 30 NOTE The intent of the following step is to raise RPV water level into Reactor Head to facilitate cooling the Head and adjacent Flange metal.

An increase in flange metal cooldown rate is expected when the water level reaches the area of the flange.

Reactor head vent line temperatures as indicated at STEAM RELIEF VALVE/ REACTOR HEAD VENT/MAIN STEAM DRAIN TEMPS-B21-TRR614, may rise to > 340oF due to the high RPV head temperatures.

The Level Band in the following step is for guidance, and can be adjusted as necessary to accommodate the Vessel Head cooldown. The following should be considered when determining the appropriate level band and injection rate.

z Bulk Coolant Temperature.

z Available Vessel Level Instrumentation.

z Steam generation rate, and impact on Drywell Floor Drain Sumps.

z Steam generation rate, and impact on Reactor Pressure.

z Water Inventory management.

z CST Water Temperature.

5.2.5.

RAISE RPV level to +270 to +300 on 1BBLR-3622A AND 1BBLR-3622B by raising injection flowrate at a rate NOT to exceed 10 inches per minute.(approx 2000 gpm), using one or more of the following systems:

Control Room Operator A.

One Primary Condensate Pump IAW HC.OP-SO.AE-0001(Q), Feedwater System Operation.)

B.

Condensate Transfer Via Shutdown Cooling IAW HC.OP-SO.BC-0002(Q) Decay Heat Removal Operation C.

CRD System 5.2.6.

ADJUST Shutdown Cooling flow as required to maintain Vessel pressure below the High Pressure Shutdown Cooling Isolation Setpoint (82 psig) while filling the RPV.

Control Room Operator 5.2.7.

WHEN RPV level is between +270" to +300",

THEN CONTINUE cooldown AND establish a temperature band of 110 °F to 130 °F.

SM/CRS

HC.OP-IO.ZZ-0005(Q)

Hope Creek Page 12 of 37 Rev. 30 5.3 Raising Refuel Floor Exhaust High Radiation Setpoints 5.3.1.

VERIFY the following:

  • The plant is in Mode 4 or 5
  • NO operations with a potential for draining the reactor vessel will take place 5.3.2.

ENTER a tracking LCO for ALL Channels of Refuel Floor Exhaust High Radiation.

NOTE The following step will make all channels of the Refuel Floor Exhaust High Radiation INOPERABLE. These channels are not required in Modes 4 and 5 (TS 3.3.2-1.2.c)

Only the HIGH alarm will be changed, the ALERT will be unaffected. The HIGH alarm will be restored by HC.OP-IO.ZZ-0001(Q).

H1SP -1SPRI-4856A H1SP -1SPRI-4856B H1SP -1SPRI-4856C 5.3.3.

DIRECT I&C to reset the RFE High Radiation setpoints IAW.

HC.OP-IO.ZZ-0005(Q)

Hope Creek Page 13 of 37 Rev. 30 5.4 Reactor Vessel Preparation for Refueling 5.4.1.

ESTABLISH AND MAINTAIN FMEA 2 housekeeping requirements for the Dryer/Separator Pool, Reactor Cavity area AND Spent Fuel Pool IAW the Foreign Material Exclusion Program.

Refuel Floor Supervisor 5.4.2.

DIRECT Maintenance Department (Electrician) to install temporary Refuel Bridge Gaitronics cable IAW Attachment 4.

SM/CRS NOTE If Shutdown Cooling becomes unavailable, the plant may be placed in the Alternate Decay Heat Removal Mode of operation using Attachment 2.

5.4.3.

IF Reactor water temperature is less than 140°F AND control rod testing OR Control Rod Drive Mechanism maintenance is required, THEN LOCK the Reactor Mode Switch in the REFUEL position.

(SEE Step 5.1.8)

AND RECORD time on Attachment 1 Section B.

[T/S 3.9.1, CD-391H]

Control Room Operator 5.4.4.

DETERMINE the water source (Condenser, Suppression Pool OR Condensate Storage Tank) that will be used to fill the Dryer/Separator AND Reactor Cavity Pools, AND whether the RHR OR Core Spray System will be used to flood the Dryer/Separator AND Reactor Cavity Pools.

SM/CRS

HC.OP-IO.ZZ-0005(Q)

Hope Creek Page 14 of 37 Rev. 30 NOTE A full flow system test from the designated water source through the Residual Heat Removal System OR Core Spray System to the Reactor Vessel can be used as a substitute for draining AND refilling stagnant runs of piping.

5.4.5.

IF the Residual Heat Removal System OR Core Spray System are to be used to transfer water to Dryer/Separator OR Reactor Cavity Pools, PERFORM the following:

A.

DRAIN AND REFILL the stagnant lengths of piping IAW applicable System Operating procedure to prevent corrosion products from entering the Reactor Vessel while flooding the pools.

SM/CRS B.

ENSURE that system piping is completely full by opening the high point vents while refilling the system.

SM/CRS 5.4.6.

ENSURE Loss Prevention has staged 250 feet of 3 fire hose and necessary connections in the Gamma Scan room in Reactor Building Elev. 162 for HC.OP-AM.TSC-0021.

Loss Prevention 5.4.7.

ENSURE Polar Crane preventive maintenance, inspections AND load tests have been completed AND are satisfactory.

Maint. Dept

HC.OP-IO.ZZ-0005(Q)

Hope Creek Page 15 of 37 Rev. 30 NOTE The following list provides level correlations for use during Refueling Operations:

z 501.5" Refuel Floor z

495.5" Fuel Pool Hi Level Alarm z

489.5" Normal Water Level (Weir) z 486.5" Fuel Pool Lo Level Alarm z

483.5" 22'2" Coverage over Vessel Flange (T/S 3.9.8) z 476.0" 23' Coverage over Spent Fuel (T/S 3.9.9) z 343.0" Top of Vessel Head z

257.5 Top of Vessel Head Flange z

217.5 Top of Vessel Shell Flange z

118.0" Bottom of Main Steam Lines z

71.5 Instrument Condensing Chamber Penetrations z

0.0" Instrument Zero BBLT-11683 is placed in service at this point in order to monitor response during RPV depressurization and thereby verify operation of level transmitter before 1BBLR-3622A and 1BBLR-3622B are removed from service during RPV Head piping removal.

The RX Cavity Shutdown Low Level Alarm 1ECLAL-N027 sensed from Indication Switch 1ECLISL-N027 is normally disabled during on line operation. It is enabled during shutdown condition AND will be connected to the temporary transmitter per T-Mod OR 1BBLT-11683.

5.4.8.

DIRECT I&C Department to ensure the calibration AND place Reactor Vessel Shutdown Range Level Instrumentation, 1BBLT-11683 in service for open vessel conditions.

CRS 5.4.9.

DIRECT Maintenance Department to de-tension the Drywell Head. (This may require ventilation secured to the refuel floor for drywell head removal).

SM/CRS 5.4.10.

DIRECT Maintenance Department to remove the Reactor Vessel head insulation package. (This may require securing Refuel Floor ventilation.).

SM/CRS

HC.OP-IO.ZZ-0005(Q)

Hope Creek Page 16 of 37 Rev. 30 5.4.11.

VERIFY I&C Department has placed Reactor Vessel Shutdown range level instrumentation in service for open vessel conditions AND the local alarm (setpoint 75"), is enabled. [CD-692A]

SM/CRS NOTE Level indication via BBLT-11683 will read approximately 27 inches higher than actual level for every psig of Reactor pressure. After the BBLT-11683 is placed in service, decreasing pressure due to head cooldown may cause indicated level to change due to vessel head pressure lowering.

5.4.12.

WHEN level indication on BBLI-R605 via BBLT-11683 is satisfactory, THEN GIVE permission to the Fuel floor Coordinator to commence removal of RPV Head piping.

SM/CRS 5.4.13.

In preparation for breaching RPV Head piping, PERFORM the following:

z ENSURE RPV steam dome pressure is approximately 0 psig using multiple indications.

SM/CRS z

COMMUNICATE to the Fuel Floor Supervisor in order to ensure proper safety precautions are taken during breach of RPV Head piping.

SM/CRS NOTE The intent of the following step is to lower the probability of steam discharge when the RPV Head piping is breached by providing a larger volume for the steam in the RPV. Once the piping is breached, it is no longer necessary to continue lowering level.

5.4.14.

WHEN the Fuel Floor is ready to breach the RPV Head piping, THEN COORDINATE with the Fuel Floor Coordinator AND COMMENCE SLOWLY LOWERING RPV level.

Control Room Operator 5.4.15.

WHEN RPV level starts to lower, THEN DIRECT Maintenance Department to remove the Reactor vessel head vent, head thermocouples, and level instrumentation piping.

SM/CRS

HC.OP-IO.ZZ-0005(Q)

Hope Creek Page 17 of 37 Rev. 30 5.4.16.

WHEN Reactor Vessel Head insulation package and flange thermocouple have been removed, DIRECT Maintenance to begin taking RPV Head/Flange metal temperatures locally every 30min., AND REPORT this Data to the Control Room for use on HC.OP-DL.ZZ-0026, Att. 3s.

SM/CRS 5.4.17.

WHEN Condensing Chamber 1BBCC-D002-B21 has been removed from the Vessel Head, the following instruments should be considered NOT operable, and entered into OP-HC-102-103-1001:

z 1BBLR-3622A, Rx Level - Post Acc. Mon.

z CRIDS Point A2593 z

1BBLR-R608-C32, Red Pen, Rx Vessel Level - Upset Range z

CRIDS Point A2577 z

1BBLI-R605, Rx Level Shutdown Range z

1BBLR-3622B, Rx Level - Post Acc. Mon.

z CRIDS Point A2596 z

1BBLR-7854, Blue Pen, Rx Water Level - RSP 5.4.18.

WHEN the RPV Head piping is initially breached, THEN MONITOR RPV level indication using 1BBLI-R605 via BBLT-11683 AND STOP lowering RPV level.

IF head and flange are sufficiently cool per maintenance, continue lowering RPV level to the flange (+218 inches).

SM/CRS

HC.OP-IO.ZZ-0005(Q)

Hope Creek Page 18 of 37 Rev. 30 CAUTION An air tight seal of the 4 RPV Head Vent piping with the RPV head installed will result in inaccurate RPV level indication in the Control Room.

5.4.19.

ENSURE that a robust vented FME flange is installed on the 4 RPV Head Vent piping prior to lowering level in the Reactor Vessel.

SM/CRS 5.4.20.

VERIFY that ALL of the administrative requirements listed in Section 5.1 of this procedure have been completed.

SM/CRS NOTE RPV head de-tensioning may commence with the RPV level above the flange, however the RPV level must be below the flange prior to removing the RPV head.

CAUTION The RPV flange is located at 217.5 inches RPV level. Maintaining level below 210 inches during RPV Head removal will prevent overflow into the Reactor Cavity area. Raising water level to > 200 in. to cover the Main Steam Dryer will significantly reduce radiation exposure and help with Reactor Vessel Flange Temperature control during RPV Head removal. Once visual verification is available on the refuel floor, the level may be raised to as close to the Reactor Vessel flange as possible without raising level to the Flange (218 in.).

5.4.21.

LOWER RPV level to approximately +208 inches, AND maintain level constant using BLI-R605 via BBLT-11683, prior to removing the RPV Head.

Control Room Operator

HC.OP-IO.ZZ-0005(Q)

Hope Creek Page 19 of 37 Rev. 30 NOTE The Reactor Mode Switch may be locked (key removed) in the REFUEL position at anytime all OPERATIONAL CONDITION 5 T/S are satisfied and Reactor water temperature is less than 140°F and vessel head closure bolts less than fully tensioned. Time and date should be recorded on Section B of Attachment 1 when the Reactor Mode Switch is in the REFUEL position. [CD-391H]

If Reactor water temperature should exceed 140°F OR if any of the T/S required for remaining in OPERATIONAL CONDITION 5 are not maintained, the Reactor Mode Switch should be locked in the SHUTDOWN position. Time and date should be recorded on Section B of when the Reactor Mode Switch is locked in the SHUTDOWN position.

Status of testing, surveillance and maintenance on required systems and equipment should be monitored. When all conditions are satisfied as described in Section 5.1. Time and date should be recorded on Section B of Attachment 1 when the Reactor Mode Switch is returned and locked in the REFUEL position.

If the Reactor Mode Switch is locked in the REFUEL OR SHUTDOWN position, and the average Rx coolant temperature is 140 °F, then, performance of the following step will result in a Mode change.

5.4.22.

DIRECT Maintenance Department to de-tension the reactor vessel head AND PERFORM the following:

SM/CRS A.

RECORD Time/Date first RPV Head Stud less than full tension. (OPCON 5)

Time Date SM/CRS B.

RECORD Time/Date last RPV Head Stud fully de-tensioned.

Time Date SM/CRS C.

WHEN RPV head is fully de-tensioned, THEN STOP recording 30 minute Head/Flange temperatures.

SM/CRS 5.4.23.

DIRECT Maintenance Department to remove the Reactor Vessel Head.

SM/CRS

HC.OP-IO.ZZ-0005(Q)

Hope Creek Page 20 of 37 Rev. 30 5.4.24.

COORDINATE with Maintenance AND RAISE RPV level to near the Vessel Flange, to reduce radiation due to the Steam Dryer not being covered. Level can be raised to near RPV Flange based on visual verification.

Control Room Operator 5.4.25.

PRIOR to flooding the Reactor Cavity DIRECT Maintenance to verify penetration covers for the following are properly torqued and/or sealed.

Maint. Dept.

z Four (4) ventilation duct flanges z

Three (3) electrical penetration blank flanges z

Head Vent blank flanges z

One (1) manhole 5.4.26.

VERIFY Maintenance Department has installed the Shielded Fuel Transfer Chute.

SM/CRS 5.4.27.

CLOSE AND TAG drain valve 1-EC-V053 to isolate the Fuel Pool Gate Interspace Area.

Control Room Operator 5.4.28.

ESTABLISH AND MAINTAIN communications between Refuel Floor and Control Room personnel. MONITOR Reactor Cavity and Dryer/Separator Pools continuously to prevent over filling.

Control Room Operator NOTE Steps 5.4.29 AND 5.4.30 should be performed concurrently.

5.4.29.

FILL the Reactor Cavity and Dryer/Separator Pools IAW one of the following procedures by injecting water into the reactor vessel.

Control Room Operator z

HC.OP-SO.AP-0001(Q), Condensate Storage and Transfer System z

HC.OP-SO.AE-0001(Q),Feedwater System Operation z

HC.OP-SO.BC-0002(Q) Decay Heat Removal Operation z

HC.OP-SO.BE-0001(Q) Core Spray System

HC.OP-IO.ZZ-0005(Q)

Hope Creek Page 21 of 37 Rev. 30 5.4.30.

COORDINATE with Maintenance Department to SLOWLY raise the Reactor Building Polar Crane Main Hoist WHILE Reactor Cavity water level increases. MAINTAIN the Reactor Vessel Steam Dryer under the maximum amount of water while removing and storing the Steam Dryer.

SM/CRS 5.4.31.

STOP filling the Reactor Cavity and Dryer/Separator Pools WHEN the level is equal to the level of the Spent Fuel Pool OR to a level which supports installation of the 360° Service Platform.

Control Room Operator 5.4.32.

DIRECT Maintenance Department to install the Main Steam Line Plugs. [CD-087E]

SM/CRS 5.4.33.

IF desired, COORDINATE with Maintenance and INSTALL the 360° Service Platform. The Service Platform displaces approximately 7000 gallons.

SM/CRS 5.4.34.

ENSURE Reactor Cavity level equals Spent Fuel Pool level.

COORDINATE with Maintenance and DEPRESSURIZE the Spent Fuel Pool Gate Seals.

SM/CRS 5.4.35.

DIRECT Maintenance Department to remove the Fuel Pool Gates.

SM/CRS 5.4.36.

DIRECT the implementation of the recurring task enabling overhead annunciation of computer points associated with Shutdown Cooling. These points will input to C3-F5.

SM/CRS 5.4.37.

ALIGN RBVS for refueling IAW HC.OP-SO.GR-0001(Q).

Control Room Operator 5.4.38.

IF the requirements of T/S 3.9.8 and 3.9.9 are satisfied, THEN ISOLATE the Residual Heat Removal AND Core Spray System vessel inventory addition capability. (This prevents inadvertent start up of these systems AND the potential for overflowing Refuel Floor Pools (See T/S 3.5.2) and can be accomplished by Caution Tagging all out of service pumps in Pull-to-Lock). [CD-238E]

SM/CRS

HC.OP-IO.ZZ-0005(Q)

Hope Creek Page 22 of 37 Rev. 30 5.4.39.

PREVENT inadvertent addition of water from Feedwater/Condensate Systems from overflowing the Refuel Floor Pools by closing the following valve groups:

A.

1AE-F032A and 1AE-F032B SM/CRS OR B.

1AE-HV1753 A, B and C 1AE-HV1744 A, B and C 1AE-LV1785 SM/CRS CAUTION If the Alternate Fuel Pool Cooling Assist mode of RHR is being utilized, then the Decay Heat removal capabilities will be reduced if the Fuel Pool Cooling system is aligned to the Reactor Well Diffusers.

5.4.40.

ALIGN the Fuel Pool Cooling system to permit operation of the Reactor Cavity and Dryer/Separator Skimmer Weirs to overflow to the Skimmer Surge Tanks IAW HC.OP-SO.EC-0001(Q).

SM/CRS 5.4.41.

ENSURE in-service Reactor Water Cleanup System (RWCU)

Pumps are aligned to take suction from the Reactor Vessel lower head area, (1BG-F101 is open) IAW HC.OP-SO.BG-0001(Q) for maximizing bottom head drain flow.

Control Room Operator 5.4.42.

IF the Reactor Mode Switch is not already in the REFUEL position (from Step 5.4.3),

AND IF Reactor water temperature is less than 140 °F THEN LOCK the Reactor Mode Switch in Refuel AND RECORD the time on Attachment 1, Section B. [T/S 3.9.1]

Control Room Operator 5.4.43.

COMPLETE Section C of Attachment 1 signifying that the plant is in OPERATIONAL CONDITION 5 AND that the Reactor Vessel, Reactor Cavity and Dryer/Separator Pools are in a refueling configuration.

SM/CRS 5.4.44.

DEFEAT NSSSS Isolation Signal capability (to Shutdown Cooling valves), by performing appropriate Section(s) of HC.OP-GP.SM-0001(Q).

SM/CRS

HC.OP-IO.ZZ-0005(Q)

Hope Creek Page 23 of 37 Rev. 30 6.0 RECORDS 6.1 RETAIN the entire procedure IAW RM-AA-101; Records Management Program

7.0 REFERENCES

7.1 Hope Creek Generating Station Technical Specifications 7.2 Hope Creek Generating Station FSAR Volume 12, Section 9.1.4.2.10.2 7.3 Station Drawings z

M-41-1(Q), Nuclear Boiler P&ID, Sht. 1 z

M-53-1(Q), Fuel Pool Cooling System P&ID z

M-51-1(Q), Residual Heat Removal System P&ID z

M-52-1(Q), Core Spray System P&ID z

M-76-1(Q), Reactor Building Ventilation System P&I z

M-44-1(Q), Reactor Water Cleanup System P&ID z

M-05-1, Condensate System P&ID z

M-06-1, Feedwater System P&ID 7.4 System Operating Procedures z

HC.OP-SO.BC-0002(Q), Decay Heat Removal Operation z

HC.OP-SO.GR-0001(Q), Reactor Building Ventilation System Operation z

HC.OP-SO.BE-0001(Q), Core Spray System Operation z

HC.OP-SO.AD-0001(Q), Condensate System Operation z

HC.OP-SO.AE-0001(Q), Feedwater System Operation z

HC.OP-SO.EC-0001(Q), Fuel Pool Cooling Water System Operation z

HC.OP-SO.BG-0001(Q), Reactor Water Cleanup System Operation z

HC.OP-AB.RPV-0009(Q), Shutdown Cooling

HC.OP-IO.ZZ-0005(Q)

Hope Creek Page 24 of 37 Rev. 30 7.5 Other Procedures

  • HC.OP-DL.ZZ-0026(Q), Daily Surveillance Log
  • HC.MD-PM.KF-0002(Q), Lubrication of Reactor Building Polar Crane Main Aux Hoists
  • HC.MD-PM.KF-0012(Q), Overhead Crane and Hoist Load Tests
  • HC.IC-GP.BB-0003(Q), Nuclear Boiler - Nondivisional Channel L-11683 /

B21-N027 Rx Cavity Flood Up Level / Rx Shutdown Range Level Setup

CD-087E, (INPO SER 38-85) z CD-443X, (FSAR 9.1.4.2.10.2) z CD-692A, (INPO SOER 82-01R01 z

CD-608G, (NSR AR M20-92-022) z CD-609G, (NHO LET 4EC-3411) z CD-210E, (INPO SOER 85-04, R-04) z CD-391H, (LER 95-035) 7.7 Letters z

GE Letter - HCGS-L-86-110 (CD-255G)

HC.OP-IO.ZZ-0005(Q)

Hope Creek Page 25 of 37 Rev. 30 ATTACHMENT 1 ENTERING OPERATIONAL CONDITION 5 FINAL CHECKS SECTION A Surveillances required for entering Operational Condition 5 are completed.

1.

Maintenance

2.

I&C

3.

Chemistry

4.

Reactor Engineering

5.

Radiation Protection

6.

Operations

7.

Technical

8.

Nuclear Site Protection

9.

ISI Date All department system requirements, above, for entering OPERATIONAL CONDITION 5 are satisfied.

SM/CRS Date SECTION B REACTOR MODE SWITCH POSITION STATUS DATE TIME MODE SWITCH POSITION SM/CRS SIGNATURE SECTION C The plant is in OPERATIONAL CONDITION 5, the Reactor Vessel, Reactor Cavity AND Dryer Separator Pools are in a Refueling configuration.

SM/CRS Date Time

HC.OP-IO.ZZ-0005(Q)

Hope Creek Page 26 of 37 Rev. 30 ATTACHMENT 2 PLACING THE PLANT IN ALTERNATE DECAY HEAT REMOVAL MODE OF OPERATION

1. System Engineering and/or Nuclear Fuels Group has provided the following information:

[CD-210E]

Analysis to determine Alternate Decay Heat Removal Methods.

System Engineer/Nuclear Fuels Date Time Time to Boil Calculations.

System Engineer/Nuclear Fuels Date Time Combined MBtu/hr vs. Days After Shutdown data tables System Engineer/Nuclear Fuels Date Time

2. The SM has been informed that the Alternate Decay Heat Removal method will adequately remove decay heat for the system lineup specified by System Engineering, IAW Technical Specification 3/4.9.11. (Alternate FPCC Assist mode may only satisfy the Action Statement requirements of 3/4.9.11.1)

SM Date Time

3. PLACE RWCU in the Regenerative Heat Exchanger Bypass Mode of operation IAW HC.OP-SO.BG-0001(Q), IF required.

SM/CRS/NCO Date Time

4. PLACE one, OR both, Fuel Pool Cooling Heat Exchangers in service IAW HC.OP-SO.EC-0001(Q).

SM/CRS/NCO Date Time

HC.OP-IO.ZZ-0005(Q)

Hope Creek Page 27 of 37 Rev. 30 ATTACHMENT 2 PLACING THE PLANT IN ALTERNATE DECAY HEAT REMOVAL MODE OF OPERATION

5. MAINTAIN flow through the core WITH either one Recirculation Pump, (IAW HC.OP-SO.BB-0002(Q)), OR one RHR Pump aligned for shutdown cooling WITH the Heat Exchanger bypassed, IAW HC.OP-SO.BC-0002(Q).

SM/CRS/NCO Date Time

6. C RHR Pump has been placed in service for Alternate Decay Heat Removal IAW HC.OP-AB.RPV-0009(Q). [CD-609G]

SM/CRS/NCO Date Time

7. D RHR Pump has been placed in service for Alternate Decay Heat Removal IAW HC.OP-AB.RPV-0009(Q). [CD-609G]

SM/CRS/NCO Date Time

8. RHR is in Alternate FPCC Assist mode IAW HC.OP-SO.BC-0002(Q), IF required.

SM/CRS/NCO Date Time

9. RWCU is being cooled by Chilled Water IAW HC.OP-SO.BC-0002(Q), IF required.

SM/CRS/NCO Date Time

10. Natural Circulation, with FPCC and RWCU as cooling medium is being utilized IAW HC.OP-SO.BC-0002(Q), IF required.

SM/CRS/NCO Date Time

HC.OP-IO.ZZ-0005(Q)

Hope Creek Page 28 of 37 Rev. 30 ATTACHMENT 3 VESSEL LEVEL INSTRUMENTATION TEMPERATURE COMPENSATION CURVES

HC.OP-IO.ZZ-0005(Q)

Hope Creek Page 29 of 37 Rev. 30 ATTACHMENT 3 VESSEL LEVEL INSTRUMENTATION TEMPERATURE COMPENSATION CURVES ACTUAL LEVEL INDICATED LEVEL

-150

-140

-130

-120

-110

-100

-90

-80

-70

-60

-50

-40

-30

-20

-10 00 10 20 30 40 50 60 0

50 100 150 0

-50

-100

-150

-200 550 450 350 250 150 REACTOR COOLANT TEMP øF GRAY AREA - INDICATED LEVEL RANGE TEMPERATURE COMPENSATION WIDE RANGE LEVEL

HC.OP-IO.ZZ-0005(Q)

Hope Creek Page 30 of 37 Rev. 30 ATTACHMENT 3 VESSEL LEVEL INSTRUMENTATION TEMPERATURE COMPENSATION CURVES UPSET RANGE LEVEL TEMPERATURE COMPENSATION GRAY AREA - INDICATED LEVEL RANGE ACTUAL LEVEL INDICATED LEVEL 0

20 40 60 80 100 120 140 160 180 0

50 100 150 200 250 0

-50 550 450 350 250 150 REACTOR COOLANT TEMP øF

HC.OP-IO.ZZ-0005(Q)

Hope Creek Page 31 of 37 Rev. 30 ATTACHMENT 3 VESSEL LEVEL INSTRUMENTATION TEMPERATURE COMPENSATION CURVE SHUTDOWN RANGE LEVEL TEMPERATURE COMPENSATION GRAY AREA - INDICATED LEVEL RANGE ACTUAL LEVEL INDICATED LEVEL 0

50 100 150 200 250 300 350 400 0

100 200 300 400 500 550 450 350 250 150 REACTOR COOLANT TEMP øF

HC.OP-IO.ZZ-0005(Q)

Hope Creek Page 32 of 37 Rev. 30 ATTACHMENT 4 INSTALLATION OF GAITRONICS COMMUNICATION CABLE TO REFUELING BRIDGE 1.0 INSTALLATION INSTRUCTIONS NOTE The Refuel Bridge should be positioned so that the west end of the bridge is not over the Fuel Pool.

CAUTION Junction Box #3 at the west end of the Refuel Bridge contains high voltage wiring for the Refuel Bridge motors AND receptacles.

Extreme care must be exercised to prevent dropping of small parts into the Fuel Pool, Cask Loading Pit, Equipment Pool OR other vital areas.

1.1 OBTAIN a communications cable from the Storeroom.

1.2 OPEN the cover on the Junction Box on the West end of the Refuel Bridge (JB3). (This is the Junction Box where the Refuel Bridge cable reel terminates).

1.3 CUT the end of the communication cable opposite the headset connection AND CONNECT to the termination points in Junction Box #3 as follows:

z Black Connector to JB3 TL1 z

White Conductor to JB3 TL2 z

Green Conductor to JB3 TL3 z

Red Conductor to JB3 TL4

HC.OP-IO.ZZ-0005(Q)

Hope Creek Page 33 of 37 Rev. 30 ATTACHMENT 4 INSTALLATION OF GAITRONICS COMMUNICATION CABLE TO REFUELING BRIDGE 1.4 ATTACH a Job Information tag to the cable. [CD-461E]

1.5 ROUTE the communication cable to the front of Junction Box #3 at the bottom.

1.6 SECURE the cable to the unistrut to prevent the cable from being pulled loose from the termination points inside the Junction Box.

1.7 CONNECT a headset to the temporary communications cable AND TEST communications to the Control Room using the Gaitronics isolate circuit.

1.8 RE-ATTACH the cover to Junction Box #3 on the West end of the Refuel Bridge.

1.9 CONFIRM communications established by calling the Control Room and confirming response.

1.10 NOTIFY the SM/CRS that the temporary Gaitronics Cable to the Refueling Bridge has been installed.

2.0 PERFORMER(S) AND VERIFIER(S)

PRINT SIGNATURE DATE

HC.OP-IO.ZZ-0005(Q)

Hope Creek Page 34 of 37 Rev. 30 ATTACHMENT 5 COOLDOWN TRANSIENT BOUNDARIES The transient assumptions used to support the flood up analysis are:

1. Cooldown from operating temperature 547°F to 150°F at 100°F/hr at normal water level of 30" (557.5" above vessel zero)
2. Flood up from normal water level, 557.5" above vessel zero, to the top of the head, 875" above vessel zero, at 15 inches per minute or 3212.8 gal/min. Source of water will be the condensate storage tank. The minimum temperature of this tank should be assumed to be 55°F. Normally this tank is maintained above 60°F.
3. After flood up cooldown to ambient temperature (100°F) at 100°F/hr.

The above is the data input for the analysis. It should be considered bounding. The procedure has conservative steps and values as guidelines, so these bounding values are not exceeded.

Having the Coolant Temperature warmer (160oF - 170oF) and Level higher (80 - 90), and filling the vessel at a slower rate (10/min.), maintains the cooldown rate of the Vessel Head less than that of the analysis, and therefore more conservative.

HC.OP-IO.ZZ-0005(Q)

Hope Creek Page 35 of 37 Rev. 30 ATTACHMENT 6 OPERATIONAL LIMITATIONS COMMENT PAGE Comments __________________________________________________________________

HC.OP-IO.ZZ-0005(Q)

Hope Creek Page 36 of 37 Rev. 30 ATTACHMENT 7 Raising Refuel Floor Exhaust High Radiation Setpoints Page 1 of 2 1.0 RAISING SETPOINTS TO A HIGH VALUE 1.1 Using RM-23A at H1SP -1SPRI-4856A, panel 10C604, PERFORM the following:

1.1.1.

SELECT Channel 1, ITEM 009.

1.1.2.

ENTER a setpoint value of 1.00 E-2.

1.1.3.

VERIFY the following:

  • Channel 1 red HIGH LED off (RM-23A) 1.2 Using RM-23A at H1SP -1SPRI-4856B, panel 10C604, PERFORM the following:

1.2.1.

SELECT Channel 1, ITEM 009.

1.2.2.

ENTER a setpoint value of 1.00 E-2.

1.2.3.

VERIFY the following:

  • Channel 1 red HIGH LED off (RM-23A) 1.3 Using RM-23A at H1SP -1SPRI-4856C, panel 10C604, PERFORM the following:

1.3.1.

SELECT Channel 1, ITEM 009.

1.3.2.

ENTER a setpoint value of 1.00 E-2.

1.3.3.

VERIFY the following:

  • Channel 1 red HIGH LED off (RM-23A)

HC.OP-IO.ZZ-0005(Q)

Hope Creek Page 37 of 37 Rev. 30 ATTACHMENT 7 Raising Refuel Floor Exhaust High Radiation Setpoints Page 2 of 2 2.0 RM-23A KEYBOARD/DISPLAY OPERATION Selecting Items: PRESS either MON key to select monitor items, or designated channel key to select channel items. PRESS numerically valued keys to obtain three digit item to be selected, then PRESS ITEM key. The present value of monitor or channel item will be displayed.

Entering Values: Monitor or channel item values are entered as a 3 (000),

or 4 (0000) digit array, or in engineering notation (0.00 E+00).

2.1 SELECT monitor or channel item to be changed as described above.

2.2 PRESS numerical keys to obtain desired value.

Example: CHANGE value of channel item 015 to a value of 1.00 E+5.

2.1 SELECT channel item 015.

2.2 Using numeric keys, PRESS "1", "0", "0", "+", "0", "5".

2.3 PRESS ENTER key, and OBSERVE value 1.00 E+5 is displayed.

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