ML110060157

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HC.OP-SO.BC-0002(Q), Rev. 25, Decay Heat Removal Operation
ML110060157
Person / Time
Site: Salem, Hope Creek  PSEG icon.png
Issue date: 10/01/2010
From:
Public Service Enterprise Group
To:
Office of Nuclear Reactor Regulation
References
LR-N10-0355 HC.OP-SO.BC-0002(Q), Rev 25
Download: ML110060157 (78)
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Text

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

Page 1 of 1 HOPE CREEK GENERATING STATION HC.OP-SO.BC-0002(Q) - Rev. 25 DECAY HEAT REMOVAL OPERATION USE CATEGORY: II

  • Packages and Affected Document Numbers incorporated into this revision:

CP No.

CP Rev.

AD No.

Rev No.

None 9

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

SUMMARY

  • Changes Steps 5.2.21.G and 5.2.21.H to use the same venting technique as in HC.OP-ST.BC-0001(Q). This is an editorial change. (70112053-0010)
  • Deleted Note 5.2.31 which was in conflict with Step 5.2.31. This note was added in error in the last revision and is an editorial change.

IMPLEMENTATION REQUIREMENTS Effective Date 10/1/10 None

HC.OP-SO.BC-0002(Q)

Hope Creek Page 1 of 77 Rev. 25 DECAY HEAT REMOVAL OPERATION TABLE OF CONTENTS Section Title Page 1.0 PURPOSE.............................................................................................................2 2.0 PREREQUISITES.................................................................................................2 3.0 PRECAUTIONS AND LIMITATIONS....................................................................4 4.0 EQUIPMENT REQUIRED...................................................................................13 5.0 PROCEDURE.....................................................................................................14 5.1 RHR Shutdown Cooling Suction Header Venting.....................................14 5.2 Placing the RHR System in Shutdown Cooling........................................16 5.3 Transfer of Shutdown Cooling to the Standby Shutdown Cooling Loop.........................................................................................................49 6.0 RECORDS..........................................................................................................54

7.0 REFERENCES

....................................................................................................54 ATTACHMENTS

, Independent Verification - Decay Heat Removal Operation..............................58, M&TE Installation and Removal for D/P Monitoring During Discharge Piping Pre-Warming...........................................................................................67 FIGURES Figure 1, RHR Pump Suction Valve Trip Interlocks..................................................................70 TABLES Table 1, Valve Table.................................................................................................................71 Table 2, Instrument Transmitter Functions...............................................................................77

HC.OP-SO.BC-0002(Q)

Hope Creek Page 2 of 77 Rev. 25 1.0 PURPOSE This procedure outlines the steps necessary for Filling and venting and operation of the Residual Heat Removal (RHR) System in the Shutdown Cooling mode of operations.

2.0 PREREQUISITES 2.1 RHR Shutdown Cooling Suction Header Venting 2.1.1.

All personnel performing any steps in this procedure should complete Attachment 1, Section 2.0, prior to performing any part of this procedure.

2.1.2.

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

2.1.3.

Radiation Protection has been notified prior to performing venting and/or draining in this procedure.

2.2 Placing the RHR System in Shutdown Cooling 2.2.1.

All personnel performing any steps in this procedure should complete Attachment 1, Section 2.0, prior to performing any part of this procedure.

2.2.2.

RHR System is in standby IAW HC.OP-SO.BC-0001(Q).

[CD-891D]

2.2.3.

Safety Auxiliaries Cooling Water System is in service supplying cooling water to RHR Pumps and Heat Exchangers to be used for shutdown cooling. [CD-562G]

2.2.4.

Condensate Storage and Transfer System AND/OR Demin Water System is in service.

2.2.5.

Liquid Radwaste System is in service.

2.2.6.

Chemistry Department has verified that the water in the Suppression Pool is within its Chemistry Specifications.

2.2.7.

IF RHR Loop A is to be used, THEN a thermocouple has been installed downstream of the 1-BC-V152 RHR PMP A DSCH HDR TO RW SUP VLV, OR a raytek (or equivalent) is available to monitor letdown temperature to the Liquid Radwaste System.

2.2.8.

Position indication for BC-HV-F050A/B is for the actuator position only.

HC.OP-SO.BC-0002(Q)

Hope Creek Page 3 of 77 Rev. 25 2.3 Transfer of Shutdown Cooling to the Standby Shutdown Cooling Loop 2.3.1.

All personnel performing any steps in this procedure should complete Attachment 1, Section 2.0, prior to performing any part of this procedure.

2.3.2.

One Loop of RHR is operating in Shutdown Cooling IAW Section 5.2.

2.3.3.

Safety Auxiliaries Cooling Water System is available to supply cooling water to RHR Pumps and Heat Exchangers to be placed in shutdown cooling.

2.3.4.

Liquid Radwaste System is in service.

2.3.5.

Chemistry Department has verified that the water in the Suppression Pool is within its Chemistry Specifications.

2.3.6.

If RHR Loop A is to be used, then a thermocouple has been installed downstream of the 1-BC-V152 RHR Pmp A Dsch Hdr to RW Sup Vlv, OR a raytek (or equivalent) is available to monitor letdown temperature to the Liquid Radwaste System.

2.3.7.

Condensate Storage and Transfer is in service.

HC.OP-SO.BC-0002(Q)

Hope Creek Page 4 of 77 Rev. 25 3.0 PRECAUTIONS AND LIMITATIONS 3.1 Precautions 3.1.1.

BC-HV-F024A(B) RHR LOOP TEST RET MOV will drain the Reactor Vessel to the Suppression Pool if opened in Shutdown Cooling. [CD-389B, CD-608D, CD-567E]

3.1.2.

BC-HV-F027A(B) RHR LOOP A(B) SUPP POOL SPRAY HDR ISLN MOV will drain the Reactor Vessel to the Suppression Pool if opened while the associated RHR Pump is in Shutdown Cooling. To prevent this from occurring, the BC-HV-F027A(B) is CLOSED and tagged while in Shutdown Cooling.

3.1.3.

BC-HV-F007A(B) RHR PUMP A(B) MIN FLOW MOV will drain the Reactor Vessel to the Suppression Pool if opened in Shutdown Cooling, due to flow below the low-flow setpoint precluding automatic valve closure. To prevent this from occurring, the BC-HV-F007A(B) is CLOSED and tagged while in Shutdown Cooling. [CD-389B, CD-608D, CD-567E]

3.1.4.

Opening BC-HV-F009 SHUTDOWN COOLING INBD ISLN MOV may cause a decrease in Reactor water level.

[CD-608D, CD-567E]

3.1.5.

IF Shutdown Cooling CAN NOT be placed in service and Reactor Recirc Pumps are NOT available, then the Reactor vessel level should be raised slowly to 80 inches, Reactor level shutdown range, using temperature compensated indication, (Vessel Level Instrumentation Temperature Compensation Curves may be required), to allow for natural circulation. Vessel metal temperatures above and below the water level, and Reactor Coolant System Temperature/Pressure Data should be monitored to ensure the T/S Cool Down limits are NOT exceeded. Also, the Reactor Water Cleanup system should be utilized in maximum cooling. [CD-693A, CD-178A, CD-973B]

3.1.6.

Discharge of water > 200°F to Liquid Radwaste System should NOT be allowed.

3.1.7.

DEFEATING the NSSSS Isolation Signals (including the loss of RPS power to NSSSS Isolation logic), to BC-HV-F008, BC-HV-F009, BC-HV-F015A AND BC-HV-F015B (Shutdown Cooling Valves), shall only be performed using HC.OP-GP.SM-0001(Q), Defeating NSSSS Isolation Signals For Shutdown Cooling. [CD-847E]

HC.OP-SO.BC-0002(Q)

Hope Creek Page 5 of 77 Rev. 25 3.1.8.

During plant Cooldown/Depressurization, similar Reactor water level instrumentation should be monitored for significant deviation (indicating possible reference line De-gassing)

AND all maintenance activities which have the potential of draining the Reactor Vessel should be terminated.

3.1.9.

During Shutdown Cooling Operations, isolation of SACS Cooling Water to the RHR Heat Exchanger could result in saturated conditions and subsequent water hammer transients when resuming cooling water flow. [CD-562G]

3.1.10.

The RHR System discharge manual cross-tie lines should NOT be used for normal Shutdown Cooling, Suppression Pool Cooling, or Suppression Pool Spray. The lines should only be used as an alternate decay heat removal (ADHR) path IAW HC.OP-AB.RPV-0009(Q), Shutdown Cooling. [CD-609G]

3.1.11.

Since the RHR System crosstie piping/valves were not tested with respect to the effects of thermal expansion on supports, restraints, and snubbers beyond 300 °F, crosstie flushing is prohibited when the flushing medium temperature is greater than 300 °F, or 67 psia (52.3 psig).

[70039531, UFSAR 3.9.2.2.2]

3.1.12.

The sampling requirements of UFSAR Section 5.2.3.2.2.2 should be met whenever the Reactor Coolant Chemistry sampling flowpaths have been isolated, and any alternate sampling method used should be temperature compensated.

3.1.13.

IF any instrument affected by this section appears to be indicating erroneously, THEN NOTIFY I&C to fill and vent the associated transmitter(s).

HC.OP-SO.BC-0002(Q)

Hope Creek Page 6 of 77 Rev. 25 3.2 Limitations 3.2.1.

Independent Verification may be performed following completion of the procedure activity or upon completion of each step. If performance of an ENSURE step which has an IV signoff results in NO component manipulation then the IV signoff should be N/Ad upon completion of the step.

3.2.2.

If valve or electrical lineup CANNOT be completed as required, then, the SM/CRS will determine whether the deviations are such that the system should NOT be placed in service or standby, as required.

3.2.3.

The Reactor Coolant System cooldown limitations of T/S 3/4.4.6 shall be observed.

3.2.4.

While the RHR System is operating in the Shutdown Cooling mode, any valve manipulations which would prevent ANY of the rated shutdown cooling flow ( 10,000 gpm) from returning to the reactor vessel via the respective Recirculation System discharge piping and jet pumps should NOT be performed. For example, recirc suction and discharge valves being open simultaneously in the loop seeing Shutdown Cooling return flow would result in a portion of the return flow being diverted back through the recirculation loop in the reverse direction, as opposed to into the respective jet pumps, where forced circulation through the core would occur. This limitation does NOT preclude reducing shutdown cooling flow to satisfy Limitations 3.2.21, 3.2.22 or 3.2.24 provided the Cavity is flooded, reducing reactor cavity level using Steps 5.2.38 or 5.2.39, or when intentionally reducing Shutdown Cooling flow to support Noble Metals Chemical Application. [CD-122H]

3.2.5.

While the RHR System is operating in the shutdown cooling mode, maintaining the rated shutdown cooling flow of approximately 10,000 GPM to the Reactor vessel via the respective Recirculation System discharge piping and Jet Pumps is essential to assure that the RHR Heat Exchanger inlet temperature is representative of actual bulk coolant temperature.

[CD-122H]

3.2.6.

During the transition from Shutdown Cooling operations to establishment of normal Reactor Recirculation System operations, the RHR System may be left in Shutdown Cooling, ONLY if BP202 is the RHR Pump in service AND AP201 is the Reactor Recirculation Pump to be started.

HC.OP-SO.BC-0002(Q)

Hope Creek Page 7 of 77 Rev. 25 3.2.7.

IF while the RHR System is operating in the shutdown cooling mode, a degraded shutdown cooling condition occurs, or IF there is indication that the RHR Heat Exchanger inlet temperature may NOT be representative of average reactor coolant temperature, then HC.OP-AB. RPV-0009(Q), Shutdown Cooling., should be referred to.

3.2.8.

The time when NEITHER the RHR System (operating in the Shutdown Cooling Mode) OR the Reactor Recirculation System is in operation should be minimized.

3.2.9.

During the transition from normal Reactor Recirculation System operations to establishment of Shutdown Cooling, only the AP201 Reactor Recirculation Pump may be left in operation until the BP202 RHR pump is operating satisfactorily, and then only until the required B RHR Loop flow of 10,000 gpm is achieved.

This limitation does NOT apply when Noble Metals Chemical Application is to be performed during plant shutdown.

3.2.10.

The Discharge Valve of any Reactor Recirculation Pump which is NOT in operation must be closed prior to establishing forced circulation using the RHR System in the Shutdown Cooling Mode of operation. Opening an idle reactor recirculation pump Discharge valve during Shutdown Cooling operations may be performed provided that the associated reactor recirculation pump Suction valve is closed. [CD-739A, CD-781A]

3.2.11.

B RHR is preferred to be used for Shutdown Cooling operation due to its Liquid Radwaste System connection. B RHR when combined with A Reactor Recirc Loop provides continuous forced circulation during the transition to Shutdown Cooling operations. B RHR or A RHR should only be placed in service once the differential temperature between the Reactor Vessel water and the water in the RHR Loop to be placed in service is less than 100°F.

3.2.12.

The RHR loop used for shutdown cooling should be associated with the SACS loop that is NOT supplying TACS.

HC.OP-SO.BC-0002(Q)

Hope Creek Page 8 of 77 Rev. 25 3.2.13.

The following parameters should be used if there is uncertainty as to whether the plant has entered Operational Condition 3 or as additional indications for monitoring purposes. IF the following indications are indicative of an Operational Condition change then, the appropriate reports should be initiated:

[CD-122H]

  • An increase in Reactor Head Vent temperature could be indicative of the onset or verify the presence of boiling in the vessel. This temperature is monitored by TE-N064 (when BB-HV-F001 and BB-HV-F002 are open), and can be read on the Control Room recorder B21-TRR614 - point 24, Reactor Head Vent.
  • 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.

(continued on next page)

HC.OP-SO.BC-0002(Q)

Hope Creek Page 9 of 77 Rev. 25 3.2.13 (continued)

  • An increase in steam dome pressure could be indicative that boiling, to some degree, is occurring in the reactor core. This parameter should be monitored using the redundant Reactor pressure indications given in Table 3.2.13, particularly those with the lowest ranges such as Reactor Low Range Pressure or the HPCI and RCIC trip units.

Table 3.2.13 REDUNDANT REACTOR VESSEL PRESSURE INDICATIONS NOMENCLATURE RANGE DESCRIPTION CONTROL ROOM PANEL 10-C650 PI-5824A 0 - 50 REACTOR LOW RANGE PRESSURE PI-5824B 0 - 50 REACTOR LOW RANGE PRESSURE PI-R605-C32 0 - 1200 REACTOR PRESSURE PR-R623A-B21 0 - 1500 PAMS PR-R623B-B21 0 - 1500 PAMS PI-3684A 0 - 1500 PAMS PI-3684B 0 - 1500 PAMS LOWER RELAY ROOM PANEL 10-C617 1FDPISL-N658A-E41 0 - 200 HPCI TRIP UNIT 1FDPISL-N658E-E41 0 - 200 HPCI TRIP UNIT LOWER RELAY ROOM PANEL 10-C641 1FDPISL-N658C-E41 0 - 200 HPCI TRIP UNIT 1FDPISL-N658G-E41 0 - 200 HPCI TRIP UNIT LOWER RELAY ROOM PANEL 10-C618 1FCPISL-N658B-E51 0 - 200 RCIC TRIP UNIT 1FCPISL-N658F-E51 0 - 200 RCIC TRIP UNIT LOWER RELAY ROOM PANEL 10-C631 1FCPISL-N658D-E51 0 - 200 RCIC TRIP UNIT 1FCPISL-N658H-E51 0 - 200 RCIC TRIP UNIT 3.2.14.

While operating in Shutdown Cooling with the Reactor Vessel temperature below 200°F, the Reactor water level should be maintained at 80 inches, shutdown range (upset range while reactor vessel disassembly is in progress) to allow for natural circulation in the event that forced circulation is lost.

Temperature-compensated indication should be used (Vessel Level Instrumentation Temperature Compensation Curves may be required). [CD-693A, CD-178A, CD-973B]

HC.OP-SO.BC-0002(Q)

Hope Creek Page 10 of 77 Rev. 25 3.2.15.

WHEN the Reactor Vessel temperature is below 200°F, the time the RHR System is operating in the Shutdown Cooling mode WITH the Reactor Vessel level 80 inches should be minimized.

3.2.16.

The RHR Shutdown Cooling operability requirements of T/S 3.4.9 and 3.9.11 shall be observed.

3.2.17.

The Depressurization Systems (Suppression Pool) operability requirements of T/S 3/4.6.2 shall be observed.

3.2.18.

The valves listed in Table BC-001 will isolate upon receipt of ANY of the following signals:

  • RPV Level Low (Level 3, + 12.5").
  • RPV High Pressure (82 psig).
  • Manual Isolation.

TABLE BC-001 EQUIPMENT NUMBER DESCRIPTION POSITION BC-HV-F008 SD COOLING OUTBD ISLN MOV CLOSE BC-HV-F009 SD COOLING INBD ISLN MOV CLOSE BC-HV-F015A(B)

RHR LOOP A(B) RET TO RECIRC CLOSE 3.2.19.

The valves listed in Table BC-002 will isolate upon receipt of ANY of the following signals:

  • RPV Level Low (Level 3, + 12.5").
  • Drywell Pressure High ( 1.68 psig).
  • Manual Isolation.

TABLE BC-002 EQUIPMENT NUMBER DESCRIPTION POSITION BC-HV-F049 RHR LOOP B DSCH TO LIQ RW ISLN MOV CLOSE BC-HV-F040 RHR LOOP B DSCH TO LIQ RW ISLN MOV CLOSE 3.2.20.

All pump operations should be performed IAW OP-HC-108-106-1001, Equipment Operational Control.

HC.OP-SO.BC-0002(Q)

Hope Creek Page 11 of 77 Rev. 25 3.2.21.

During refueling operations in which any LPRM, SRM, IRM or Neutron Source Holder assemblies are NOT completely surrounded by fuel and/or blade guides to provide lateral support, limitations on total flow through the core region are required. Combined total flow through the core region shall be limited to a maximum value of 23,000 gpm. This corresponds to a maximum RHR System Shutdown Cooling flow of 7000 gpm.

[CD-989B]

3.2.22.

During refueling operations with the cavity flooded, RHR System Shutdown Cooling flow may be reduced to 7000 gpm to support in-vessel work.

3.2.23.

The NSSSS is required to be reset prior to establishing a shutdown cooling flowpath.

3.2.24.

The following RHR Pump flow limitations shall be complied with at all times: [70044148]

Continuous Duty - Pump flow should be >1,800 gpm under continuous duty. Continuous duty is defined as operation of

> 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period.

Low Flow Duty - Pump flow between 500 - 1,800 gpm is limited to 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period.

Low Low Flow Duty - Pump flow between 400 - 500 gpm is limited to 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period.

Starts/Stops - During pump starts and stops, flow can be very low. Pump flow < 400 gpm is limited to 1/2 hour in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period.

3.2.25.

RHR Pump operation should be avoided at flows above 11,000 gpm to prevent pump runout.

3.2.26.

Valves and breakers will be manipulated during this procedure for positive control to prevent vessel drain down events. When tagging is performed after the valves and breakers are positioned, then refer to Attachment 1 and verify proper documentation of required position.

HC.OP-SO.BC-0002(Q)

Hope Creek Page 12 of 77 Rev. 25 3.3 Interlocks 3.3.1.

BC-HV-F048A(B) A(B) RHR HX SHELL SIDE BYP MOV CAN NOT be closed for 3 minutes following a LPCI initiation.

3.3.2.

ALL the following valves must be closed to allow opening BC-HV-F006A(B) RHR PMP A(B) SUCT FROM RECIRC:

  • BC-HV-F004A(B) A(B) RHR PMP SUPP POOL SUCT MOV
  • BC-HV-F027A(B) RHR LOOP A(B) SUPP CHAMBER SPRAY HDR ISLN MOV 3.3.3.

WHEN BC-HV-F006A(B) is opened, the associated BC-HV-F004A(B) OR BC-HV-F024A(B) CAN NOT be electrically opened.

3.3.4.

HV-F007A(B,C,D) RHR PMP A(B,C.D) MIN FLOW MOV, will automatically close if its respective loop pump discharge flow is

> 1250 gpm. It will automatically open (after a 10 second time delay) if its respective loop pump is running and its discharge flow is < 1250 gpm.

3.3.5.

The RHR A(B) FPC MODE SUCT VLV CLOSURE TRIP OVERRIDE keylock switch(es), located on 10C617 (10C618)

Division 1(2) RHR & CS Relay VB, inhibit the trip/start permissive of A(B) RHR Pumps upon loss of suction flow path.

This enables start of A(B) RHR Pump with the Shutdown Cooling Suction Valves, BC-HV-F008 & BC-HV-F009, and The Torus Suction Valves, BC-HV-F004A(B) closed. ALL interlocks, isolations, and initiations of the RHR System are unaffected with the exception of the pump trip/start permissive described above.

The SM must review and approve use of this override.

[CD-847E]

HC.OP-SO.BC-0002(Q)

Hope Creek Page 13 of 77 Rev. 25 3.3.6.

Remote operation of BC-HV-F008 is dependent upon the position of Keylock Switch HS-11495 RHR SUCTION CLG OTBD ISOL VLV LOCAL ISOL SW, located on MCC 10B242 Bkr 242082. The two-position switch affects valve operation as follows:

  • In the ARMED position full control of the valve is available from the Control Room or RSP.
  • In the DISARMED position the opening control circuit is disabled to prevent inadvertent opening of the valve. The valve position indication and alarms will remain functional.

3.3.7.

To ensure an adequate suction path and allow the RHR pump to operate the following must be satisfied: (REFER to Figure #1)

  • For RHR pump C or D:

F004C(D) must be 100% OPEN.

  • For RHR pump A or B EITHER:

(Note: may be overridden)

HV-F004A(B) must be open OR HV-F006A(B), HV-F008 and HV-F009 must ALL be OPEN If this valve alignment is not satisfied, the respective pump breaker will trip immediately upon breaker closure, or if the pump is running and the valves are < 100% open the pump breaker will trip.

4.0 EQUIPMENT REQUIRED

  • 12" Pipe wrench or equivalent
  • Hoses
  • Valves seals
  • Key #10 (For remote operation of BC-HV-F008 Keylock Switch HS-11495)
  • Pressure gauge for determining if system is experiencing voiding during the pre-warm of the discharge piping (prior to placing Shutdown Cooling in service). Gauge should be ~0-200 psig (Expected reading should be <82 psig. Gauge to be installed at P-BC-V9946 (V9958) PP-N058A(B)
  • Raytek or other equivalent temperature-sensing device (A loop only)
  • Demin Water supply rig (double check valve, drain valve and isolation valve)

(if required)

HC.OP-SO.BC-0002(Q)

Hope Creek Page 14 of 77 Rev. 25 5.0 PROCEDURE NOTE All operations are performed from Panel 10C650, Section A, unless otherwise noted.

Local Panel 10C618 is located in the Control/Diesel Generator Bldg. Elev. 102' Room 5302.

5.1 RHR Shutdown Cooling Suction Header Venting 5.1.1.

ENSURE all prerequisites have been satisfied IAW Section 2.1.

5.1.2.

DEPRESSURIZE the RHR Shutdown Cooling Suction Header piping IAW one of the following methodologies:

A.

DEPRESSURIZE using 1-BC-V165 and 1-BC-V166 RHR SDC Suct Vnt Vlvs (RB 102, Rm 4329)

THEN INITIAL Attachment 1.

OR NOTE Tech Spec 3.4.3.2 Action d for 1BCPISH-N657 should be complied with when performing the following venting.

B.

DEPRESSURIZE using 1BCPT-N057-E11, SHUTDN CLG TO RHR PUMPS pressure transmitter as follows:

1.

REMOVE fitting cap from 1BCPT-N057 tubing drain line (i.e., downstream of P-BC-V-9947-HD)

2.

ATTACH drain tubing with fitting to P-BC-V9947-HD AND ROUTE to drain.

3.

ESTABLISH communications between E11-N657 (Panel 10C618 - Lower Relay Room) and 1BCPT-N057 (RB 77 Rm 4216) and Main Control Room.

4.

LOG initial pressure on 1BCPT-N057, date, and time in Control Room Log(s).

5.

THROTTLE OPEN P-BC-V9947-HD (1/8 to 1/4 turn from full closed)

6.

MONITOR E11-N657 for pressure decrease.

continued on next page

HC.OP-SO.BC-0002(Q)

Hope Creek Page 15 of 77 Rev. 25 5.1.2.B (continued)

NOTE Previous performance conducted with the P-BC-V9947-HD throttled open 1/8 turn required 15 min for line to depressurize from 145 psig to 25 psig.

7.

WHEN pressure on E11-N657 decreases to 0 psig THEN CLOSE P-BC-V9947-HD AND INITIAL.

8.

LOG final pressure as read on E11-N657, date, and time in Control Room Log(s).

9.

REMOVE drain tubing and fitting from P-BC-V9947-HD.

10. RE-INSTALL fitting cap on 1BCPT-N057 drain line.
11. PERFORM independent verification IAW Attachment 1.

HC.OP-SO.BC-0002(Q)

Hope Creek Page 16 of 77 Rev. 25 5.2 Placing the RHR System in Shutdown Cooling 5.2.1.

ENSURE all prerequisites have been satisfied IAW Section 2.2.

5.2.2.

ENSURE all Precautions and Limitations applicable to Shutdown Cooling operation have been reviewed for applicability.

NOTE Step 5.2.3 can be performed in concurrently with Steps 5.2.4 through 5.2.26.F.

5.2.3.

INSTALL Measuring and Test Equipment (M&TE) as specified in Section 4.0 and IAW Attachment 2 - D/P Monitoring During Discharge Piping Pre-Warming NOTE Verify Condensate Storage and Transfer System pressure control valve can maintain 140 psig. This should be performed prior to the completion of the RHR system flush to determine if use of Demin Water system is required.

Step 5.2.4 can be performed concurrently with Steps 5.2.7 through 5.2.20 5.2.4.

FOR Condensate Storage And Transfer System, PERFORM the following:

A.

PLACE the following Condensate Storage and Transfer pumps and Refueling Water Pump in STOP (Local Panel 00C113): (Refueling Water Pump hand-switch is a spring return to normal switch)

  • HS-2061A CNDS TRANSFER PUMP 0AP155 MOTOR
  • HS-2061B CNDS TRANSFER PUMP 0BP155 MOTOR
  • HS-2063A OR B CNDS JKY XFR PUMP 0B(A)P156 MOTOR (whichever Jky Pmp is NOT in lead on HSS-2063)
  • HS-2054A-2 REFUEL WATER PUMP 0AP157 B.

ADJUST PIC-2044A CNDS XFR PUMPS DISCHARGE PRESS controller to ~ 140 psig (Local Panel 00C113).

C.

VERIFY PIC-2044A CNDS XFR PUMPS DISCHARGE PRESS controller is maintaining pressure ~ 140 psig (Local Panel 00C113).

HC.OP-SO.BC-0002(Q)

Hope Creek Page 17 of 77 Rev. 25 5.2.5.

PLACE the following Condensate Storage and Transfer pumps and Refueling Water Pump in their normal (auto) position (Local Panel 00C113): (Refueling Water Pump hand-switch is a spring return to normal switch)

  • HS-2061A CNDS TRANSFER PUMP 0AP155 MOTOR
  • HS-2061B CNDS TRANSFER PUMP 0BP155 MOTOR
  • HS-2063A OR B CNDS JKY XFR PUMP 0B(A)P156 MOTOR (whichever Jky Pmp is NOT in lead on HSS-2063)
  • HS-2054A-2 REFUEL WATER PUMP 0AP157 5.2.6.

ADJUST PIC-2044A CNDS XFR PUMPS DISCHARGE PRESS controller to ~ 150 psig (Local Panel 00C113).

5.2.7.

ENSURE the following valves are OPEN:

  • BC-HV-F047A(B) RHR HX SHELL SIDE INLET MOV
  • BC-HV-F003A(B) RHR HX A(B) OUTLET VLV 5.2.8.

ENSURE BC-HV-F048A(B) RHR HX SHELL SIDE BYP MOV is CLOSED.

NOTE RHR Pump and piping is flushed with clean Torus water for ten minutes at 8,000 to 10,000 gpm PRIOR to placing the loop in shutdown cooling. [CD-937A]

5.2.9.

START the A(B)P202 RHR PUMP, AND THROTTLE OPEN BC-HV-F024A(B) RHR LOOP A(B)

TEST RET MOV, UNTIL FI-R603A(B) or FR-R608A(B) - CRIDS A3137(A3139),

LOOP A(B) FLOW indicates 8,000 to 10,000 gpm.

5.2.10.

WHEN 5 minutes have elapsed THEN OPEN BC-HV-F048A(B) RHR HX SHELL SIDE BYP MOV.

HC.OP-SO.BC-0002(Q)

Hope Creek Page 18 of 77 Rev. 25 5.2.11.

DIRECT Chemistry Department to perform the following:

A.

PERFORM the following to set up sample:

1.

OPEN BC-HV-F079A(B) HX A(B) SAMPLE LINE INBD ISLN VLV.

2.

OPEN BC-HV-F080A(B) HX A(B) SAMPLE LINE OUTBD ISLN VLV.

B.

MONITOR the RHR HX Outlet Sample for conductivity at the Reactor Building Sample Station 5.2.12.

WHEN the RHR HX Outlet conductivity sample results are received, PERFORM the following, as applicable:

A.

IF conductivity at Hx Outlet is 1.0 µmho/cm, THEN, PROCEED to Step 5.2.13.

B.

IF conductivity at Hx Outlet is between 1.0 - 2.0 µmho/cm, THEN, PERFORM the following:

1.

DIRECT the Chemistry Department to VERIFY if Reactor Coolant conductivity is 1.0 µmho/cm AFTER Shutdown Cooling is in service.

2.

IF Reactor Coolant conductivity is > 1.0 µmho/cm THEN, MAXIMIZE Reactor Water Cleanup Filter Flow AND RPV cooldown within the limits of T/S UNTIL 200°F.

3.

PROCEED to Step 5.2.13.

C.

IF conductivity at Hx Outlet is > 2.0 µmho/cm, THEN, PERFORM the following:

1.

CONTINUE RHR Pump AND piping flush UNTIL conductivity matches Torus water conductivity or until 2.0 µmho/cm.

2.

PROCEED to Step 5.2.13 AND PERFORM actions as specified in 5.2.13.B.

HC.OP-SO.BC-0002(Q)

Hope Creek Page 19 of 77 Rev. 25 5.2.13.

WHEN RHR HX Outlet conductivity sample is no longer required, THEN, CLOSE the following valves AND INITIAL Attachment 1:

A.

BC-HV-F080A(B) HX A(B) SAMPLE LINE OUTBD ISLN VLV.

B.

BC-HV-F079A(B) HX A(B) SAMPLE LINE INBD ISLN VLV.

5.2.14.

PERFORM the following to shut down the A(B) RHR Pump:

NOTE Steps 5.2.14.A through 5.2.14.C should be performed in rapid succession.

A.

CLOSE BC-HV-F024A(B) RHR LOOP A(B) TEST RET MOV AND INITIAL Attachment 1.

B.

WHEN BC-HV-F024A(B) RHR LOOP A(B) TEST RET MOV is fully closed, THEN, VERIFY BC-HV-F007A(B) auto opens.

C.

WHEN BC-HV-F007A(B) is full open, THEN, STOP the A(B)P202 RHR PUMP.

NOTE 5.2.21.D through 5.2.21.E.2 may be performed concurrently with 5.2.15 through 5.2.21.C.

5.2.15.

CLOSE BC-HV-F003A(B) RHR HX A(B) OUTLET VLV.

5.2.16.

ENSURE BC-HV-F048A(B) A(B) RHR HX SHELL SIDE BYP MOV is OPEN. [70041940]

5.2.17.

CLOSE BC-HV-F004A(B) A(B) RHR PMP SUPP POOL SUCT MOV AND INITIAL Attachment 1.

HC.OP-SO.BC-0002(Q)

Hope Creek Page 20 of 77 Rev. 25 NOTE This section may be continued once the valve is re-positioned and its breaker opened (step completion signoff after safety tagging completed).

BC-HV-F006A(B) RHR PMP A(B) SUCT FROM RECIRC will not open if BC-HV-F004A(B) RHR PMP SUPP POOL SUCT MOV OR BC-HV-F024A(B) RHR LOOP A(B) TEST RET MOV OR BC-HV-F027A(B) RHR LOOP A(B) SUPP POOL SPRAY HDR ISLN MOV are OPEN.

BC-HV-F024A(B) RHR PMP FULL FLOW TEST AND BC-HV-F004A(B) RHR PMP SUPP POOL SUCT MOV will not open if the associated BC-HV-F006A(B) is OPEN.

BC-HV-F027A(B) RHR LOOP A(B) SUPP POOL SPRAY HDR ISLN MOV will drain the Reactor Vessel to the Suppression Pool if opened while the associated RHR pump is in shutdown cooling.

1-BC-V315 (V314) SUP POOL SPRY HDR MAN ISLN VLV may be tagged CLOSED instead of tagging the associated breaker for the BC-HV-F027A(B)

(if required to support outage activities), although BC-HV-F027A(B) must still be closed.

5.2.18.

VERIFY BC-HV-F027A(B) is CLOSED THEN OPEN breaker 52-212083 (52-222083)

AND INITIAL Attachment 1 THEN TAG breaker open.

5.2.19.

CLOSE BC-HV-F007A(B) RHR PMP A(B) MIN FLOW MOV THEN OPEN breaker 52-212041(52-222041)

AND INITIAL Attachment 1 THEN TAG breaker open.

5.2.20.

OPEN BC-HV-F006A(B) RHR PMP A(B) SUCT FROM RECIRC.

HC.OP-SO.BC-0002(Q)

Hope Creek Page 21 of 77 Rev. 25 CAUTION The following fill and vent steps assume that the BC-HV-F008 AND BC-HV-F009 are closed as an initial condition.

5.2.21.

PERFORM the following to fill and vent the Shutdown Cooling suction piping for the RHR Loop to be placed in service:

[CD-891D]

A.

PRESS NUCLEAR STEAM SUPPLY SHUTOFF SYSTEM TRIP LOGIC A RESET AND TRIP LOGIC D RESET PBs.

B.

PLACE BC-HV-F008 SHUTDOWN COOLING OUTBD ISLN MOV Keylock Switch HS-11495 in the ARMED position (10B242 Bkr 242082), AND LOG in Control Room log(s).

C.

OPEN BC-HV-F008 S/D COOLING OUTBD ISLN MOV.

NOTE Main Control Room Overhead Alarm A6-C5; RHR S/D CLG SUCTION HDR PRESSURE HI, is expected to alarm while the fill and vent is being performed. Monitor suppression pool level during fill and vent.

WHEN the fill and vent is being performed as part of the restoration following a loss of shutdown cooling, Steps 5.2.21.D through 5.2.21.J are NOT required to be performed WHEN alternate SDC is established initially using the C or D RHR pumps, Steps 5.2.21.D through 5.2.21.J are required to be performed.

D.

Either Condensate Storage and Transfer or Demin water can be used for supplying water to vent SDC suction piping. System pressure must be maintained below 150 psig to prevent lifting RHR system relief valves. (either Step 5.2.21.E or 5.2.21.F).

(continued on next page)

HC.OP-SO.BC-0002(Q)

Hope Creek Page 22 of 77 Rev. 25 5.2.21 (continued)

E.

IF using Condensate Storage And Transfer System, PERFORM the following:

1.

PLACE the following Condensate Storage and Transfer pumps and Refueling Water Pump in STOP (Local Panel 00C113): (Refueling Water Pump hand-switch is a spring return to normal switch)

  • HS-2061A CNDS TRANSFER PUMP 0AP155 MOTOR
  • HS-2061B CNDS TRANSFER PUMP 0BP155 MOTOR
  • HS-2063A OR B CNDS JKY XFR PUMP 0B(A)P156 MOTOR (whichever Jky Pmp is NOT in lead on HSS-2063)
  • HS-2054A-2 REFUEL WATER PUMP 0AP157
2.

ADJUST PIC-2044A CNDS XFR PUMPS DISCHARGE PRESS controller to ~ 140 psig (Local Panel 00C113).

3.

VERIFY PIC-2044A CNDS XFR PUMPS DISCHARGE PRESS controller is maintaining pressure ~ 140 psig (Local Panel 00C113).

4.

UNLOCK AND OPEN 1-AP-V048 Cond Stor & Xfr to RHR B Suct Hdr Fill & Flush Isln Vlv (local).

5.

UNLOCK AND SLOWLY crack open 1-BC-V191 Cond Stor & Xfr to Recirc Suct. 2-3 turns.

6.

GO TO Step 5.2.21.G.

(continued on next page)

HC.OP-SO.BC-0002(Q)

Hope Creek Page 23 of 77 Rev. 25 5.2.21 (continued)

F.

IF using Demin Water, PERFORM the following:

1.

INSTALL Demin Water supply to supply rig and FLUSH hoses for approximately 5 minutes.

2.

CLOSE Demin Water isolation valve (hose outlet).

3.

REMOVE cap and CONNECT supply hose to 1-BC-V167/168 RCIRC LOOP B TO RHR SUP TC ISO (room 4329).

4.

OPEN 1-BC-V167/168 RCIRC LOOP B TO RHR SUP TC ISO.

5.

OPEN Demin Water isolation valve(hose outlet).

NOTE 5.2.21.G and 5.2.21.H may be performed concurrently. If water is not coming out of the vent, 1-BC-V165/166 and both vent flow paths are open, close 1-BC-V165/166 and perform venting in order.

G.

VENT the Shutdown Cooling Suction piping as follows:

1.

OPEN 1-BC-V285, RHR Suct From Recirc LP B Vnt (Top of Torus - Inboard from 180° Az).

2.

CRACK OPEN 1-BC-V284, RHR Suct from Recirc LP B Vnt (Top of Torus - Inboard from 180° Az) 1/2 to 1 turn UNTIL no air appears after at least two minutes AND a solid stream of water issues from the high point vent THEN CLOSE 1-BC-V284.

3.

WAIT at least 30 seconds, AND VENT using 1-BC-V284, RHR Suct from Recirc LP B Vnt

4.

IF air bubbles were observed in Step, 5.2.21.G.3 THEN REPEAT Steps 5.2.21.G.2 thru 5.2.21.G.4.

5.

ENSURE 1-BC-V284, RHR Suct from Recirc LP B Vnt is CLOSED AND CLOSE AND LOCK 1-BC-V285, RHR Suct From Recirc LP B Vnt AND RECORD performer and verifier on Attachment 1.

(continued on next page)

HC.OP-SO.BC-0002(Q)

Hope Creek Page 24 of 77 Rev. 25 5.2.21.G (continued)

H.

VENT the Shutdown Cooling Suction piping as follows:

1.

OPEN 1-BC-V165, Recirc Loop B to RHR Vnt Isln (North Pipe Chase).

2.

CRACK OPEN 1-BC-V166, Recirc Loop B to RHR Vnt (North Pipe Chase) 1/2 to 1 turn UNTIL no air appears after at least two minutes AND a solid stream of water issues from the high point vent THEN CLOSE 1-BC-V166.

3.

WAIT at least 30 seconds, AND VENT using 1-BC-V166, Recirc Loop B to RHR Vnt.

4.

IF air bubbles were observed in Step, 5.2.21.H.3 THEN REPEAT Steps 5.2.21.H.2 thru 5.2.21.H.4.

5.

ENSURE 1-BC-V166, Recirc Loop B to RHR Vnt is CLOSED AND CLOSE AND LOCK 1-BC-V165, Recirc Loop B to RHR Vnt Isln AND RECORD performer and verifier on.

I.

IF Condensate Storage and Transfer was used, PERFORM the following:

1.

CLOSE AND LOCK 1-BC-V191 AND INITIAL Attachment 1.

2.

CLOSE AND LOCK 1-AP-V048 (local)

AND INITIAL Attachment 1.

(continued on next page)

HC.OP-SO.BC-0002(Q)

Hope Creek Page 25 of 77 Rev. 25 5.2.21 (continued)

J.

IF Demin Water was used, PERFORM the following:

1.

CLOSE and LOCK 1-BC-V167/168 RCIRC LOOP B TO RHR SUP TC ISO and INITIAL on Attachment 1.

for 1-BC-V167.

2.

ISOLATE and DRAIN Demin Water supply rig.

3.

CLOSE Demin Water isolation valve (hose outlet).

4.

REMOVE hose from 1-BC-V167/168 RCIRC LOOP B TO RHR SUP TC ISO.

5.

INSTALL CAP on 1-BC-V168 RCIRC LOOP B TO RHR SUP TC ISO and INITIAL on Attachment 1.

6.

REMOVE and STORE Demin Water Supply rig.

5.2.22.

ENSURE Main Control Room Overhead Alarm A6-C5; RHR S/D CLG SUCTION HDR PRESSURE HI, is CLEAR.

CAUTION While in shutdown cooling the following valves must remain closed to prevent uncontrolled drainage from the Reactor Vessel:

[CD-389B, CD-608D, CD-157E, CD-567E]

BC-HV-F004A(B) RHR PMP A(B) SUPP POOL SUCT MOV BC-HV-F024A(B) RHR LOOP A(B) TEST RET MOV BC-HV-F010A(B) RHR LOOP C(D) TEST RET MOV BC-HV-F007A(B) RHR PMP A(B) MIN FLOW MOV BC-HV-F027A(B) RHR LOOP A(B) SUPP POOL SPRAY HDR ISLN MOV Opening BC-HV-F009 SHUTDOWN COOLING INBD ISLN MOV may cause decrease in Reactor water level. [CD-608D, CD-157E, CD-567E]

5.2.23.

OPEN BC-HV-F009 SHUTDOWN COOLING INBD ISLN MOV.

HC.OP-SO.BC-0002(Q)

Hope Creek Page 26 of 77 Rev. 25 NOTE Steps 5.2.24 through 5.2.25 can be performed concurrently with Step 5.2.26.

5.2.24.

PLACE the following Condensate Storage and Transfer pumps and Refueling Water Pump in their normal (auto) position (Local Panel 00C113): (Refueling Water Pump hand-switch is a spring return to normal switch)

  • HS-2061A CNDS TRANSFER PUMP 0AP155 MOTOR
  • HS-2061B CNDS TRANSFER PUMP 0BP155 MOTOR
  • HS-2063A OR B CNDS JKY XFR PUMP 0B(A)P156 MOTOR (whichever Jky Pmp is NOT in lead on HSS-2063)
  • HS-2054A-2 REFUEL WATER PUMP 0AP157 5.2.25.

ADJUST PIC-2044A CNDS XFR PUMPS DISCHARGE PRESS controller to ~ 150 psig (Local Panel 00C113).

NOTE Prior to commencing RHR Loop warm-up, the Radwaste Control Room should be notified to ensure available capacity ( 10,000 - 15,000 gals).

RHR Loop B or RHR Loop A prewarming is required if the differential temperature between the reactor vessel water and the RHR loop to be used is greater than 100°F.

5.2.26.

PERFORM the following to warm up the B RHR Loop so that it may be placed in Shutdown Cooling:

A.

UNLOCK AND CLOSE 1-BC-V262 ECCS Jockey Pmp D Disch to RHR Loop B (local). [PR 961104058]

B.

ENSURE BC-HV-4439 LP B DSCH TO LIQ RW is OPEN.

C.

OPEN BC-HV-F049 RHR LOOP B DSCH TO LIQ RW ISLN MOV.

(continued on next page)

HC.OP-SO.BC-0002(Q)

Hope Creek Page 27 of 77 Rev. 25 5.2.26 (continued)

NOTE To prevent exceeding heatup rate, BC-HV-F040 should be pressed for approx. 2 - 3 seconds then released while temperature is being monitored. If further adjustments to BC-HV-F040 are required, then they should be made in small increments.

Step 5.2.26.D will allow reactor vessel water to flow from the recirc shutdown cooling connection to radwaste, bypassing the RHR heat exchanger.

D.

THROTTLE OPEN BC-HV-F040 RHR LOOP B DSCH TO LIQ RW ISLN MOV to achieve required heatup of the suction portion of the B RHR Loop.

CAUTION Water > 200°F should NOT be discharged to the liquid radwaste system. Reactor vessel level should be monitored during the following evolution.

E.

MONITOR TE-N032 (TR-R605, Channel 7).

F.

WHEN temperature reaches 180° to 200°F THEN, CLOSE BC-HV-F040.

G.

CLOSE BC-HV-F006B RHR PMP B SUCT FROM RECIRC.

NOTE If the HV-F050B does not open after multiple attempts then continue and warm up the line using the HV-F122B only.

CAUTION If the HV F050B is not open, and the flow is passing through the HV F122B only (although the HV F050B may be passing some flow HV F122B piping 1 diameter/orifice), minimize BC-HV-F040 opening to prevent voiding of RHR piping.

[70030917]

H.

PRESS AND HOLD HV F050B/HV F122B RHR LOOP B SHTDN COOL ISLN CHECK VLV test open Pb.

(continued on next page)

HC.OP-SO.BC-0002(Q)

Hope Creek Page 28 of 77 Rev. 25 5.2.26 (continued)

I.

WHILE monitoring the open position of F050B, OPEN BC-HV-F015B RHR LOOP B RET TO RECIRC.

J.

IF the HV F050B closed while the BC-HV-F015B was being opened in Step 5.2.26.I THEN:

1.

RE-CLOSE BC-HV-F015B

2.

RELEASE then PRESS AND HOLD HV F050B/HV F122B test open Pb

3.

VERIFY HV F050B indicates open.

4.

REPEAT Step 5.2.26.I.

K.

OPEN P-BC-V9958 gauge isolation at PP-N058B RHR LPCI INJECTION LINE B Instrument Root Valve. (1 Root Valve located inside pipe chase 4321)

AND INFORM Control Room of injection line pressure.

L.

COMPARE PP-N058B injection line pressure to reactor pressure AND DETERMINE initial differential between the indications.

Initial Differential (approx.) _____________________

M.

PERIODICALLY MONITOR the following for changes while continuing with Step 5.2.26.N:

  • PP-N058B injection line pressure
  • Reactor pressure
  • HV F050B (F122B) position (continued on next page)

HC.OP-SO.BC-0002(Q)

Hope Creek Page 29 of 77 Rev. 25 5.2.26 (continued)

NOTE To prevent exceeding heatup rate, BC-HV-F040 should be pressed for approx. 2 - 3 seconds then released while temperature is being monitored. If further adjustments to BC-HV-F040 are required, then they should be made in small increments.

Step 5.2.26.N will allow reactor vessel water to flow from the recirc shutdown cooling connection to radwaste, bypassing the RHR heat exchanger.

CAUTION Water > 200°F should NOT be discharged to the Liquid Radwaste system. Reactor Vessel level should be monitored during the following evolution.

N.

THROTTLE BC-HV-F040 to establish flowpath to Radwaste.

CAUTION If the differential between the PP-N058B injection line pressure and reactor pressure approaches zero then voiding is occurring in the RHR piping. To avoid this condition the differential should be maintained greater than one-half of that initially observed (5.2.22.L) throughout the entire pre-warming evolution.

(Ex. If initial differential is 20 psid then a differential of greater than one-half of that initially observed (10 psid) should be maintained between indications throughout the entire pre-warming evolution) Maintaining differential pressure will prevent additional venting of the RHR SDC return line.

O.

IF the pressure differential between injection line pressure and reactor pressure is less than one-half of that initially observed in Step 5.2.26.L THEN EITHER:

  • THROTTLE CLOSED on BC-HV-F040 to re-establish the differential OR
  • CLOSE BC-HV-F040 until the cause for the change has been determined and corrected.

(continued on next page)

HC.OP-SO.BC-0002(Q)

Hope Creek Page 30 of 77 Rev. 25 5.2.26 (continued)

CAUTION Water > 200°F should NOT be discharged to the liquid radwaste system. Reactor vessel level should be monitored during the following evolution.

P.

MONITOR TE-N032 (TR-R605, Channel 7).

Q.

WHEN temperature reaches 180° to 200°F THEN, CLOSE BC-HV-F040 AND INITIAL Attachment 1.

R.

VERIFY the differential has been maintained greater than one-half of that initially observed in Step 5.2.26.L.

S.

CLOSE BC-HV-F015B.

T.

RELEASE HV-F050B/HV-F122B test open Pb AND VERIFY HV-F050B closes AND INITIAL Attachment 1.

U.

CLOSE BC-HV-F049 AND INITIAL Attachment 1.

V.

CLOSE P-BC-V9958 AND INITIAL Attachment 1.

W.

OPEN BC-HV-F006B.

X.

OPEN AND LOCK 1-BC-V262 (local)

AND INITIAL Attachment 1. [PR 961104058]

Y.

WHILE continuing in this section, REMOVE M&TE as specified in Section 4.0 and IAW Attachment 2.

HC.OP-SO.BC-0002(Q)

Hope Creek Page 31 of 77 Rev. 25 NOTE RHR Loop B or RHR Loop A prewarming is required if the differential temperature between the Reactor Vessel water and the RHR Loop to be used is greater than 100°F.

Prior to commencing RHR Loop warm-up, the Radwaste Control Room should be notified to ensure available capacity ( 10,000 - 15,000 gals).

5.2.27.

PERFORM the following to warm up the A RHR Loop so that it may be placed in Shutdown Cooling:

A.

CLOSE 1-BC-V212 C ECCS Jockey Pmp to RHR Loop A Isln Vlv (local). [PR 961104058]

B.

ENSURE BC-HV-4439 LP B DSCH TO LIQ RW is OPEN.

C.

ENSURE a thermocouple has been installed downstream of the 1-BC-V152 RHR Pump A Dsch Hdr to RW Sup Vlv.

OR a Raytek (or equivalent) is available.

D.

OPEN 1-BC-V153 RHR Pump A Dsch Hdr to RW Isol.

NOTE Step 5.2.27.E will allow Reactor Vessel water to flow from the Recirc Shutdown Cooling connection to Radwaste, bypassing the RHR Heat Exchanger.

E.

THROTTLE OPEN 1-BC-V152 to achieve required heatup of the suction portion of the A RHR Loop.

CAUTION Water > 200°F should NOT be discharged to the Liquid Radwaste system. Reactor Vessel level should be monitored during the following evolution.

F.

WHEN temperature reaches 180°F, THEN, CLOSE 1-BC-V152.

G.

CLOSE BC-HV-F006A RHR PMP A SUCT FROM RECIRC.

(continued on next page)

HC.OP-SO.BC-0002(Q)

Hope Creek Page 32 of 77 Rev. 25 5.2.27 (continued)

NOTE If the HV-F050A does not open after multiple attempts then continue and warm up the line using the HV-F122A only.

CAUTION If the HV F050A is not open, and the flow is passing through the HV F122A only (although the HV F050A may be passing some flow HV F122A piping 1 diameter/orifice), minimize 1-BC-V152 opening to prevent voiding of RHR piping.

[70030917]

H.

PRESS AND HOLD HV F050A/HV F122A RHR LOOP A SHTDN COOL ISLN CHECK VLV test open Pb.

I.

WHILE monitoring open position of HV F050A/HV F122A, OPEN BC-HV-F015A RHR LOOP A RET TO RECIRC.

J.

IF the HV F050A closed while the BC-HV-F015A was being opened in Step 5.2.27.I THEN:

1.

RE-CLOSE BC-HV-F015A

2.

RELEASE then PRESS AND HOLD HV F050A/HV F122A test open Pb

3.

VERIFY HV F050A indicates open.

4.

REPEAT Step 5.2.27.I.

K.

OPEN P-BC-V9946 gauge isolation at PP-N058A RHR LPCI INJECTION LINE A Instrument Root Valve. (1 Root Valve located inside pipe chase 4329) AND INFORM Control Room of injection line pressure.

L.

COMPARE PP-N058A injection line pressure to reactor pressure AND DETERMINE initial differential between the indications.

Initial Differential (approx.) _____________________

(continued on next page)

HC.OP-SO.BC-0002(Q)

Hope Creek Page 33 of 77 Rev. 25 5.2.27 (continued)

M.

PERIODICALLY MONITOR the following for changes while continuing with Step 5.2.27.N:

  • PP-N058A injection line pressure
  • Reactor pressure
  • HV-F050A position NOTE To prevent exceeding heatup rate, 1-BC-V152 should be throttled while temperature is being monitored. If further adjustments to 1-BC-VF152 are required, then they should be made in small increments.

Step 5.2.27.N will allow reactor vessel water to flow from the recirc shutdown cooling connection to radwaste, bypassing the RHR heat exchanger.

CAUTION Water > 200°F should NOT be discharged to the Liquid Radwaste system. Reactor Vessel level should be monitored during the following evolution.

N.

THROTTLE 1-BC-V152 to establish flowpath to radwaste (SEE Note above).

(continued on next page)

HC.OP-SO.BC-0002(Q)

Hope Creek Page 34 of 77 Rev. 25 5.2.27 (continued)

CAUTION If the differential between the PP-N058A injection line pressure and reactor pressure approaches zero then voiding is occurring in the RHR piping. To avoid this condition the differential should be maintained greater than one-half of that initially observed (5.2.27.L) throughout the entire pre-warming evolution.

(Ex. If initial differential is 20 psid then a differential of greater than one-half of that initially observed (10 psid) should be maintained between indications throughout the entire pre-warming evolution) Maintaining differential pressure will prevent additional venting of the RHR SDC return line.

O.

IF the pressure differential between injection line pressure and reactor pressure is less than one-half of that initially observed in Step 5.2.27.L THEN EITHER:

  • THROTTLE CLOSED on 1-BC-V152 to re-establish the differential OR
  • CLOSE 1-BC-V152 until the cause for the change has been determined and corrected.

CAUTION Water > 200°F should NOT be discharged to the Liquid Radwaste system. Reactor Vessel level should be monitored during the following evolution.

P.

WHEN temperature reaches 180°F THEN, CLOSE 1-BC-V152 AND INITIAL Attachment 1.

Q.

VERIFY the differential pressure has been maintained greater than one-half of that initially observed in 5.2.27.L.

R.

CLOSE BC-HV-F015A.

(continued on next page)

HC.OP-SO.BC-0002(Q)

Hope Creek Page 35 of 77 Rev. 25 5.2.27 (continued)

S.

RELEASE HV-F050A/HV-F122A test open Pb AND VERIFY HV-F050A closes AND INITIAL Attachment 1.

T.

CLOSE 1-BC-V153 AND INITIAL Attachment 1.

U.

CLOSE P-BC-V9946 AND INITIAL Attachment 1.

V.

OPEN BC-HV-F006A.

W.

OPEN AND LOCK 1-BC-V212 (local)

AND INITIAL Attachment 1. [PR 961104058]

X.

WHILE continuing in this section, REMOVE M&TE IAW Attachment 2.

5.2.28.

IF Noble Metals Chemical Application is to be performed during plant shutdown, THEN PERFORM the following:

A.

ADJUST both Reactor Recirc Pumps speed as required by HC.DE-SP.ZZ-0001(Q), Noble Metals Chemical Addition-Infrequently Performed Evolution.

B.

GO TO Step 5.2.31.

(continued on next page)

HC.OP-SO.BC-0002(Q)

Hope Creek Page 36 of 77 Rev. 25 5.2.28 (continued)

NOTE Prior to starting an RHR pump to establish Shutdown Cooling flow, the following applies:

If the BP202 RHR Pump is to be placed in Shutdown Cooling, then, the AP201 Reactor Recirculation Pump should be left in service to provide forced core flow until the RHR required flow of 10,000 gpm is obtained, and the BP201 Reactor Recirculation Pump should be secured with its discharge valve shut. Otherwise, both Reactor recirculation Pumps should be removed from service with their discharge valves shut IAW HC.OP-SO.BB-0002(Q). [CD-739A, CD-781A]

5.2.29.

IF Reactor Recirc Pump(s) are operating, THEN, PERFORM one of the following: [CD-781A, CD-739A]

  • IF RHR Loop B will be used for Shutdown Cooling, AND it is desired to maintain a Reactor Recirc Pump in service until rated Shutdown Cooling flow is established, THEN, SECURE BP201 Reactor Recirc Pump IAW HC.OP-SO.BB-0002(Q),

AND MAINTAIN AP201 running to provide forced core flow.

  • IF RHR Loop B will be used for Shutdown Cooling, AND it is NOT desired to maintain a Reactor Recirc Pump in service until rated Shutdown Cooling flow is established, THEN, SECURE both Reactor Recirc Pumps IAW HC.OP-SO.BB-0002(Q).
  • IF RHR Loop A will be used for Shutdown Cooling, THEN, SECURE both Reactor Recirc Pumps IAW HC.OP-SO.BB-0002(Q).

5.2.30.

ENSURE the Discharge Valve associated with any Reactor Recirculation Pump which is NOT in operation is CLOSED.

HC.OP-SO.BC-0002(Q)

Hope Creek Page 37 of 77 Rev. 25 CAUTION Manual OR automatic opening of BC-HV-F007A(B) RHR PMP A(B) MIN FLOW MOV will drain Reactor Vessel to Suppression Pool. [CD-608D, CD-567E]

If BC-HV-F015 A(B) RHR LOOP A(B) RET TO RECIRC does NOT open immediately to establish flow, the RHR pump should be secured.

BC-HV-F027A(B) RHR LOOP A(B) SUPP POOL SPRAY HDR ISLN MOV will drain the Reactor Vessel to the Suppression Pool if opened while the associated RHR pump is in shutdown cooling. [CD-608D, CD-567E]

5.2.31.

START the A(B)P202 RHR PUMP AND IMMEDIATELY THROTTLE OPEN BC-HV-F015A(B)

RHR LOOP A(B) RET TO RECIRC UNTIL FI-R603A(B) or FR-R608A(B) - CRIDS A3137(A3139),

LOOP A(B) FLOW indicates 3000 gpm. [CD-133B, CD-177E]

5.2.32.

MAINTAIN RHR Loop in shutdown cooling at 3000 gpm as indicated on FI-R603A(B) or FR-R608A(B) - CRIDS A3137(A3139), LOOP A(B) FLOW, for 3 minutes.

HC.OP-SO.BC-0002(Q)

Hope Creek Page 38 of 77 Rev. 25 5.2.33.

WHEN conditions of Step 5.2.32 have been satisfied, THEN, PERFORM the following:

A.

IF Noble Metals Chemical Application is to be performed during plant shutdown, THEN PERFORM the following:

NOTE RHR flow should be raised slowly with ~1000 gpm changes to minimize the impact on vessel clarity. The control room should coordinate with fuel movers prior to adjusting flow to maintain vessel clarity.

1.

SLOWLY OPEN BC-HV-F015A(B) RHR LOOP A(B)

RET TO RECIRC UNTIL FI-R603A(B) or FR-R608A(B) - CRIDS A3137(A3139), LOOP A(B)

FLOW indicates flow required by HC.DE-SP.ZZ-0001(Q), Noble Metals Chemical Addition-Infrequently Performed Evolution.

2.

GO TO Step 5.2.34.

NOTE RHR flow should be raised slowly with ~1000 gpm changes to minimize the impact on vessel clarity. The control room should coordinate with fuel movers prior to adjusting flow to maintain vessel clarity.

B.

SLOWLY OPEN BC-HV-F015A(B) RHR LOOP A(B) RET TO RECIRC UNTIL FI-R603A(B) or FR-R608A(B) - CRIDS A3137(A3139), LOOP A(B) FLOW indicates required flow.

NOTE The following step may be performed concurrently while continuing in this procedure, but the time the Reactor Recirc Pump remains in service once the required RHR flow is achieved should be minimized.

C.

IF in service, THEN SECURE the AP201 Reactor Recirculation Pump IAW HC.OP-SO.BB-0002(Q).

HC.OP-SO.BC-0002(Q)

Hope Creek Page 39 of 77 Rev. 25 CAUTION If BC-HV-F003A(B) RHR HX A(B) OUTLET VLV is used to throttle RHR flow through the RHR Heat Exchanger, then BC-HV-F048A(B) A(B) RHR HX SHELL SIDE BYP MOV must be fully open. [CD-503B]

If BC-HV-F003A(B) RHR HX A(B) OUTLET VLV is CLOSED fully, then RHR INLET TO HX A(B) TE N004A(B) (CRIDS point A2380(A2382) or TR-R605 point 1(2)), will not be accurate. When BC-HV-F003A(B) is fully closed then utilize RHR DISCH FROM HX A(B) TE N027A(B) (CRIDS point A2381(A2383) or TR-R605 point 3(4)), to MONITOR system temperature.

BC-HV-F003A(B) RHR HX A(B) OUTLET VLV should be opened slowly to avoid a "cold slug" discharge into the recirculation piping.

5.2.34.

PERFORM the following as necessary to maintain the Shutdown Cooling return to RPV temperature relatively constant, as monitored on TR-R605 point 3(4) OR CRIDS A2381(A2383),

while maintaining the required RHR Shutdown Cooling flow, simultaneously:

NOTE RHR flow should be raised slowly with ~1000 gpm changes to minimize the impact on vessel clarity. The control room should coordinate with fuel movers prior to adjusting flow to maintain vessel clarity.

A.

IF temperature is increasing, THEN PERFORM the following:

1.

Slowly THROTTLE OPEN on the BC-HV-F003A(B)

RHR HX A(B) OUTLET VLV.

2.

IF the BC-HV-F003A(B) is fully opened, THEN, THROTTLE CLOSED BC-HV-F048A(B) A(B)

RHR HX SHELL SIDE BYP MOV continued on next page

HC.OP-SO.BC-0002(Q)

Hope Creek Page 40 of 77 Rev. 25 5.2.34 (continued)

B.

IF temperature is decreasing, THEN, PERFORM the following:

1.

THROTTLE OPEN on the BC-HV-F048A(B)

A(B) RHR HX SHELL SIDE BYP MOV.

2.

IF the BC-HV-F048A(B) A(B) RHR HX SHELL SIDE BYP MOV is fully open, THEN, THROTTLE CLOSED on the BC-HV-F003A(B) RHR HX A(B) OUTLET VLV.

C.

PERFORM the following to maintain shutdown cooling flow:

1.

THROTTLE BC-HV-F015B RHR LOOP B RETURN TO RECIRC as necessary to maintain required flow on FI-R603B or FR-R608(B) - CRIDS A3139.

5.2.35.

MAINTAIN the RPV Metal Temperatures and RHR SDC System water temperature difference < 240°F.

REFERENCE Crids point A2381(A2383)

OR Recorder TR-R605 - point 3(4) for RHR SDC system, AND CRIDS points A3569 & A3578 for Vessel flange.

HC.OP-SO.BC-0002(Q)

Hope Creek Page 41 of 77 Rev. 25 CAUTION If BC-HV-F003A(B) RHR HX A(B) OUTLET VLV is used to throttle RHR flow through the RHR Heat Exchanger, then BC-HV-F048A(B) A(B) RHR HX SHELL SIDE BYP MOV must be fully open.

If BC-HV-F003A(B) RHR HX A(B) OUTLET VLV is CLOSED fully, then RHR INLET TO HX A(B) TE N004A(B) (CRIDS point A2380(A2382) OR TR-R605 point 1(2)), will not be accurate when BC-HV-F003A(B) is fully closed, then utilize RHR DISCH FROM HX A(B)

TE N027A(B) (CRIDS point A2381(A2383) OR TR-R605 point 3(4)), to MONITOR system temperature. [CD-503B]

BC-HV-F003A(B) RHR HX A(B) OUTLET VLV should be opened slowly to avoid a "cold slug" discharge into the recirculation piping.

5.2.36.

PERFORM the following as necessary to initiate the cooldown AND Control the cooldown rate, while maintaining the required RHR Shutdown Cooling flow, simultaneously: [CD-133B]

A.

PERFORM the following to increase the cooldown rate:

1.

Slowly THROTTLE OPEN on the BC-HV-F003A(B)

RHR HX A(B) OUTLET VLV.

2.

IF the BC-HV-F003A(B) is fully open, THEN, THROTTLE CLOSED on the BC-HV-F048A(B) A(B) RHR HX SHELL SIDE BYP MOV.

B.

PERFORM the following to decrease the cooldown rate:

1.

THROTTLE OPEN on the BC-HV-F048A(B)

A(B) RHR HX SHELL SIDE BYP MOV.

2.

IF the BC-HV-F048A(B) A(B) RHR HX SHELL SIDE BYP MOV is fully open, THEN, THROTTLE CLOSED on the BC-HV-F003A(B) RHR HX A(B) OUTLET VLV.

C.

To maintain Shutdown Cooling flow THROTTLE the BC-HV-F015A(B) RHR LOOP A(B) RET TO RECIRC, as necessary, to maintain the required RHR Shutdown Cooling flow.

5.2.37.

RECORD Reactor Vessel temperatures and pressures IAW Integrated Operating Procedure HC.OP-IO.ZZ-0004(Q);

Shutdown from Rated Power to Cold Shutdown AND HC.OP-DL.ZZ-0026(Q), Attachment 3s; Surveillance Log.

HC.OP-SO.BC-0002(Q)

Hope Creek Page 42 of 77 Rev. 25 NOTE If the Main Condenser is available, and a decrease in level is required, then the Reactor Vessel water level should be decreased IAW HC.OP-SO.BG-0001(Q), Reactor Water Cleanup System Operation.

CAUTION While operating in Shutdown Cooling with the reactor vessel temperature below 200°F, the Reactor vessel level should be maintained at 80 inches, reactor level shutdown range (upset range while reactor vessel disassembly is in progress), using temperature compensated indication (Vessel Level Instrumentation Temperature Compensation Curves may be required), to allow for natural circulation in the event that forced circulation is lost. [CD-693A, CD-178A, CD-973B]

The Reactor vessel level should be reduced to 60 - 65 inches when removing shutdown cooling from operation to restore reactor recirculation pump(s), AND the potential to put water into the steam lines exists as part of the changeover.

At NO time should Reactor Vessel water level be decreased below Level 4 (+ 30 " ).

Using RHR in SDC to lower cavity level during a cavity draindown evolution could result in uncovering RPV components resulting in elevated radiation levels on the refuel floor.

[SEN285]

5.2.38.

IF B RHR is in SDC AND a decrease in Reactor Vessel water level is required THEN, PERFORM the following:

A.

NOTIFY Radwaste Operator of impending discharge to the Liquid Radwaste System.

NOTE Water at > 200°F, as indicated on E41-TR-R605 RHR-HPCI TEMPERATURES (10C650C),

should NOT be discharged to the Liquid Radwaste System.

B.

OPEN BC-HV-F049 RHR LOOP B DSCH TO LIQ RW ISLN MOV.

C.

THROTTLE OPEN BC-HV-F040 RHR LOOP B DSCH TO LIQ RW ISLN MOV to achieve required Reactor Vessel water level decrease rate.

continued on next page

HC.OP-SO.BC-0002(Q)

Hope Creek Page 43 of 77 Rev. 25 5.2.38 (continued)

D.

WHEN required Reactor Vessel water level is reached, THEN, CLOSE BC-HV-F040 RHR LOOP B DSCH TO LIQ RW ISLN MOV AND INITIAL Attachment 1.

E.

CLOSE BC-HV-F049 RHR LOOP B DSCH TO LIQ RW ISLN MOV AND INITIAL Attachment 1.

CAUTION While operating in Shutdown Cooling with the reactor vessel temperature below 200°F, the Reactor vessel level should be maintained at 80 inches, reactor level shutdown range (upset range while reactor vessel disassembly is in progress), using temperature compensated indication (Vessel Level Instrumentation Temperature Compensation Curves may be required), to allow for natural circulation in the event that forced circulation is lost. [CD-693A, CD-178A, CD-973B]

The Reactor vessel level should be reduced to 60 - 65 inches when removing shutdown cooling from operation to restore reactor recirculation pump(s), AND the potential to put water into the steam lines exists. At NO time should Reactor Vessel water level be decreased below Level 4 (+ 30 " ).

Alternate Vessel letdown flowpath can only be used while in Operational Conditions 4 and 5.

5.2.39.

IF BC-HV-F040 OR BC-HV-F049 RHR LOOP B DSCH TO LIQ RW ISLN MOVs are unavailable for use in decreasing Reactor Vessel level, OR the A Loop of RHR is in service in the SDC mode, THEN, PERFORM the following to utilize Alternate Vessel Letdown flowpath to decrease level:

A.

NOTIFY Radwaste Operator of impending discharge to the Liquid Radwaste System.

CAUTION Water at > 200°F should NOT be discharged to the Liquid Radwaste System.

B.

ENSURE BC-HV-4439 LP B DSCH TO LIQ RW is OPEN.

(continued on next page)

HC.OP-SO.BC-0002(Q)

Hope Creek Page 44 of 77 Rev. 25 5.2.39 (Continued)

C.

UNLOCK AND OPEN the appropriate valve for the RHR Pump aligned for Shutdown Cooling:

  • 1-BC-V153 RHR Pump A Dsch Hdr to RW Iso Vlv.
  • 1-BC-V062 RHR Pump B Dsch Hdr to RW Iso Vlv.

CAUTION Communications should be established AND maintained continuously between the control room AND the operator controlling the letdown rate locally at the Discharge Header Isolation Valve. The operator should standby in a low dose area to quickly respond.

D.

THROTTLE OPEN the appropriate valve for the RHR Pump aligned for Shutdown Cooling, to initiate AND control the letdown rate:

  • 1-BC-V152 RHR Pump A Dsch Hdr to RW Sup Vlv
  • 1-BC-V061 RHR Pump B Dsch Hdr to RW Sup Vlv E.

WHEN desired Reactor Vessel level decrease has been achieved, THEN, CLOSE the appropriate valve for the RHR Pump aligned for Shutdown Cooling AND INITIAL Attachment 1.

  • 1-BC-V152 RHR Pump A Dsch Hdr to RW Sup Vlv
  • 1-BC-V061 RHR Pump B Dsch Hdr to RW Sup Vlv F.

CLOSE AND LOCK the appropriate valve for the RHR Pump aligned for Shutdown Cooling AND INITIAL Attachment 1.

  • 1-BC-V153 RHR Pump A Dsch Hdr to RW Iso Vlv.
  • 1-BC-V062 RHR Pump B Dsch Hdr to RW Iso Vlv.

HC.OP-SO.BC-0002(Q)

Hope Creek Page 45 of 77 Rev. 25 CAUTION The local operator should remain stationed at the valves for the entire duration of the makeup.

The makeup rate should be determined by the operator monitoring the vessel level AND controlled by the local operator (turns open)

IF an RHR Shutdown Cooling System isolation occurs, THEN, makeup should be terminated.

5.2.40.

IF necessary to makeup to, OR increase the Reactor Vessel level via the inservice RHR SD Cooling Loop, THEN, PERFORM the following:

A.

ESTABLISH communications between the local operator stationed at the valves and the control room.

B.

UNLOCK AND OPEN 1-AP-V048 Cond Stor & Xfr to RHR B Suct Hdr Fill & Flush Isln Vlv (local).

C.

UNLOCK AND THROTTLE OPEN 1-BC-V191 Cond Stor

& Xfr to Recirc Suct Hdr Sup Vlv (local) as necessary, to initiate makeup via the SD Cooling loop.

D.

Closely MONITOR Reactor Vessel level.

E.

WHEN desired level is reached, THEN, CLOSE AND LOCK 1-BC-V191 Cond Stor & Xfr to Recirc Suct Hdr Sup Vlv AND INITIAL Attachment 1.

F.

CLOSE AND LOCK 1-AP-V048 Cond Stor & Xfr to RHR B Suct Hdr Fill & Flush Isln Vlv (local)

AND INITIAL Attachment 1.

5.2.41.

PRIOR to removing Shutdown Cooling flow, AND re-establishing Reactor Recirculation flow, IF the potential exists to put water into the steam lines as a part of the changeover, THEN RETURN Reactor Operating Level to 60 - 65 inches using temperature-compensated Reactor Level Shutdown Range indication. (REFERENCE Steps 5.2.38 AND 5.2.39)

HC.OP-SO.BC-0002(Q)

Hope Creek Page 46 of 77 Rev. 25 NOTE The time with no forced circulation should be minimized.

Vessel metal temperatures above AND below the water level AND Reactor Coolant System Temperature/Pressure Data should be monitored to ensure the TS Cooldown limits are NOT exceeded.

CAUTION During the transition from Shutdown Cooling operations to establishment of normal Reactor Recirculation System operations, the RHR System may be left in Shutdown Cooling, only if BP202 is the RHR Pump in service and AP201 is the Reactor Recirc Pump to be started.

5.2.42.

IF the BP202 RHR Pump is being removed from service in preparation for establishing Reactor Recirculation operations, AND it is desired to maintain forced core flow, THEN, PLACE the AP201 Reactor Recirculation Pump in service IAW HC.OP-SO.BB-0002(Q), PRIOR to securing the BP202 RHR Pump.

5.2.43.

REMOVE Shutdown Cooling from service as follows:

NOTE Steps 5.2.43.A and 5.2.43.B should be performed in rapid succession.

A.

CLOSE BC-HV-F015A(B) RHR LOOP A(B) RET TO RECIRC AND INITIAL Attachment 1.

B.

WHEN BC-HV-F015A(B) RHR LOOP A(B) RET TO RECIRC is fully closed, THEN, IMMEDIATELY STOP A(B)P202 RHR PUMP.

(continued on next page)

HC.OP-SO.BC-0002(Q)

Hope Creek Page 47 of 77 Rev. 25 5.2.43 (continued)

NOTE Steps 5.2.43.C thru 5.2.43.G are intended to allow SDC to remain available to be promptly returned to service if, for example, either Reactor Recirculation Pump fails to start, or, the RCS heatup rate is unacceptable, by allowing the completion of this section to be delayed following the closure of the F006A(B).

C.

CLOSE BC-HV-F006A(B) RHR PMP A(B) SUCT FROM RECIRC AND INITIAL Attachment 1.

CAUTION If SDC is to remain available to be promptly returned to service and SACS flow remains aligned to the RHR Hx then cooldown of the Hx contents will occur.

D.

IF required IAW HC.OP-SO.EG-0001(Q),

THEN, PRESS AND HOLD the close PB until EG-HV-2512A(B) RHR HX SACS RTN ISLN MOV indicates closed AND INITIAL Attachment 1.

E.

ENSURE keepfill is aligned, as necessary, IAW HC.OP-SO.BC-0001(Q). [80043859]

F.

IF required to return Shutdown Cooling to service THEN PERFORM the following:

1.

ENSURE SACS is in service to the RHR Heat Exchanger for the RHR loop to be placed in service IAW HC.OP-SO.EG-0001(Q).

2.

RE-OPEN BC-HV-F006A(B)

AND GO TO Step 5.2.29.

G.

WHEN no longer necessary to maintain Shutdown Cooling available THEN CONTINUE with completion of this section.

H.

CLOSE BC-HV-F008 SHUTDOWN COOLING OUTBD ISLN MOV AND INITIAL Attachment 1.

I.

CLOSE BC-HV-F009 SHUTDOWN COOLING INBD ISLN MOV AND INITIAL Attachment 1.

continued on next page

HC.OP-SO.BC-0002(Q)

Hope Creek Page 48 of 77 Rev. 25 5.2.43 (continued)

J.

PLACE Keylock Switch HS-11495 in the DISARMED position (10B242 Bkr 242082),

AND LOG in Control Room Log(s)

AND INITIAL Attachment 1. [CD-407Y]

NOTE Steps 5.2.43.K through 5.2.43.O may be performed concurrently.

K.

IF necessary, RELEASE TAG from breaker 52-212041(52-222041)

THEN OPEN BC-HV-F007A(B)

AND INITIAL Attachment 1.

CAUTION BC-HV-F006A(B) RHR PMP A(B) SUCT FROM RECIRC must be fully closed prior to performing Step 5.2.43.L.

L.

OPEN BC-HV-F004A(B) A(B) RHR PMP SUPP POOL SUCT MOV AND INITIAL Attachment 1.

M.

OPEN BC-HV-F048A(B) A(B) RHR HX SHELL SIDE BYP MOV AND INITIAL Attachment 1.

N.

OPEN BC-HV-F003A(B) RHR HX A(B) OUTLET VLV AND INITIAL Attachment 1.

O.

REMOVE Red Blocking tag from 52-212083 (52-222083) breaker for BC-HV-F027A(B) (or 1-BC-V315 (V314)

IF used as alternate blocking point), IAW OP-AA-109,.

CLOSE breaker 52-212083 (52-222083)

AND INITIAL Attachment 1.

NOTE The RHR loop being removed from Shutdown Cooling should be flushed for 1-4 hours to reduce the dose in the RHR System. The time requirement should be based on the dose rate and the reduction trend as determined by Radiation Protection.

5.2.44.

PLACE the RHR loop in Suppression Pool Cooling IAW HC.OP-SO.BC-0001(Q) to reduce rad levels.

HC.OP-SO.BC-0002(Q)

Hope Creek Page 49 of 77 Rev. 25 5.3 Transfer of Shutdown Cooling to the Standby Shutdown Cooling Loop 5.3.1.

ENSURE all Prerequisites have been satisfied IAW Section 2.3.

NOTE BC-HV-F027A(B) RHR LOOP A(B) SUPP POOL SPRAY HDR ISLN MOV will drain the Reactor Vessel to the Suppression Pool IF opened while the associated RHR pump is in shutdown cooling.

CAUTION While in shutdown cooling, the following valves shall be closed to prevent uncontrolled drainage from the Reactor Vessel: [CD-389B, CD-608D, CD-157E, CD-567E]

  • BC-HV-F004A(B) RHR PMP A(B) SUPP POOL SUCT MOV
  • BC-HV-F027A(B) RHR LOOP A(B) SUPP POOL SPRAY HDR ISLN IF the Reactor is in Mode 4 or Refuel or if a mode change is not desired, the delay in starting the second RHR Loop after having secured the first Loop should not approach the Time to Boil value. [PR 971028283]

5.3.2.

PERFORM the following to prepare loop to be placed in Shutdown Cooling:

A.

IF a flush on the loop to be placed in Shutdown Cooling is required, THEN REFER TO Steps 5.2.5 through 5.2.14.

continued Next Page

HC.OP-SO.BC-0002(Q)

Hope Creek Page 50 of 77 Rev. 25 5.3.2 (Continued)

B.

ENSURE the following Valves are CLOSED:

  • BC-HV-F004A(B) A(B) RHR PMP SUPP POOL SUCT MOV
  • BC-HV-F007A(B) RHR PUMP A(B) MIN FLOW MOV
  • BC-HV-F027A(B) RHR LOOP A(B) SUPP POOL SPRAY HDR ISLN MOV NOTE This section may be continued once the valve is re-positioned and its breaker opened (step completion signoff after safety tagging completed).

C.

VERIFY BC-HV-F007A(B) is CLOSED THEN TAG breaker 52-212041(52-222041) OPEN AND INITIAL Attachment 1.

NOTE 1-BC-V315 (V314) SUP POOL SPRY HDR MAN ISLN VLV may be tagged CLOSED instead of tagging the associated breaker for the BC-HV-F027A(B)

(if required to support outage activities), although BC-HV-F027A(B) must still be closed.

This section may be continued once the valve is re-positioned and its breaker opened (step completion signoff after safety tagging completed).

D.

VERIFY BC-HV-F027A(B) is CLOSED AND TAG breaker 52-212083 (52-222083) OPEN AND INITIAL Attachment 1.

5.3.3.

OPEN BC-HV-F006A(B) RHR PMP A(B) SUCT FROM RECIRC for the RHR Loop to be placed in S/D Cooling.

HC.OP-SO.BC-0002(Q)

Hope Creek Page 51 of 77 Rev. 25 NOTE RHR Loop B OR RHR Loop A prewarming is required IF the differential temperature between the Reactor Vessel water AND the RHR Loop to be utilized is greater than 100°F.

5.3.4.

IF prewarming of the Loop of RHR to be placed in S/D Cooling is required THEN, PERFORM Steps 5.2.26 OR 5.2.27 of this procedure to equalize temperatures; OTHERWISE PROCEED.

5.3.5.

SECURE the inservice Shutdown Cooling Loop as follows:

A.

ENSURE 1-BC-V262 (1-BC-V212), ECCS Jockey Pmp D(C) DISCH to RHR Loop B(A) is LOCKED OPEN (local),

AND INITIAL Attachment 1.

NOTE Steps 5.3.5.B through 5.3.5.C should be performed in rapid succession.

B.

CLOSE BC-HV-F015B(A) RHR LOOP B(A) RET TO RECIRC AND INITIAL Attachment 1.

C.

WHEN BC-HV-F015B(A) RHR LOOP B(A) RET TO RECIRC is fully closed, THEN, IMMEDIATELY STOP B(A)P202 RHR PUMP.

D.

CLOSE BC-HV-F006B(A) RHR PMP B(A) SUCT FROM RECIRC AND INITIAL Attachment 1.

5.3.6.

ENSURE SACS is in service to the RHR Heat Exchanger for the RHR loop to be placed in service IAW HC.OP-SO.EG-0001(Q).

HC.OP-SO.BC-0002(Q)

Hope Creek Page 52 of 77 Rev. 25 CAUTION Manual OR automatic opening of BC-HV-F007A(B) RHR PMP A(B) MIN FLOW MOV will drain Reactor Vessel to Suppression Pool. [CD-608D, CD-567E]

If BC-HV-F015 A(B) RHR LOOP A(B) RET TO RECIRC does NOT open immediately to establish flow, then the RHR pump should be secured.

BC-HV-F027A(B) RHR LOOP A(B) SUPP POOL SPRAY HDR ISLN MOV will drain the Reactor Vessel to the Suppression Pool if opened while the associated RHR pump is in shutdown cooling. [CD-608D, CD-567E]

5.3.7.

START RHR PUMP A(B)P202 AND IMMEDIATELY THROTTLE OPEN BC-HV-F015A(B)

RHR LOOP A(B) RET TO RECIRC LOOP UNTIL FI-R603A(B) OR FR-R608A(B) - CRIDS A3137(A3139),

LOOP A(B) FLOW indicates 3000 gpm.

[CD-133B, CD-177E]

5.3.8.

MAINTAIN the RHR Loop in shutdown cooling at 3000 gpm as indicated on FI-R603A(B) OR FR-R608A(B) - CRIDS A3137(A3139), LOOP A(B) FLOW, for 3 minutes.

NOTE RHR flow should be raised slowly with ~1000 gpm changes to minimize the impact on vessel clarity. The control room should coordinate with fuel movers prior to adjusting flow to maintain vessel clarity.

5.3.9.

WHEN conditions of Step 5.3.8 have been satisfied, THEN, OPEN BC-HV-F015A(B) RHR LOOP A(B) RET TO RECIRC UNTIL FI-R603A(B) OR FR-R608A(B) - CRIDS A3137(A3139),

LOOP A(B) FLOW indicates required flow.

NOTE Steps 5.3.10 AND 5.3.11 may be performed concurrently.

5.3.10.

OPERATE the in-service RHR Shutdown Cooling Loop IAW Section 5.2.

HC.OP-SO.BC-0002(Q)

Hope Creek Page 53 of 77 Rev. 25 5.3.11.

PERFORM the following to restore the RHR Loop that was removed from Shutdown Cooling:

A.

IF necessary, RELEASE TAG from breaker 52-222041(52-212041)

THEN OPEN BC-HV-F007B(A)

AND INITIAL Attachment 1.

CAUTION BC-HV-F006B(A) RHR PMP B(A) SUCT FROM RECIRC must be fully closed PRIOR to performing Step 5.3.11.B.

B.

OPEN BC-HV-F004B(A) B(A) RHR PMP SUPP POOL SUCT MOV AND INITIAL Attachment 1.

C.

ENSURE the following Valves are OPEN AND INITIAL :

  • BC-HV-F047B(A) RHR HX SHELL SIDE INLET MOV
  • BC-HV-F003B(A) RHR HX SHELL SIDE OUTLET MOV D.

RELEASE tag from 52-222083 (52-212083) for BC-HV-F027B(A) OR 1-BC-V315 (V314)

AND POSITION as necessary THEN INITIAL Attachment 1.

NOTE The RHR loop being removed from Shutdown Cooling should be flushed for 1-4 hours to reduce the dose in the RHR System. The time requirement should be based on the dose rate and the reduction trend as determined by Radiation Protection.

5.3.12.

PLACE the RHR loop in Suppression Pool Cooling IAW HC.OP-SO.BC-0001(Q) to reduce rad levels.

HC.OP-SO.BC-0002(Q)

Hope Creek Page 54 of 77 Rev. 25 6.0 RECORDS 6.1 RETAIN the following IAW RM-AA-101; Records Management Program:

  • Procedure cover page
  • Attachment 1 - Independent Verification Worksheet
  • Attachment 2 - M&TE Installation and Removal For D/P Monitoring During Discharge Piping Pre-Warming

7.0 REFERENCES

7.1 P&ID

  • M-51-1, Shts. 1 & 2 7.2 Logic Diagrams
  • J-51-0 7.3 Electrical Diagrams
  • E-0006-1 Shts 1 & 2
  • E-0021-1 Shts 1 - 6 7.4 UFSAR
  • 9.1.3.2.3 7.5 Vendor Manuals
  • E11-C002 Ingersoll Rand RHR Pumps 7.6 Panel Drawings
  • D3.35

HC.OP-SO.BC-0002(Q)

Hope Creek Page 55 of 77 Rev. 25 7.8 GE Documents

  • GEK-90300, Vol.VII, Pt.2, Sept. 1983 N1-E11-1040-20, RHR System
  • N1-B21-1090-62, Nuclear Steam Supply Shutoff System
  • GE-NE 523-A080-0895, DRF 137-0010-8, Class 3, August 1995 7.9 Other References
  • EOP Appendix C calculations (PSBP # 309346)
  • Application Information Document #67, 10/82
  • Design Calculation HTC.6-007 7.10 Cross References
  • HC.OP-IO.ZZ-0004(Q) - Shutdown from Rated Power to Cold Shutdown
  • HC.OP-DL.ZZ-0026(Q) - Surveillance Log
  • OP-HC-108-106-1001 - Equipment Operational Control
  • HC.OP-SO.BB-0002(Q) - Reactor Recirculation System Operation
  • HC.OP-SO.ED-0001(Q) - Reactor Auxiliary Cooling System Operation
  • HC.OP-SO.EG-0001(Q) - SACS & TACS System Operation

HC.OP-SO.BC-0002(Q)

Hope Creek Page 56 of 77 Rev. 25 7.11 Commitment Documents

  • CD-891D, INPO O+MR 247
  • CD-935E, OM-116, GE-KT-7-048
  • CD-897F, GE SASR 90-103
  • CD-389B, AID 67
  • CD-609G
  • CD-407Y, F09-316C-004
  • CD-989B, GE-SIL 404R1
  • CD-122H, PR 950709092, PR 970117243, LER 95-016

HC.OP-SO.BC-0002(Q)

Hope Creek Page 57 of 77 Rev. 25 7.12 Corrective Actions

  • PR 970529200
  • PR 961104058
  • PR 971028283
  • PR 970117243
  • PR 970618318
  • PR 980804102
  • PR 970221182
  • PR 970920124
  • PR 971128143
  • PR 961227150
  • PR 961102198
  • PR 961227172
  • PR 961124100
  • PR 971027219
  • 70039531 - Mode Restriction for Crosstie Flushing
  • 70041940 - Added Valve Verification Check of F048, 7.13 Fuel Pool Cooling Assist Mode References
  • Safety Evaluation HCT.8-0010 (FSAR Change Request H97-049)
  • GE Analysis - GE-NE-T23-00745 Fuel Pool cooling Analysis for New Mode of RHR FPCC Assist Mode

HC.OP-SO.BC-0002(Q)

Hope Creek Page 58 of 77 Rev. 25 ATTACHMENT 1 Page 1 of 9 INDEPENDENT VERIFICATION DECAY HEAT REMOVAL OPERATION NOTE Performer should indicate which of the following components were manipulated. Verification is only required on those components which were manipulated. Completed Verification Worksheets should be attached to the completed Daily Log package for retention.

(Section 6.0 should be referred to for retention requirements.)

RHR Shutdown Cooling Suction Header Venting STEP NOMENCLATURE

  1. REQ POSITION PERF VERF 1-BC-V165, RHR SDC SUCT VNT VLV CLOSED AND LOCKED 5.1.2.A 1-BC-V166, RHR SDC SUCT VNT VLV CLOSED 5.1.2.B.7 P-BC-V9947-HD, 1BCPT-N057 HIGH SIDE DRAIN CLOSED
  1. May be changed, under direction of SM/CRS only to support condition other than normal standby lineup

HC.OP-SO.BC-0002(Q)

Hope Creek Page 59 of 77 Rev. 25 ATTACHMENT 1 Page 2 of 9 INDEPENDENT VERIFICATION DECAY HEAT REMOVAL OPERATION NOTE Performer should indicate which of the following components were manipulated. Verification is only required on those components which were manipulated. Completed Verification Worksheets should be attached to the completed Daily Log package for retention.

(Section 6.0 should be referred to for retention requirements.)

Placing the RHR System in Shutdown Cooling STEP NOMENCLATURE

  1. REQ POSITION PERF VERF 5.2.13.A BC-HV-F080A(B), HX SAMPLE LINE OUTBD ISLN VLV CLOSED 5.2.13.B BC-HV-F079A(B), HX SAMPLE LINE INBD ISLN VLV CLOSED 5.2.14.A BC-HV-F024A(B), RHR LOOP TEST RET MOV CLOSED 5.2.17 BC-HV-F004A(B), RHR PMP SUPP POOL SUCT MOV CLOSED BC-HV-F027A(B), RHR LOOP SUPP POOL SPRAY HDR ISLN MOV CLOSED 5.2.18 52-212083(52-222083), RHR LOOP SUPP POOL SPRAY HDR ISLN MOV BREAKER OPEN BC-HV-F007A(B), RHR PMP MIN FLOW CLOSED 5.2.19 52-212041(52-222041), RHR PMP MIN FLOW BREAKER OPEN 1-BC-V284, RHR SUCT FROM RECIRC LP B VNT CLOSED 5.2.21.G.5 1-BC-V285, RHR SUCT FROM RECIRC LP B VNT LOCKED CLOSED 1-BC-V165, RECIRC LOOP B TO RHR VNT ISLN LOCKED CLOSED 5.2.21.H.5 1-BC-V166, RECIRC LOOP B TO RHR VNT ISLN CLOSED 5.2.21.I.1 1-BC-V191, COND STOR & XFR TO RECIRC SUCT HDR SUP VLV LOCKED CLOSED 5.2.21.I.2 1-AP-V048, COND STOR & XFR TO RHR B SUCT HDR FILL & FLUSH ISLN VLV LOCKED CLOSED
  1. May be changed, under direction of SM/CRS only to support condition other than normal standby lineup

HC.OP-SO.BC-0002(Q)

Hope Creek Page 60 of 77 Rev. 25 ATTACHMENT 1 Page 3 of 9 INDEPENDENT VERIFICATION DECAY HEAT REMOVAL OPERATION NOTE Performer should indicate which of the following components were manipulated. Verification is only required on those components which were manipulated. Completed Verification Worksheets should be attached to the completed Daily Log package for retention.

(Section 6.0 should be referred to for retention requirements.)

Placing the RHR System in Shutdown Cooling (continued)

STEP NOMENCLATURE

  1. REQ POSITION PERF VERF 5.2.21.J.1 1-BC-V167 RCIRC LOOP B TO RHR SUP TC ISO LOCKED CLOSED 5.2.21.J.5 1-BC-V168 RCIRC LOOP B TO RHR SUP TC ISO LOCKED CLOSED CAPPED 5.2.26.Q BC-HV-F040, RHR LOOP B DSCH TO LIQ RW ISLN MOV CLOSED 5.2.26.T BC-HV-F050B/HV-F122B, RHR LOOP B SHTDN COOL ISLN CHK VLV CLOSED 5.2.26.U BC-HV-F049, RHR LOOP B DSCH TO RW ISLN MOV CLOSED 5.2.26.V P-BC-V9958, ISOLATION PP-N058B CLOSED 5.2.26.X 1-BC-V262, ECCS JOCKEY PMP D DISCH TO RHR LOOP B LOCKED OPEN
  1. May be changed, under direction of SM/CRS only to support condition other than normal standby lineup

HC.OP-SO.BC-0002(Q)

Hope Creek Page 61 of 77 Rev. 25 ATTACHMENT 1 Page 4 of 9 INDEPENDENT VERIFICATION DECAY HEAT REMOVAL OPERATION NOTE Performer should indicate which of the following components were manipulated. Verification is only required on those components which were manipulated. Completed Verification Worksheets should be attached to the completed Daily Log package for retention.

(Section 6.0 should be referred to for retention requirements.)

Placing the RHR System in Shutdown Cooling (continued)

STEP NOMENCLATURE

  1. REQ POSITION PERF VERF 5.2.27.P 1-BC-V152, RHR PUMP A DSCH HDR TO RW SUP VLV CLOSED 5.2.27.S BC-HV-F050A, RHR LOOP A SHTDN COOL ISLN CHK VLV CLOSED 5.2.27.S 1-BC-V153, RHR PUMP A DSCH HDR TO RW ISOL CLOSED 5.2.27.U P-BC-V9946, ISOLATION PP-NO58A CLOSED 5.2.27.W 1-BC-V212, C ECCS JOCKEY PMP TO RHR LOOP A ISLN VLV LOCKED OPEN
  1. May be changed, under direction of SM/CRS only to support condition other than normal standby lineup

HC.OP-SO.BC-0002(Q)

Hope Creek Page 62 of 77 Rev. 25 ATTACHMENT 1 Page 5 of 9 INDEPENDENT VERIFICATION DECAY HEAT REMOVAL OPERATION NOTE Performer should indicate which of the following components were manipulated. Verification is only required on those components which were manipulated. Completed Verification Worksheets should be attached to the completed Daily Log package for retention.

(Section 6.0 should be referred to for retention requirements.)

Vessel level adjustments

  1. May be changed, under direction of SM/CRS only to support condition other than normal standby lineup STEP NOMENCLATURE
  1. REQ POSITION PERF VERF 5.2.38.D BC-HV-F040, RHR LOOP B DSCH TO LIQ RW ISLN MOV CLOSED 5.2.38.E BC-HV-F049, RHR LOOP B DSCH TO RW ISLN MOV CLOSED 1-BC-V152, RHR PUMP A DSCH HDR TO RW SUP VLV CLOSED 5.2.39.E 1-BC-V061, RHR PUMP B DSCH HDR TO RW SUP VLV CLOSED 1-BC-V153, RHR PUMP A DSCH HDR TO RW ISO VLV LOCKED CLOSED 5.2.39.F 1-BC-V062, RHR PUMP B DSCH HDR TO RW ISO VLV LOCKED CLOSED 5.2.40.E 1-BC-V191, COND STOR & XFR TO RECIRC SUCT HDR SUP VLV LOCKED CLOSED 5.2.40.F 1-AP-V048, COND STOR & XFR TO RHR B SUCT HDR FILL & FLUSH ISLN VLV LOCKED CLOSED

HC.OP-SO.BC-0002(Q)

Hope Creek Page 63 of 77 Rev. 25 ATTACHMENT 1 Page 6 of 9 INDEPENDENT VERIFICATION DECAY HEAT REMOVAL OPERATION NOTE Performer should indicate which of the following components were manipulated. Verification is only required on those components which were manipulated. Completed Verification Worksheets should be attached to the completed Daily Log package for retention.

(Section 6.0 should be referred to for retention requirements.)

Removing Shutdown Cooling From Service STEP NOMENCLATURE

  1. REQ POSITION PERF VERF 5.2.43.A BC-HV-F015A(B), RHR LOOP RET TO RECIRC CLOSED 5.2.43.C BC-HV-F006A(B), RHR PMP SUCT FROM RECIRC CLOSED 5.2.43.D EG-HV-2512A(B), RHR HX SACS RTN ISLN MOV CLOSED 5.2.43.H BC-HV-F008, SHUTDOWN COOLING OUTBD ISLN MOV CLOSED 5.2.43.I BC-HV-F009, SHUTDOWN COOLING INBD ISLN MOV CLOSED 5.2.43.J HS-11495, RHR SUCTION CLG OTBD ISOL VLV LOCAL ISOL SW DISARMED 52-212041(52-222041), BC-HV-F007A(B) RHR PMP MIN FLOW MOV CLOSED 5.2.43.K BC-HV-F007A(B), RHR PUMP MIN FLOW MOV OPEN 5.2.43.L BC-HV-F004A(B), RHR PMP SUPP POOL SUCT MOV OPEN 5.2.43.M BC-HV-F048A(B), RHR HX SHELL SIDE BYP MOV OPEN 5.2.43.N BC-HV-F003A(B), RHR HX OUTLET VLV OPEN 5.2.43.O Breaker 52-212083 (52-222083),

BC-HV-F027A(B) (or 1-BC-V315 (V314)

CLOSED

  1. May be changed, under direction of SM/CRS only to support condition other than normal standby lineup

HC.OP-SO.BC-0002(Q)

Hope Creek Page 64 of 77 Rev. 25 ATTACHMENT 1 Page 7 of 9 INDEPENDENT VERIFICATION DECAY HEAT REMOVAL OPERATION NOTE Performer should indicate which of the following components were manipulated. Verification is only required on those components which were manipulated. Completed Verification Worksheets should be attached to the completed Daily Log package for retention.

(Section 6.0 should be referred to for retention requirements.)

Transfer of Shutdown Cooling to the Standby Shutdown Cooling Loop STEP NOMENCLATURE

  1. REQ POSITION PERF VERF BC-HV-F007A(B), RHR PUMP MIN FLOW MOV CLOSED 5.3.2.C 52-212041(52-222041), BC-HV-F007A(B) RHR PMP MIN FLOW MOV OPEN BC-HV-F027A(B), RHR LOOP SUPP CHAMBER SPRAY HDR ISLN MOV CLOSED 5.3.2.D 52-212083(52-222083), RHR LOOP SUPP POOL SPRAY HDR ISLN MOV BREAKER OPEN 1-BC-V262, ECCS JOCKEY PMP D DISCH TO RHR LOOP B LOCKED OPEN 5.3.5.A 1-BC-V212, ECCS JOCKEY PMP C DISCH TO RHR LOOP A LOCKED OPEN 5.3.5.B BC-HV-F015B(A), RHR LOOP B(A) RET TO RECIRC CLOSED 5.3.5.D BC-HV-F006B(A), RHR PMP B(A) SUCT FROM RECIRC CLOSED
  1. May be changed, under direction of SM/CRS only to support condition other than normal standby lineup

HC.OP-SO.BC-0002(Q)

Hope Creek Page 65 of 77 Rev. 25 ATTACHMENT 1 Page 8 of 9 INDEPENDENT VERIFICATION DECAY HEAT REMOVAL OPERATION NOTE Performer should indicate which of the following components were manipulated. Verification is only required on those components which were manipulated. Completed Verification Worksheets should be attached to the completed Daily Log package for retention.

(Section 6.0 should be referred to for retention requirements.)

Transfer of Shutdown Cooling to the Standby Shutdown Cooling Loop (continued)

STEP NOMENCLATURE

  1. REQ POSITION PERF VERF BC-HV-F007B(A), RHR PUMP B(A) MIN FLOW MOV OPEN 5.3.11.A 52-222041 (52-212041), BC-HV-F007B(A) RHR PMP B(A) MIN FLOW MOV CLOSED 5.3.11.B BC-HV-F004B(A), RHR PMP B(A) SUPP POOL SUCT MOV OPEN BC-HV-F047B(A) RHR HX SHELL SIDE INLET MOV OPEN BC-HV-F048B(A) RHR HX SHELL SIDE BYP MOV OPEN 5.3.11.C BC-HV-F003B(A) RHR HX SHELL SIDE OUTLET MOV OPEN 52-212083(52-222083), RHR LOOP SUPP POOL SPRAY HDR ISLN MOV BREAKER CLOSED BC-HV-F027A(B), RHR LOOP SUPP CHAMBER SPRAY HDR ISLN MOV CLOSED 1-BC-V315, SUP POOL SPRY HDR MAN ISLN VLV LOCKED OPEN 5.3.11.D 1-BC-V314, SUP POOL SPRY HDR MAN ISLN VLV LOCKED OPEN
  1. May be changed, under direction of SM/CRS only to support condition other than normal standby lineup

HC.OP-SO.BC-0002(Q)

Hope Creek Page 66 of 77 Rev. 25 ATTACHMENT 1 Page 9 of 9 INDEPENDENT VERIFICATION DECAY HEAT REMOVAL OPERATION

1.0 DESCRIPTION

OF TASK(S) / SECTION(S) / STEP(S) COMPLETED:

2.0 PROCEDURE PERFORMER(S) AND VERIFIER(S) 2.1 I have read and understand the steps of this procedure that I am required to perform.

(All Departments)

PRINT NAME SIGNATURE INITIALS DATE/TIME 3.0 FINAL REVIEW & APPROVAL 3.1 The completed procedure has been reviewed for completion and is determined satisfactory.

SM/CRS Date/Time

HC.OP-SO.BC-0002(Q)

Hope Creek Page 67 of 77 Rev. 25 ATTACHMENT 2 (Page 1 of 3)

M&TE INSTALLATION AND REMOVAL FOR D/P MONITORING DURING DISCHARGE PIPING PRE-WARMING 1.0 PRECAUTIONS 1.1 The on-duty operator has the responsibility of ensuring the appropriate M&TE is obtained AND properly installed. At the conclusion of the procedure evolution, the operator has the following responsibilities:

1.1.1.

ENSURE the M&TE is removed from service AND returned to its proper storage location.

1.1.2.

DETERMINE if the M&TE was damaged during the evolution.

1.1.3.

OBSERVE good radiological practices to prevent the spread of contamination.

1.1.4.

DRAIN the instrument tubing prior to returning it.

1.2 The performing operator must follow all applicable precautions stated in Section 3.0 of this procedure.

HC.OP-SO.BC-0002(Q)

Hope Creek Page 68 of 77 Rev. 25 ATTACHMENT 2 (Page 2 of 3)

M&TE INSTALLATION AND REMOVAL FOR D/P MONITORING DURING DISCHARGE PIPING PRE-WARMING 2.0 M&TE INSTALLATION 2.1 OBTAIN the key to the Operations Hot M&TE locker from the WCCS.

2.2 OBTAIN the following from the Hot M&TE locker:

2.2.1.

M&TE Pressure Gauge with a range of ~ 0-200 psig.

2.2.2.

One length of instrument tubing ~ 8 feet long.

2.3 PERFORM the following to install Pre-Warming Discharge Piping M&TE gauge:

2.3.1.

REMOVE the cap on test connection fitting.

2.3.2.

INSTALL pressure gauge at pressure point downstream of P-BC-V9946 (V9958) PP-N058A(B) RHR LPCI INJECTION LINE A(B) Instrument Root Valve. (1 Root Valve located inside pipe chase 4329(4321)).

2.3.3.

REQUEST operations OPEN P-BC-V9946 (V9958).

2.3.4.

VENT instrument and sensing line.

2.3.5.

REQUEST operations CLOSE P-BC-V9946 (V9958),

PP-N058A(B) RHR LPCI INJECTION LINE A(B) Instrument Root Valve.

(1 Root Valve located inside pipe chase 4329(4321)).

HC.OP-SO.BC-0002(Q)

Hope Creek Page 69 of 77 Rev. 25 ATTACHMENT 2 (Page 3 of 3)

M&TE INSTALLATION AND REMOVAL FOR D/P MONITORING DURING DISCHARGE PIPING PRE-WARMING NOTE Independent Verification should be used on steps annotated with a ___ ___ signoff.

3.0 REMOVAL OF M&TE 3.1 OBTAIN the key for the Hot M&TE locker from the WCCS.

3.2 VERIFY P-BC-V9946 (V9958), PP-N058A(B) RHR LPCI INJECTION LINE A(B) Instrument Root Valve.

(1 Root Valve located inside pipe chase 4329(4321)) is CLOSED.

3.3 VENT AND DRAIN tubing AND DISCONNECT pressure gauge and all fittings and tubing.

3.4 RESTORE the test connection cap.

3.5 RETURN M&TE to Hot M&TE locker.

3.6 VERIFY the M&TE appears undamaged.

3.7 RETURN the key to the WCCS.

HC.OP-SO.BC-0002(Q)

Hope Creek Page 70 of 77 Rev. 25 FIGURE 1 Page 1 of 1 RHR PUMP SUCTION VALVE TRIP INTERLOCKS K46B F009(8)

S/D COOLING K46A F006A(B)

S/D COOLING F004A(B)

TORUS SUCTION S66A(B)

FUEL POOL COOLING MODE SUCTION TRIP OVERRIDE (OPEN IN OVERRIDE)

K25A(B)

TRIPS PUMP WHEN ENERGIZED K46A(B)

SWITCH LOCATED ON H11-P617(P618)

IN LOWER RELAY RM A(B) RHR PUMP SUCTION VALVE TRIP INTERLOCK NOTE: ALL VALVE CONTACTS ARE FROM LIMIT SWITCH POSITIONS AND CLOSE WHEN THE VALVES ARE NOT FULLY OPEN.

IF ANY VALVES IN THE SUCTION PATH ARE NOT FULLY OPEN AND THE FPC MODE SUCTION IS NOT OVERRIDDEN (A&B ONLY),

THEN THE RESPECTIVE RHR PUMP BREAKER WILL TRIP IMMEDIATELY UPON BREAKER CLOSURE.

F004C(D)

TORUS SUCTION K25C(D)

TRIPS PUMP WHEN ENERGIZED C(D) RHR PUMP SUCTION VALVE TRIP INTERLOCK

HC.OP-SO.BC-0002(Q)

Hope Creek Page 71 of 77 Rev. 25 TABLE 1 VALVE TABLE Valve Power Auto Actuations Interlocks F007A

  • B C

D (Minflow) 10B212 10B222 10B232 10B242 Open after 10 sec TD with Flow less than 1250 GPM - Auto close when RHR Loop flow exceed 1270 GPM To enable:

(1) Respective pump bkr must be closed and loop flow less than 1250 GPM (2) 10 sec time delay - enable operator to establish flowpath (ie. SDC) prior to auto open.

  • F004A B

C D

(Torus Suction) 10B212 10B222 10B232 10B242 F004D gets OPEN signal when Channel D RSP transfer switch is placed in EMERG.

  • All valves can operate w/o overload protection/Key removable in OPEN (1) F004A(B) must be 100% closed as permissive to open F006A(B).

(2) Channel B RSP to EMERG transfer F004B to RSP (3) F004C(D) must be 100% OPEN for C(D) pump breaker to close and remain closed. If C(D) pump running and F004C(D) is <100% open, the resp. pump breaker will trip.

(4) EITHER F004A(B) OR F006A(B) F008 & F009 must be 100% open to allow the A(B) pump breaker to close and remain closed.

F006A B

(S/D cooling Suction) 10B212 10B222 F006A receives a close command when channel B RSP transfer SW placed in EMERG. This transfers control of F006B to RSP.

To OPEN F006A(B) following must be 100%

closed:

(1) F004A(B)

(2) F024A(B)

(3) F027A(B)

F009 (S/D cooling suction) 10B212 Close on NS4 signals 12.5" or 82 psig Reactor press. F009 from NS4 Channel A and B Manual initiation Off Channel A (F009) 1 Channel A RSP transfer to EMERG/F009; Transfer to RSP B/P the NS4 isolations

HC.OP-SO.BC-0002(Q)

Hope Creek Page 72 of 77 Rev. 25 TABLE 1 VALVE TABLE Valve Power Auto Actuations Interlocks F015A,B (S/D cooling return, F008 (S/D cooling suction) 10B481 10B242 10B242 Close on NS4 signals 12.5" or 82 psig reactor pressure. These valves off NS4 channels C and D manual initiation off Channel D.

NS4 logic (D) must be reset following isolation. First 3 are throttle valves, Channel D RSP transfer SW to EMERG > F015B, and F008 Overload B/P with "OVLD BYP in OPEN (CLOSE)" Switch. F008 can be opened remotely only if MCC breaker Key Lock switch is in ARM position.

F010A B

10B232 10B242 Close on either auto or man LPCI init.

signal Loop "C" logic for 10A Loop "D" logic 10B (1) LPCI initiation logic must be reset to allow operation. Placing Channel D RSP to EMERG will close F010B. ("OVLD BYP in OPEN (CLOSE)")

F024A B

(RHR A&B Full Flow Test) 10B212 10B222 Auto close on LPCI init. signal (auto or man) A logic for 24A; B logic for 24B.

Can be overridden when all of the following exist concurrently: (1) LPCI init. signal present (2) F017A(B) 100%

CLOSED. (AUTO CLOSE OVRD p/b on 650 panel)

Initiation signal must be reset to disable manual OVRD condition. Placing Channel B RSP to EMERG transfer control of F024B to RSP (and B/P all automatic control features and OVLD protection) F024A(B).

F027A B

10B212 10B222 Auto close on LPCI init. logic "A" for 27A; logic "B" for 27B (man OVRD when following conditions exist concurrently (1)

LPCI init. present (2) DW press. (3) respective injection valve F017A(B) 100% closed)

OVERRIDDEN and illuminates when auto-close signal B/P. B RSP/EMERG closes F027B bypassing all auto control and OVLD protection.

Man OVRD in effect until init. signal reset F027A(B) must be 100% closed to open F006A(B)

(Torus Spray)

HC.OP-SO.BC-0002(Q)

Hope Creek Page 73 of 77 Rev. 25 TABLE 1 VALVE TABLE Valve Power Auto Actuations Interlocks F017A B

C D

LPCI Injection) 10B212 10B222 10B232 10B242 Auto open on LPCI init. if following condition exist:

(1) LPCI init. present in respective RHR loop logic (2) Power is avail. on respective pump bus (3) Reactor press. less than 450 psig (may be overridden by "AUTO OPEN OVRD")

Rx press. must be less than 450 psig to open valve either MAN or AUTO. Placing Ch. B RSP to EMERG will close F017B & inhibit all associated automatic & OVLD protection Features. The LPCI injection valve must be 100% closed (in the respective loop with a LPCI initiation signal present) to OPEN: F027A(B), F024A(B), F016, F021 F047A B

(HX Inlet) 10B212 10B222 None Placing Ch. B RSP to EMERG transfers F047B to RSP F003 A B

(HX Inlet) 10B212 10B222 Throttle Valve Placing Ch. B RSP to EMERG transfers F003B to RSP F048A B

(HX Bypass) 10B212 10B222 OPEN upon receipt of a LPCI initiation signal Valve operation is inhibited for 3 minutes upon receipt of LPCI init. signal, valve interlocked open Ch. B RSP to EMERG transfers F048B to the RSP.

OVLD protection can be bypassed in the OPEN direction (BYP IN OPEN)

HC.OP-SO.BC-0002(Q)

Hope Creek Page 74 of 77 Rev. 25 TABLE 1 VALVE TABLE Valve Power Auto Actuations Interlocks F079A B

F080A B

(RHR Sample) 1AJ481 1AJ481 1DJ481 1DJ481 Close on 12.5", 1.68 psig DW F079A(B) - NS4 logic A B F080A(B) - NS4 logic C & D Note: These are solenoid valves NS4 logic must be reset to operate valves F075 (S.W. Crosstie) 10B222 None 3 pos Keylock OPEN/OVLD ENBL/CLOSE RHR Pump A

B C

D 10A401 10A402 10A403 10A404

-129 or 1.68% DW with offsite power, A

& B immediate C & D 5 sec TD w/o offsite power immediately after D/G Bkr closes and Bus voltage reset. Pump Mtr. Bkr. Inop Alarm (1) Loss of control power (2) Bkr. not in operate position (3)

Local control (Test) switch in Pull to lock (4) Closing spring not charged (5) Loss; of trip coil continuity. "AUTO START OVRD" indicates pump stopped with initiation signal present.

No Bkr. Inop is required to start the associated pump. F004A(B,C,D) Full open or F006A(B), F008, F009 is required to allow the pump to remain running following a start, otherwise the pump breaker will close then immediately trip. When started SACS supply to RHR pump seal & oil cooler will open (HV 2520-D). Pump start is permissive for minflow valve Pump B can be operated from RSP by transferring control to RSP Control

1.

All from CR.

2.

B from RSP

3.

All locally at respective breaker or in case of "B" RSP

a. Pull to Lock/Trip/Close
b. Norm - EMERG "Other" Four stage centrifugal 10,000 GPM @

175# Mechanical seal cooled &

lubricated by pump discharge

HC.OP-SO.BC-0002(Q)

Hope Creek Page 75 of 77 Rev. 25 TABLE 1 VALVE TABLE Valve Power Auto Actuations Interlocks F016A B

F021A B

(Containment Spray) 10B212 10B222 10B451 10B222 None for all 4 valves F016A(B) & F021A(B) interlocked such that both valves can only be opened simultaneous when LPCI init. signal present and Hi DW and F017A(B) is 100% closed. F016B and F021A(B) receive CLOSE signals upon transfer to RSP RSP CH A to EMERG transfers F021A RSP CH B to EMERG transfers F021B and F016B to RSP F040 (Radwaste) 10B242 Close upon receipt of Lvl 3 (12.5) or 1.68 psig in both CH C&D of NS4 also close in response to NS4 Channel D manual isolation. Throttle Valve NS4 logic must be reset to operate valve. BYP IN CLOSE will bypass OVLD. CH D RSP to EMERG transfer operation to RSP F049 (Radwaste) 10B411 Close upon receipt of Lvl 3 (12.5) or 1.68 psig DW in Channel A & B of NS4 concurrently or manual isolation from Channel A CH A RSP to EMERG/transfer control to RSP NS4 logic must be reset to allow valve operation HV-4439 (Radwaste) 10B242 None CH A RSP to EMERG/Control to RSP

HC.OP-SO.BC-0002(Q)

Hope Creek Page 76 of 77 Rev. 25 TABLE 1 VALVE TABLE Valve Power Auto Actuations Interlocks ECCS Jockey Pump DP228 CP228 10B242 10B232 CH D RSP to EMERG/starts DP228 None Characteristic 20 GPM at 100 psig/110 psig shutoff head RHR Heat Exchanger A & B None Characteristics SACS tube side Flowrate and/also conductivity Temp indication (Recorder) shell side inlet &

outlet and tube side outlet.

None

HC.OP-SO.BC-0002(Q)

Hope Creek Page 77 of 77 Rev. 25 TABLE 2 INSTRUMENT TRANSMITTER FUNCTIONS VALVE PARAMETER TRANSMITTER LOGIC FUNCTION F009 Reactor Pressure PT-7853A RSP Open Permissive for RSP Control PT-N078A NS4(A)

NS4(B)

Isolation Signal for Normal Valve Control F008 Reactor Pressure PT-7853D RSP Open Permissive for RSP Control PT-N078C PT-N078D NS4(C)

NS4(D)

Isolation Signal for Normal Valve Control

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