ML110060580

Salem/Operations, S1.OP-IO.ZZ-0007(Q), Rev. 16, Cold Shutdown to Refueling

ML110060580
Person / Time
Site:	Salem
Issue date:	02/24/2010
From:	Public Service Enterprise Group
To:	Office of Nuclear Reactor Regulation
References
LR-N10-0355 S1.OP-IO.ZZ-0007(Q), Rev 16
Download: ML110060580 (25)

Text

PSEG Internal Use Only Page 1 of 1 PSEG NUCLEAR L.L.C.

SALEM/OPERATIONS S1.OP-IO.ZZ-0007(Q) REV. 16 COLD SHUTDOWN TO REFUELING USE CATEGORY: I Biennial Review Performed: Yes ____ No ____ NA T DCP Packages and Affected Document Numbers incorporated into this revision: None The following OTSCs were incorporated into this revision: None REVISION

SUMMARY

, Step 1.3.1, added Date/Time Surveillance completed + 7 days:

[70105187]

Editorial enhancement as lessons learned in Refueling Outage 2R17.

This information will assist those outside the Control Room in planning when the next Source Range T/S Surveillance is to be performed.

Replaced the reference to "70027610" with "70106301".

[70106301]

T/S Amendments 263 /245 (NRC SEV) changed the definition of "CORE ALTERATIONS".

The "lifting of the Upper Internals" is no longer considered a "CORE ALTERATION" as defined in Technical Specifications.

IMPLEMENTATION REQUIREMENTS Effective Date:

February 24, 2010 None

S1.OP-IO.ZZ-0007(Q)

Salem 1 Page 1 of 24 Rev. 16 COLD SHUTDOWN TO REFUELING TABLE OF CONTENTS SECTION TITLE PAGE 1.0 PURPOSE................................................................ 2 2.0 PREREQUISITES.......................................................... 2 3.0 PRECAUTIONS AND LIMITATIONS......................................... 2 4.0 EQUIPMENT/MATERIAL REQUIRED........................................ 3 5.0 PROCEDURE............................................................. 4 5.1 Mode 5 To Mode 6 Operations......................................... 4 5.2 Core Alteration Operations (No Fuel Movement)........................... 7 5.3 Core Alteration Operations (Fuel Movement)............................. 8 5.4 Completion And Review.............................................. 9 6.0 RECORDS............................................................... 10

7.0 REFERENCES

............................................................ 10 ATTACHMENTS Requirements and Reviews For Mode 6................................. 13 Requirements And Review For Core Alterations (No Fuel Movement)................................................ 15 Requirements And Review For Core Alterations -

Movement Of Irradiated Fuel In The Reactor Pressure Vessel................ 17 1R11A, 1R12A, And 1R12B Control Functions........................... 21 Completion Sign-Off Sheet........................................... 22

S1.OP-IO.ZZ-0007(Q)

Salem 1 Page 2 of 24 Rev. 16 1.0 PURPOSE 1.1 To provide the instructions necessary to:

1.1.1 Transition from Cold Shutdown (Mode 5) to Refueling (Mode 6).

1.1.2 Prepare for CORE ALTERATIONS.

1.1.3 Prepare for Movement of Irradiated Fuel in the Reactor Pressure Vessel.

2.0 PREREQUISITES

___ 2.1 ENSURE a RCS vent path is established IAW S1.OP-SO.PZR-0006(Q), RCS Venting.

___ 2.2 ENSURE RCS is degassed IAW S1.OP-SO.CVC-0011(Q), RCS Degassification, OR Chemistry RCS sample analysis is acceptable to allow opening the RCS.

___ 2.3 ENSURE Refueling Canal Drain Flange is installed.

(Refueling Canal Drain Flange Drain Valve 1WL221 is located on this flange) 3.0 PRECAUTIONS AND LIMITATIONS

___ 3.1 A maximum of one Safety Injection Pump OR one Centrifugal Charging Pump shall be OPERABLE IAW T/S Surveillances 4.5.3.2.a or 4.5.3.2.b while in Mode 5 or 6 when the head is on the Reactor Pressure Vessel.

___ 3.2 13 Charging Pump flow path shall be aligned to Unit 2 OR the pump shall be C/T when 11 or 12 Safety Injection Pump is capable of injection into the core with RCS temperature #312°F with the Reactor Vessel Head installed.

[C0565]

___ 3.3 S1.OP-IO.ZZ-0010(Q), Spent Fuel Pool Manipulations, is to remain active while in Section 5.3 of this procedure.

___ 3.4 Maintaining RCS Activity at #0.05 uci/ml prior to filling the Refueling Cavity will result in lowered dose rates, #2.5 mr/hr, at the refueling water surface during refueling evolutions.

___ 3.5 Direct communications shall be maintained between the Control Room and personnel at the refueling station during CORE ALTERATIONS (T/S 3.9.5).

[70106301]

___ 3.6 CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components, within the reactor vessel with the vessel head removed and fuel in the vessel.

Suspension of CORE ALTERATION shall not preclude completion of movement of a component to a safe conservative location.

[70106301]

S1.OP-IO.ZZ-0007(Q)

Salem 1 Page 3 of 24 Rev. 16

___ 3.7 The boron concentration of the Refueling Canal, Fuel Storage Pool, and the Refueling Cavity shall be maintained within the limits of the COLR when connected to the Reactor Coolant System to comply with T/S 3.9.1 in Mode 6.

___ 3.8 1R11A, 1R12A, and 1R12B are NOT required by Technical Specifications in Mode 6.

Test jumpers will be installed IAW Attachment 4 to defeat the Containment Ventilation Isolation control function in Mode 6. The test jumpers may be removed on an intermittent basis to support testing of the associated monitors.

The test jumpers shall NOT be removed when all of the following conditions exist:

Movement of irradiated fuel within the containment is in progress, and Containment Equipment Hatch is removed, and Containment Purge To Plant Vent is relied upon as the required ventilation flow path in Attachment 3, Step 1.9.1.

4.0 EQUIPMENT/MATERIAL REQUIRED None

S1.OP-IO.ZZ-0007(Q)

Salem 1 Page 4 of 24 Rev. 16 5.0 PROCEDURE 5.1 Mode 5 To Mode 6 Operations 5.1.1 INITIATE the following:

S1.OP-IO.ZZ-0107(Q), Cold Shutdown To Refueling Administrative Requirements

, Requirements and Reviews for Mode 6.

S1.OP-IO.ZZ-0010(Q), Spent Fuel Pool Manipulations.

S1.OP-ST.CAN-0007(Q), Refueling Operations - Containment Closure.

5.1.2 When Attachment 1 is completed with Mode 6 entry authorized:

A.

ENSURE the RCS is drained to <104 ft elevation IAW S1.OP-SO.RC-0005(Q), Draining the Reactor Coolant System to $101 Ft Elevation OR S1.OP-SO.RC-0006(Q), Draining the Reactor Coolant System to <101 Ft Elevation With Fuel In The Vessel.

B.

NOTIFY Outage Management that the requirements to initiate Reactor Pressure Vessel Head detensioning are satisfied.

5.1.3 When the first stud (during first pass of Reactor Head detensioning process) is detensioned:

RECORD time Mode 6 is entered in the Control Room Narrative Log.

UPDATE WCM to Mode 6.

S1.OP-IO.ZZ-0007(Q)

Salem 1 Page 5 of 24 Rev. 16 NOTE 1R11A control function is normally defeated in Modes 1-6.

1R12A and 1R12B control functions are normally defeated in Mode 6 and enabled in Modes 1-5.

5.1.4 NOTIFY Maintenance to perform Attachment 4, 1R11A, 1R12A, And 1R12B Control Functions.

5.1.5 ENSURE the following valves are CLOSED:

1WL2, FUEL XFER CANAL DRAIN 1WL3, FUEL XFER CANAL DRAIN 5.1.6 CLOSE the following valves:

1RC2, REACTOR HEAD INNER SEAL LEAK-OFF VALVE 1RC3, REACTOR HEAD OUTER SEAL LEAK-OFF VALVE 5.1.7 Direct a second Operator to PERFORM Independent Verification that 1RC2 and 1RC3 are CLOSED:

IV Signature Date

S1.OP-IO.ZZ-0007(Q)

Salem 1 Page 6 of 24 Rev. 16 CAUTION The Containment Noble Gas Monitor (1R12A) could momentarily exceed the alarm setpoint during preparations for, and during the Reactor Pressure Vessel Head Lift.

This event is considered a pre-planned sequence during reactor disassembly which is NOT reportable IAW the ECG.

[PR990411101]

5.1.8 Prior to initiating the Reactor Pressure Vessel Head Lift, NOTIFY Outage Management that the Reactor Pressure Vessel Head Lift is authorized.

5.1.9 When the Reactor Pressure Vessel Head is removed FILL the Refueling Cavity as follows:

A.

IF surveillances are to be performed at this time, COORDINATE with Outage Scheduling any of the following surveillances that are to be completed during the Refueling Cavity filling:

S1.OP-ST.CS-0005(Q), In Service Testing Containment Spray Valves - Mode 6 S1.OP-ST.RHR-0005(Q), In Service Testing Residual Heat Removal Valves and Orifices S1.OP-ST.SJ-0006(Q), In Service Testing Safety Injection Valves - Mode 6 NOTE The boron concentration of the Refueling Canal, Fuel Storage Pool, and the Refueling Cavity shall be maintained within the limits of the COLR when connected to the Reactor Coolant System to comply with T/S 3.9.1 in Mode 6.

B.

FILL the Refueling Cavity IAW S1.OP-SO.SF-0003(Q),

Filling the Refueling Cavity.

5.1.10 INITIATE S1.OP-SO.SF-0009(Q), Refueling Operations.

5.1.11 INITIATE Attachment 2, Requirements and Review for Core Alterations (No Fuel Movement).

S1.OP-IO.ZZ-0007(Q)

Salem 1 Page 7 of 24 Rev. 16 5.2 Core Alteration Operations (No Fuel Movement) 5.2.1 When Attachment 2 is completed and CORE ALTERATIONS with no movement of irradiated fuel in the reactor pressure vessel is authorized:

A.

ENSURE 11CA330 is OPEN AND PLACE Information Only tag on 11CA330 bezel:

"Air supply to the refueling manipulator crane".

B.

ENSURE direct communications between the Control Room and personnel at the refueling station are established within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> prior to start of Core Alterations AND verified at least once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during Core Alterations using an Additional Reading/Operator Action Log IAW OP-SH-111-101-1001, Use and Development of Operating Logs.

(T/S 4.9.5)

C.

NOTIFY personnel in the Control Room AND the refueling station that CRS permission is required to discontinue direct communications between the Control Room and personnel at the refueling station.

[70106301]

D.

IF any control rod is to be moved within the reactor pressure vessel, ENSURE the last recorded Reactor Pressure Vessel Water Level in S1.OP-DL.ZZ-0002(Q) is within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of control rod movement (T/S 4.9.10).

E.

NOTIFY Outage Management that (except for fuel movement) the requirements to commence CORE ALTERATIONS are satisfied.

5.2.2 INITIATE Attachment 3, Requirements and Review for Core Alterations - Movement of Irradiated Fuel in the Reactor Pressure Vessel.

S1.OP-IO.ZZ-0007(Q)

Salem 1 Page 8 of 24 Rev. 16 5.3 Core Alteration Operations (Fuel Movement) 5.3.1 When Attachment 3, Requirements and Review for Core Alterations -

Movement of Irradiated Fuel in the Reactor Pressure Vessel is completed and movement of irradiated fuel in the reactor pressure vessel is authorized:

A.

ENSURE direct communications between the Control Room and personnel at the refueling station are established within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> prior to start of Core Alterations AND verified at least once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during Core Alterations using an Additional Reading/Operator Action Log IAW OP-SH-111-101-1001, Use and Development of Operating Logs.

(T/S 4.9.5)

B.

NOTIFY personnel in the Control Room AND the refueling station that CRS permission is required to discontinue direct communications between the Control Room and personnel at the refueling station.

[70106301]

C.

ENSURE Fuel Handling Area administrative and Technical Specifications requirements are satisfied IAW S1.OP-IO.ZZ-0010(Q),

Spent Fuel Pool Manipulations.

D.

ENSURE the last recorded Reactor Pressure Vessel Water Level in S1.OP-DL.ZZ-0002(Q) is within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of fuel movement (T/S 4.9.10).

E.

NOTIFY Outage Management that the requirements to commence fuel movement are satisfied.

F.

When the Reactor Pressure Vessel is defueled:

REMOVE Information Only tag from 11CA330 bezel.

MAINTAIN Unit 1 IAW S1.OP-DL.ZZ-0002(Q),

Control Room Log - Mode 5, 6 and Defueled.

MAINTAIN Salem Integrated Decay Heat Management requirements specified in SC.OM-AP.ZZ-0001(Q),

Shutdown Safety Management Program - Salem Annex.

S1.OP-IO.ZZ-0007(Q)

Salem 1 Page 9 of 24 Rev. 16 5.4 Completion And Review 5.4.1 COMPLETE Attachment 5, Sections 1.0 and 2.0, AND FORWARD this procedure to the SM/CRS for review and approval.

5.4.2 SM/CRS PERFORM the following:

A.

REVIEW this procedure with Attachments 1-5 for completeness and accuracy.

B.

COMPLETE Attachment 5, Section 3.0.

C.

IF this procedure is terminated prior to completion, RECORD reason, date and time of termination on, Section 1.0.

D.

IF this procedure is completed successfully, 1.

ATTACH completed S1.OP-IO.ZZ-0107(Q), Cold Shutdown to Refueling Administrative Requirements to this procedure.

2.

FORWARD completed procedure, including any terminated procedure, if applicable, to Operations Staff.

END OF PROCEDURE SECTION

S1.OP-IO.ZZ-0007(Q)

Salem 1 Page 10 of 24 Rev. 16 6.0 RECORDS 6.1 Retain the following IAW RM-AA-101, Records Management Program:

This Entire Procedure

7.0 REFERENCES

7.1 Updated Final Safety Analysis Report 7.1.1 Section 4, Reactor 7.1.2 Section 5, Reactor Coolant System and Connected Systems 7.1.3 Section 7, Instrumentation and Controls 7.1.4 Section 8, Electrical Systems 7.1.5 Section 9, Auxiliary Systems 7.1.6 Section 15.1, Condition 1, Normal Operation and Operational Transients 7.2 Technical Specifications - Unit 1 7.2.1 3.1.2.3, Charging Pump - Shutdown 7.2.2 3.3.3.1, Radiation Monitoring Instrumentation 7.2.3 3.8.1.1, A.C. Sources - Operating 7.2.4 3.8.1.2, A.C. Sources - Shutdown 7.2.5 3.8.2.1, A.C. Distribution - Operating 7.2.6 3.8.2.2, A.C. Distribution - Shutdown 7.2.7 3.8.2.3, 125-Volt D.C. Distribution - Operating 7.2.8 3.8.2.4, 125-Volt D.C. Distribution - Shutdown 7.2.9 3.8.2.5, 28-Volt D.C. Distribution - Operating 7.2.10 3.8.2.6, 28-Volt D.C. Distribution - Shutdown 7.2.11 4.9.12, Fuel Handling Area Ventilation System 7.3 Procedures 7.3.1 S1.OP-IO.ZZ-0001(Q), Refueling to Cold Shutdown 7.3.2 S1.OP-IO.ZZ-0107(Q), Cold Shutdown To Refueling Administrative Requirements 7.3.3 S1.OP-SO.SF-0001(Q), Fill and Transfer of the Spent Fuel Pool

S1.OP-IO.ZZ-0007(Q)

Salem 1 Page 11 of 24 Rev. 16 7.4 Drawings 7.4.1 205201, No. 1 Unit Reactor Coolant System 7.4.2 205228, No. 1 Unit Chemical and Volume Control System 7.4.3 205231, No. 1 Unit Component Cooling System 7.4.4 205232, No. 1 Unit Residual Heat Removal 7.4.5 205233, No. 1 Unit Spent Fuel Cooling 7.4.6 205234, No. 1 Unit Safety Injection System 7.4.7 205240, No. 1 Unit Waste Disposal - Gas 7.5 Others 7.5.1 DCP 80029150 And 80029155, Unit CVCS Cross-Tie 7.5.2 INPO SOER 88-3, Losses of RHR With Reduced Reactor Vessel Water Level 7.5.3 NRC INFO 87-23, Loss Of Decay Heat Removal Function At PWRs With Partially Drained Reactor Coolant Systems 7.5.4 PIR #990411101, ESF Actuation During Reactor Head Lift (2R12A) 7.5.5 SC-R200-MSE-0738-1, Mid-Loop Operation, 10/10/88 7.5.6 Westinghouse Owners Group Abnormal Response Guideline WOG-ARG-1, Loss of RHR While Operating at Mid-Loop Conditions 7.5.7 80050653, Technical Specification Amendment 263/245, Refueling Operations, Relaxation of T/S Requirements Applicable During The Movement Of Irradiated Fuel.

7.6 Cross-References 7.6.1 Technical Specifications - Unit 1:

A.

3.4.9.3, RCS Overpressure Protection Systems B.

3.9.2, Instrumentation C.

4.9.8.2, Low Water Level (RHR Loops)

D.

4.1.2.1.a.1 & 2, Boration Systems Flowpath - Shutdown E.

4.1.2.1.b, Boration Systems Flowpath - Shutdown F.

4.1.2.3, Charging Pump - Shutdown G.

4.1.2.5.a & b, Borated Water Sources - Shutdown H.

4.5.3.2.a & b, ECCS Subsystems - TAVG <350°F I.

4.8.1.2, Electrical Power Systems - Shutdown J.

4.8.2.4.1, 125VDC Distribution System - Shutdown K.

4.8.2.6.1, 28VDC Distribution System - Shutdown L.

4.9.1, Boron Concentration M.

4.9.2, Instrumentation N.

4.9.3, Decay Time O.

4.9.4.1, Containment Building Penetrations P.

4.9.4.2, Containment Equipment Hatch Q.

4.9.4.3, Containment Purge Isolation R.

4.9.5, Communications S.

4.9.8.1, Refueling Operations - All Water Levels (Coolant Circulation)

T.

4.9.10, Reactor Pressure Vessel Water Level

S1.OP-IO.ZZ-0007(Q)

Salem 1 Page 12 of 24 Rev. 16

7.6.2 Procedures

A.

SC.OM-AP.ZZ-0001(Q), S/D Safety Management Program - Salem Annex B.

CY-AP-120-100, RCS Chemistry C.

CY-AP-120-3100, PWR Startup Chemistry For Recirculating S/Gs D.

SC.CH-TI.ZZ-0180(Q), Sampling Schedule and Chemistry Specifications E.

S1.OP-DL.ZZ-0001(Q), Control Room Logs F.

S1.OP-DL.ZZ-0002(Q), Control Room Log - Mode 5, 6 and Defueled G.

S1.OP-IO.ZZ-0010(Q), Spent Fuel Pool Manipulations H.

S1.OP-SO.CBV-0002(Q), Containment Pressure-Vacuum Relief I.

S1.OP-SO.RHR-0001(Q), Initiating RHR J.

S1.OP-SO.SF-0003(Q), Filling the Refueling Cavity K.

S1.OP-SO.WG-0006(Q), Containment Purge to Plant Vent 7.7 Commitments 7.7.1 C0565 - NLR N94229, POPS Setpoint Nonconservatism 7.7.2 C0636 - NSO AMEN 131/110, LER 88-06, Letter NLR-N91094

S1.OP-IO.ZZ-0007(Q)

Salem 1 Page 13 of 24 Rev. 16 ATTACHMENT 1 (Page 1 of 2)

REQUIREMENTS AND REVIEWS FOR MODE 6 1.0 TECHNICAL SPECIFICATIONS REQUIREMENTS

___ 1.1 The Reactor Coolant System boron concentration shall be maintained within the limits specified in the Core Operating Limits Report (COLR) and shall be verified at least once every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in Mode 6 (T/S 3.9.1).

___ 1.2 Two Source Range neutron flux monitors are OPERABLE each with continuous visual indication in the Control Room and one with audible indication in the Containment and Control Room (T/S 3.9.2), including the following:

OHA E-13, SR HI FLUX AT S/D Audio Count Rate Channel

___ 1.3 1N31 & 1N32 Channel Checks performed and recorded in S1.OP-DL.ZZ-0002(Q),

Control Room Log - Mode 5, 6 and Defueled, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (T/S 4.9.2.b.)

___ 1.4 At least one RHR Loop is in service IAW S1.OP-SO.RHR-0001(Q), Initiating RHR, maintaining RCS temperature >50°F and #140°F with coolant circulation $1000 gpm as verified at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> IAW S1.OP-DL.ZZ-0002(Q) (T/S 4.9.8.1).

___ 1.5 Two independent RHR Loops are OPERABLE when RCS Level will be <23 feet above the top of the Reactor Pressure Vessel flange (T/S 3.9.8.2).

___ 1.6 Unit Logs: Control Room, Primary and Secondary. Required Technical Specification readings must be current for Mode 6 and unsatisfactory conditions resolved.

There are no T/S Action Statements which would prohibit entry into Mode 6.

___ 1.7 S1.OP-DL.ZZ-0001(Q), Control Room review is complete for conditions that could prevent entering Mode 6.

___ 1.8 Control Room Area Ventilation is aligned IAW S1/S2.OP-SO.CAV-0001(Q),

Control Area Ventilation Operation, as required by T/S 3.7.6.1 (3.7.6) for Modes 5 and 6.

S1.OP-IO.ZZ-0007(Q)

Salem 1 Page 14 of 24 Rev. 16 ATTACHMENT 1 (Page 2 of 2)

REQUIREMENTS AND REVIEWS FOR MODE 6 2.0 ADMINISTRATIVE REQUIREMENTS 2.1 SM/CRS REVIEW the following:

2.1.1 ORAM status supports Mode 6 entry.

2.1.2 Technical Specification Action Statement Log to ensure entry into Mode 6 is permitted by Technical Specifications.

2.2 WCM Update And Review:

2.2.1 CHANGE WCM to Operating Mode 6.

2.2.2 GENERATE a Components in Off Normal Position Report (Off-Normal and Off Normal Tagged).

2.2.3 POSITION all components as required for Mode 6 OR DOCUMENT on the report the reason a component cannot be positioned and the justification for entering Mode 6.

2.2.4 UPDATE WCM for the new positions.

2.2.5 GENERATE an Unavailable Equipment Report and review for equipment required for entering Mode 6.

2.2.6 ATTACH the Components Off Normal Position Report (Off Normal and Off Normal Tagged) and the Unavailable Equipment Report to this procedure.

2.2.7 ENSURE all equipment required for Mode 6 is OPERABLE OR a justification is provided.

3.0 FINAL REVIEW

[C0636]

Administrative and Technical Specifications requirements for Mode 6 entry (Sections 1.0 - 2.0) are completed.

S1.OP-IO.ZZ-0107(Q), Cold Shutdown To Refueling Administrative Requirements has been reviewed. Systems - Technical Assessment Open or Required Action Items have been resolved and permission to proceed to Mode 6 has been granted:

/

Control Room Supervisor Date / Time

/

Shift Manager Date / Time

S1.OP-IO.ZZ-0007(Q)

Salem 1 Page 15 of 24 Rev. 16 ATTACHMENT 2 (Page 1 of 2)

REQUIREMENTS AND REVIEW FOR CORE ALTERATIONS (NO FUEL MOVEMENT) 1.0 TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENTS

___ 1.1, Sections 1.0 - 3.0, are completed and in periodicity.

___ 1.2 The boron concentration of the Refueling Canal, Fuel Storage Pool, and the Refueling Cavity shall be maintained within the limits of the COLR when connected to the Reactor Coolant System. The boron concentration of each volume shall be verified at least once every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> while in Mode 6 (T/S 3.9.1).

___ 1.3 The following Technical Specification Surveillance Requirements are completed and within periodicity:

1.3.1 SC.IC-FT.NIS-0011(Q) and SC.IC-FT.NIS-0012(Q),

for N31 & N32 Source Range Channels completed at least once per 7 days (as required by T/S 4.9.2):

Date/Time Surveillance completed:

________ / ________

Date/Time Surveillance completed + 7 days (overdue date):

________ / ________

Present Date/Time:

________ / ________

1.3.2 IF any control rod is to be moved within the reactor pressure vessel, S1.OP-DL.ZZ-0002(Q), Reactor Pressure Vessel Water Level, is performed within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> prior to the start of movement of any control rod in the reactor pressure vessel (as required by T/S 4.9.10):

Date/Time Surveillance completed:

________ / ________

Present Date/Time:

________ / ________

S1.OP-IO.ZZ-0007(Q)

Salem 1 Page 16 of 24 Rev. 16 ATTACHMENT 2 (Page 2 of 2)

REQUIREMENTS AND REVIEW FOR CORE ALTERATIONS (NO FUEL MOVEMENT) 2.0 FINAL REVIEW

[C0636]

Administrative and Technical Specifications requirements for CORE ALTERATIONS (Section 1.0) is completed.

S1.OP-IO.ZZ-0107(Q), Cold Shutdown To Refueling Administrative Requirements has been reviewed. Systems - Technical Assessment Open or Required Action Items have been resolved and permission to proceed with CORE ALTERATIONS:

/

CRS Date / Time

/

SM Date / Time

S1.OP-IO.ZZ-0007(Q)

Salem 1 Page 17 of 24 Rev. 16 ATTACHMENT 3 (Page 1 of 4)

REQUIREMENTS AND REVIEW FOR CORE ALTERATIONS -

MOVEMENT OF IRRADIATED FUEL IN THE REACTOR PRESSURE VESSEL 1.0 TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENTS

___ 1.1, Sections 1.0 - 3.0, are completed and in periodicity.

___ 1.2, Sections 1.0 - 2.0, are completed and in periodicity.

___ 1.3 ENSURE the appropriate on-shift personnel as determined by the Operations Manager have reviewed S1.OP-AB.SF-0001(Q), Loss of Spent Fuel Pool Cooling, prior to commencing core offload. Refer to SC.OM-AP.ZZ-0001(Q),

Shutdown Safety Management Program - Salem Annex.

___ 1.4 IF movement of irradiated fuel is to occur between October 15th through May 15th the Reactor is subcritical for $80 hours ($3 days and 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> as required by TSAS 3.9.3.a):

Reactor Subcritical Date/Time:

________ / ________

Present Date/Time:

________ / ________

___ 1.5 IF movement of irradiated fuel is to occur between May 16th through October 14th, the Reactor is subcritical for $168 hours ($7 consecutive days as required by TSAS 3.9.3.b):

Reactor Subcritical Date/Time:

________ / ________

Present Date/Time:

________ / ________

___ 1.6 S1.OP-DL.ZZ-0002(Q), the water level shall be determined to be at least 23 feet over the reactor pressure vessel flange within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> prior to the start of movement of fuel assemblies or control rods (T/S 4.9.10):

Date/Time Surveillance completed:

________ / ________

Present Date/Time:

________ / ________

S1.OP-IO.ZZ-0007(Q)

Salem 1 Page 18 of 24 Rev. 16 ATTACHMENT 3 (Page 2 of 4)

REQUIREMENTS AND REVIEW FOR CORE ALTERATIONS -

MOVEMENT OF IRRADIATED FUEL IN THE REACTOR PRESSURE VESSEL

___ 1.7 IF movement of irradiated fuel is to occur with the Reactor subcritical for <168 hours (between October 15th through May 15th),

Obtain CCW refueling temperature requirement from Outage Management (Prior to each refueling outage an Engineering Calculation will be performed to ensure that the decay heat load expected and the river water temperature are adequate to meet the required heat removal capability for core offload after the reactor has been subcritical for at least 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />).

CCW refueling temperature requirement:

1. ________°F Date/Time:

________ / ________

Slowly adjust CCHX Controller setpoint(s) as required to maintain the CCW refueling temperature requirement.

Ensure both Unit 1 and Unit 2 Spent Fuel Heat Exchangers are available with Component Cooling Water flow capability of at least 3,000 gpm each.

Date/Time:

________ / ________

___ 1.8 The following Technical Specification Surveillance Requirements are completed and within periodicity:

1.8.1 S1.OP-ST.CAN-0007(Q), each of the required containment building penetrations shall be determined to be either in its required condition or capable of being closed by a manual or automatic containment isolation valve at least once per 7 days (T/S 4.9.4.1):

Date/Time Surveillance completed:

________ / ________

Present Date/Time:

________ / ________

1.8.2 S1.OP-ST.CBV-0004(Q), verify, once per 18 months, each required containment purge isolation valve actuates to the isolation position on a manual actuation signal (T/S 4.9.4.3):

Date/Time Surveillance completed:

________ / ________

Present Date/Time:

________ / ________

S1.OP-IO.ZZ-0007(Q)

Salem 1 Page 19 of 24 Rev. 16 ATTACHMENT 3 (Page 3 of 4)

REQUIREMENTS AND REVIEW FOR CORE ALTERATIONS -

MOVEMENT OF IRRADIATED FUEL IN THE REACTOR PRESSURE VESSEL NOTE In the event of a Fuel Handling Accident (FHA) the following ventilation requirements will ensure that airflow will be into containment allowing continuous monitoring of the containment atmosphere until containment closure is accomplished. If for any reason, these ventilation requirements can not be met, movement of fuel assemblies within the containment building shall be discontinued until the ventilation flow path(s) can be restored or the equipment hatch and personnel airlocks are closed.

(T/S Bases 3/4.7.7, T/S Amendment 263/245 Safety Evaluation)

___ 1.9 IF movement of irradiated fuel within the containment building is planned with the Containment Equipment Hatch OPEN, 1.9.1 At least one of the following ventilation flow path(s) shall be established:

Containment Purge To Plant Vent IAW S1.OP-SO.WG-0006(Q), or Auxiliary Building Ventilation System in operation IAW S1.OP-SO.ABV-0001(Q) with both of the following conditions satisfied:

a suction flowpath through at least one Containment Airlock, and 1R41A and 1R41D radiation monitors are OPERABLE.

1.9.2 Maintenance has completed Attachment 4, 1R11A, 1R12A, And 1R12B, Control Functions, (test jumpers are installed) (Refer to Step 3.8).

1.9.3 SC.MD-FR.CAN-0001(Q), once per refueling prior to the start of movement of irradiated fuel assemblies, verify the capability to install, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, the equipment hatch (T/S 4.9.4.2):

Date/Time Surveillance completed:

________ / ________

Present Date/Time:

________ / ________

1.9.4 A periodic verification (once per shift) of the ventilation flow path(s) established in Step 1.9.1 is required IAW S1.OP-DL.ZZ-0002(Q)

(T/S Amendment 263/245 Safety Evaluation).

S1.OP-IO.ZZ-0007(Q)

Salem 1 Page 20 of 24 Rev. 16 ATTACHMENT 3 (Page 4 of 4)

REQUIREMENTS AND REVIEW FOR CORE ALTERATIONS -

MOVEMENT OF IRRADIATED FUEL IN THE REACTOR PRESSURE VESSEL 2.0 FINAL REVIEW

[C0636]

Administrative and Technical Specifications requirements for movement of irradiated fuel in the reactor pressure vessel (Section 1.0) is completed.

S1.OP-IO.ZZ-0107(Q), Cold Shutdown To Refueling Administrative Requirements has been reviewed. Systems - Technical Assessment Open or Required Action Items have been resolved and permission to proceed with the movement of irradiated fuel in the reactor pressure vessel:

/

CRS Date / Time

/

SM Date / Time

S1.OP-IO.ZZ-0007(Q)

Salem 1 Page 21 of 24 Rev. 16 ATTACHMENT 4 (Page 1 of 1) 1R11A, 1R12A, AND 1R12B CONTROL FUNCTIONS NOTE 1R11A Control Function is normally defeated in Modes 1-6.

1R12A and 1R12B Control Functions are normally defeated in Mode 6 and enabled in Modes 1-5.

1.0 1R11A - CONTROL FUNCTION DEFEAT:

[Drawings 226507, 203481, and 220236]

___ 1.1 ENSURE the following test jumpers are connected:

TB42 terminals 2 to 3 in Auxiliary Rack 58-1 IV TB3 terminals 6 to 8 in Auxiliary Rack 59-1 IV

___ 1.2 ENSURE Job Information Tags are applied to test jumpers 2.0 1R12A AND 1R12B - CONTROL FUNCTION DEFEAT:

[Drawings 226507, 203480, 220236 and 220239]

___ 2.1 CONNECT the following test jumpers:

TB42 terminals 1 to 2 in Auxiliary Rack 58-1 IV TB3 terminals 3 to 6 in Auxiliary Rack 59-1 IV

___ 2.2 APPLY Job Information Tags to test jumpers

S1.OP-IO.ZZ-0007(Q)

Salem 1 Page 22 of 24 Rev. 16 ATTACHMENT 5 (Page 1 of 3)

COMPLETION SIGN-OFF SHEET 1.0 COMMENTS (INCLUDE procedure deficiencies and corrective actions.)

S1.OP-IO.ZZ-0007(Q)

Salem 1 Page 23 of 24 Rev. 16 ATTACHMENT 5 (Page 2 of 3)

COMPLETION SIGN-OFF SHEET 2.0 SIGNATURES Print Initials Signature Date

S1.OP-IO.ZZ-0007(Q)

Salem 1 Page 24 of 24 Rev. 16 ATTACHMENT 5 (Page 3 of 3)

COMPLETION SIGN-OFF SHEET 2.0 SIGNATURES (continued)

Print Initials Signature Date 3.0 SM/CRS FINAL REVIEW AND APPROVAL This procedure with Attachments 1-4 is reviewed for completeness and accuracy.

All deficiencies, including corrective actions, are clearly recorded in the Comments Section of Attachment 5. Technical Specification compliance and procedure compliance is evaluated.

Signature: ________________________________________________

Date: _________

SM/CRS