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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211C3311999-04-30030 April 1999
Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood
ML20205A0871999-03-22022 March 1999
Revs to Odcm,Including Rev 2.0 to Chapter 10, Radioactive Effluent Treatment & Monitoring & Rev 1.9 to Chapter 12, Radiological Effluent Technical Stds (Rets)
ML20199E0361999-01-12012 January 1999
Proposed Tech Specs Section 3.10, Fuel Handling & Storage, Eliminating Reference to Initiation of Generating Station EP Action That Is Incorrect & Not Part of Reason for Min FSP Water Level TS
ML20196F6451998-11-30030 November 1998
Proposed Tech Specs 3/4.1.A,3/4.10.B & 3/4.12.B,proposing Changes to Relocate Requirement to Remove RPS Shorting Links Which Enable non-coincident Scram for Neutron Instrumentation,To Licensee Controlled Document
ML20237A8651998-08-0707 August 1998
Qualified Unit 1 Supervisor Initial & Continuing Training Program
ML20151S2691998-07-31031 July 1998
Rev 1.8 to Chapter 12 of Dresden Station Odcm
ML20217N9331998-04-30030 April 1998
Rev 1.7 to Chapter 12 of Dresden Station Odcm
ML20216H4321997-12-31031 December 1997
Revs to OCDM for Braidwood,Including Rev 1.8 to Chapter 10, Rev 1.9 to Chapter 11,rev 2 to Chapter 12 & Rev 2 to App F
ML20216H8551997-12-31031 December 1997
Revs to OCDM for Dresden Station,Including Rev 1.9 to Chapter 10,rev 1.3 to Chapter 11,rev 1.6 to Chapter 12 & Rev 1.1 to App F
ML20198M2491997-12-18018 December 1997
Revs to Ocdm,Including Rev 1.3 to Chapter 11, Radiologicial Environ Monitoring Program & Rev 1.6 to Chapter 12, Radiological Effluent Technical Stds (Rets)
ML20216H8241997-10-31031 October 1997
Revs to OCDM for Byron Station,Including Rev 1.3 to Chapter 10,rev 1.5 to Chapters 11 & 12 & Rev 1.3 to App F
ML20216H9041997-10-31031 October 1997
Revs to OCDM for Zion Station,Including Rev 1.9 to Chapter 10,rev 1.1 to Chapter 11,rev 1.9 to Chapter 12 & Rev 1.1 to App F
ML20198P1601997-10-20020 October 1997
Rev 1.5 to Odcm,Chapter 12
ML20212A2941997-10-0202 October 1997
Rev 56 to Dresden Nuclear Power Plant for Insertion in NRC Security Plan.Rev Withheld
ML20216C6381997-08-29029 August 1997
Proposed Tech Specs,Incorporating New Siemens' Methodologies That Will Enhance Operational Flexibility & Reducing Likelihood of Future Plant Derates
ML20196G8781997-07-18018 July 1997
Proposed Tech Specs,Meeting Administrative Commitment Resulting from from Plant TS Improvement Program
ML20148K6141997-06-0505 June 1997
Proposed Tech Specs,Updating Revised TS to Format Consistent W/Recently Approved TS Upgrade for DNP & Proposed Other Miscellaneous Changes Re Decommissioning Status of Unit 1
ML20141A6411997-05-31031 May 1997
Rev 1.4,Chapter 12 to Radiological Effluent Technical Stds (RETS) of ODCM
ML20216H8691997-03-31031 March 1997
Revs to OCDM for LaSalle Station,Including Rev 1.8 to Chapter 10,rev 1.9 to Chapter 11,rev 1.8 to Chapter 12 & Rev 1.7 to App F
ML17187A7991997-02-17017 February 1997
Proposed Tech Specs 3/4.7.K & 3/4.8.C Re Issues Resulting from Comeds Efforts to Reconstitute Design Basis of Chrs
ML20137C0011997-01-31031 January 1997
Odcm,Dresden Annex Revs 1.9 to Chapter 10, Radioactive Effluent Treatment & Monitoring, 1.2 to Chapter 11, Radiological Environ Monitoring Program & 1.3 to Chapter 12, Radiological Effluent Technical Standards
ML20135B0581996-11-25025 November 1996
Proposed Tech Specs,Submitting Update to Administrative Controls Section of TS Which Reflects Transition of Overall Corporate Responsibility for Storage of Spent Nuclear Fuel
ML20129F3231996-10-23023 October 1996
Proposed Tech Specs Replacing All Existing Pages of Unit 1 TS
ML20129C2391996-10-16016 October 1996
Proposed Tech Specs for Dresden 2 & 3 & Quad Cities 1 & 2, marked-up to Show Transition Verbiage
ML20129D3981996-09-20020 September 1996
Proposed Tech Specs 3/4.6.K,updating Pressure-Temp Curves to 22 Effective Full Power Yrs & TS Bases
ML20216H8841996-06-30030 June 1996
Revs to ODCM for Quad Cities,Including Rev 1.8 to Chapters 10,11,12 & App F
ML20113B6001996-06-20020 June 1996
Proposed Tech Specs,Incorporating New NRC Approved Thermal Limit Licensing Methodology in List of Approved Methodologies Used in Establishing Thermal Limits in Cycle Specific COLR & Change to Fuel Assembly Design Features
ML20112E6341996-05-22022 May 1996
Proposed Tech Specs Requesting Emergency Amend to License DPR-25 Temporarily Modifying Description of Certain Corner Room Steel Supports to Match Current Configuration Until Mod During Next Refueling Outage
ML20086D4741995-06-30030 June 1995
Proposed Tech Specs Re TS Upgrade Program for Dresden Units 2 & 3 & Quad Cities Units 1 & 2
ML20092C8091995-05-12012 May 1995
Rev 2, Shroud Repairs Program for Dresden Units 2 & 3, Back-up Calculations for RPV Stress Rept Number 25A5691, May 1995
ML20087H8651995-05-0202 May 1995
Proposed Tech Specs Re TS Upgrade Program Section 3/4.10
ML20085M6171994-07-31031 July 1994
Rev 1.1 to Chapter 12, Radioactive Effluent Technical Stds of Dresden ODCM
ML20063F9011994-01-31031 January 1994
Rev 1.0 to Chapters 10,11,12 & App F to Odcm,Dresden Station Units 2 & 3
ML17179B0931993-09-10010 September 1993
Rev 2 to Dresden Station 3rd Interval IST Plan, Sections 2,13 & 14,pages 2-1,13-1 to 13-4 & 14-40,respectively
ML20058E8751993-09-0303 September 1993
Revised AOP-6.3, Loss of RHR Shutdown Cooling
ML20058E8351993-06-10010 June 1993
Revised AOP-7.4, Control Room Inaccessibility
ML20127D0691992-12-30030 December 1992
Corporate Emergency Response Organization Required Reading Package 92-11
ML20125D6381992-12-0808 December 1992
Proposed Tech Specs 3/4.1 Re Reactor Protection Sys
ML20058E8681992-09-29029 September 1992
Rev 56A to AOP 1BOA PRI-5, Control Room Inaccessibility Unit 1
ML20106A6221992-09-15015 September 1992
Proposed TS 2.0, Safety Limits & Limiting Safety Sys Settings & 3/4.11, Power Distribution Limits
ML20081M1251992-08-31031 August 1992
Rev 17 to Procedure Dgp 03-04 Control Rod Movements
ML20099D7791992-07-29029 July 1992
Proposed Tech Specs Sections 1.0, Definitions, 3/4.0, Applicability & 3/4.3, Reactivity
ML20096F1161992-04-24024 April 1992
Proposed Ts,Changing OL Section 2.G Re Reporting Requirements
ML20081M1851992-01-31031 January 1992
Rev 17 to Procedure DAP 07-02, Conduct of Shift Operations
ML20081M1611991-11-20020 November 1991
Rev 0 to Procedure DAP 14-4, Control Rod Sequences
ML20058E8761991-11-18018 November 1991
Rev 56 to AOP Bwoa PRI-10, Loss of Rh Cooling Unit 1
ML20081M0311991-11-15015 November 1991
Rev 2 to Procedure Doa 0300-12, Mispositioned Control Rod (W-2,W-3)
ML20081M1721991-08-31031 August 1991
Rev 15 to Procedure DAP 07-01, Operations Dept Organization
ML20081M1401991-05-17017 May 1991
Rev 6 to Procedure DOP 0400-02, Control Rod Minimizer
ML20081M1971990-08-30030 August 1990
Rev 9 to Procedure DAP 07-05, Operating Logs & Records
1999-04-30
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20211C3311999-04-30030 April 1999
Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood
ML20205A0871999-03-22022 March 1999
Revs to Odcm,Including Rev 2.0 to Chapter 10, Radioactive Effluent Treatment & Monitoring & Rev 1.9 to Chapter 12, Radiological Effluent Technical Stds (Rets)
ML20237A8651998-08-0707 August 1998
Qualified Unit 1 Supervisor Initial & Continuing Training Program
ML20151S2691998-07-31031 July 1998
Rev 1.8 to Chapter 12 of Dresden Station Odcm
ML20217N9331998-04-30030 April 1998
Rev 1.7 to Chapter 12 of Dresden Station Odcm
ML20216H4321997-12-31031 December 1997
Revs to OCDM for Braidwood,Including Rev 1.8 to Chapter 10, Rev 1.9 to Chapter 11,rev 2 to Chapter 12 & Rev 2 to App F
ML20216H8551997-12-31031 December 1997
Revs to OCDM for Dresden Station,Including Rev 1.9 to Chapter 10,rev 1.3 to Chapter 11,rev 1.6 to Chapter 12 & Rev 1.1 to App F
ML20198M2491997-12-18018 December 1997
Revs to Ocdm,Including Rev 1.3 to Chapter 11, Radiologicial Environ Monitoring Program & Rev 1.6 to Chapter 12, Radiological Effluent Technical Stds (Rets)
ML20216H9041997-10-31031 October 1997
Revs to OCDM for Zion Station,Including Rev 1.9 to Chapter 10,rev 1.1 to Chapter 11,rev 1.9 to Chapter 12 & Rev 1.1 to App F
ML20216H8241997-10-31031 October 1997
Revs to OCDM for Byron Station,Including Rev 1.3 to Chapter 10,rev 1.5 to Chapters 11 & 12 & Rev 1.3 to App F
ML20198P1601997-10-20020 October 1997
Rev 1.5 to Odcm,Chapter 12
ML20212A2941997-10-0202 October 1997
Rev 56 to Dresden Nuclear Power Plant for Insertion in NRC Security Plan.Rev Withheld
ML20141A6411997-05-31031 May 1997
Rev 1.4,Chapter 12 to Radiological Effluent Technical Stds (RETS) of ODCM
ML20216H8691997-03-31031 March 1997
Revs to OCDM for LaSalle Station,Including Rev 1.8 to Chapter 10,rev 1.9 to Chapter 11,rev 1.8 to Chapter 12 & Rev 1.7 to App F
ML20137C0011997-01-31031 January 1997
Odcm,Dresden Annex Revs 1.9 to Chapter 10, Radioactive Effluent Treatment & Monitoring, 1.2 to Chapter 11, Radiological Environ Monitoring Program & 1.3 to Chapter 12, Radiological Effluent Technical Standards
ML20216H8841996-06-30030 June 1996
Revs to ODCM for Quad Cities,Including Rev 1.8 to Chapters 10,11,12 & App F
ML20092C8091995-05-12012 May 1995
Rev 2, Shroud Repairs Program for Dresden Units 2 & 3, Back-up Calculations for RPV Stress Rept Number 25A5691, May 1995
ML20085M6171994-07-31031 July 1994
Rev 1.1 to Chapter 12, Radioactive Effluent Technical Stds of Dresden ODCM
ML20063F9011994-01-31031 January 1994
Rev 1.0 to Chapters 10,11,12 & App F to Odcm,Dresden Station Units 2 & 3
ML17179B0931993-09-10010 September 1993
Rev 2 to Dresden Station 3rd Interval IST Plan, Sections 2,13 & 14,pages 2-1,13-1 to 13-4 & 14-40,respectively
ML20058E8751993-09-0303 September 1993
Revised AOP-6.3, Loss of RHR Shutdown Cooling
ML20058E8351993-06-10010 June 1993
Revised AOP-7.4, Control Room Inaccessibility
ML20127D0691992-12-30030 December 1992
Corporate Emergency Response Organization Required Reading Package 92-11
ML20058E8681992-09-29029 September 1992
Rev 56A to AOP 1BOA PRI-5, Control Room Inaccessibility Unit 1
ML20081M1251992-08-31031 August 1992
Rev 17 to Procedure Dgp 03-04 Control Rod Movements
ML20081M1851992-01-31031 January 1992
Rev 17 to Procedure DAP 07-02, Conduct of Shift Operations
ML20081M1611991-11-20020 November 1991
Rev 0 to Procedure DAP 14-4, Control Rod Sequences
ML20058E8761991-11-18018 November 1991
Rev 56 to AOP Bwoa PRI-10, Loss of Rh Cooling Unit 1
ML20081M0311991-11-15015 November 1991
Rev 2 to Procedure Doa 0300-12, Mispositioned Control Rod (W-2,W-3)
ML20081M1721991-08-31031 August 1991
Rev 15 to Procedure DAP 07-01, Operations Dept Organization
ML20081M1401991-05-17017 May 1991
Rev 6 to Procedure DOP 0400-02, Control Rod Minimizer
ML20081M1971990-08-30030 August 1990
Rev 9 to Procedure DAP 07-05, Operating Logs & Records
ML20058E8601990-04-30030 April 1990
Rev 55 to AOP 1BOA PRI-10, Loss of Rh Cooling Unit 1
ML20055C3401990-02-13013 February 1990
Revised Dssp Procedures,Consisting of Rev 2 to Dssp 100-B, Rev 2 to Dssp 100-B1 & Rev 3 to Dssp 100-A2/B2
ML20245L7651989-08-0707 August 1989
Rev 0 to Offsite Dose Calculation Manual
ML20150C1171988-02-29029 February 1988
Rev 1 to Dresden Nuclear Power Station Process Control Program
ML20237J8081987-08-31031 August 1987
Rev 0 to Emergency Plan Implementing Procedure EPIP 200-T4, Containment Radiation Time Dependent Correction Factors
ML20235S3091987-07-31031 July 1987
Rev 0 to NSHP-RP Guidance 1100-2, Radiation Chemistry Foremen Shift Coverage
ML20205C8311986-04-30030 April 1986
Rev 11A to Offsite Dose Calculation Manual
ML20203L3551986-04-30030 April 1986
Rev 0 to Comm Ed Training Program Description for Station Control Room Engineer/Shift Technical Advisor
ML20099D0241984-09-30030 September 1984
Rev 7 to Dts 1600-7, Unit 2/3 Integrated Primary Containment Leak Rate Test
ML20090H7611984-03-31031 March 1984
Procedure INPO 84-010(NUTAC), Vendor Equipment Technical Info Program
ML20070J0071982-10-0101 October 1982
IE Bulletin 79-14 & Tap Piping Evaluation,Quad Cities Units 1 & 2 & Dresden Units 2 & 3, Revision 0
ML20070H9951982-09-30030 September 1982
EDS-NUTECH Interface Control Instructions, Revision 0
ML20199E3821982-07-0707 July 1982
Rev 0 to Emergency Plan Implementing Procedure EPIP 500-9, Operational Check of Notification Phone List
ML20062B4351982-07-0707 July 1982
Public Version of Revision 2 to Emergency Plan Implementing Procedure EPIP 100-C7, Security Director & Revision 0 to EPIP 500-9, Operational Check of Notification Phone List
ML20062B1761982-06-30030 June 1982
Public Version of Revision 2 to Emergency Plan Implementing Procedure EPIP 100-C8, Rad/Chem Director. Revised Index of Station Group Director Duties Encl
ML20054J8691982-06-0202 June 1982
Public Version of Revised Generating Station Emergency Plan Environ Director Emergency Plan Implementing Procedures, Including Revision 2 to Procedure ED-3 Re Demand Polling of Meteorological Data
ML20054H4291982-05-28028 May 1982
Public Version of Generating Stations Emergency Plan Telephone Directory
ML20054H1521982-05-28028 May 1982
Public Version of Generating Stations Emergency Plan Telephone Directory
1999-04-30
[Table view] |
Text
Jresden Station 3rd Interval
- nservice Testing Plan REVISION
SUMMARY
SHEET Section Description Page(s) Revision Date INFORMATION COMMON TO PUMPS AND VALVES 1 Table of Contents 1-1 1 07/93 2 Revision Summary Sheet 2-1 1 07/93 3 Introduction and Plan Description 3-1 to 3-11 1 07/93 4 List of IST P&ID's 4-l to 4-2 0 03/92 PUMPS Pump Listing by EPN:
5 ASME Class 1, 2, and 3 Pumps 5-1 to 5-8 1 07/93 6 Augmented IST Pumps 6-1 to 6-2 1 07/93 7 Relief Request Index/Summaries Sheet 7-1 1 07/93 8 Relief Requests 8-1 to 8-11 *
- 9 Technical Approach and Position 9-1 1 07/93 Index/Summaries 10 Technical Approach and Positions 10-1 to 10-2 *
- VALVES Valve Listing by EPN 11 ASME Class 1, 2, and 3 Valves 11-1 to 11-122 1 07/93 12 Augmented IST Valves 12-1 to 12-72 1 07/93 13 Relief Requests Index/Summaries 13-1 to 13-4 2 09/93 14 Relief Requests 14-1 to 14-48 *
- 15 Technical Approach and Position 15-1 1 07/93 Index/Summaries*
16 Technical Approach and Positions 16-1 to 16-12 *
- The current revlSlon/date for each md1v1dual Relief Req uest ' Technical A pproach &
Position and' Cold Shutdown Justification is listed on the Index/Summary Sheet for these sections.
9309220078 930910
~DR ADOCK 05000237 (2-1) Revision 2
a_Dresden Station 3rd Interval WJ,nservice Testing Plan VALVE RELIEF REQUEST INDEX/SUMMARIES (Page 1 of 4)
IRequest Relief I Page(s)
I Rev. I Date I Summary I
RV-OOA 14-1 0 03/92 Primary Containment Isolation Valves Local leak rate tests will be conducted in accordance with 10CFR50, Appendix J.
RV-OOB 14-2 0 03/92 Excess Flow Check Valves Exercise during reactor refueling outages
' in accordance with Technical Specification 4.7.D.l.b.
RV-OOC 14-3 1 07/93 FW and RWCU Check Valves Verified closed during reactor refueling outages.
RV-02A 14-4 to 14-5 1 07/93 Electromatic Relief Valves Exercise without timing at least once per operating cycle in accordance with the Technical Specification 4.5.D. l.b.
RV-02B 14-6 1 07/93 Deleted.
RV-02C 14-7 0 03/92 Feedwater Check Valves Exercise closed during reactor refueling outages.
RV-02D 14-8 to 14-9 1 07/93 MSIV Accumulator Check Valves Exercise closed each reactor refueling outage.
RV-02E 14-10 to 14-11 1 07/93 Main Steam Relief Valve Discharge Piping Vacuum Breakers Full stroke exercise without measuring the torque and visually inspect the internals during cold shutdowns.
(13-1) Revision 2
A Dresden Station 3rd Interval Wlnservice Testing Plan VALVE RELIEF REQUEST INDEX/SUMMARIES
\ (Page 2 of 4)
IRelief Request I Page(s)
I Rev. I Date I Summary I
RV-02F 14-12 0 03/92 Reactor Head Spray Check Valves Exercise and leak test during reactor refueling outages.
RV-03A 14-13 to 14-14 1 07/93 CRD Back11p Scram and Scram Dump Valves Exercise without timing and verify proper venting during cold shutdowns.
RV-03B 14-15 to 14-16 0 03/92 CRD Scram Inlet and Outlet Valves Individual scram insertion times and exercising will be performed in accordance with the Technical Specifications.
RV-03C 14-17 to 14-18 1 07/93 ARl/ATWS Valves Exercise without timing and verify proper operation during cold shutdowns.
RV-llA 14-19 to 14-20 0 03/92 SBLC Injection Check Valves Exercise open with the injection test and closed with local leak rate testing during reactor refueling outages.
RV-13A 14-21 1 07/93 Isolation Condenser Make Up Valves Disassemble and inspect in accordance with the sampling technique.
RV-14A 14-22 to 14-23 0 03/92 Core Spray Minimum Flow Check Valves Disassemble and inspect in accordance with the sampling technique.
RV-14B 14-24 1 07/93 Core Spray Keep Ftll Check Valves Test as a series combination with both being repaired or replaced as necessary.
(13-2) Revision 2
aDresden Station 3rd Interval Wlnservice Testing Plan VALVE RELIEF REQUEST INDEX/SUMMARIES (Page 3 of 4)
IRelief Request I Page(s)
I Rev. I Date I Summary I
RV-15A 14-25 to 14-26 0 03/92 LPCI Minimum flow Check Valves Disassemble and inspect in accordance with the sampling technique.
RV-15B 14-27 1 07/93 LPCI Keep Fill Check Valves Test as a series combination with both being repaired or replaced as necessary.
RV-23A 14-28 to 14-29 1 07/93 HPCI Pump Torus Suction Valves Partial Stroke exercise each quarter and disassemble and inspect in accordance with the sampling technique.
RV-23B 14-30 to 14-31 0 03/92 HPCI Injection Check Valve Full stroke exercise open and closed during reactor refueling outages and measure the torque required to full stroke exercise open during cold shutdowns.
RV-23C 14-32 1 07/9J HPCI Keep Fill Check Valves Test as a series combination with both being repaired or replaced as necessary.
RV-230 14-33 to 14-34 1 07/93 HPCI Turbine Exhaust Vacuum Breakers Func~onally test open and closed each refueling outage as an assembly.
(13-3) Revision 2
A Dresden Station 3rd Interval Wlnservice Testing Plan VALVE RELIEF REQUEST INDEX/SUMMARIES (Page 4 of 4)
Relief Request Page(s) Rev. Date Summary RV-23E 14-35 to 14-36 1 07/93 HPCI Turbine Exhaust Check Valves Leak test during reactor refueling outages.
RV-23F 14-37 0 03/92 HPCI Minimum Flow Check Valves Disassemble and inspect according to the sampling techniques.
RV-23G 14-38 to 14-39 0 03/92 HPCI Gland Seal Condenser Check Valves Disassemble and inspect according to the sampling technique.
RV-23H 14-40 2 09/93 HPCI D~in Pot Solenoid Exercise valve quarterly without timing.
RV-24A 14-41 1 07/93 CAM System Isolation Valves Exercise closed during reactor refueling outages.
RV-25A 14-42 to 14-43 1 07/93 ACAD Containment Isolation Valves Exercise during reactor refueling outages .
RV-47A 14-44 0 03/92 TIP Nitrogen Purge Valves Exercise closed during reactor refueling outages.
RV-52A 14-45 0 07/93 Unit .3 Diesel Fuel Oil Transfer Solenoid Valve Stroke without timing.
RV-57A 14-46 1 07/93 C.R. HV AC Cooling Water Flow Control Valve Fail Safe test and monitor stem travel for degradation without timing.
RV-66A 14-47 0 03/92 Diesel Air Start Solenoid Verify operable during monthly Diesel Runs.
(13-4) Revision 2
Jresden Station 3rd Interval 911service Testing Plan RELIEF REQUEST NUMBER RV-23H (Page 1 of 1)
DESCRIPTION Relief is requested from stroke timing the High Pressure Coolant Injection (HPCI) drain pot solenoid valves.
COMPONENT IDENTIFICATION/FUNCTION P&ID/
VALVE SIZE CAT CLASS CORD FUNCTION 2-2301-32* 1" B 2 51/C7 HPCI Drain Pot Solenoid 3-2301-32 l" B 2 374/C7 HPCI Drain Pot Solenoid CODE REOUIREMENT(Sl IWV-3410 Valve exercising Test: Category A and B valves shall be exercised at least once every three months.
BASIS FOR RELIEF These solenoid valves are totally enclosed with no evidence of position indication available.
Therefore, no direct method of timing these valves exists.
These valves can be opened by a handswitch, and also periodically operate automatically during HPCI Surveillance tests. Although monitoring for degradation is not practicable, the valves can be determined to have stroked by functional testing.
ALTERNATE TEST Since there are no indicating lights or other evidence of position indication, these valves will be stroked quarterly without timing. On a refuel outage basis, the HPCI Drain Pot will be filled until the limits are reached and then observed to verify that the 2(3)-2301-32 valves adequately open to drain the water. In addition, as part of a preventive maintenance program, these valve assemblies will be replaced every third refuel outage.
(14-40) Revision 2
