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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
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ML17325B6061999-05-21021 May 1999 Proposed Tech Specs Revising Limitations on Positive Reactivity Additions ML17325B5891999-05-0707 May 1999 Rev 5 to PMP 7200.RST.004, Expanded Sys Readiness Review Program. ML17325B5901999-05-0707 May 1999 Rev 1 to PMP 7200.RST.006, Expanded Sys Readiness Review Program for Level 2 Sys. ML17325B5551999-04-19019 April 1999 Proposed Tech Specs 3/4.8.1.2, Electrical Power Systems & Associated Bases,Providing one-time Extension of 18-month Surveillance Interval for Specific SRs ML17325B4671999-03-0303 March 1999 Rev 5 to Cook Nuclear Plant Restart Plan. 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[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML17325B5901999-05-0707 May 1999 Rev 1 to PMP 7200.RST.006, Expanded Sys Readiness Review Program for Level 2 Sys. ML17325B5891999-05-0707 May 1999 Rev 5 to PMP 7200.RST.004, Expanded Sys Readiness Review Program. ML17325B4671999-03-0303 March 1999 Rev 5 to Cook Nuclear Plant Restart Plan. ML17335A4071998-11-0202 November 1998 Rev 4 to Cook Nuclear Plant Restart Plan. ML17325B4431998-11-0202 November 1998 Rev 4 to Cook Nuclear Plant Restart Plan. with 981216 Ltr ML17335A2301998-09-12012 September 1998 Rev 3 to Cook Nuclear Plant Restart Plan. ML17335A2721998-09-0404 September 1998 Rev 0 to PL-CNSI-98-007, Transportation & Emergency Response Plan for DC Cook Unit 2 SG Project. ML17335A2751998-09-0202 September 1998 Rev 1 to ER-98-012, Evaluation of Dose Rate from U-Tube End of DC Cook SG Lower Assembly. ML17335A2731998-08-21021 August 1998 Rev 0 to ST-307, Structural Evaluation of DC Cook Unit 2 Sgla Package. 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ML17332A2491994-08-0303 August 1994 Rev 7 to Plant Manager Procedure (PMP) 12 PMP 6010 OSD.001, Odcm. ML20063K0631994-02-11011 February 1994 Change Sheet 1 to Rev 5 to Plant Manager Procedure (PMP) 12 PMP 6010 RPP.304, Use of HEPA Vacuum Cleaners. W/ Updated Index,Page 14 ML17331B0441993-11-0909 November 1993 Rev 15 to Emergency Response Manual. W/931109 Ltr ML17334B4851993-08-0909 August 1993 Rev 14 to Emergency Response Manual. W/930809 Ltr ML17334B4821993-04-0202 April 1993 Rev 3 of Pump Inservice Test Program. ML17329A5431992-06-11011 June 1992 Change Sheet 7 to Rev 6 to Procedure PMP 2080 EPP.107, Notification of Plant Personnel. ML20077S7281991-03-14014 March 1991 Rev 3 to PMP 6010.OSD.001, Odcm ML17325B3791990-03-0101 March 1990 Change Sheet 1 to Rev 3 to Procedure PMP 2080 EPP.106, Initial Offsite Notification. ML17334B3551990-02-0505 February 1990 Rev 2 to DC Cook Nuclear Plant Units 1 & 2 Inservice Testing Pump Program. ML17334B3561990-02-0505 February 1990 Rev 3 to DC Cook Nuclear Plant Unit 2 Inservice Testing Valve Program. ML17334B3571990-02-0505 February 1990 Rev 3 to DC Cook Nuclear Plant Unit 1 Inservice Testing Valve Program. ML20246M2191989-03-21021 March 1989 Procedure MS-3.2.1.9-1B, Maint & Surveillance Ite Medium Voltage Switchgear Equipment ML17325B0511988-12-0909 December 1988 Interim Acceptance Criteria for Safety-Related Piping Sys. ML17334B1491987-10-0505 October 1987 Rev 2 to DC Cook Nuclear Plant Unit 1 Inservice Testing Valve Program. ML17334B1501987-10-0505 October 1987 Rev 2 to DC Cook Nuclear Plant Unit 2 Inservice Testing Valve Program. ML20212A3191986-10-0202 October 1986 Rev 1 to Procedure 12 PMP 4021 TRP.001, Reactor Trip Review ML17324A9301986-05-29029 May 1986 Rev 0 to Procedure 1MHP2140.082.001, Maint Procedure for Repowering RHR Pump. ML17324A9321986-05-29029 May 1986 Rev 0 to Procedure 1MHP2140.082.003, Maint Procedure for Repowering Pressurizer Backup Heaters. ML17324A9331986-05-29029 May 1986 Rev 0 to Procedure 1MHP2140.082.005, Maint Procedure for Repowering Containment Valves. ML17324A9341986-05-29029 May 1986 Rev 0 to Procedure 1 Thp 6030 IMP.304, Pressurizer PORV Cable Repair. ML17324A9351986-05-29029 May 1986 Rev 0 to Procedure 1 Thp 6030 IMP.305, App R Post-Fire Repowering of In-Containment Valves. ML17334A9711986-05-22022 May 1986 Rev 0 to Procedure 12-OHP 4023.100.001, Unit 1 Emergency Remote Shutdown. ML20213F6011986-05-15015 May 1986 Rev 1 to Procedure PMP 6010.OSD.001, Offsite Dose Calculation Manual ML17324A9001986-05-0101 May 1986 Rev 1 to Procedures Generation Package,Part Iv,Training for Donald C Cook Nuclear Plant Emergency Operating Procedures. ML17324A8991986-05-0101 May 1986 Rev 1 to Procedures Generation Package,Part Ii,Writers Guide for Donald C Cook Nuclear Plant Emergency Operating Procedures. ML17324A8971986-05-0101 May 1986 Rev 1 to Procedures Generation Package,Part I,Specific Technical Guidelines for Donald C Cook Nuclear Plant. ML18005A0161986-05-0101 May 1986 Rev 1 to Procedures Generation Package,Part III, Verification/Validation for Donald C Cook Nuclear Plant Emergency Operating Procedures. ML20195C5361986-03-15015 March 1986 Public Version of Emergency Response Manual for DC Cook Nuclear Plant ML20141D7121986-02-28028 February 1986 Rev 0 to Master Insp Plan ML20137J6061985-12-17017 December 1985 Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 2 to Erp 2.07, Outside Agency Liaison, Rev 1 to Erp 2.08, Initial Assessment Group Runner & Rev 2 to Erp 5.01.W/860117 Release Memo ML17334A9441985-11-0505 November 1985 Change Sheet 1 of Rev 9 to Spec DCCFP101QCN, Matl & Application Spec - Initial & Repair Installations, Revising App D Silicon Foam Scope of Work to Identify New Fire Barriers & for Cross Referencing Fire Zones ML17334A9191985-10-15015 October 1985 Implementation Plan of Reg Guide 1.97,Rev 3 for Donald C Cook Nuclear Plant Units 1 & 2, Status Rept 1999-05-07
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ATTACHMENT 5 FORM 5411 INDIANA 8 NIICHIGAN EIECMIG CDNP4NY DONALD C. COOK NUCLEAR PLANT PROCEDURE COVER SHEET pggg~iire No. 2-OHP 4021. 002. 00 Hevhion No. 2 DRAINING REACTOR COOLANT SYSTEM SCOPE OF REVIS1ON Revision 1 - Revised and rewritten to standardize format. Addressed Change Sheets 1 through 6.
Revision 2 - Minor revisions due to shift review . Delet d Data Signoff Sheet 5.2 Addressed Procedure Change Sheets 1 and 2.
SIGNATURES REVISION NUMBER ORIGINAL Rev. 1 Rev. 2 PREPARED BY J. Osborne R. Bl th p/ / // A DEPARTMENT HEAD APPROVAL B. Sversson K. Baker INTERFACING DEPARTMENT HEAD CONCURRENCE QUALITY ASSURANCE SUPERVISOR APPROVAL R. Keith J. Stietzel PLANT NUCLEAR SAFETY COMMITTEE D. Shaller D. Palme.
PLANT MANAGER APPROVAL R. Jurgensen W. Smith, Jr..i'~',.-,-
APPROVAL DATE 06-07-77 02-18-82 EFFECTIVE DATE 6.-0 -77 02-18-82
'I'-Z4 8405220202 8405i7 PDR ADQCK 050003i6 P . PDR
sa 2-OHP 4021.002.005 LZST OF EFFECTZVE PAGES PAGE NUMBER REVZSZON NUMBER AND DATE Page 1 of 6 Revision 2, 03-09-84 Page 2 of 6 Revision 2, 03-09-84 Page 3 of 6 Revision 2, 03-09-84 Page 4 of 6 Revision 2, 03-09-84 Page 5 of 6 Revision 2, 03-09-84 Page 6 of 6 Revision 2, 03-09-84 DATA/SZGNOFF SHEET 5.1 Page 1 of 2 Revision 2, 03-09-84 Page 2 o 2 Revision 2, 03-09-84
?age 1 of 1 Rev. 2
2-OHP 4021.002 '05 INDIANA 6 MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT DRAINING REACTOR COOLANT SYSTEM 1.0 OBJECTIVE 1.1 To lower the reactor coolant level in the Reactor Coolant System prior to removing the reactor vessel head or performing maintenance work requiring a reduced water level.
2.0 REFERENCES
2.1 Technical Specifications, Appendix A, Section 3.9.1.
2.2 AEP Flow Diagrams:
2.2.1 2-OP-5128-4, Reactor Coolant System.
2.2.2 2-OP-5128A-10, Reactor Coolant System.
2.2.3 2-OP-5'29-3, CVCS Reactor Letdown and Charging.
2.2.4 12-OP-5137A-5, WDS Vents and Drains.
- 2. 2. 5 2-OP-5143-3, Emergency Core Cooling.
2.3 Plant Operating Procedure, 2-OHP 4021.017.002, Placing in Service and Operation of Residual Heat Removal Loop.
3.0 INITIAL CONDITIONS ? ERFORi~iED BY 3.1 If reactor vessel Keff less than or head is to be unbolted, verify equal to 0.95 and Tavg less than or equal to 140'F. Zf in cold snutdown, verify Keff less than 0.99 and Tavg less than or equal to 200'F.
3 ~ 2 The Residual Heat Removal System is in operation, maintaining reactor coolant system temperature.
3.3 The reactor coolant drain tank and a minimum of one o the drain tank pumps is operable. The discharge of the reactor coolant drain tank pump is 1'ned up to selected CVCS HUT tanks through CS-460.
Page 1 of 6 Rev. 2
P ERFORMED BY 3 ' There is sufficient capacity in the CVCS holdup tanks to receive coolant released from the Reactor Coolant System when the pressurizer and the reactor vessel head are drained.
3.5 The pressurizer backup and variable heater breakers must be tagged open.
3.6 The pressurizer is open to the pressurizer relief tank through a power operated relief valve.
3.7 A nitrogen blanket of 5 psig is being maintained in the pressurizer from the pressurizer relief tank through the relief valve discharge line.
3.8 A temporary tygon hose is connected to valve 2-RC-116-L3 for level indication. The tygon hose is looped so the top of the loop is at least ten (10) feet above the intended level indication desired and attached to manual vent 2-WD-238 on the pressur'zer rel'ef tanks The blank lange on the PRT vent (2-WD-238) requires being replaced by a flange with a piping tee on 't with temporary valves on the two (2) free ends. One end is to connect to the level tygon hose. The other is to be connected to a tygon hose that is routed to the instrument room purge exhaust suction valve.
Ensure there are no loop seals or kinks in the tygon hose to be used or level indication.
3.9 Pressurizer level is in the indicating range or filled solid.
3.10 The reactor head vent is connected to the pressurizer relief tank via installed vent spool piece.
3.11 Shut and tag shut primary water to boric acid blender 12-PW-263. ~Terify CLOSED and hang a clearance on primary water to chemical mix'g tank 2-PW-256 and primary water flush to emergencv boration line 2-PW-265. This helps to avoid an inadvertent dilution while at half loop.
3.12 If a tygon the closed hose is to be used circuit television for level indication, monitor mus be connected and funtioning properly.
Page 2 of 6 Rev. 2
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2-OHP 4021.002.005 4.0 PRECAUTIONS 4.1 The applicable Radiation Protection procedures for handling radioactive liquids and for venting vapors and gasses must be observed.
4.2 The water level in the reactor vessel must be below the vessel flange before the head is unbolted for removal.
The reactor flange elevation is 621 feet, 14 inches.
The elevation of 4 loop is 614 feet, 0 inches. For RCP seal work and/or steam generator manway removal, the level must be brought to the center line of the hot and cold legs. This is commonly referred to as half loop. The level should be at half loop for a peri-od of eight hours after the PRT and tygon level instru-mentation is vented to atmosphere before allowing man-ways to be removed.
4.3 The pressurizer relief tank level must be reduced to less than 5% to allow nitrogen flow to the pressurizer through the open power operated relief valve.
4.4 Maintain reactor coolant system temperature greater than 60'F to ensure the reactor head temperature remains greater than 60'F until tension is relieved from the reactor head studs per Westinghouse refueling procedure.
4.5 Do not drain Reactor Coolant System below center line of the loops (614'") when nuclear fuel is in the vessel or while on RHR.
4.6 Anytime draining of the RCS is in progress, careful observation of the RHR System is recuired. The pump amperage is the firs" indication o cavitation or loss of suction.
5.0 DATA/SIGNOFF SHEETS 5.1 Data/Signof Sheet 5.1, Draining Reactor Coolan Valve Lineup.
6.0 INSTRUCTIONS PERFORMED BY 6.1 Complete the attached Data/Signoff Sheet 5.1, Draining Peactor Coolant Valve Lineup.
6.2 Start low p essure letdown from the Reactor Coolant System via the Residual Heat Removal System following 2-OHP 4021.017.002, Placing In Service and Operation of Residual Heat Removal Loop.
Page 3 of 6 Rev. 2
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2-OHP 4021.002.005 P ERZORMED BY 6.3 Monitor pressurizer relief tank pressure while draining the system. Maintain a positive nitrogen pressure not to exceed 5 psig.
6.4 Close reactor coolant drain tank vents to vent header 2-DCR-201 and 2-DCR-203. This is to prevent getting water into vent header when draining Reactor Coolant System.
6.5 Open loop drain isolation valves 2-RC-113-L1, 2-RC-113-L2, 2-RC-113-L3, and 2-RC-113-L4.
6.6 Loop drains flushing These steps are to be done in sequence so the loop drains are flushed clean of crud. Open the drain valves wide to allow full flow to the reactor coolant drain tank. Valve off if necessary to control reactor coolant drain tank level and then reopen to obtain the required flushing time.
6.. 6 . 1 , Open 2-RC-114-L'nd allow full flow for a minimum of two (2) minutes.
6.6.2 Open 2-RC-114-L4 and allow full flow for a minimum of three (3) minutes.
6.6.3 Open 2-RC-1'4-L2 and allow full flow for' minimum of two (2) minutes.
6.6.4 Open 2-RC-114-L3 and allow full flow for a minimum of three (3) minutes.
6.7 After completion of ste'p 6.6, the our (4) loop drains should be used as system drains. These drains and the low pressure letdown of step 6.2 o this procedure can be used in any combination to control the drainage from the system.
NCTE When using loop drains, station an operator at the Waste Disposal System panel to observe reactor coolant dra'n tank level so that drainage can be controlled to prevent flooding the reactor coolant drain tank.
Page 4 of 6 Rev. 2
2-OHP 4021.002.005 PERFORMED BY 6.8 When pressurizer level is reduced to 5% indicated, open the reactor head vent valves 2-RC-132 and 2-RC-133. Reactor coolant will now flow through the connected sightglass to the pressurizer relief tank. Monitor this tank level while draining this way and maintain the level less than 5%.
6.9 When reactor coolant stops 'flowing through the flow indicator connected to the head vent valve, close all drains.
6.10 Place temporary refueling water. level indicator in service (tygon hose) by opening valves 2-RC-113-L3, 2-RC-116-L3, 1-WD-238, and temporary valve on tygon hose. Refer to Precaution 4.3.
6.11 Continue draining the Reactor Coolant System by either or both methods of step 6.7 of this procedure. Do not use the loo 3 drain for this because it will cause a false level indication.
6.12 As the indicated level approaches half loop, slow down the drainage and stop is reached.
it when the level 6.13 While maintaining level at half loop perform the following steps:
6.13.1 Close tne temporary valve on the at the PRT vent. leve'ygon 6.13.2 Remove N supply from PRT by closing 1-GCR-30$ .
6.13.3 Slowly vent PRT to instrument room purge exhaust by cracking or throttling temporary valve.
6.13.4 When PRT is fully vented, slowly throttle open temporary valve on the tygon level hose.
6.14 Close RC-116-L3.
6.15 Close temporary valve on tygon level hose at PRT.
Then disconnect the tygon. hose from the valve and have it run up alongside I3 RCP to a height greater than the reactor flange (greater than 622'levation).
Page 5 of 6 Rev. 2
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2MHP 4021.002.005 PERFORMED BY 6.16 While monitoring the level, slowly open RC-116-L3.
(Ensure it is not allowed to overflow.)
6.17 Reestablish level at half loop or where desired for work to be performed.
6.18 Maintain level at half loop for eight hours pre-ferred (a minimum of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) .
6.19 Declare RCS at half loop.
PROCEDURE VERIFIED COMPLETE BY DATE REVIEWED BY DATE SRO 7.0 FINAL CONDITIONS.
7.1 Reactor coolant level is at the desired level re-quired for system maintenance. This level can be anywhere down to the center line of the loops.
Page 6 of 6 Rev. 2
2-OHP 4021.002.005 DATA/SIGNOFF SHEET 5.1 LATEST EEV. CHECKED DPPZNINQ PEACTOR COOLANT VALVE LINEUP VALVE P ERFORMED VALVE NUMBER DESCRIPTION POSITION BY 2-NRV-163 Pressurizer Spray Loop 3 CL 2-NRV-164 Pressurizer Spray Loop 4 CL 2-GCR-301 N2 to Pressurizer Pelief Tank OP 2-RRV-103 Pressuri er Fe'ief Tank Vent CL 2-RC-118 Reactor Vessel Flange Leakoff (Outer) CL 2-RC llo Reactor Vessel Flange Leakoff (Inner) CL 2-DRV-100 Reacto" Vessel Flange Leakoff Isolation 2-RC-113 Ll Reactor Coolant Loop 1 Dra'n Valve CL 2-RC-113 L2 Reacto" Coo'ant Loop 2 Drain Valve CL 2-RC-3 13 L3 Reactor Coo'ant Loop 3 Drain Valve 2-RC-113 L4 Reactor Coclant Loop 4 Drain Valve CL 2-RC-114 Ll Reactcr Coolart Lccp Drain Isolatior. Valve C 2-RC-4 L2 Reactor Coolant Lcop 2 Drain Isolation Valve CL 2-RC-114 L3 Reactor Cco'ant Loop 3 Drain Isolaticn Va'e CL 2-RC-114 L4 Reactor Ccolant Loop 4 Drain Zsolat'on Valve CL OP Open Page 1 of 2 CL Closed Rev ~ 2
2-OHP 4021.002.005 DATA/SIGNOFF SHEET 5.1 DPAINING REACTOR COOLANT VALVE LINEUP VALVE PERFORMED VALVE NUMBER DESCRIPTION POSITION BY 2-RC-116 L3 Refueling Water Level
'ndicator solation CL 2-NRV-15 3 P.O. Relief to Pressurizer Relief Tank OP 2-NRV-152 P.O. Pelief to Pressurizer Relief Tank OP 2-N RV-1 5 1 P.O. Pelief to Pressurizer Relief Tank OP 2-RC-121 R.V. Head Vent to Pressurizer Relief Tank OP 2-RC-137 R.V. Head Vent to Pressurizer Relief Tank OP 2-RC-138 R.V. Vent to R.V. Level Instrumentation CP 2-RC-132 Sightglass Inlet Isolation CL 2-RC-133 Sightglass Out'et Isolat'on Temporary valve "or PRT Vent to Instrument Room Purge Evhaust CL DATA/SIGNOFF SHEET VERIFIED COMPLETE BY DATE REVIEWED BY DATE SRO
- of
- Open OP Page 2 CL Closed Rev. 2
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