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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17335A5581999-10-12012 October 1999 Proposed Tech Specs Surveilllance Requirement 4.6.2.2.d for Spray Additive Sys to Relocate Details Associated with Acceptance Criteria & Test Parameters to Associated TS Bases ML17335A5611999-10-11011 October 1999 Proposed Tech Specs Pages,Correcting TS Pages Inadvertently Submitted in 990923 Submittal ML17335A5431999-10-0101 October 1999 Proposed Tech Specs Re Containment Recirculation Sump Water Inventory ML17326A1591999-09-23023 September 1999 Proposed Tech Specs Re Movement of SG Sections in Auxiliary Bldg for SG Replacement Project ML17326A1461999-09-17017 September 1999 Proposed Tech Specs Pages for Credit of Rod Cluster Control Assemblies for Cold Leg LBLOCA Subcriticality ML17326A1181999-09-10010 September 1999 Proposed Tech Specs Pages,Revising TS Surveillance Requirement 4.4.7,TS Tables 4.4-3,3.4-1 & TS Surveillance Requirement 4.11.2.2 Re RCS & Gas Storage Tank Sampling ML17326A0941999-08-17017 August 1999 Proposed Tech Specs,Removing voltage-based Repair Criteria, F* Repair Criteria & Sleeving Methodologies from Unit 1 TS & Clarifying Bases Section ML17326A1471999-05-28028 May 1999 Non-proprietary Version of Control Rod Insertion Following Cold Leg LBLOCA at DC Cook,Units 1 & 2. 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. ML17335A3581998-12-0303 December 1998 Proposed Tech Specs 4.6.5.1, Ice Condenser,Ice Bed & Associated Bases,Reflecting Max Ice Condenser Flow Channel Blockage Assumed in Accident Analyses ML17335A3681998-12-0303 December 1998 Proposed Tech Specs,Adding New TS Re Distributed Ignition Sys ML17335A3651998-12-0303 December 1998 Proposed Tech Specs 3/4.7.7, Sealed Source Contamination & Associated Bases Addressing Revised Testing Requirements for Fission Detectors ML17335A3621998-12-0303 December 1998 Proposed Tech Specs Removing Obsolete Info to Provide Consistency Between Units 1 & 2 to Provide Consistency with Std Tech Specs,To Provide Clarification & to Correct Typos ML17325B4431998-11-0202 November 1998 Rev 4 to Cook Nuclear Plant Restart Plan. with 981216 Ltr ML17335A4071998-11-0202 November 1998 Rev 4 to Cook Nuclear Plant Restart Plan. ML17335A2781998-10-0808 October 1998 Proposed Tech Specs Sections 3.3.3.8 & 3.3.3.6,placing Tighter Restrictions on Amount of Time RWST Water Level Instrumentation Can Be Out of Svc Before Compensatory Actions Are Required ML17335A2691998-10-0808 October 1998 Proposed Tech Specs 3.4.1.3 Re Reactor Coolant Loop Requirements in Modes 4 & 5 ML17335A2651998-10-0808 October 1998 Proposed Tech Specs Changing Containment Sys TS Bases 3/4.6.1.4, Internal Pressure & 3/4.6.1.5, Air Temp. ML17335A2341998-09-14014 September 1998 Proposed Tech Specs Page 3/4 5-6,revising Runout Limits for SI Pump to 675 Gpm Unless Pump Is Specifically Tested to Higher Flow Rate Not Exceeding 700 Gpm 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. 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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
[Table view] |
Text
-PRESSURIZER VENTING OPERATION AEP/AMP REYISION 0 MARCH 1981 8107210420 810715 PDR ADOCK 05000315 F'DR
~1 PRESSURIZER VENTING OPERATION A.PURPOSE The objective of this instruction is to specify the required operator actions and precautions necessary to vent non-condensible gases from the pressurizer vapor space.This instruction may also be used as an alternate method of depressurizing
'the reactor coolant system which may be required by the actions of another operating instruction.
B.INITIAL CONDITIONS CAUTION: The pressurizer vent should rot'be used as the primary means of depressurizing the RC$during an inadequate core cooling event.Refer to Inadequate Core Cooling Guidelines-for appropriate operator actions and precautions.
NOTE: This guideline assumes that the reactor containment conditions are near normal"nd: an accurate pr essurizer pressure and level indication
<is available.
CAUTION: Do not open the pressurizer vent while the safety injection system is in operation unless an RCS depressurization is required by an Emergency Operating Instruction.
1.Sampling has indicated the presence of a significant quantity of non-condensible gases in the pressurizer vapor space.2.Abnormal'onditions have been experienced with the pressurizer level and pressure control systems 3.Pressurizer spray is-ineffective in reducing the pressurizer pressure.March, 1981 Revision 0 Page 1 4.Plant events have occurred (such as inadvertent gas addition, accumulator tank discharge, core uncovery, etc.)that may result in non-condensible gases being collected in the pressurizer.
5.An RCS depressurization is required.by another operating instruction and pressurizer spray is~not available and/or the use of the power operated relief~valves is not desirable.
6.The reactor vessel head has been vented, if required, prior to venting the pressurizer
., C.IMMEDIATE ACTIONS None KttE'P i NOTE: If the pressurizer is being vented because large quantities of non-condensible gases are preventing a depressurization, then the actions of steps marked by an asterisk are not applicable.
1.Terminate any changes to the reactor coolant system that may be in progress and bring the RCS to as-close to a steady-state condition.
as possible.*2.If not already performed, sample the pressurizer vapor space for the presence of non-condensible gases.If a signficant quantity of non-condensible gases is not found, then return to the appropriate operating instruction.
March, 1981 Revision 0 Page 2
!.'1 l~g~3.In preparation for venting;isolate the containment purge and exhaust systems and the pressure vacuum relief line and start all available containment air circu lation equipment 4.Increase the RCS sub-cooling to (insert plant specific value wnich is 50'F above the value which is the sum of the errors for the temperature measurement system used, and for the pressure measurement system translated into temperature using the sat-uration tables)by either initiating an RCS pressurization or by dumping steam from the non-faulted steam generators.
NOTE: If the pressurizer is being vented for the purpose of initiating RHR operation and the RCS temperature is less than 350'F, then additional sub-cooling margin is not required.5.Perform the actions of Appendix A to determine the maximum allowable time period or venting.6.If no+already performed, manually block the low pressure SI-initiation if the permissive is energized.
CAUTION:-The venting operation may result in pressure decreasing below the SI setpoint.Action should be taken to manually block the automatic SI signal when the permissive is energized.
- 7.Increase charging flow to maximum to limit the depressurization rate during the venting period.Pressurizer level will trend upward during the venting operation.
March, 1981 Revision 0 Page 3 0 I E 8.Open the vent isolation valves in one pressurizer vent flowpath.NOTE'f one or both valves fail to open, close both valves and open the isolation valves in the parallel flow path.9.Close both vent isolation valves when: a)The time period determined in Step 5 is met, OR*b)Pressurizer pressure decreases by 200 psi, OR c)Pressurizer level increases above 80 of span, OR d)Reactor coolant sub-cooling deer ases below (insert plant specific valve which is the sum of the errors for the temperature measurement system used, and for the pressure measurement system translated into temperature using the'aturation tables).I 10.Re-establish normal charging flow and restore the pressurizer water level to the normal operating range.ll.If the venting was terminated prior to removing enough of the non-condensible gases to restore normal pressurizer control or to reduce pressure to the required condition, then return to Step 4.NOTE: If multiple venting operations are required and the containment hydrogen concentration is equal to or greater than 3 volume percent, the provisions must be made to March, 1981 Revision 0 Page 4 5 BESSURIZ ER F l&IJRE 2 I'ate J a/a%i DONALD C.COO<NUCLEAR rLANT uNIT NOS.1 AND.Z
"'A,HaTL r CCN7I't SKI a C t1~---0 Ig I'V v+-e)ILL EI.O~I': flILl.nt'L'I4~-~OLf.;.:)I'b UEN7;RIAL;a='ThMC.L FLIa.-n~g MQT a-"t~<<l>CIIf.~EMIR UrdIT TflAIIJ-arl 6, TIEAI~!2 E./a E.!)B'VRA,I<SRN E Fdg Sort[REACTOR.RNO PRCS~uR I?.Eg VENTS'L'ar Is(7OPa XILgl'llUab Ut.N'V LIN>>T I=.i~a Y"~fl Y>>'5 a'.anal Qt f.5t.h 0 F.a"L c.Iat>I 0 Vni Va=I I I I I I I ll'l ALACK 0I417 8 t'a'6.5 o Ti l 5 L'ii Ht.Rag aaI!.:1~Ll".'aa=a TLatb)~'.IQQ'i I:.Dovsa-'~liaa.Ate SOLE, HO I Ea VALV F I I I I I I I I I.I I,)I Hl ALAIIVI U/ah l T r\~tlgfaa>X)EN~t'LaM a C<SL.t'.l I.ltF.'3t'I VKhhY'lMF.
)l G'Q bw>RO~Puu.Iatg.IiCAg fOR HEAb VGrUT t tao Pf'ESSUR'ZER HEAD VCILT LOGIC-QIACRAYl F a c,.s Dca4 J Q//$0/s'/
<<~I 0 0 VALVE NUMBER SHT.NO.FUNCTION FLOYI I}I A G SVSTEIn 924i9A 92498 92490 9249D 9249E 9249P 9250A 9250B 92500 9250D 9250E 9250" 9236 9239A 9239B 9244 330 331 332 333 334 335 336 337 33B 339 340 341 342 343 344 DRV}NING CONTROL SYSTEM DRUM}IING CONTROL SYSTEH DRfRf}IING CO}<<TROL SYSTEM DRU}OIING CONTROI SYSTFH DRU}f}GNG CONTROI.SYSTEM DRV}OfING CONTROL SYSTFH DRLYfMIC CONTROL SYSTAf DRIDQ}ING COhTROL SYST}2f DRIBQflttG CONTROL SYSTEM DR}BOflt}C CONTROL SYSTEM DRUHHINC CONTROL SYSTEH DRUMMING CONTROL SYSTEH DRIPHIhG CONTROL SYSTEM DRU}0}ttiC CONTROL SYSTKH DRU}QII}tC CONTROL SYSTEM 110E197 Sh.2 110E197 Sh.2 110E197 Sh.2 IIOLI97>>.2 110E 197 S}1.2 110E197 S}I.2 110E197 Sh.2 110E197 Sh.2 110E197 Sh.2 110E197 Sh.2 I IOEI97 Sh.2 110E197 Sh.2 110E197 S}L.2 110E197 Sh.2 110E197 Sh.2 I-PV-I<<3-PV-I 220 I-PV-2 2-PV-R 220 I-Pv-3 2-Pf-3 2zl I-PV-4}2-FV-4 22 I PRESSURI'ZKF<<'.
VER I ISOLATION PRESSURE!ZER.
VEh'T ISOLA~ION PRE.SBURI Z E'VE.NT150LAT ION P'R'FSSURIZEI." VER i!SOLAR 109<<zG54c44 Zf"5 C44 2fc 54C4 4 zf-.5m4 4 I-HV'~!>-I-IV-.l 220 HEAD VE.I'<<T ISO}ANION zc 5 con I-IHV-2.<<"I-IV-c;P<<Y I-WV-3 2 HV-3 221 I-HV-4, 2.I-IV-4 22 I-IK&~}VFN I I&r31 WW}OM HK AD VE.NT IGC>LA'PION I-IE.<<E<<D VE.N ISOLA ION 2Q 5-SC4 Zt" 54C-k 4 Zf" 6 4C44 i'i EC}<ate gI<<!f If;EL<<<<'EY0 27<<50 g~t<<rn<I<<'<<P.~g C<<AE<<<</Akll 359>><<~I I r}<><<<<r<</I~ll i>>>><><<J<<<<t l X 0 T-0<<7<<<<<<1<<<<<<I<<<<fl U o~~Qg ny<<o r<<O>n A 0 O Z I Z 0 r m n tV~>>>>pl-~.Qz 0 e~~~)a) 4J I O lOA~p Rll OPEN RI2 R21 D PEII R22 VAt.V E I-PV-3 2-PV-3 I-PV.4 2-PV-+I-HV-3 2-HV.3 I-HV-$2-HV" r IOA, Ncr.0 ENCRGI=E.2o TO OPEN he 20 20 n rr.O ra.20[hc NOTES I.5 UALVE NO.2.I/O SEE SS.9EV.~AM.P.~Sate.T l~3.CASL=TRAIN"'rp'AGN=TIC REE.D SWI TCHES Yi"s'i~pnouse Ele"Ir'c Corp"raliol Mv~,,, INDIANA AND MICHIGAN ELECTRIC CO.~LQC C UNIT NO 182.ELEMENTARY Vr 1RIII 1 6 rip/g J.6a-~/A>/~SOLE.NOID VAL'VE 5QLBQ.7 SHEET-22 I 0 CP 5~
4.The maximum allowable venting period is then determined from curve 81 (RCS Pressure vs.Hydrogen Flow Rate).This curve was generated from a calculation which determined the flow rate of hydrogen at various RCS pressures through a 3/8" orificed line.The calculation assumed pure hydrogen which is conservative since the gaseous void in the vessel head will probably be some mixture of gases including steam.February, 1981 Revision 0 Page 12
~~r y~~~ooae~0~Oat~~4~0~0~O~~0 ATTACHi~)ENT 5 TO AEP:HRC:05i'8}}