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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. 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. ML17335A1931998-08-28028 August 1998 Proposed Tech Specs Requesting Extension of SG Surveillance TS 4.4.5.3,which TSs Require to Be Performed on 990408,until End of Current Fuel Cycle Currently Scheduled for Mar 2000 ML17335A2731998-08-21021 August 1998 Rev 0 to ST-307, Structural Evaluation of DC Cook Unit 2 Sgla Package. ML17334A7301998-05-0606 May 1998 Rev 2 of Cook Nuclear Plant Restart Plan. ML17325B5271998-04-0707 April 1998 Rev 1 to Cook Nuclear Plant Restart Plan. ML17334B8041998-04-0303 April 1998 Rev 1 to Valve IST Program for DCP Third 10-Yr Interval. ML17325B5261998-03-0707 March 1998 Rev 0 to Cook Nuclear Plant Restart Plan. ML17334B7031998-03-0303 March 1998 Proposed Tech Specs Pages,Removing Word Immediately from Unit 1 Hydrogen Recombiner Surveillance Requirement 4.6.4.2.b.4 & Revising Unit 1 & 2 TS 3/4.6.4 Bases ML20212A7051997-10-21021 October 1997 Proposed Tech Specs 3/4.6.5 Re Ice Weight & Surveillance Requirement ML17333B0751997-10-0808 October 1997 Proposed Tech Specs 3/4.6.5 & 3/4.5.5 Re Ice Weight & SR ML17333B0451997-09-19019 September 1997 Proposed Tech Specs,Deleting Requirement for Automatic Valve Closure Feature on RHR Sys Suction from RCS ML17333A9891997-08-11011 August 1997 Proposed Tech Specs,Reflecting Changes for Moderator Temp Coefficient Measurement in Response to RAI ML17333A9851997-08-11011 August 1997 Proposed Tech Specs,Allowing Filling of ECCS Accumulators W/O Declaring ECCS Equipment Inoperable ML17335A2121997-08-0101 August 1997 Proposed Tech Specs 4.7.1.2.g Deleting Wording When Secondary Steam Supply Pressure Is Greater than 310 Psig. ML17333A8301997-03-26026 March 1997 Proposed Tech Specs Modifying TS 4.7.5.1.e.2 Which Describes Control Room Ventilation Sys Autostart Functions ML17333A8331997-03-26026 March 1997 Proposed Tech Specs Involving Grammatical Correction to Wording of Unit 2 TS 3.4.8,Action a for Modes 1,2 & 3 & Returning Frequency Requirement to TS 4.7.1.2.c & 4.7.1.2.d That Was Inadvertently Deleted in Prior Amend ML17333A8261997-03-26026 March 1997 Proposed Tech Specs Removing Administrative Controls Related to Quality Assurance Requirements IAW Guidance of Administrative Ltr 95-06 ML20135C3781997-02-24024 February 1997 Revised Proposed Tech Specs Page Re 3/4, Limiting Condition for Operation & Surveillance Requirements ML17333A7161996-12-20020 December 1996 Proposed Tech Specs Change to Allow for Repair of Hybrid Sleeved SG Tubes in Response to RAI ML17333A7151996-12-20020 December 1996 Proposed Tech Specs 3/4.4.10 Re Reactor Coolant Sys ML17333A5161996-07-22022 July 1996 Proposed Tech Specs,Informing Operations Superintendent Will Have to Hold SRO License,Have Held Senior Operator License or Been Certified to Have Senior Operator Knowledge ML17334B5951996-07-11011 July 1996 Proposed Tech Specs,Supporting Operation of Facility at Increased Core Rated Thermal Power of 3,588 Mwt ML17333A4771996-06-19019 June 1996 Proposed Tech Specs Re Voltage Based Repair Criteria for Repair of Westinghouse SG Tubes Affected by Outside Diameter Stress Corrosion Cracking,Per GL 95-05 ML17333A4841996-06-11011 June 1996 ISI & Testing. ML17333A4651996-06-11011 June 1996 Proposed Tech Specs Re Administrative Controls Related to QA 1999-09-23
[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. ML17334A7301998-05-0606 May 1998 Rev 2 of Cook Nuclear Plant Restart Plan. ML17325B5271998-04-0707 April 1998 Rev 1 to Cook Nuclear Plant Restart Plan. ML17334B8041998-04-0303 April 1998 Rev 1 to Valve IST Program for DCP Third 10-Yr Interval. ML17325B5261998-03-0707 March 1998 Rev 0 to Cook Nuclear Plant Restart Plan. ML17333A4841996-06-11011 June 1996 ISI & Testing. ML17333A4701996-02-0808 February 1996 In-Service Pump Test Plan, Units 1 & 2 ML17334B5661995-11-30030 November 1995 Vols I & II of Third 10-Yr Interval Long-Term Inservice Exam Plan for Class,1,2 & 3 Sys & Components for DC Cook Nuclear Plant,Unit 1, Final Plan ML17334B5671995-11-30030 November 1995 Vols I & II of Third 10-Yr Interval Long-Term Inservice Exam Plan for Class 1,2 & 3 Sys & Components for DC Cook Nuclear Plant,Unit 2, Final Plan ML17332A2521994-08-0303 August 1994 Rev 3 to Plant Manager Procedure (PMP) 12 PMP 3150 PCP.100, Radwaste Pcp. 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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BACKGROUND INFORMATION FOR PRESSURIZER VENTING OPERATION REVISION 0 MARCH 1981
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PRESSURIZER VENTING OPERATION I. GENERAL OISCUSS ION A. PURPOSE The operator actions and precautions specified in this guideline are those instructions necessary to vent non-condensibJe gases from the pressurizer vapor space.
If an RCS depressurization is required hy another instruction and pressurizer spray and power operated relief valves are not available,-
hen the pressurizer vent system may be. used for the depressurization.
B. INITIAL CONDITIONS The CAUTION warns the operator that the pressurizer vent system is not designed for and should not be used 'as the primary means to mitigate an inadequate core cooling event. The vent flowpath is not sized to provide this capability and should only be used in conjunction with the Inadequate Core Cooling Guidelines.
The NOTE >ndicates that the pressurizer level and pressure requirements throughout the guideline do not include error allocations due to an adverse containment environment. Therefore, it is assumed that contain-ment temper ature is near normal opeating conditions.
The CAUTION warns the operator that any venting op'er ation should be performed under a s .able plant condition and the venting while safety injection is running may result in the undesirable condition of a water-solid pressurizer.
- 1. A larger than normal concentration of non-condensible gases is present in the pressurizer vapor space.
March, 1981 Revision 0 Page 1
- 2. Variations from the normal'ressurizer pres'sure and level response due to normal charging and spraying operations may be observed.
- 3. If non-condensible gases are present in the vapor space, then spray ng will not condense the gases and the normal depressur-ization will not occur.
- 4. Gases in the reactor coolant system may result from several types,,
of plant events. An accumulator tanl; discharge or a core uncovery may result in non-condensible gases (e.g. nitrogen and hydrogen) being trapped in the RCS. Inadvertent gas addition to the vapor space is another event which would result in non-condensibles collecting in the pressurizer.
- 5. If an RCS depressurization is required by another operating instruction, then the pressurizer vent may be used if the normal spray or PORV's are either not available or if their use is undesirable.
- 6. If gases are also present in the RCS, and the reactor vessel head, then the head should be vented prior 'to venting the pressurizer.'f the pressurizer was vented first, the depressurization may result in the vessel head gas bubble expanding to the point w'here natural circulation core cooling may be disturbed.
C. IMMEDIATE ACTIONS None March, 1981 Revision 0 Page 2
II. BASIS FOR SUBSEQUENT ACTIONS The NOTE identifies certain steps (marked by an asterisk) which are not applicable if the pressurizer is being vented because large quantities of non-condensible gases are preventing an RCS depressur-ization.
- l. Once non-condensible gases are detected or suspected in the RCS, then any changes being made to the primary system should be terminated and a steady-state condition should be established.
This step refers to events like a POST-LOCA cooldown, a normal plant cooldown, or a plant recovery 'from a design basis event.
- 2. If a large amount of gases are not detected in the vapor space, then there is no need to vent the pressurizer unless the vent system is being used as an alternate depressurization method.
- 3. The venting operation will result in. pressurizer gases being vented to the containment. Therefore the containment purge and exhaust system should be isolated to. prevent the release of any radioactive gases to the environment: All available containment air circulation equipment should be started to prevent any hydrogen from forming a gas pocket and to ensure a representative hydrogen"-
concentration is obtained. in Step 5.
- 4. Increasing the reactor coolant sub-cooling 50'F above the minimum plant specific value ensures. that reactor coolant sub-cooling will be maintained over the entire range of RCS operating conditions if the .venting operation is terminated following a 200 psi decrease in RCS pressure. The preferred method of obtaining the additional sub-cooling is increasing RCS pressure since this will aid in condensing any steam bubble present. If the additional 50'F sub-cooling is already established then proceed to Step 5.
March, 1981 Revision 0 Page 3
The NOTE indicates that if RCS pressure is less than 350'F and the venting is being performed to initiate Repidual Heat Removal operation, then additional sub-cooling is not required and the actions of Step 4 are not applicable.
- 5. The actions of Appendix A "Venting Time Period" determine the maximum allowable time period for venting which will limit the containment hydrogen concentration to less than 3 volume percent.
This limit i.s required to prevent a potentially explosive hydrogen concentration from being developed inside the containment.
- 6. This step and the following CAUTION warns the operator that RCS pressure will decrease during the venting and if initial pressure is near the low pressure safety injection actuation setpoint, then SI may be automatically initiated during the venting. The operator is instructed.'to block the low pressure SI actuation if and/or when the block permissive is energized to prevent an inadvertent SI.
- 7. Charging flow is increased to maximum to limit the net mass depletion of the RCS during the venting period. A second charging pump should be started if it will provide additional mal:"-up flow.
The NOTE alerts the operator that the pressurizer level will increase during the vapor space venting due to water entering the pressurizer to replace the net:.vapor mass removed 'by the
'enting.
- 8. Both isolation valves in one vent flowpath must be opened to initiate the venting operation. The NOTE instructs the operator to close both isolation valves in the flowpath if one or both of the valves fail to open. The isolation valves in the redundant flowpath should then be .opened. This prevents two flowpaths being open if the failed valve suddenly opens.
March, 1981 Rev'ision 0 Page 4
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- 9. The venting operation is terminated when enough gases have been
.removed to restore normal pressurizer control or when the time limit determined in Step 5 is met. Note, that if the pressurizer is being vented to initiate RHR operation, then the pressurizer venting does not have to be terminated when pressure decreases by 200 psi.
- 10. Normal pressurizer pressure and level control is restored after the completion of the venting. A stable level and pressure should;-be maintained while it is determined if further venting is required.
ll. If the venting was terminated prior to removing enough gases to restore normal pressurizer control or to reduce pressure to the required condition, then the operator should return to Step 4 and repeat the venting operation.
The NOTE alerts the operator that if the time period for venting "
determined in Appendix A is met before normal pressurizer level con rol is restored then the containment hydrogen concentration must be reduced and a new venting period calculated prior to performing additional venting. The '.hydrogen concentration could be reduced through the use of the containment hydrogen re-combiners or by the purge and exhaust system if radioactive gas concentrations are w'ithin limits. The new venting period will be based upon the, reduced hydrogen concentration.
- 12. The operator should return to the appropriate operating instruction following the successful completion of .the venting of the pressur-izer vapor space.
March, 1981 Revision 0 Page 5
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'I III. BASIS FOR APPENOIX A "VE!ITING TIYiE PERI00" During a core uncovery event, there exi sts the potential for a significant amount of hydrogen generat d in the core which could be trapped in the reactor vessel head and released to the containment atmosphere during the venting operation. The containment hydrogen concentration is limited to less than 4 volume percent to prevent a potential explosive mix'ure with oxygen, therefore, the amount of hydrogen that can be vent d to the containment is restricted. A maximum allowable time period for venting is determined to limit the containment hydrogen concentration.
- 1. The total containment volume in cubic feet is first determined and then converted to standard temperature and pressure conditions.
Note that the pressure term for the conversion is only applicable to sub-atmospheric containments and ca'n be deleted for the remaining plants.
. 2. The containment hydrogen concentration's then determined in volume percent units. This value can be fo nd by direct sampling or by hydrogen monitors. Sufficient time =nould be allowed for the air circulation equipment to mix the containment atmosphere prior to sampling in order to determine a representative concentration.
I The NOTE identifies to the operator that the containment hydrogen concentration will be insignificant if there has been no leakage from the RCS to the containment. The operator may assume the H2'concentration to be 0 volume percent.
- 3. The maximum volume of hydrogen that can be vented is calculated which will limit the containment hydrogen concentration to less than 3 volume percent.
Ma'eh,, 1981 Revision 0 Page 6
- 4. The maximum allowable ventina period is then determined from curve =-"1 (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" ori iced 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.
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ATTACHMENT '3 TO AEP:NRC:0584