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Category:TECHNICAL SPECIFICATIONS
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 ML17325B6061999-05-21021 May 1999 Proposed Tech Specs Revising Limitations on Positive Reactivity Additions 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 ML17335A3681998-12-0303 December 1998 Proposed Tech Specs,Adding New TS Re Distributed Ignition Sys 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 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 ML17335A3651998-12-0303 December 1998 Proposed Tech Specs 3/4.7.7, Sealed Source Contamination & Associated Bases Addressing Revised Testing Requirements for Fission Detectors 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. ML17335A2691998-10-0808 October 1998 Proposed Tech Specs 3.4.1.3 Re Reactor Coolant Loop Requirements in Modes 4 & 5 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 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 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 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 ML17333A9851997-08-11011 August 1997 Proposed Tech Specs,Allowing Filling of ECCS Accumulators W/O Declaring ECCS Equipment Inoperable ML17333A9891997-08-11011 August 1997 Proposed Tech Specs,Reflecting Changes for Moderator Temp Coefficient Measurement in Response to RAI 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. ML17333A8261997-03-26026 March 1997 Proposed Tech Specs Removing Administrative Controls Related to Quality Assurance Requirements IAW Guidance of Administrative Ltr 95-06 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 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 ML17333A4651996-06-11011 June 1996 Proposed Tech Specs Re Administrative Controls Related to QA ML17333A4221996-04-0808 April 1996 Revised Proposed Ts,Moving TS 4.0.4 Exemption Statement for MSSVs Into Section 4.7.1.1 ML17333A3571996-03-12012 March 1996 Proposed Tech Specs,Removing TSs Re Shutdown & Control Rod Position Indication While in Modes 3,4 & 5 ML17333A3301996-02-29029 February 1996 Proposed Tech Specs Re Boric Acid Storage Sys Boron Concentration ML17333A3231996-02-26026 February 1996 Proposed TS 5.6.2 Re Increase in Max Nominal Fuel Assembly Enrichment Limit,Taking Credit for Use of Integral Fuel Burnable Absorber Matl ML17333A3221996-02-22022 February 1996 Proposed Tech Specs,Proposing to Remove Requirement That Operations Superintendent Must Hold or Have Held Sol at Plant or Similar Reactor ML17333A3171996-02-22022 February 1996 Proposed Tech Specs,Modifying Table 4.8-1,DG Test Schedule by Ref Rg 1.9,Rev 3 Rather than Rg 1.108,Rev 1 Criteria for Determination of Valid DG Test ML17333A3121996-02-16016 February 1996 Proposed Tech Specs Section 3.6.1.6,removing Words Structure & Steel Liner to Be Consistent W/Unit 2 Containment Sys Wording ML17333A2671996-01-12012 January 1996 Proposed Tech Specs,Modifying TS Section 4.4.11 to Eliminate SR Demonstrating Operability of Emergency Power Supply for Pressurizer PORVs & Block Valves ML17333A2411995-12-19019 December 1995 Proposed Tech Specs 3/4.6.1.2,3/4.6.1.3,3/4.6/1/6 & 3/4.6.1.7,replacing Option a Scheduling Requirements for Types A,B & C Tests (Overall Integrated & Local Containment Leakage Rate) W/Requirement Per 10CFR50 App J Option B ML17332B0131995-11-10010 November 1995 Proposed Tech Specs Modifying Surveillance Testing of EDG During Refueling & Normal Operations ML17332A9991995-10-20020 October 1995 Proposed Tech Specs Adding Exemption to TS 4.0.4 in SR for MSIV ML17332A9151995-08-0808 August 1995 Proposed Tech Specs Re Deletion of Component Cyclic or Transient Limit Table ML17332A8751995-08-0404 August 1995 Proposed Tech Specs for Repair of Hybrid Expansion Joint Sleeved SG Tubes ML17332A8291995-06-30030 June 1995 Proposed Tech Specs Re Fuel Reconstitution,Per GL 90-02 ML17332A8111995-06-20020 June 1995 Proposed Tech Specs Removing Fire Protection Systems from Licenses 1999-09-23
[Table view] 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
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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION 'PAGE 3/4. 2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE......'..."."------."...- "... 3/4 2-1 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR............................ 3/4 2-5 3/4.2.3 NUCLEAR ENTHALPY HOT CHANNEL FACTOR... . . ... ...-.-.- 3/4 2-9 3/4.2.4 QUADRANT POWER TILT RATIO............................... 3/4 2-13 3/4.2.5 DNB PARAMETERS MO DE 1 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ e ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 2-15 MO DES 2, 3, 4 and 5..................................... 3/4 2-17 3/4.2.6 ALLOWABLE POWER LEVEL................................... 3/4 2-19 I
3/4. 3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION................... - ~ 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION............. .... ..................... 3/4 3-14 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation.................... 3/4 3-34 Movable Incore Detectors.... 3/4 3-38 Seismic Instrumentation...........-.....-.---....... " .. 3/4 3-38a I Meteorological Instrumentation.......-.................. 3/4 3-39 Remote Shutdown Instrumentation...................-..- ~ ~ 3/4 3-42 Fire Detection Instrumentation. 3/4 3-46 Post-Accident Instrumentation.... .-- ~ ~ ~ ~ " ~ ~ ~ ~ ~ " -- -~ ~ ~ ~ 3/4 3-50 Radioactive Liquid Effluent Instrumentation......... 3/4 3-53 Radioactive Gaseous Process and Effluent Monitoring Instrumentation............ 3/4 3-62 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power Operation............................. 3/4 4-1 D.C. COOK - UNIT 2 Amendment Ho. pj, 1O2 9402240308 'F40215 PDR ADDCK 050003l6 PDR
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ B 3/4 0 1 3/4.1.1 BORATION CONTROL ...........--................. - ~ ~ ~ ~ ~ B 3/4 1-1 3/4.1.2 BORATION SYSTEMS B 3/4 1-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES B 3/4 1-4 4
3/4.2.1 AXIAL FLUX DIFFERENCE ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ B 3/4 2-1 3/4.2.2 and 3/4.2.3 HEAT FLUX HOT ADiNNEL FACTOR AND NUCLEAR EÃHBQ.PY HOT CHANNEL FACTOR ......... ~ ~ ~ ~ ~ ~ ~ ~ ~ B 3/4 2-4 3/4.2.4 QUADRANT POWER TILT RATIO ~ ~ ~ . ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ B 3/4 2-5 3/4.2.5 DNB PLQQMETERS e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ B 3/4 2-5 3/4.2.6 ALLOVABLE POWER LEVEL ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ B 3/4 2-5 4
3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY FEATURE INSTRUMENTATION B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION B 3/4 3-la 4 4 0 C 0 3/4.4.1 . REACTOR COOLOT LOOPS B 3/4 4-1 3/4.4.2 and 3/4.4.3 SAFETY VALVES B 3/4 4-2.
3.4.4.4 P RESSURIZER ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ B 3/4 4-2 3/4.4. 5 STEAM GENERATOR TUBE INTEGRITY....................... B 3/4 4-24 3/4.4.6 REACTOR COOIANT SYSTEM LEAKAGE ...................... B 3/4 4-3 3.4.4.7 CHEMISTRY ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ B 3/4 4-4 3/4t4 8~ SPECIFIC ACTIVITY ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ B 3/4 4-5 COOK NUCLEAR PLANT - UNIT 2 XII AMENDMENT NO. W, ~ 142
I N STi? Ui"ENTAT ON 3 . 3.4 TURBINE OYEPSPEED?ROTECTION LIMIT.RG CONOITION FOR OPERATION 3.3.4.1 t least one turbine overspeed protection sys em halI be OPEUBLE APPLIC"BILIT HOOES 1, 2 and 3.
ACT! GN:
- a. Mith on stop valve or one control valv per high pressure turbine s earn lead inoperable or with ne reheat stop valve or one reheat intercept valve per low p essure turbine steam lead.
inoperable, operation may continue or up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided the inoperab valve(s) is restor to OPERABLE status or at least one val in he af ected team lead is closed; otherwise, isolate the tu ine from the s am supply within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
- b. Kith the above re . ired turb'ne overspeed pro-.ec 'on system otherwise i perabl , within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> either restore the system to OPEP~ E s . us or isolate the turLine from the steam supply.
SUR'lEILLANCE RLOUIREMENTS 4.3.4.1.1 The provisions o Speci ic tion 4.0.'4 a'e not applicable.
l 4.3.4.1'.2 The above req red turbine o rspeed pro. ection svs em shall be dmonstrat d OPEPABLE:
- a. At least o e per 7 days by cycli each of the following valves th ugh a. least one comple cycle from the running PQSltlOn
- l. 4 ur high pressure turbine stop v ives.
- 2. Four high pressure turbine con rol ives.
Six low pressure turbine reheat s op v ives.
- 4. Six low pressure turbine ret'.e'at in ercep valves.
- 0. C. COOK - UN.'T 2 3/4 3-oo N ienwmefl l, .s~ I
At lees. once 31 "ays by dire observa .ion of tie move-ment of each of : . a"ove valve through ore complete cycle from the runnina position.
c~ At least once per 18 mc hs pericr..ance of a C:-All IcL CAI.I:R~T:0."I on the t ne ove "eed proto t on syst ..s.
- d. 4t least once p . <0 months by di sass 'bl inc at lees. one of each of the ove valves and performina visual and surface inspection f valve seats, disks and s:ems d verifying no uracc p le flaws or corrosion.
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3 4. 3 INSTRUMENTATION BASES 3/4.3.3.M RADIOACTIVE GASEOUS EFFLUENT INSTRUMENTATION The radioactive effluent gaseous instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents dux'ing actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance vith NRC approved methods in the OCDN to ensure that the alarm/trip vill occur prior to exceeding the limits of 10 CFR Part 20. This instrumentation also includes provisions fox monitox'ing the concentrations of potentially explosive gas mixtures in the vaste gas holdup system. The OPERABILITY and use of this instxumentation is consistent vith the requirements of Genex'al Design Criteria specified in Section 11.3 of the Final Safety Analysis Report for the Donald C. Cook Nuclear Plant.
3/ . . TURBINE OVERSPEED PROTECTION This specification x vided to ensure that turbine overspeed protection instrumentation a e turb speed control valves are OPERABLE and vill protect the tu m excessive overspeed.
Protection from turbine e sive overspee uired since excessive overspeed of the t e could generate potentially ing missiles vhich could act and damage safety related components, eq t or stru es.
COOK NJCL~ P<T - UNIT 2 B 3/4 3'-4 ANENDMENT NO. 115
Attachment 3 to AEP:NRC:1168A PROPOSED REVISED TECHNICAL SPECIFICATION PAGES
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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION gAAG 3 4 2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 2-1 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR 3/4 2-5 3/4.2.3 NUCLEAR EPQQQZY HOT CHANNEL FACTOR 3/4 2-9 3/4.2.4 qUADRANT POWER TILT RATIO 3/4 2-13 3/4.2.5 DNB PARAMETERS MODE 1 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
' ~ ~ ~ ~ 3/4 2-15 MODES 2, 3, 4 and 5 3/4 2-17 3/4.2.6 ALLOWABLE POWER LEVEL 3/4 2-19 3 4 3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION .................... 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION 3/4 3-14 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation .................. 3/4 3-34 Movable Incore Detectors 3/4 3-38 Seismic Instrumentation ........ 3/4 3-38a Meteorological Instrumentation ........................ 3/4 3-39 Remote Shutdown Instrumentation 3/4 3-42 Fire Detection Instrumentation ........................ 3/4 3-45
'Post-Accident Instrumentation . 3/4 3-50 Radioactive Liquid Effluent Instrumentation............ 3/4 3-53 Radioactive Gaseous Process and Effluent Monitoring Instrumentation.. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 3-62 3 4 4 REACTOR COOLANT SYST 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power Operation ...... ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 4 1 COOK NUCLEAR PLANT - UNIT 2 AMENDMENT NO. M, 402
INDEX BASES SECTION PAGE 3 4 0 PPLICABILITY . . ................................. B 3/4 0-1 3 4 1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL ..................................... B 3/4 1-1 3/4.1.2 BORATION SYSTEMS .................. ................. B 3/4 1-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES ........................... B 3/4 1-4 3 4 2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE B 3/4 2-1 3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR AND NUCLEAR ENTHALPY HOT CHANNEL FACTOR B 3/4 2-4 3/4.2.4 QUADRANT POWER TILT RATIO B 3/4 2-5 3/4.2.5 DNB PARAMETERS B 3/4 2-5 3/4.2.6 ALLOWABLE POWER LEVEL B 3/4'-5 3 4 3 INSTRUMENTATION 3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY FEATURE INSTRUMENTATION .............................. B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION B 3/4 3-la 3 4 4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS B 3/4 4-1' 3/4.4.2 and 3/4.4.3 SAFETY VALVES 3/4 4-2 3.4.4.4 PRESSURIZER B 3/4 4-2 3/4.4.5 STEAM GENERATOR TUBE INTEGRITY B 3/4 4-2a 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE B 3/4 4-3 3.4.4.7 CHEMISTRY B 3/4 4-4 3/4.4.8 SPECIFIC ACTIVITY B 3/4 4-5 COOK NUCLEAR PLANT - UNIT 2 XII AMENDMENT NO. QO, 407, 442
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3 4 3 INSTRUMENTATION BASES 3/4.3.3.10 RADIOACTIVE GASEOUS EFFLUENT INSTRUMENTATION The radioactive effluent gaseous instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. This instrumentation also includes provisions for monitoring the concentrations of potentially explosive gas mixtures in the waste gas holdup system. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria specified in Section 11.3 of the Final Safety Analysis Report for the Donald C. Cook Nuclear Plant.
COOK NUCLEAR PLANT - UNIT 2 B 3/4 3-4 AMENDMENT NO.
Attachment 4 to AEP:NRC:1168A COOK NUCLEAR PLANT COST BENEFICIAL LICENSING ACTION DELETE UNIT 2 TURBINE OVERSPEED PROTECTION SYSTEM T/S to AEP:NRC:1168A Page 1 Delete Unit 2 Turbine Overs eed Protection S stem T S Re ulato Re uirement:
Cook Nuclear Plant Unit 2 Technical Specifications 3/4.3.4 requires that turbine overspeed protection valve testing be performed every 7 days, and a number of other detailed requirements, to assure that the Unit 2 turbine overspeed protection system is operable.
Effect of Re uirement:
There is a significant potential for the action item in T/S 3/4,3,4 to lead to a unit shut down. Also, the 7 day test frequency creates a constraint for mode changes, which increases outage critical path time.
ationale for Re lato Chan e:
Deleting this requirement will make the Unit 2 T/S consistent with the new standard T/S, and with the Unit 1 T/S. These requirements are unique to Unit 2.
A roximate Cost of Re uirement:
The requirement adds about 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> to critical path to each outage, because it does not permit a change from mode 4 to mode 3. At $ 250,000 per day for replacement power, 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> per outage, and approximately 11.5 outages remaining for Unit 2, the plant lifetime cost savings from eliminating this requirement is approximately $ 1,800,000.
Identification:
AEPSC initiated CBLA effort.
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