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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
[Table view] |
Text
Attachment 2 to AEP:NRC:0916AB Proposed Revised Technical Specification Pages SSOS250055 SBOS15 PDR ADOCK 05000316 P PDC
3 4.1 REACTIVITY CONTROL SYSTEMS 3 4.1.1 BORATION CONTROL SHUTDOWN MARGIN - STANDBY STARTUP AND POWER OPERATION LIMITING COND TION 0 OP R TIO 3.1.1.1 The SHUTDOWN MARGIN shall be > 2.0% hk/k.
APPLICABILITY: MODES 1, 2*, and 3.
ACTION:
With the SHUTDOWN MARGIN < 2.0% Iph,k/k, immediately initiate and continue boration at > 10 gpm of 20,000 ppm boric acid solution or equivalent until the required SHUTDOWN MARGIN is restored.
SURVEI LANC R UIR M S 4.1.1.1.1 The SHUTDOWN MARGIN shall be determined to be > 2.0% b,k/k:
a 0 Within one hour after detection of an inoperable control rod(s) and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter while the rod(s) is inoperable. If the inoperable control rod is immovable or untrippable, the above required SHUTDOWN MARGIN shall be increased by an amount at least equal to the withdrawn worth of the immovable or untrippable control rod(s).
- b. When in MODES 1 or 2", at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that control bank withdrawal is within the limits of Specification 3.1.3.6.
- c. When in MODE 2 , within 4 hours prior to achieving reactor criticality by verifying that the predicted critical control rod position is within the limits of Specification 3. 1.3.6.
- See Special Test Exception 3. 10. 1
¹ With K > 1.0
¹¹ W1th K < 1.0 D.C. COOK - UNIT 2 3/4 l-l AMENDMENT NO.
t~ >>
REACTIVITY CONTROL SYSTEMS SURV LLANC E UIR M NTS Continued
- d. Prior to initial operation above 5% RATED THERMAL POWER after each fuel loading, by consideration of the factors of e below, with the control banks at the maximum insertion limit of Specification 3.1.3.6.
- e. When in MODE 3, at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by consideration of the following factors:
- 1. Reactor coolant system boron concentration,
- 2. Control rod position,
- 3. Reactor coolant system average temperature,
- 4. Fuel burnup based on gross thermal energy generation,
- 5. Xenon concentration, and
- 6. Samarium concentration.
- 4. 1. 1. 1.2 The overall core reactivity balance shall be compared to predicted i
values to demonstrate agreement within 1% hk/k at least once per 31 Effective Full Power Days (EFPD). This comparison shall consider at least those factors stated in Specification 4. 1. l. l. l.e, above. The predicted reactivity values shall be adjusted (normalized) to correspond to the actual core conditions prior to exceeding a fuel burnup of 60 Effective Full Power Days after each fuel loading.
- 4. 1. 1, 1.3 Prior to blocking ESF Functional Units in accordance with footnotes ¹ and ¹¹ of Table 3.3-3, SHUTDOWN MARGIN shall be determined to be greater than or equal to 2.0% d k/k by consideration of the factors of
- 4. l. l. l.e above. The Reactor Coolant System average temperature used in making this SHUTDOWN MARGIN determination shall be less than or equal to 350'F. This SHUTDOWN MARGIN shall be maintained at all times when the ESF functions are blocked in-MODE 3.
D. C. COOK - UNIT 2 3/4 1-2 AMENDMENT NO.
t ki
IITY CONTROL S EMS SHUTDOWN MARGIN - SHUTDOWN LI ITING CO DITION FOR OPERATION 3.1.1 ~ 2 The SHUTDOWN MARGIN shall be:
- a. In MODE 4:
- 1. Greater than or equal to 2.0% hk/k when operating with one or more Reactor Coolant Loops in accordance with Specification 3.4.1.3.
- 2. Greater than the value shown in Figure 3.1-3 when operating with no Reactor Coolant Loops but one or more Residual Heat Removal Loops in accordance with Specification 3.4,1.3.
be In MODE 5:
- 1. Greater than or equal to 1.0% 5k/k when operating with one or more Reactor Coolant Loops in accordance with Specification 3 '.1.3.
- 2. Greater than the value shown in Figure 3.1-3 when operating with no Reactor Coolant Loops but one or more Residual Heat Removal Loops in accordance with Specification 3.4.1 3. ~
APPLICABILITY: MODES 4 and 5 ACTION:
With SHUTDOWN MARGIN less than the above limits, immediately initiate and continue boration at greater than or equal to 10 gpm of 20,000 ppm boric acid solution or equivalent until the required SHUTDOWN MARGIN is restored.
SURVEILLANCE RE UIREMENTS 4.1.1.2 The SHUTDOWN MARGIN shall be determined to be greater than or equal to the above limits:
- a. Within one hour after detection of an inoperable control rod(s) and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter while the rod(s) is inoperable. If .the inoperable control rod is immovable or untrippable, the SHUTDOWN MARGIN shall be increased by an amount at least equal to the withdrawn worth of the immovable or untrippable control rod(s).
D. C. COOK - UNIT 2 3/4 1-3 AMENDMENT NO.
n O
O I
5.0 o
MODES 4 & 5 I
a 3.0 O
A ODE 4 2.0 f,+.
~"
~ ~
t T ~ r M "1 ~
"~
= ~ *~ I
MODE 5 Y 0.0L I l 200 400 600 800 1000 1200 1400 1600 1800 2000 BORON CONCENTRATION (PPM)
O Figure 3.1-3 REQUIRED SHUTDOWN MABGIN
CO'ASTROL REACTIVITY SYSTEMS MODERATOR TEMPERATURE COEFFICIENT LIMITING CONDITIO FOR OPERATION 3.1.1.4 The moderator temperature coefficient (MTC) shall be:
Within the region of acceptable operation in Figure 3.1-2, and
-4
- b. Less negative than -B.5 x 10 5k/k/ 0 F for the all rods withdrawn, end of cycle life (EOL), RATED THERi4fAL POWER condition.
APPLICABILITY: Specification 3. 1. 1.4.a - NODES 1 and 2* only~
Specification 3.1.1.4.b - NODES 1, 2 and 3 onl~
ACTION:
- a. With the NTC more positive than the limit of 3.1.1.4.a above:
- 1. Establish and maintain control rod withdrawal limits sufficient to restore the MTC to within its limits within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. These withdrawal limits shall be in addition to the insertion limits of Specification 3.1.3.6.
- 2. Maintain the control rods within the withdrawal limits established above until subsequen" measurement verifies that the MTC has been restored to within its limit for the all rods withdrawn condition.
- 3. Prepare and submit a Special Repor" to the Commission pursuant to Specification 6.9.2 within 10 days describing the value of the measured MTC, the interim control rod withdrawal limits and the predicted average core burnup necessary for restoring the positive MTC to within its limit for the all rods withdrawn condition.
With the MTC more negative than the limit of 3.1.1.4.b above, be in HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- With K eff greater than or equal to 1.0 See Special Test Exception 3.10.3 D. C. COOK - UNIT 2 3/4 1-5 AMENDMENT NO.
REACTIVITY CONTROL SYSTEMS SURVEILLANCE + EQUIREMENTS 4.1.1.4.1 The MTC shall be determined to be within its limits by confirmatory measurements. Measured MTC values shall be extrapolated and/or compensated to permit direct comparison with the above limits.
4.1.1.4.2 The MTC shall be determined to be within its limits during each fuel cycle as follows:
a) The MTC shall be measured and compared to the BOL limit of Specification 3.1.1.4.a, above, prior to initial operation above i% of RATED THERMAL POWER, after each fuel loading.
b) The MTC shall be measured at any THERMAL POWER within 7 EFPD after reaching an equilibrium boron concentration of 300 ppm and the extrapolated MTC value compared to the EOL limit. In the event this comparison indicates that the MTC will be more negative than the EOL limit, the MTC shall be remeasured at least once per 14 EFPD during the remainder of the fuel cycle and the MTC value compared to the EOL limit.
D. C. COOK - UNIT 2 3/4 1-6 Amendment No.
TABLE 3.3-4 Continued ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES
- 4. STEAM LINE ISOLATION
- a. Manual Not Applicable Not Applicable Ce d.
Automatic Actuation Logic Containment Pressure Steam High-High Flyv in Tvo Steam Lines High Coincident with Tavg Not Applicable
< A 2.9 psig function defined as follows:,,A ap correspon-Not Applicable
< A 3.0 psig function defined as follovs: A hp correspon-I Low-Low ding to 1.47 x 10 lbs/hr ding to 1.62 x 10 lbs/hr steam flov between 04 and steam flow between 04 and 204 load and then a dp 204 load and then a zp in-increasing linearly to a creasing linearly to a hp zp6corresponding to 4.02 x cop'esponding to 4.07 x 10 lbs/hr at full load. 10 lbs/hr at full load.
T avg-> 541 F. T > 539 F.
- e. Steam Line Pressure Low > 600 psig steam line > 585 psxg steam lane pressure pressure
- 5. TURBINE TRIP AND FEEDWATER ISOLATION
- a. Steam Generator Water Level < 674 of narrow range < 684 of narrow range High-High instrument span each steam Instrument span each steam generator generator
TABLE 3.3-5 Continued ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS
- 3. Pressurizer Pressure-Low
- a. Safety Injection (ECCS) < 24.0"/12.0¹
- b. Reactor Trip (from SI) < 2.0
- c. Feedwater Isolation < 8.0
- d. Containment Isolation-Phase "A" < 18.0¹
- e. Containment Purge and Exhaust Isolation Not Applicable Motor Driven Auxiliary Feedwater Pumps < 60.0 9, Essential Service Water System < 48.0"/13.0¹
- 4. Differential Pressure Between Steam Lines-Hi h
'a ~ Safety Injection (ECCS) < 12.0¹/24.0¹¹
- b. Reactor Trip (from SI) < 2.0 C. Feedwater Isolation < 8.0
- d. Containment Isolation-Phase "A" < 18.0¹/28.0¹¹
- e. Containment Purge and Exhaust Isolation Not Applicable Motor Driven Auxiliary Feedwater Pumps < 60.0
- g. Essential Service Water System < 13.0¹/48.0¹¹
- 5. Steam Flow in Two Steam Lines - Hi h Coincident with Tav LOW LOW
'a ~ Safety Injection (ECCS) Not Applicable b, Reactor Trip (from SI) Not Applicable C. Feedwater Isolation Not Applicable
- d. Containment Isolation-Phase "A" Not Applicable
- e. Containment Purge and Exhaust Isolation Not Applicable Auxiliary Feedwater Pumps Not Applicable g, Essential Service Water System Not Applicable
- h. Steam Line Isolation < 10 D. C. COOK - UNIT 2 3/4 3-27 AMENDMENT NO.
E 3 4. 1 REACTIVITY CONTROL SYSTEMS BAS S 3 4.1.1 BORATION CONTROL 3 4.1.1.1 and 3 4.1.1.2 SHUTDOWN MARGIN A sufficient SHUTDOWN MARGIN ensures that 1) the reactor can be made subcritical from all operating conditions, 2) the reactivity transients associated with postulated accident conditions are controllable within acceptable limits, and 3) the reactor will be maintained sufficiently subcritical to preclude inadvertent criticality in the shutdown condition.
SHUTDOWN MARGIN requirements vary throughout core life as a function of fuel depletion, RCS boron concentration, and RCS Tav The most restrictive condition for increased load events occurs at EOL, with T at no load operating temperature, and is associated with a postulate5 steam line break accident and resulting uncontrolled RCS cooldown. In the analysis of this accident, a minimum SHUTDOWN MARGIN of 2.0% hk/k is initially required to control the reactivity transient and automatic ESF is assumed to be available.
Technical Specification requirements call for verification that the SHUTDOWN MARGIN is greater than or equal to that which would be required for the MODE 3 low temperature value, 350'F, prior to blocking safety injection on either the P-ll or P-12 permissive interlocks. This assures in the event of an inadvertent opening of two cooldown steam dump valves that adequate shutdown reactivity is available to allow the operator to identify and terminate the event.
With T < 200'F, the reactivity transients resulting from a postulated steam line Nanak cooldown are minimal and a 1% hk/k SHUTDOWN MARGIN provides adequate protection for this event.
In shutdown MODES 4 and 5 when heat removal is provided by the residual heat removal system, active reactor coolant system volume may be reduced.
Increased SHUTDOWN MARGIN requirements when operating under these conditions is provided for high reactor coolant system boron concentrations to ensure sufficient time for operator response in the event of a boron dilution transient.
The SHUTDOWN MARGIN requirements are based upon the limiting conditions described above and are consistent with FSAR safety analysis assumptions.
3 4.1.1.3 BORON DILUTION A minimum flow rate of at least 3000 GPM provides adequate mixing, prevents stratification and ensures that reactivity changes will be gradual during boron concentration reductions in the Reactor Coolant System. A flow rate of at least 3000 GPM will circulate an equivalent Reactor Coolant System volume of 12,612 cubic feet in approximately 30 minutes. The reactivity change rate associated with boron reductions will therefore be within the capability for operator recognition and control.
D. C. COOK - UNIT 2 8 3/4 1-1 AMENDMENT NO.