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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
3/4.2 POWER DISTRIBUTION L IM ITS AXIAL FLUX DIFFERENCE (AFD LIMITING CONDITION FOR OPERATION 3.2.1 The indicated AXIAL FLUX DIFFERENCE (AFD) shall be maintained within a
+55 target band (flux difference units) about the target flux difference.
APPLICABILITY: MODE 1 ABOVE 50K RATED THERMAL POWER*
I ACTION:
- a. With the indicated AXIAL FLUX DIFFERENCE outside of the +5 ~
,target band about the target flux difference and with THERMAL POWER:
- l. Above 81/ of RATED THERMAL POWER, within 15 minutes:
a) Either restore the indicated AFD to within the target band limits, or b) Reduce THERMAL= POWER to less than 815 of RATED THERMAL POWER.
- 2. Between 50'. and 81 /. of RATED THERMAL POWER:
a) POWER OPERATION may continue provided:
- 1) The indicated AFD has not been outside of the
+5/ target band for more than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> penalty deviation cumulative during the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and
- 2) The indicated AFD is within the limits shown on Figure 3. 2-1. 0therwi se, reduce THERMAL POWER to less than 505 of RATED THERMAL POWER within 30 minutes and reduce the Power Range Neutron Flux-High Trip Setpoints to < 555 of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
b) Surveillance testing of the Power Range Neuter on Flux Channels may be performed pursuant to Specification 4.3.1.1.1 provided the indicated AFD is maintained within the limits of Figure 3.2-1. A total of 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> operation may be accumulated with the AFD out-side of the target band during this testing without penal ty devia tion.
I I .I .I D. C. COOK - UNIT 2 3/4 2-1
OWER DISTRIBUTION LIMITS C CTIOH: (Continued) c) Surveillance. testing of the APDMS may be performed pursuant to Specification 4.3.3.7.1 provided the indicated AFD is maintained within the limits of Figure 3.2-1. A total of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of operation may accumulated with the AFD outside of the'target
'e band duri ng this testing without penalty deviation.
- b. THERMAL POWER shall not be increased above 81Ã of RATED THERMAL POWER unless the indicated AFD is within the +5K target band and,ACTION 2.a) 1), above has been satisfied.
'c. THERMAl POWER shall not be increased above 50% of RATED THERMAL POWER unless the indicated AFD has not been outside of the
+5'arget band for. more than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> penalty deviation cumulative during the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE RE UIREMEHTS C
4.2;1.1 The indicated AXIAL FLUX DIFFERENCE shall be determined to be within its limits during POWER OPERATION above 15K of RATED THERMAL POWER by:
- a. Monitoring the indicated AFO for each OPERABLE excore channel:
At least once per 7 days when the AFD Monitor Alarm is OPERABLE, and
- 2. At least once per hour for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after restoring the AFD Monitor A'larm to OPERABLE status.
- b. Monitoring and logging the indicated AXIAL FLUX DIFFERENCE for each OPERABLE excore channel at least once per hour for the first, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and at least once per 30 minutes thereafter, when the AXIAL FLUX DIFFERENCE Monitor Alarm is inoperable.
The logged values of the indicated AXIAL FLUX DIFFERENCE shall be assumed, to exist during the interval preceding each logging.
D. C. COOK '- UNIT 2 3/4 2-2
Unacceptable Unacceptable Operation Oper ation Acceptab'I e 60 0 per tion
(-2s,so) ~ (25,50) 40 20 0
-50 -40 - 30 . -20 - IO 0 10 .20 30 '0 50 FLUX DIFFERENCE {bl) %
FIGURE 3.2-1 AXIALFLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER O. C. COOK' UNIT 2 3/4 2-4
(L POWER DISTRIBUTION LIMITS AXIAL POWER DIS1RIBUTION LIMITING COflDITION FOR OPERATION 3.2.6 The axial power distribution shall be 'limited by the following-relationship:
1.99 V, Z CF (Z)] =
{R .)(PL)(1.03){1 + a ){1.07)
Where:
- a. is the norma lized axial distribution from thimble F
j.(Z) power j at core elevation Z.
- b. PL is the fraction of RATED THERMAL POWER.
- c. K{Z) is the function obtained from Figure 3.2-2 for a given core height location'.
R., for thimble j, is determined from at least n=6 in-core flux maps. covering the full configuration of permissib'le rod patterns above 91! of RATED THERMAL POWER in accordance with: I n
R. = ~ R..
j n ~
1 ij Where:
R..=
ij ~ij Z~>iax and [F..
1J (Z)]f< t fax is the maximum value'of the normalized axial distribution at elevation Z from thimble j in map i which had a measured peaking factor without uncertainties or densification allowance of F~Meas
- 0. C. COOK - UfllT 2 3/zl 2-17 Amendment No. 17
~ 'OWER DISTRIBUTION LIMITS LIMITING COND I I ION FOR OPERATION Continued
- o. is the standard deviation associated with thimble j, expressed as a fraction or percentage of R., and is derived from n flux maps from the relationship below, or 0.02, (2X) whichever is greater.
o =
f ~(R -R.) ]
, R.
The factor 1.07 is comprised of 1.02 and 1.05 to account for the axial power distribution instrumentation accuracy and the measure-ment uncertainty associated with F using the movable detector system respectively.
The factor 1.03 is the engineering uncertainty factor.
APPLICABILITY: MODE 1 above 91/ OF RATED THERMAL POWER .
. ACTION;
- a. With a F (Z), factor exceeding [F.(Z)]
j S by < 4 percent, reduce J
THERMAL POWER one percent for every percent by which the F.(Z) factor exceeds its limit within 15 minutes and within the next two hours either reduce the F.(Z) factor to within its limit J
or reduce THERMAL POWER to Slà or less of RATED THERMAL POWER.
- b. With a F.(Z) factor exceeding [F-(Z)]S J
by > 4 percent, reduce J
THERMAL POWER to 915 or less of RATED THERMAL POWER within 15 minutes.
à The APDHS may be out of service when surveillance for determini ng power'istribution maps is being performed.
D. C. COOK - UNIT 2 3/4 2-18
POWER DISTRIBUTION LIMITS SURVEILLANCE RE UIREMENTS 4.2.6.1 F.(Z) shall be determined to be within its limit by:
J a'. Either using the APDMS to monitor the thimbles required per Specification 3.3.3.6 at the following frequencies.
- 1. At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, and
- 2. Immediately and at intervals of 10, 30, 60, 90, 120, 240 C
and.480 minutes following:
a)'Increasing the THERMAL POWER above 91K of RATED THERMAL POWER, or b) Movement of control bank "D" more than an accumulated total of 5 steps in any one direction.
- b. Or using the movable incore detectors at the following fre-quencies when the APDMS is inoperable:
- l. At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, and
- 2. At intervals of 30, 60, 90, 120, 240 and 480 minutes following:
a) Increasing the THERMAL POWER above 91Ã of RATED THERMAL POWER, or b) Movement of control bank "0" more than an accumulated total of 5 steps in any one direction.
4 .2.6.2 When the movable incore detectors are used to moni tor F .(Z),
J at least 2 thimbles shall be monitored and an F.(Z) accuracy equivalent J
to that obtained from the APDMS shall be maintained.
D. C. COOK - UNIT 2 3/4 2-19 II f '
I
~ ~
POWER DISTRIBUTION LIMITS BASES Although it is intended that the plant will be operated with the AXIAL FLUX DIFFERENCE within the +5" target band about the target flux difference, during rapid plant THERIQL POWER reductions, control rod motion will cause the AFD to deviate outside of the tar get band at re-duced THERMAL POWER levels. This deviation will not affect the xenon redistribution sufficiently to change the envelope of peaking factors which may be reached on a subsequent return to RATED THERMAL POWER (with the AFD within the target band) provided the time duration of the devi-ation is limited. 'ccordingly, a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> penalty deviation limit cumu-lative during the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is provided or operation outside of the target band but within the limits of Figure 3.2-1 while at THERtlAL POWER levels between 50% and 81% of RATED THERtQL POWER. For THERIQL POWER levels between 15% and 50% of RATED THERHAL POWER, deviations of the AFD outside of the target band are less significant. The penalty of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> actual time reflects this reduced significance.
Provisions for monitoring the AFD on. an. automatic basis are derived from the plant process computer through the AFD Monitor Alarm. The computer determines the one minute average of each of the OPERABLE excore detector outputs and provides an alarm message immediately i the AFD for at least 2 of 4 or 2 of 3 OPERABLE excore channels are outside the target band and the THERI)AL" POWER is gr eater than 81% of RATED THERMAL PO'WER. During operation at THERMAL POWER levels between SOll and 81% and between,15,. and 50% RATED THEfNAL POWER, the computer outputs an alarm message when the penalty deviation accumulat'es beyond the limits of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, respectively.
Figure B 3/4 2-1 shows a typical monthly target band.
D.C. COOK - UNIT 2 B-3/4 2-2
5 4 g
ATTACHMENT No. 2 to AEP:NRC:0564 A modification was made to the high pressure turbine in Unit 2 during the current refueling outage to improve overall turbine efficiency.
The current Technical Specification setpoint for the P-7 permissive in the logic of the Reactor Protection System (RPS) is low and needs to be increased to the new value of the first stage turbine impulse chamber pressure corresponding to 10/,'power (66 psia). Our calculations indicate that the current P-7 setpoint may cause unnecessary tripping of the reactor since Reactor Trip from a Turbine Trip could occur during the turbine overspeed tests with the current (low) setpoint of the impulse chamber pressure. Raising, the setpoint of the P-7 permissive to 66 psia will I
avoid possible unnecessary reactor trips, is consistent with the FSAR value for Reactor Trip/Turbine Trip at o) above 10$ power, and will not adversely affect the health and safety of the public.
The proposed revision is indicated on the attached page by a vertical line in the right margin.
TABLE 3. 3-1 Continued DESIGNATION CONDITION AND SETPOINT FUNCTION P-7 With 2 of 4 Power Range Neutron P-7 prevents or defeats Flux Channels > 11% of RATED the automatic block of THERMAL POWER or 1 of 2 Turbine reactor trip on: Low impulse chamber pressure channels flow in more than one
> 66 psia. primary coolant loop, reactor coolant pump under-voltage and under-frequency, turbine trip,
'pressurizer low pressure, and pressurizer high level.
P-8 With 2 of 4 Power Range Neutron P-8 prevents or defeats Flux channels > 51% of RATED .the automatic block of THERMAL POWER. reactor trip on low coolant flow in a single loop.
P-10 With 3 of 4 Power range neutron P-10 prevents or defeats flux channels ( 9% of RATED the manual block of: Power THERMAL POWER. range low setpoint reactor trip, Intermediate range reactor trip, and intermediate range rod stops.
Provides input to P-7.
D. C. COOK - UNIT 2 3/4 3-8
ll