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Results
Other: 3F1085-02, Withdraws Tech Spec Change Request 53 & Rev 1 to Change Request 53,dtd 791120 & 821119,respectively.Overly Restrictive Allowable Outage Time Addressed Generically by Tech Spec Improvement Program & AIF, 3F1285-11, Withdraws Several Tech Spec Change Request Outstanding Issues Reported in NUREG-0748,Vol 5,Number 9,per NRC Request.Issues Include Remote Shutdown Panel,Intake Canal & Nuclear Instrumentation Calibr, ML20066H075
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MONTHYEARML20066H0751982-11-19019 November 1982 Tech Spec Change Request 53,Revision 1,allowing Calibr Error of Up to 2% Rated Thermal Power in out-of-core Instrumentation Project stage: Other ML20066H0411982-11-19019 November 1982 Application to Amend App a of License DPR-72,consisting of Tech Spec Change Request 53,Revision 1,allowing Calibr Error of Up to 2% Rated Thermal Power in out-of-core Instrumentation Project stage: Request 3F1085-02, Withdraws Tech Spec Change Request 53 & Rev 1 to Change Request 53,dtd 791120 & 821119,respectively.Overly Restrictive Allowable Outage Time Addressed Generically by Tech Spec Improvement Program & AIF1985-10-0101 October 1985 Withdraws Tech Spec Change Request 53 & Rev 1 to Change Request 53,dtd 791120 & 821119,respectively.Overly Restrictive Allowable Outage Time Addressed Generically by Tech Spec Improvement Program & AIF Project stage: Other 3F1285-11, Withdraws Several Tech Spec Change Request Outstanding Issues Reported in NUREG-0748,Vol 5,Number 9,per NRC Request.Issues Include Remote Shutdown Panel,Intake Canal & Nuclear Instrumentation Calibr1985-12-19019 December 1985 Withdraws Several Tech Spec Change Request Outstanding Issues Reported in NUREG-0748,Vol 5,Number 9,per NRC Request.Issues Include Remote Shutdown Panel,Intake Canal & Nuclear Instrumentation Calibr Project stage: Other 1985-10-01
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20212C0961999-09-16016 September 1999 Proposed ITS & Bases Changes Strikeout & Shadowed Text & Revision Bar Format,Increasing Licensed Capacity for Spent Fuel Assembly Storage in SFP & Revising Configuration for Storage of Fresh Fuel ML20211L1011999-09-0202 September 1999 Proposed Tech Specs Re Once Though SG Tube Surveillance Program,Alternate Repair Criteria (ARC) for Axial Tube End Crack (Tec) Indications ML20209D2971999-07-0808 July 1999 Proposed Tech Specs,Changing ITS for CREVS & VFTP & Correcting Typo in ITS Section 5.6.2.12 ML20195B8091999-05-26026 May 1999 Proposed Tech Specs,Revising ITS Bases That Will Update NRC Copies of ITS ML20195B7081999-05-17017 May 1999 Proposed ITS Section 3.3.8, EDG Lops, SR 3.3.8.1,revising Note for Surveillance & Deleting Note for Frequency ML20206S7691999-05-12012 May 1999 Proposed Improved Tech Specs Pages 3.4-21 Through 3.4-21D ML20206N1401999-05-10010 May 1999 Proposed ITS Administrative Controls Section 5.8, High Radiation Area ML20206M0961999-05-0707 May 1999 Proposed Tech Specs,Revising Wording for SR 3.5.2.5 to Be More Consistent with NUREG-1430,Rev 1 & Clarifying Process of Valve Position Verification ML20206H6541999-05-0505 May 1999 Proposed Tech Specs,Proposing Alternate Repair Criteria for Axial Tube End crack-like Indications in Upper & Lower Tubesheets of CR-3 OTSGs ML20204D9211999-03-18018 March 1999 Proposed Tech Specs Re OTSG Tubes Surveillance Program,Tube Repair Roll Process ML20202E6551999-01-27027 January 1999 Proposed Tech Specs Re OTSG Tubes Surveillance Program,Insp Interval Extension ML20196D6761998-11-30030 November 1998 Proposed Tech Specs LCO 3.9.3,allowing Both Doors in Personnel Air Locks & Single Door in Oeh to Be Open During Refueling Operations ML20195K4551998-11-24024 November 1998 Proposed Tech Specs,Installing diesel-driven EFW Pump to Remove Interim ITS & Provide Resolution to EDG Capacity Limitations ML20195K0031998-11-23023 November 1998 Proposed Tech Specs Re LAR Number 241,rev 0 for High Pressure Injection Sys Mods ML20195H6581998-11-17017 November 1998 Proposed Improved Tech Specs (Its),Revising 5.7.2 by Changing Type of Structural Integrity Assessment Required from Probabilistic to Deterministic ML20155F4501998-10-30030 October 1998 Proposed Revised Improved Tech Specs (ITS) Deleting Note Re Number of Required Channels for Degrees of Subcooling Function & Subdividing Core Exit Temp Function Into Two New Functions in ITS Table 3.3.17-1 ML20155F4021998-10-30030 October 1998 Proposed Revised Improved Tech Specs (ITS) Section 5.6.2.19, ITS Section 3.4.11,Bases 3.4.11 & 3.4.3 Re PTLR & LTOP Limits ML20155F9551998-10-30030 October 1998 Proposed Tech Specs Pages to LAR 245,changing Methodology for Sf Pool B Criticality Analysis ML20154P3101998-10-16016 October 1998 Proposed Tech Specs Resolving USQ by Leaving Valves DHV-34 & DHV-35 Normally Closed ML20154C1581998-09-30030 September 1998 Proposed Tech Specs Pages Re LAR 238,to Correct RCS Leakage Detection Capability of RB Atmosphere Gaseous Radioactivity Monitor Described in ITS Bases & FSAR ML20238F4761998-08-31031 August 1998 Proposed Tech Specs,Proposing New Repair Process for Plant OTSGs ML20151X0431998-08-31031 August 1998 Proposed Tech Specs Adding Three Addl Reg Guide 1.97 Type a Category 1 Pami Variables & One Type B Category 1 Pami Variable to ITS Table 3.3.17-1, Pami ML20236V8831998-07-30030 July 1998 Proposed Tech Specs Pages Re CREVS & Ventilation Filter Test Program ML20236E9851998-06-30030 June 1998 Proposed Tech Specs Re Exigent License Amend Request 228,rev 1 for Once Through SG Tube Surveillance Program ML20249B2671998-06-18018 June 1998 Proposed Tech Specs Pages Re one-time Exigent License Amend to Allow Operation W/Number of Indications Previously Identified as Tube End Anomalies & Multiple Tube End Anomalies in OTSG Tubes ML20247P8931998-05-22022 May 1998 Proposed Improved Tech Specs 5.2.1 Re Onsite & Offsite Organizations ML20217P5181998-04-28028 April 1998 Proposed Tech Specs Re Reactor Coolant Pump Motor Flywheel Insp ML20217G0121998-04-23023 April 1998 Proposed Improved Tech Specs Section 5.7.2, Special Repts, Clarifying That Complete Results of OTSG Tube Inservice Insp Shall Be Submitted to NRC 90 Days After Startup (Breaker Closure) ML20217C6341998-03-20020 March 1998 Proposed Tech Specs Re Editorial Changes to Improved TS Saftey Limits & Administrative Controls to Replace Titles of Senior Vice President,Nuclear Operations & Vice President, Nuclear Production W/Position of Chief Nuclear Officer ML20217C4931998-03-20020 March 1998 Proposed Improved Tech Specs 5.6.2.8.c Re Reactor Coolant Pump Motor Flywheel Insp ML20203D1611998-02-20020 February 1998 Proposed Tech Specs,Providing Revs to CR-3 Improved TS Bases That Update NRC Copies of Improved TS ML20198S9151998-01-22022 January 1998 Proposed Tech Specs Consisting of Rev 1 to TS Change Request 210,correction of Typo & Addition of Footnotes ML20202G8511997-12-0505 December 1997 Proposed Tech Specs Establishing New Improved TSs (ITS) Surveillance Requirement for Performance of Periodic Integrated Leak Test of Cche Boundary & Revising ITS Bases 3.7.12 to Define Operability of Cche ML20202G7991997-12-0505 December 1997 Proposed Tech Specs Revising Description of Starting Logic for RB Recirculation Sys Fan Coolers to Ensure That Only One RB Fan Starts on Es RB Isolation & Cooling Signal ML20199G8461997-11-21021 November 1997 Proposed Tech Specs Pages Involving Additional Restrictions, Editorial Clarifications & Typos ML20212F2741997-10-31031 October 1997 Proposed Tech Specs Pages Re Decay Heat Removal Requirements in Mode 4 ML20212C9801997-10-25025 October 1997 Proposed Tech Specs Re Power Operated Relief Valve Lift Setpoint TS Limit That Has Been Revised for Instrument Uncertainty ML20217F5231997-10-0404 October 1997 Proposed Tech Specs Pages Addressing Revision to Description of Electrical Controls for Operating Reactor Building (RB) Recirculation Sys fan/cooler,AHF-IC,as Discussed in FSAR & Improved TS ML20217D2741997-10-0101 October 1997 Proposed Tech Specs Adding Methodology to Monitor first-span Intergranular Attack (Iga) Indications & Disposition Growth During Future B OTSG Eddy Current Exams ML20210T9771997-09-12012 September 1997 Proposed Tech Specs Replacement Pages Re New Improved TS 3.4.11 Re Low Temp Overpressure Protection Sys ML20216F8481997-09-0909 September 1997 Proposed Tech Specs Re Analysis Rev for Makeup Sys Letdown Line Failure Accident as Discussed in FSAR ML20217Q2121997-08-26026 August 1997 Proposed Tech Specs Changing Design Basis of EDG Air Handling Sys ML20217N2501997-08-20020 August 1997 Proposed Improved Tech Specs 5.6.2.10 Re Tube Surveillance ML20210K8921997-08-16016 August 1997 Proposed Tech Specs 3.8.1.3,requesting one-time Outage on Each EDG to Perform Necessary Mod & Maint ML20151L7541997-08-0404 August 1997 Proposed Tech Specs Extending Frequency of EDG Surveillances During Period of Time CR-3 EDGs Are Being Modified ML20196J1431997-07-29029 July 1997 Proposed Tech Specs Adding EDG Kilowatt Indication to post- Accident Monitoring Instrumentation to Support CR-3 Restart Issue of EDG Load Mgt ML20196H0281997-07-18018 July 1997 Proposed Tech Specs Changes Establishing Requirements for Low Temperature Overpressure Protection Sys ML20148K7811997-06-14014 June 1997 Proposed Tech Specs Re Efw,Hpi,Emergency Feedwater Initiation & Control Sys ML20138H8781997-05-0101 May 1997 Proposed Tech Specs Replacing Prescriptive Requirements of 10CFR50,App J,Option a w/performance-based Approach to Leakage Testing Contained in 10CFR50,App J,Option B ML20137X5361997-04-18018 April 1997 Proposed Tech Specs,Providing Revs to CR-3 Improved TS Bases That Update NRC Copies of Improved TS 1999-09-02
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20212C1121999-09-16016 September 1999 Criticality Safety Analysis of W Spent Fuel Storage Racks in Pool B of Crystal River Unit 3 ML20212C0961999-09-16016 September 1999 Proposed ITS & Bases Changes Strikeout & Shadowed Text & Revision Bar Format,Increasing Licensed Capacity for Spent Fuel Assembly Storage in SFP & Revising Configuration for Storage of Fresh Fuel ML20211L1011999-09-0202 September 1999 Proposed Tech Specs Re Once Though SG Tube Surveillance Program,Alternate Repair Criteria (ARC) for Axial Tube End Crack (Tec) Indications ML20212C0991999-08-31031 August 1999 Criticality Safety Analysis of Crystal River Unit 3 Pool a for Storage of 5% Enriched Mark B-11 Fuel in Checkerboard Arrangement with Water Holes ML20209D2971999-07-0808 July 1999 Proposed Tech Specs,Changing ITS for CREVS & VFTP & Correcting Typo in ITS Section 5.6.2.12 ML20195B8091999-05-26026 May 1999 Proposed Tech Specs,Revising ITS Bases That Will Update NRC Copies of ITS ML20195B7081999-05-17017 May 1999 Proposed ITS Section 3.3.8, EDG Lops, SR 3.3.8.1,revising Note for Surveillance & Deleting Note for Frequency ML20206S7691999-05-12012 May 1999 Proposed Improved Tech Specs Pages 3.4-21 Through 3.4-21D ML20206N1401999-05-10010 May 1999 Proposed ITS Administrative Controls Section 5.8, High Radiation Area ML20206M0961999-05-0707 May 1999 Proposed Tech Specs,Revising Wording for SR 3.5.2.5 to Be More Consistent with NUREG-1430,Rev 1 & Clarifying Process of Valve Position Verification ML20206H6541999-05-0505 May 1999 Proposed Tech Specs,Proposing Alternate Repair Criteria for Axial Tube End crack-like Indications in Upper & Lower Tubesheets of CR-3 OTSGs ML20204D9211999-03-18018 March 1999 Proposed Tech Specs Re OTSG Tubes Surveillance Program,Tube Repair Roll Process ML20205A7651999-03-18018 March 1999 Rev 29 to AR-305, Es E Annunciator Response ML20205A7961999-03-15015 March 1999 Rev 22 to AR-301, ESA Annunciator Response ML20205A8051999-03-15015 March 1999 Rev 33 to AR-303, ESC Annunciator Response ML20205A8211999-03-15015 March 1999 Rev 35 to AR-403, PSA H Annunciator Response ML20205A3441999-03-12012 March 1999 Rev 25 to AR-402, PSA G Annunciator Response ML20204D5781999-03-0909 March 1999 Rev 10 to AP-513, Toxic Gas ML20204D5821999-03-0808 March 1999 Rev 22 to AR-603, Tgf O Annunciator Response ML20207H7741999-03-0303 March 1999 Rev 15 to AR-602, Tgf N Annunciator Response ML20207J6591999-03-0202 March 1999 Rev 18 to AR-504, ICS L Annunciator Response ML20207J6461999-03-0202 March 1999 Rev 21 to AR-301, ESA Annunciator Response ML20206S7561999-02-28028 February 1999 Rev 2 to Pressure/Temp Limits Rept, Dtd Feb 1999 ML20203C7461999-02-0303 February 1999 Rev 2 to AR-801, FSA Annunciator Response ML20202E6551999-01-27027 January 1999 Proposed Tech Specs Re OTSG Tubes Surveillance Program,Insp Interval Extension ML20202B1411999-01-22022 January 1999 Rev 22 to AR-401, PSA F Annunciator Response ML20199G5201999-01-15015 January 1999 Rev 11 to AP-961, Earthquake ML20199G5581999-01-12012 January 1999 Rev 4 to AP-404, Loss of Decay Heat Removal ML20199G5691999-01-12012 January 1999 Rev 4 to AP-604, Waterbox Tube Failure ML20198T2411999-01-0606 January 1999 Rev 19 to AR-701, Ssf P Annunciator Response ML20196G6771998-12-0101 December 1998 Rev 17 to Annunciator Response AR-702, Ssf Q Annunciator Response ML20196D6761998-11-30030 November 1998 Proposed Tech Specs LCO 3.9.3,allowing Both Doors in Personnel Air Locks & Single Door in Oeh to Be Open During Refueling Operations ML20196G5851998-11-25025 November 1998 Rev 32 to AR-303, ESC Annunciator Response ML20196G3371998-11-25025 November 1998 Reissued Rev 15 to AR-702, Ssf Q Annunciator Response ML20195K4551998-11-24024 November 1998 Proposed Tech Specs,Installing diesel-driven EFW Pump to Remove Interim ITS & Provide Resolution to EDG Capacity Limitations ML20196F6691998-11-24024 November 1998 Rev 11 to AP-330, Loss of Nuclear Svc Cooling ML20195K0031998-11-23023 November 1998 Proposed Tech Specs Re LAR Number 241,rev 0 for High Pressure Injection Sys Mods ML20196F7721998-11-23023 November 1998 Rev 3 to EOP-12, Station Blackout ML20196F7031998-11-23023 November 1998 Rev 3 to AP-404, Loss of Decay Heat Removal ML20196F7541998-11-23023 November 1998 Rev 7 to EOP-08, LOCA Cooldown ML20196F7461998-11-23023 November 1998 Rev 6 to EOP-07, Inadequate Core Cooling ML20196F7241998-11-23023 November 1998 Rev 2 to AP-510, Rapid Power Reduction ML20196F7161998-11-23023 November 1998 Rev 9 to AP-470, Loss of Instrument Air ML20196F8711998-11-23023 November 1998 Rev 28 to AR-305, Es E Annunciator Response ML20196F9451998-11-19019 November 1998 Rev 7 to AP-1080, Refueling Canal Level Lowering ML20196F9381998-11-19019 November 1998 Rev 27 to AP-770, Emergency Diesel Generator Actuation ML20195H6581998-11-17017 November 1998 Proposed Improved Tech Specs (Its),Revising 5.7.2 by Changing Type of Structural Integrity Assessment Required from Probabilistic to Deterministic ML20196D8321998-11-13013 November 1998 Rev 1 to Crystal River Unit 3 ASME Section Xi,Isi Program Interval 3 & Ten Yr NDE Program ML20195H8761998-11-0505 November 1998 Rev 23 to AR-302, Esb Annunciator Response ML20155F4021998-10-30030 October 1998 Proposed Revised Improved Tech Specs (ITS) Section 5.6.2.19, ITS Section 3.4.11,Bases 3.4.11 & 3.4.3 Re PTLR & LTOP Limits 1999-09-02
[Table view] |
Text
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l TECHNICAL SPECIFICATION CHANGE REQUEST NO. 53, REVISION 1 Replace pages 3/4 3-2,3/4 3-3, 3/4 3-8, and 3/410-2 of Appendix A with the attached corresponding revised pages.
PROPOSED CHANGES
- 1) On page 3/4 3-2: Add note reference (c) to item 4 under APPLICABLE MODES.
- 2) On page 3/4 3-3: Add note (c) which reads, "See Special Test Exception 3.10.2."
- 3) On page 3/43-8: To item 2, add the sentence, " Adjust channel if absoluti.
difference is greater than or equal to 2 percent."
- 4) On page 3/4 3-8: Revise item 3 to read, " Compare incore to out-of-core measured AXIAL POWER IMBALANCE above 30% RATED THERMAL POWER. Recalibrate if absolute difference is greater than or equal to 3.5 percent.
- 5) On page 3/4 10-2: Revise Technical Specification 3.10.2 to read, "The limitations of Specifications 3.1.1.3, 3.1.3.1, 3.1.3.2, 3.1.3.5, 3.1.3.6, 3.1.3.7 and 3.3.1.1 (Item 4)may be suspended during the performance of PHYSICS TEST provided:"
REASON FOR PROPOSED CHANGES The existing surveillance procedure for verifying Nuclear Instrumentation (NI) calibration against heat balance is excessively restrictive. It requires calibration of the NI channel if the absolute difference between heat balance and NI output is greater than or equal to 2% The time period presently allowed to complete the calibration is I hour; then plant shutdown must begin. This change allows the channel to be adjusted to agree with heat balance, rather than be recalibrated, if the absolute difference is greater than or equal to 2% Surveillance procedures may be more restrictive than the 2% limit allowed by Technical Specifications in order to maintain economic benefits associated with a more precise NI adjustment.
SAFETY ANALYSIS OF PROPOSED CHANGE Adjustment of an NI channel will compensate for core variation thereby assuring accurate indication and trip functions. Required periodic calibration of the channel will maintain its integrity. This change is consistent with the original accident analysis assumptions in the CR-3 Final Safety Analysis Report. This is not an unreviewed safety question, and the health and safety of the plant personnel and the public are not affected.
4 8211230142 821119 PDR ADOCK 05000302 P PDR i - -.
g TABLE 3.3-1
- c j REACTOR PROTECTION SYSTEM INSTRUMENTATION
-t
% MINIMUM
- e TOTAL NO. CHANNELS CHANNELS APPLICABLE E FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION rn f 1. Manual Reactor Trip 1 1 1 1, 2 and
- 3 E 2. Nuclear Overpower 4 2 3 1, 2 2#
'"i 3. RCS Outlet Temperature-High 4 2 3 1,2 3#
- 4. Nuclear Overpower Based on RCS Flow and AXIAL POWER IMBALANCE 4 2(a) 3 1,2(c) 2# I
- 5. RCS Pressure-Low 4 2(a) 3 1, 2 3#
- 6. RCS Pressure--High 4 2 3 1, 2 3#
- 7. Variable Low RCS Pressure 4 2(a) 3 1, 2 3#
Y 8. Reactor Containment Pressure-High 4 2 3 1, 2 3#
- 9. Intermediate Range, Neutron Flux and Rate 2 0 2 1, 2 and
- 10. Source Range, Neutron Flux and Rate A. Startup 2 0 2 2## and
- 5 B. Shutdown 2 0 1 3,4 and 5 6
- 11. Control Rod Drive Trip Breakers 2 per trip 1 per trip 2 per trip 1, 2 and
system system system
- 12. Reactor Trip Module 2 per trip 1 per trip 2 per trip 1, 2 and
system system system
- 13. Shutdown Bypass RCS Pressure-High 4 2 3 2**,3** 6#
4**,5**
- 14. Reactor Coolant Pump Power Monitors 2 per pump 1 from 2 or 2 per pump 1, 2 25 more pumps (a,b)
TABLE 3.3-1 (Cantinued)
TABLE NOTATION With the control rod drive trip breakers in the closed position and the control rod drive system capable of rod withdrawal.
- When Shutdown Bypass is actuated.
- The provisions of Specification 3.0.4 are not cpplicable.
- High voltage to detector may be de-energized above 10-10 amps on both Intermediate Range channels.
(a) Trip may be manual:y bypassed when RCS pressure 1720 psig by actuating Shutdown Bypass provided that:
(1) The Nuclear Overpower Trip Setpoint is 5% of RATED THERMAL POWER, (2) The Shutdown Bypass RCS Pressure-High Trip Setpoint of 1720 psig is imposed, and (3) The Shutdown Bypass is removed when RCS pressure 1800 psig.
(b) Trip may be manually bypassed when reactor power is less than or equal to 2475 MWt and 4 reactor coolant pumps are operating.
(c) See Special Test Exception 3.10.2. l ACTION STATEMENTS ACTION 1 - With the nurober of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least 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 /> and/or open the control rod drive trip breakers.
ACTION 2 - With the number of OPERABLE channels orie less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided all of the following conditions are satisfied:
- a. The inoperable channel is placed in the tripped condition within one hour.
- b. The Minimum Channels OPERABLE requirement is met; however, one additional channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.1.1.
CRYSTAL RIVER - UNIT 3 3/43-3
TABLE 4.3-1 (Continued)
NOTATION
- With any control rod drive trip breaker closed.
- - When Shutdown Bypass is actuated.
(1) - If not performed in previous 7 days.
(2) - Heat balance only, above 15% of RATED THERMAL POWER. Adjust channel if absolute difference is greater than or equal to 2 percent.
(3) - Compare incore to out-of-core measured AXIAL POWER IMBALANCE above 30% of RATED THERMAL POWER. Recalibrate if absolute difference is greater than or equal to 3.5 percent.
(4) - AXIAL POWER IMBALANCE and loop flow indications only.
(5) - Verify at least one decade overlap if not verified in previous 7 days.
(6) - Each train tested every other month.
(7) - Neutron detectors may be excluded from CHANNEL CALIBRATION.
(S) - Flow rate measurement sensors may be excluded from CHANNEL CALIBRATION. However, each flow measurement sensor shall be calibrated at least once per 13 months.
1 CRYSTAL RIVER - UNIT 3 3/43-8
SPECIAL TEST EXCEPTIONS PHYSICS TESTS LIMITING CONDITION FOR OPERATION 3.10.2 The limitations of Specifications 3.1.1.3, 3.1.3.1, 3.1.3.2, 3.1.3.5, 3.1.3.6, 3.1.3.7, and 3.3.1.1 (Item 4) may be suspended during the performance of l PHYSICS TESTS provided:
- a. The THERMAL POWER does not exceed 5% of RATED THERMAL POWER, and
- b. The reactor trip setpoints on the OPERABLE Nuclear Overpower Channels are set at 6 25% of RATED THERMAL POWER.
- c. The nuclear instrumentation Source Range and Intermediate Range high startup rate control rod withdrawal inhibit are OPERABLE.
APPLICABILITY: MODE 2.
ACTION:
With the THERMAL POWER > 5% of RATED THERMAL POWER, immediately open the control rod drive trip breakers.
SURVEILLANCE REQUIREMLNTS 4.10.2.1 The THERMAL POWER shall be determined to be .4 5% of RATED THERMAL POWER at least once per hour during PHYSICS TESTS.
4.10.2.2 Each Source and Intermediate Range and Nuclear Overpower Channel shall be subjected to a CHANNEL FUNCTIONAL TEST within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to initiating PHYSICS TESTS.
CRYSTAL RIVER - UNIT 3 3/4 10-2