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MONTHYEARML0704605842007-03-21021 March 2007 Issuance of Amendment No. 182 Revision to Technical Specifications for Use of Beacon Power Distribution Monitoring System Project stage: Approval ML0706803502007-03-21021 March 2007 License and Technical Specification Pages - Amendment No. 182 Revision to Technical Specifications for Use of Beacon Power Distribution Monitoring System Project stage: Other 2007-03-21
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Category:Technical Specification
MONTHYEARULNRC-06827, Supplement to License Amendment Request Regarding Support System Requirements for Residual Heat Removal and Control Room Air Conditioning Systems Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029)2023-11-20020 November 2023 Supplement to License Amendment Request Regarding Support System Requirements for Residual Heat Removal and Control Room Air Conditioning Systems Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029) ML23310A0512023-11-0606 November 2023 EIP-ZZ.OO1O1, Addendum 2, Revision 22, Emergency Action Level Technical Bases Document ML23227A1272023-08-15015 August 2023 Corrected Proposed Technical Specification 55.16 Changes (Markup) ML23227A1282023-08-15015 August 2023 Corrected Proposed Technical Specification 5.5.16 Changes (Clean Pages) ML23206A2252023-07-25025 July 2023 Corrected Proposed Technical Specification 5.5.16 Changes (Clean Pages) ML23206A2242023-07-25025 July 2023 Corrected Proposed Technical Specification 5.5.16 Changes (Markup) ML23093A0952023-05-10010 May 2023 Issuance of Amendment No. 232 Regarding Technical Specification Changes for Spent Fuel Storage ML23088A1222023-03-29029 March 2023 Attachment 2: Revised (Clean) Technical Specification Pages ML23088A1232023-03-29029 March 2023 Attachment 3: Marked-Up Technical Specification, Bases Pages ML23088A1212023-03-29029 March 2023 Attachment 1: Marked-Up Technical Specification Pages ML23088A2542023-03-23023 March 2023 EIP-ZZ-00101, Addendum 2, Revision 020, Emergency Action Level Technical Bases Document ML23052A0472023-02-21021 February 2023 Enclosure 5 - Revised Technical Specification Bases (for Information Only) ML23067A1832022-12-29029 December 2022 Rev. 18 to Technical Specification, Bases Change, Table of Contents ML23067A1752022-12-29029 December 2022 Rev. 18 to Technical Specification, Bases Change, Chapter 3.3, Instrumentation ML23067A1762022-12-29029 December 2022 Rev. 18 to Technical Specification Bases, Chapter 3.5, Emergency Core Cooling System S(Eccs) ML23067A1742022-12-29029 December 2022 Rev. 18 to Technical Specifications, Bases Change, Chapter 3.7, Plant Systems ML23067A1772022-12-29029 December 2022 Rev. 18 to Technical Specification Bases Change, Chapter B3, Safety Limits (Sls) ML23067A1782022-12-29029 December 2022 Rev. 18 to Technical Specification, Bases Change, Chapter 3.6, Containment Systems ML23067A1852022-12-29029 December 2022 Rev. 18 to Technical Specification, Bases Change, Chapter B 3.9, Refueling Operations ML23067A1842022-12-29029 December 2022 Rev. 18 to Technical Specification, Bases Change, Chapter 3.4, Reactor Coolant System ML23067A1822022-12-29029 December 2022 Rev. 18 to Technical Specification, Bases Change, Chapter 3.8, Electrical Power Systems ML23067A1792022-12-29029 December 2022 Rev. 18 to Technical Specification Bases, Implemented Change Notice Log ULNRC-06782, Rev. 18 to Technical Specification Bases, List of Effective Sections2022-12-29029 December 2022 Rev. 18 to Technical Specification Bases, List of Effective Sections ML23067A1802022-12-29029 December 2022 Rev. 18 to Technical Specification Bases, Chapter 3.1, Reactivity Control Systems ML23067A1812022-12-29029 December 2022 Rev. 18 to Technical Specification, Bases Change, Chapter B2, Safety Limits (Sls) ML23067A1862022-12-29029 December 2022 Rev. 18 to Technical Specification, Bases Change, Chapter 3.2, Power Distribution Limits ML22335A5092022-12-0101 December 2022 Description and Assessment of the Proposed Change ML22335A5112022-12-0101 December 2022 Attachment 2 - Proposed TS Bases Changes (Markups) ML22307A3142022-11-0303 November 2022 Attachment 2: Proposed Technical Specification 5.5.16 Changes (Markup) ML22307A3152022-11-0303 November 2022 Attachment 3: Proposed Technical Specification 5.5.16 Changes (Clean Pages) ML22285A1202022-10-12012 October 2022 Attachment 3 to Enclosure 1: Marked-Up Technical Specifications Bases (for Information Only) ML22251A3452022-09-0808 September 2022 Attachment 2: Retyped TS Pages for TS 3.6.8 ML22242A1262022-08-29029 August 2022 Attachment 2 to Enclosure 1 - Revised Clean Technical Specifications ML22242A1272022-08-29029 August 2022 Attachment 3 to Enclosure 1 - Marked-Up Technical Specification Bases ML22242A1252022-08-29029 August 2022 Attachment 1 to Enclosure 1 - Marked-Up Existing Technical Specifications ML22216A2422022-08-0404 August 2022 Proposed Technical Specification Changes (Mark-Up) ML22181B1342022-06-30030 June 2022 Attachment 4 - Replacement for Attachment 4, Proposed Changes to Technical Specification Bases Changes (Mark-Up) Pages (for Information), of ULNRC-06688 ML22153A1792022-06-0202 June 2022 Attachment 3 - Marked-Up Technical Specifications Bases ULNRC-06686, Attachment 4: Proposed Technical Specifications Bases Changes (Mark-Up)2021-12-0909 December 2021 Attachment 4: Proposed Technical Specifications Bases Changes (Mark-Up) ML21335A4572021-12-0101 December 2021 Enclosure 5: Proposed Technical Specification Bases Changes (Mark-up - for Info Only) ML21294A4102021-10-21021 October 2021 Enclosure 10 - Program Implementation ML21294A4112021-10-21021 October 2021 Enclosure 11 - Monitoring Program ML21294A4092021-10-21021 October 2021 Enclosure 9 - Key Assumptions and Sources of Uncertainty ML21294A4122021-10-21021 October 2021 Enclosure 12 - Risk Management Action Examples ML21294A4072021-10-21021 October 2021 Enclosure 7 - PRA Model Update Process ML21294A4062021-10-21021 October 2021 Enclosure 6 - Justification of Application of At-Power PRA Models to Shutdown Modes ML21294A4052021-10-21021 October 2021 Enclosure 5 - Baseline Core Damage Frequency (CDF) and Large Early Release Frequency (LERF) ML21294A4042021-10-21021 October 2021 Enclosure 4 - Information Supporting Justification of Excluding Sources of Risk Not Addressed by the PRA Models ML21294A4032021-10-21021 October 2021 Enclosure 3 - Information Supporting Technical Adequacy of PRA Models Without PRA Standards Endorsed by Regulatory Guide 1.200, Revision 2 ML21294A4082021-10-21021 October 2021 Enclosure 8 - Attributes of the Real Time Risk Model 2023-08-15
[Table view] Category:Amendment
MONTHYEARML23206A2242023-07-25025 July 2023 Corrected Proposed Technical Specification 5.5.16 Changes (Markup) ML23206A2252023-07-25025 July 2023 Corrected Proposed Technical Specification 5.5.16 Changes (Clean Pages) ML23093A0952023-05-10010 May 2023 Issuance of Amendment No. 232 Regarding Technical Specification Changes for Spent Fuel Storage ML23088A1222023-03-29029 March 2023 Attachment 2: Revised (Clean) Technical Specification Pages ML23088A1212023-03-29029 March 2023 Attachment 1: Marked-Up Technical Specification Pages ML22251A3452022-09-0808 September 2022 Attachment 2: Retyped TS Pages for TS 3.6.8 ML22242A1262022-08-29029 August 2022 Attachment 2 to Enclosure 1 - Revised Clean Technical Specifications ML22242A1252022-08-29029 August 2022 Attachment 1 to Enclosure 1 - Marked-Up Existing Technical Specifications ML21294A3992021-10-21021 October 2021 Attachment 5 - Cross-Reference of TSTF-505 and Callaway Technical Specifications ML21294A4122021-10-21021 October 2021 Enclosure 12 - Risk Management Action Examples ML21294A4102021-10-21021 October 2021 Enclosure 10 - Program Implementation ML21294A4112021-10-21021 October 2021 Enclosure 11 - Monitoring Program ML21294A4092021-10-21021 October 2021 Enclosure 9 - Key Assumptions and Sources of Uncertainty ML21294A4082021-10-21021 October 2021 Enclosure 8 - Attributes of the Real Time Risk Model ML21294A4072021-10-21021 October 2021 Enclosure 7 - PRA Model Update Process ML21294A4062021-10-21021 October 2021 Enclosure 6 - Justification of Application of At-Power PRA Models to Shutdown Modes ML21294A4052021-10-21021 October 2021 Enclosure 5 - Baseline Core Damage Frequency (CDF) and Large Early Release Frequency (LERF) ML21294A4042021-10-21021 October 2021 Enclosure 4 - Information Supporting Justification of Excluding Sources of Risk Not Addressed by the PRA Models ML21294A4032021-10-21021 October 2021 Enclosure 3 - Information Supporting Technical Adequacy of PRA Models Without PRA Standards Endorsed by Regulatory Guide 1.200, Revision 2 ML21294A4022021-10-21021 October 2021 Enclosure 2 - Information Supporting Consistency with Regulatory Guide 1.200, Revision 2 ML21294A4012021-10-21021 October 2021 Enclosure 1 - List of Revised Required Actions to Corresponding PRA Functions ML21294A4002021-10-21021 October 2021 Attachment 6 - Description and Assessment Specific to TSTF-439 ML21294A3972021-10-21021 October 2021 Attachment 3 - Revised Technical Specification Pages ML21294A3962021-10-21021 October 2021 Attachment 2 - Proposed Technical Specification Changes (Mark-Up) ML21294A3952021-10-21021 October 2021 Attachment 1 - Description and Assessment ML20070R1212020-03-10010 March 2020 Technical Specification Page Markup ML20070R1142020-03-10010 March 2020 Description and Assessment of the Proposed Change ULNRC-06433, License Amendment Request for Emergency Action Level (EAL) Changes2018-09-0404 September 2018 License Amendment Request for Emergency Action Level (EAL) Changes ULNRC-06264, Revision of TS 2.1.1.1 and 5.6.5 to Remove Uncertainties from the DNBR Safety Limit and Adopt Approved WCAP-14565-P-A Methodology2015-11-0909 November 2015 Revision of TS 2.1.1.1 and 5.6.5 to Remove Uncertainties from the DNBR Safety Limit and Adopt Approved WCAP-14565-P-A Methodology ML15062A0522015-03-0606 March 2015 NRC-Callaway-TS-renewed License ULNRC-05832, Revision of Technical Specification 3.3.8, TAC No. ME51732011-12-13013 December 2011 Revision of Technical Specification 3.3.8, TAC No. ME5173 ML1130706942011-11-0303 November 2011 Attachment 5 - Control Building Room Locations and P&ID Excerpts ML1130706832011-11-0303 November 2011 Attachment 1 - Technical Specification Page Mark Up ML1130706812011-11-0303 November 2011 Enclosure Page 1 of 22, Evaluation of the Proposed Change ULNRC-05804, Facility Operating License NPF-30 - Proposed Revision to Technical Specification 3.6.6, Containment Spray and Cooling Systems, (License Amendment Request LDCN 09-0025)2011-06-30030 June 2011 Facility Operating License NPF-30 - Proposed Revision to Technical Specification 3.6.6, Containment Spray and Cooling Systems, (License Amendment Request LDCN 09-0025) ULNRC-05793, Application for Amendment to Facility Operating License NPF-30 (LDCN 10-0036) Revision of Technical Specification 3.3.8,2011-06-16016 June 2011 Application for Amendment to Facility Operating License NPF-30 (LDCN 10-0036) Revision of Technical Specification 3.3.8, ULNRC-05682, Application for Amendment, Revision of Technical Specification 3.3.92010-03-0404 March 2010 Application for Amendment, Revision of Technical Specification 3.3.9 ULNRC-05560, Revision of Technical Specifications 3.8.4 and 3.8.5, Application for Amendment to Facility Operating License NPF-30 (LDCN 08-002)2008-12-29029 December 2008 Revision of Technical Specifications 3.8.4 and 3.8.5, Application for Amendment to Facility Operating License NPF-30 (LDCN 08-002) ML0824602412008-11-24024 November 2008 Issuance of Amendment No. 187, Revise Technical Specification 5.5.8, Inservice Testing Program, Testing Frequencies ULNRC-05494, Application for Amendment to Facility Operating License NPF-30 OL1283 - Revision of Technical Specifications 3.3, 3.7, and 3.82008-06-0303 June 2008 Application for Amendment to Facility Operating License NPF-30 OL1283 - Revision of Technical Specifications 3.3, 3.7, and 3.8 ML0706803502007-03-21021 March 2007 License and Technical Specification Pages - Amendment No. 182 Revision to Technical Specifications for Use of Beacon Power Distribution Monitoring System ML0632801852006-11-17017 November 2006 Callaway - Proposed Revision to Technical Specification 3.9.2 Unborated Water Source Isolation Valves and Associated Revisions to Technical Specification 3.3.9 Boron Dilution Mitigation System (Bdms) (License Amendment Request OL 1238) ULNRC-05345, Proposed Revision to Technical Specification 3.9.2 Unborated Water Source Isolation Valves and Associated Revisions to Technical Specification 3.3.9 Boron Dilution Mitigation System (Bdms).2006-11-17017 November 2006 Proposed Revision to Technical Specification 3.9.2 Unborated Water Source Isolation Valves and Associated Revisions to Technical Specification 3.3.9 Boron Dilution Mitigation System (Bdms). ULNRC-05314, Exigent Request for Revision to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation.2006-07-19019 July 2006 Exigent Request for Revision to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation. ULNRC-05301, Proposed Revision to Technical Specification TSs 3.7.10, 3.7.11 and 3.7.132006-06-0707 June 2006 Proposed Revision to Technical Specification TSs 3.7.10, 3.7.11 and 3.7.13 ULNRC-05297, Proposed Revision to Technical Specifications for Use of Beacon Power Distribution Monitoring System2006-05-25025 May 2006 Proposed Revision to Technical Specifications for Use of Beacon Power Distribution Monitoring System ULNRC-05269, Proposed Revision to Technical Specification 3.9.2 Unborated Water Source Isolation Valves and Associated Revisions to Technical Specification 3.3.9 Boron Dilution Mitigation System (Bdms) (License Amendment Request OL 1238)2006-03-28028 March 2006 Proposed Revision to Technical Specification 3.9.2 Unborated Water Source Isolation Valves and Associated Revisions to Technical Specification 3.3.9 Boron Dilution Mitigation System (Bdms) (License Amendment Request OL 1238) ULNRC-05206, License Amendment Request OL 1258 Revision to Technical Specification 3.7.3, Main Feedwater Isolation Valves (Mfiv'S)2005-09-0909 September 2005 License Amendment Request OL 1258 Revision to Technical Specification 3.7.3, Main Feedwater Isolation Valves (Mfiv'S) ML0506903182005-03-0808 March 2005 Technical Specification Pages Re Elimination of Requirements to Provide Monthly Operating Reports & Annual Occupational Radiation Exposure Reports ULNRC-05117, Technical Specification Revisions Associated with the Steam Generator Replacement Project2005-02-11011 February 2005 Technical Specification Revisions Associated with the Steam Generator Replacement Project 2023-07-25
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(4) U E, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source of special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) UE, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level UE is authorized to operate the facility at reactor core power levels not in excess of 3565 megawatts thermal (100% power) in accordance with the conditions specified herein.
(2) Technical Specifications and Environmental Protection Plan*
The Technical Specifications contained in Appendix A, as revised through Amendment No. 182 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3) Environmental Qualification (Section 3.11. SSER #3) **
Deleted per Amendment No. 169 Amendments 133, 134, &135 were effective as of April 30, 2000 however these amendments were implemented on April 1, 2000.
The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.
Amendment 182
Rod Position Indication 3.1.7 3.1 REACTIVITY CONTROL SYSTEMS 3.1.7 Rod Position Indication LCO 3.1.7 The Digital Rod Position Indication (DRPI) System and the Demand Position Indication System shall be OPERABLE.
APPLICABILITY: MODES 1 and 2.
ACTIONS
NOTE-------------------------------
Separate Condition entry is allowed for each inoperable rod position indicator and each demand position indicator.
COMPLETION CONDITION REQUIRED ACTION TIME TIME A. One DRPI per group A.1 Verify the position of the Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> inoperable for one or more rods with inoperable groups. position indicators indirectly by using core power distribution measurement information.
OR A.2 Reduce THERMAL 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> POWER to
(continued)
CALLAWAY PLANT 3.1-16 Amendment No. 182
Rod Position Indication 3.1.7 ACTIONS (continued)
COMPLETION REQUIRED ACTION TIME CONDITION TIME B. More than one DRPI per B.1 Place the control rods Immediately group inoperable for one or under manual control.
more groups.
AND B.2 Monitor and record RCS Once per 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Tavg.
AND B.3 Verify the position of the Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> rods with inoperable position indicators indirectly by using core power distribution' measurement information.
AND B.4 Restore inoperable 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> position indicators to OPERABLE status such that a maximum of one DRPI per group is inoperable.
C. One or more rods with C.1 Verify the position of the 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> inoperable DRPIs have rods with inoperable been moved in excess of 24 position indicators steps in one direction since indirectly by using core the last determination of the power distribution rod's position. measurement information.
OR C.2 Reduce THERMAL 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> POWER to _ 50% RTP.
(continued)
CALLAWAY PLANT 3.1-17 Amendment No. 182
FQ(Z) (FQ Methodology) 3.2.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.2.1.2 NUll------------------------------
If Fc(Z) measurements indicate z FZ)]
maximum over has increased since the previous evaluation of F&(Z)
- a. Increase F '(Z) by the appropriate factor specified in the COLR and reverify Fw(Z) is within limits; or
- b. Repeat SR 3.2.1.2 once per 7 EFPD until two successive power distribution measurements I indicate
[FF(Z)]
K(Z) J maximum over z has not increased.
Verify Fw(Z) is within limit Once after each refueling prior to THERMAL POWER exceeding 75%
RTP AND (continued)
CALLAWAY PLANT 3.2-4 Amendment No. 182
QPTR 3.2.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.4.1 ----------------------- NOTE ---------------
- 1. With input from one Power Range Neutron Flux channel inoperable and THERMAL POWER
< 75% RTR the remaining three power range channels can be used for calculating QPTR.
- 2. SR 3.2.4.2 may be performed in lieu of this Surveillance.
Verify QPTR is within limit by calculation. 7 days SR 3.2.4.2 ---------- ----- NOTE ---------------
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after input from one or more Power Range Neutron Flux channels are inoperable with THERMAL POWER
> 75% RTP.
Verify QPTR is within limit using power distribution 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> measurement information. I CALLAWAY PLANT 3.2-13 Amendment No. 182
RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS I............------------- NOTE-------------------------------
Refer to Table 3.3.1 1 to determine which SRs apply for each RTS Function.
SURVEILLANCE FREQUENCY SR 3.3.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.1.2 ----------------------- NOTE ----------------
Not required to be performed until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after THERMAL POWER is > 15% RTP.
Compare results of calorimetric heat balance 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> calculation to power range channel output. Adjust power range channel output if calorimetric heat balance calculation results exceed power range channel output by more than +2% RTP.
SR 3.3.1.3 ------------------ NOTE ---------------
Not required to be performed until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after THERMAL POWER is > 50% RTP.
Compare results of incore power distribution 31 effective full I measurements to Nuclear Instrumentation System power days (NIS) AFD. Adjust NIS channel if absolute difference (EFPD) is Ž 2%.
(continued)
CALLAWAY PLANT 3.3-12 Amendment No. 182
RTS Instrumentation 3.3.1 SURVEILLANCE FREQUENCY SR 3.3.1.4 ----------------------- NOTE ---------------
This Surveillance must be performed on the reactor trip bypass breaker for the local manual shunt trip only prior to placing the bypass breaker in service.
Perform TADOT. 62 days on a STAGGERED TEST BASIS SR 3.3.1.5 Perform ACTUATION LOGIC TEST. 92 days on a STAGGERED TEST BASIS SR 3.3.1.6 ----------------------- NOTE ---------------
Not required to be performed until 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after achieving equilibrium conditions with THERMAL POWER > 75 % RTP.
Calibrate excore channels to agree with incore power 92 EFPD distribution measurements. I SR 3.3.1.7 ----------------------- NOTE ---------------
- 1. Not required to be performed for source range instrumentation prior to entering MODE 3 from MODE 2 until 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after entry into MODE 3.
- 2. Source range instrumentation shall include verification that interlocks P-6 and P-10 are in their required state for existing unit conditions.
Perform COT. 184 days (continued)
CALLAWAY PLANT 3.3-13 Amendment No. 182