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Category:Technical Specification
MONTHYEARRA-23-0279, Supplement to Application to Adopt Risk-Informed Completion Times TSTF-505, Revision 2 and Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power2023-11-0202 November 2023 Supplement to Application to Adopt Risk-Informed Completion Times TSTF-505, Revision 2 and Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power RA-18-0190, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-02-16016 February 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RA-22-0091, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2023-02-16016 February 2023 Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RA-22-0118, License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies2023-02-0101 February 2023 License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies RA-22-0080, Independent Spent Fuel Storage Installation, McGuire, Units 1 & 2, Independent Spent Fuel Storage Installation, Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System2022-04-0707 April 2022 Independent Spent Fuel Storage Installation, McGuire, Units 1 & 2, Independent Spent Fuel Storage Installation, Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System RA-21-0302, Application to Revise Technical Specifications to Adopt TSTF-569, Rev. 2, Revise Response Time Testing Definition2022-02-24024 February 2022 Application to Revise Technical Specifications to Adopt TSTF-569, Rev. 2, Revise Response Time Testing Definition RA-20-0107, Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2022-01-18018 January 2022 Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position RA-21-0027, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2021-09-16016 September 2021 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections RA-20-0207, Duke Energy - Application to Revise the Technical Specification for Engineered Safety Feature Actuation System (ESFAS) Instrumentation2020-12-0303 December 2020 Duke Energy - Application to Revise the Technical Specification for Engineered Safety Feature Actuation System (ESFAS) Instrumentation RA-19-0006, License Amendment Application to Relocate Technical Specification Unit/Facility Staff Qualification ANSI N18.1-1971, ANSI/ANS-3.1-1978 and ANSI/ANS-3.1-1981 Requirements to the Duke Energy Corporation Quality Assurance Program Description2019-07-0808 July 2019 License Amendment Application to Relocate Technical Specification Unit/Facility Staff Qualification ANSI N18.1-1971, ANSI/ANS-3.1-1978 and ANSI/ANS-3.1-1981 Requirements to the Duke Energy Corporation Quality Assurance Program Description RA-18-0232, Proposed Editorial Error Correction of Technical Specification (TS) 3.0, Surveillance Requirement Applicability, SR 3.0.5 and Proposed Removal of Expired TS Footnotes from the MNS2019-02-0505 February 2019 Proposed Editorial Error Correction of Technical Specification (TS) 3.0, Surveillance Requirement Applicability, SR 3.0.5 and Proposed Removal of Expired TS Footnotes from the MNS RA-18-0166, Supplement to Non-Voluntary License Amendment Request (LAR) to Correct Non-Conservative Technical Specification 3.4.11 - PORVs2018-09-13013 September 2018 Supplement to Non-Voluntary License Amendment Request (LAR) to Correct Non-Conservative Technical Specification 3.4.11 - PORVs ML18191A5452018-07-10010 July 2018 Attachment 2 - McGuire Technical Specification 3.8.1 Bases Marked Up Pages RA-18-001, Attachment 2 - McGuire Technical Specification 3.8.1 Bases Marked Up Pages2018-07-10010 July 2018 Attachment 2 - McGuire Technical Specification 3.8.1 Bases Marked Up Pages RA-18-000, Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications2018-05-10010 May 2018 Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications RA-18-0001, Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - License Amendment Application to Remove Heaters from Ventilation System Technical Specifications2018-05-10010 May 2018 Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - License Amendment Application to Remove Heaters from Ventilation System Technical Specifications ML18130A8072018-05-10010 May 2018 Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications RA-17-0005, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing2017-11-0707 November 2017 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing RA-17-0045, Supplement: Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules.2017-10-12012 October 2017 Supplement: Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules. ML17237A0492017-08-17017 August 2017 Technical Specification Bases - List of Effected Sheets ML17237A0482017-08-17017 August 2017 Technical Specification Bases (Rev. 150) ML17237A0462017-08-17017 August 2017 Document Transmittal Form Regarding Technical Specification Changes - Amendment Nos. 296/275 ML17186A0682017-06-26026 June 2017 Tech Spec Bases - List of Affected Sections ML17186A0672017-06-26026 June 2017 Revision 151 to Tech Spec Bases - B 3.6.13 and B 3.6.14 ML17186A0662017-06-26026 June 2017 TS 3.6.13 Amendment 292/271 and TS 3.6.14 Amendment 294/273 ML17186A0692017-06-26026 June 2017 Issue Tech Spec - List of Affected Pages ML17136A2792017-05-0303 May 2017 Technical Specification Leep, Rev. 109 ML17136A2782017-05-0303 May 2017 Technical Specification Bases - Loes, Rev. 133 ML17136A3612017-05-0303 May 2017 Technical Specification Bases, Revision 149 ML17136A3602017-05-0303 May 2017 Technical Specification Amendment Nos. 285/264 ML17124A3682017-04-19019 April 2017 Tech Spec Bases List of Effected Pages ML17124A3712017-04-19019 April 2017 Bases B 3.5.1 - Accumulators ML17094A6722017-03-29029 March 2017 Issue Selected License Commitment Cslcl 16.7.14 Revision ML17094A6732017-03-29029 March 2017 Issue SLC List of Effected Pages ML17090A4522017-03-23023 March 2017 Revision to Technical Specification 3.3.2 - Amendment 293/272 ML17090A4512017-03-23023 March 2017 Revision to Technical Specification 3.8.1 - Amendment 293/272 ML17090A4352017-03-22022 March 2017 Technical Specification Bases ML17090A4502017-03-22022 March 2017 Revision to Technical Specification Bases - B 3.6.15 ML17094A6702017-03-15015 March 2017 Issue MNS-SLC-16.9.15. Snubbers MNS-16-092, License Amendment Request to Revise Technical Specifications Section 5.5.2, Containment Leakage Rate Testing Program for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2016-12-19019 December 2016 License Amendment Request to Revise Technical Specifications Section 5.5.2, Containment Leakage Rate Testing Program for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML16305A1442016-10-20020 October 2016 Issue MNS Technical Specification 5.5 RA-16-0019, Duke Energy Progress - Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Proces2016-09-27027 September 2016 Duke Energy Progress - Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Process ML16265A5312016-08-30030 August 2016 Issue MNS Tech Spec Bases List of Effective Sections ML16265A5322016-08-30030 August 2016 Technical Specification Bases 3.6.14 Revisions, List of Revisions and Dates ML16250A0142016-08-29029 August 2016 Amendment 287 ML16243A3492016-08-23023 August 2016 Mccguire, Units 1 and 2, Revision 143 to Issue MNS Technical Specification Bases 3.3.1 ML16243A3482016-08-23023 August 2016 Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation. ML16243A3512016-08-23023 August 2016 Revision 105 to Technical Specifications List of Effective Pages ML16243A3502016-08-23023 August 2016 Revision 129 to Technical Specification Bases ML16243A3572016-08-18018 August 2016 Technical Specification Bases Revision 001, List of Revised Sections 2023-02-16
[Table view] Category:Bases Change
MONTHYEARRA-23-0279, Supplement to Application to Adopt Risk-Informed Completion Times TSTF-505, Revision 2 and Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power2023-11-0202 November 2023 Supplement to Application to Adopt Risk-Informed Completion Times TSTF-505, Revision 2 and Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power RA-22-0091, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2023-02-16016 February 2023 Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RA-22-0118, License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies2023-02-0101 February 2023 License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies RA-21-0302, Application to Revise Technical Specifications to Adopt TSTF-569, Rev. 2, Revise Response Time Testing Definition2022-02-24024 February 2022 Application to Revise Technical Specifications to Adopt TSTF-569, Rev. 2, Revise Response Time Testing Definition RA-20-0107, Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2022-01-18018 January 2022 Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position RA-18-0232, Proposed Editorial Error Correction of Technical Specification (TS) 3.0, Surveillance Requirement Applicability, SR 3.0.5 and Proposed Removal of Expired TS Footnotes from the MNS2019-02-0505 February 2019 Proposed Editorial Error Correction of Technical Specification (TS) 3.0, Surveillance Requirement Applicability, SR 3.0.5 and Proposed Removal of Expired TS Footnotes from the MNS RA-18-0166, Supplement to Non-Voluntary License Amendment Request (LAR) to Correct Non-Conservative Technical Specification 3.4.11 - PORVs2018-09-13013 September 2018 Supplement to Non-Voluntary License Amendment Request (LAR) to Correct Non-Conservative Technical Specification 3.4.11 - PORVs ML18191A5452018-07-10010 July 2018 Attachment 2 - McGuire Technical Specification 3.8.1 Bases Marked Up Pages RA-18-001, Attachment 2 - McGuire Technical Specification 3.8.1 Bases Marked Up Pages2018-07-10010 July 2018 Attachment 2 - McGuire Technical Specification 3.8.1 Bases Marked Up Pages RA-17-0045, Supplement: Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules.2017-10-12012 October 2017 Supplement: Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules. ML17237A0462017-08-17017 August 2017 Document Transmittal Form Regarding Technical Specification Changes - Amendment Nos. 296/275 ML17237A0482017-08-17017 August 2017 Technical Specification Bases (Rev. 150) ML17237A0492017-08-17017 August 2017 Technical Specification Bases - List of Effected Sheets ML17186A0662017-06-26026 June 2017 TS 3.6.13 Amendment 292/271 and TS 3.6.14 Amendment 294/273 ML17186A0672017-06-26026 June 2017 Revision 151 to Tech Spec Bases - B 3.6.13 and B 3.6.14 ML17186A0682017-06-26026 June 2017 Tech Spec Bases - List of Affected Sections ML17186A0692017-06-26026 June 2017 Issue Tech Spec - List of Affected Pages ML17136A3612017-05-0303 May 2017 Technical Specification Bases, Revision 149 ML17136A3602017-05-0303 May 2017 Technical Specification Amendment Nos. 285/264 ML17136A2792017-05-0303 May 2017 Technical Specification Leep, Rev. 109 ML17136A2782017-05-0303 May 2017 Technical Specification Bases - Loes, Rev. 133 ML17124A3682017-04-19019 April 2017 Tech Spec Bases List of Effected Pages ML17124A3712017-04-19019 April 2017 Bases B 3.5.1 - Accumulators ML17094A6722017-03-29029 March 2017 Issue Selected License Commitment Cslcl 16.7.14 Revision ML17094A6732017-03-29029 March 2017 Issue SLC List of Effected Pages ML17090A4522017-03-23023 March 2017 Revision to Technical Specification 3.3.2 - Amendment 293/272 ML17090A4512017-03-23023 March 2017 Revision to Technical Specification 3.8.1 - Amendment 293/272 ML17090A4352017-03-22022 March 2017 Technical Specification Bases ML17090A4502017-03-22022 March 2017 Revision to Technical Specification Bases - B 3.6.15 ML17094A6702017-03-15015 March 2017 Issue MNS-SLC-16.9.15. Snubbers RA-16-0019, Duke Energy Progress - Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Proces2016-09-27027 September 2016 Duke Energy Progress - Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Process ML16265A5312016-08-30030 August 2016 Issue MNS Tech Spec Bases List of Effective Sections ML16265A5322016-08-30030 August 2016 Technical Specification Bases 3.6.14 Revisions, List of Revisions and Dates ML16250A0142016-08-29029 August 2016 Amendment 287 ML16243A3482016-08-23023 August 2016 Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation. ML16243A3502016-08-23023 August 2016 Revision 129 to Technical Specification Bases ML16243A3512016-08-23023 August 2016 Revision 105 to Technical Specifications List of Effective Pages ML16243A3492016-08-23023 August 2016 Mccguire, Units 1 and 2, Revision 143 to Issue MNS Technical Specification Bases 3.3.1 ML16243A3572016-08-18018 August 2016 Technical Specification Bases Revision 001, List of Revised Sections ML16243A3552016-08-17017 August 2016 Renewed Facility Operating License, Amendment 284 ML16243A3522016-08-17017 August 2016 Technical Specification 3.4.18, Amendment Nos. 284/263, Steam Generator (SG) Tube Integrity. ML16243A3542016-08-17017 August 2016 Technical Specification Bases 3.4.18, Revision 144, Steam Generator (SG) Tube Integrity RA-16-0007, Duke Energy Carolinas, LLC, Application to Revise TS to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability Using the Consolidated Line Item Improvement Process2016-06-23023 June 2016 Duke Energy Carolinas, LLC, Application to Revise TS to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability Using the Consolidated Line Item Improvement Process ML16139A5572016-05-10010 May 2016 Technical Specification Bases 3.3.1 Rev. 001, Revision 141 ML16139A5552016-05-10010 May 2016 Technical Specification Bases 3.9.3, Revision 001, Revision 142 MNS-16-020, License Amendment Request Removal of Superseded Technical Specification Requirements2016-05-0505 May 2016 License Amendment Request Removal of Superseded Technical Specification Requirements MNS-16-015, License Amendment Request (LAR) for One-Time Extension of Appendix J Type a Integrated Leakage Rate Test Interval2016-02-18018 February 2016 License Amendment Request (LAR) for One-Time Extension of Appendix J Type a Integrated Leakage Rate Test Interval ML16056A2432016-02-18018 February 2016 Emergency Action Level Technical Bases Document Redline MNS-16-016, Emergency Action Level Technical Bases, Revision 1 Redline. Part 1 of 22016-02-18018 February 2016 Emergency Action Level Technical Bases, Revision 1 Redline. Part 1 of 2 ML16056A2452016-02-18018 February 2016 Emergency Action Level Technical Bases, Revision 1 Redline. Part 2 of 2 2023-02-16
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- 1. AREVA NP2. BLUE DOT LIBRARY3. MCG DOC CNTRL MISC MAN4. MCG OPS PROCEDURE GP5. MCG PLANT ENG. LIBR.6. MCGRPAD PROT7. OPS HUMAN PERFORMANCE
-8. OPS TRNG MGR.9. QATS-10. RESIDENT NRC INSPECT11. SCIENTECH
- CLEARWIR, FL12. SERV BLDG FILE ROOM -13. U S NUC REG WASHINGTON, DC14. USNRC15. WESTINGHOUSE ELECTRIC CO LLCDuke EnergyDOCUMENT TRANSMITTAL FORMFacility:
MCGUIRE NUCLEAR STATIONSUBJECTMNS-TSB-B 3.1.3 RCS MODERATOR TEMPERATURE COEFFICIENT-REV 136Date: 7128/2015 Document Transmittal
- TR-NUC-MC-000332 Purpose:
IssueReleased By:13225 Haaers Ferry RoadDocument Manaaement MGO2MHuntersville, NC 28078MNSDCRMc@duke-eneray.corn Page 1 of 11: DocumentID.
.....41 1 1 18 9 1 ii 213115ILICN -MC -MNS-TSB-B 311.3 -136 -ISSUED "YI YI YI YI YI FIE FIE FIE FIE FIE FY" YI YI YI YIRemarks:
PLEASE DISTRIBUE THIS TO TSB MANUAL HOLDERS REFERENCE TRANSM1T~AL TR-NUC-MC000287---FOR DISTRIBUTION ENTITIES MTCB 3.1.3BASESB 3.1 REACTIVITY CONTROL SYSTEMSB 3.1.3 Moderator Temperature Coefficient (MTC)BASESBACKGROUND According to GDC 11 (Ref. 1), the reactor core and its interaction with theReactor Coolant System (RCS) must be designed for inherently stablepower operation, even in the possible event of an accident.
In particular, the net reactivity feedback in the system must compensate for anyunintended reactivity increases.
The MTC relates a change in core reactivity to a change in reactorcoolant temperature (a positive MTC means that reactivity increases withincreasing moderator temperature; conversely, a negative MTC meansthat reactivity decreases with increasing moderator temperature).
Thereactor is designed to operate with a negative MTC over the largestpossible range of fuel cycle operation.
Therefore, a coolant temperature increase will cause a reactivity
- decrease, so that the coolant temperature tends to return toward its initial value. Reactivity increases that cause acoolant temperature increase will thus be self limiting, and stable poweroperation will result.MTC values are predicted at selected burnups during the safetyevaluation analysis and are confirmed to be acceptable bymeasurements.
Both initial and reload cores are designed so that theMTC is less than zero when THERMAL POWER is at RTP. The actualvalue of the MTC is dependent on core characteristics, such as fuelloading and reactor coolant soluble boron concentration.
The core designmay require additional fixed distributed poisons to yield an MTC at or nearBOC within the range analyzed in the plant accident analysis.
For somedesigns, the burnable absorbers may burn out faster than the fueldepletes early in the cycle. This may cause the boron concentration toincrease with burnup early in the cycle and the most positive MTC not tooccur at BOC but somewhat later in the cycle. For these core designs,the predicted difference between the BOC MTC, and the most positiveMTC is used to adjust the BOC measured MTC to ensure that the MTCremains less than the limit during the entire cycle. The end of cycle (EOC)MTC is also limited by the requirements of the accident analysis.
Fuelcycles that are designed to achieve high burnups or that have changes toother characteristics are evaluated to ensure that the MTC does notexceed the EOC limit.The limitations on MTC are provided to ensure that the value of thiscoefficient remains within the limiting conditions assumed in the UFSARaccident and transient analyses.
McGuire Units 1 and 2 B3131Rvso o 3B3.1.3-1Revision No. 136 MTCB 3.1.3BASESBACKGROUND (continued)
If the LCO limits are not met, the unit response during transients may notbe as predicted.
The core could violate criteria that prohibit a return tocriticality, or the departure from nucleate boiling ratio criteria of theapproved correlation may be violated, which could lead to a loss of thefuel cladding integrity.
The SRs for measurement of the MTC at the beginning and near the endof the fuel cycle are adequate to confirm that the MTC remains within itslimits, since this coefficient changes slowly, due principally to changes inRCS boron concentration associated with fuel and burnable absorberdepletion.
APPLICABLE The acceptance criteria for the specified MTC are:SAFETY ANALYSESa. The MTC values must remain within the bounds of those used inthe accident analysis (Ref. 2); andb. The MTC must be such that inherently stable power operations result during normal operation and accidents, such as overheating and overcooling events.The UFSAR, Chapter 15 (Ref. 2), contains analyses of accidents thatresult in both overheating and overcooling of the reactor core. MTC isone of the controlling parameters for core reactivity in these accidents.
Both the most positive value and most negative value of the MTC areimportant to safety, and both values must be bounded.
Values used inthe analyses consider worst case conditions to ensure that the accidentresults are bounding (Ref. 2).The consequences of accidents that cause core overheating must beevaluated when the MTC is positive.
Such accidents include the rodwithdrawal transient from any power level (Ref. 3), turbine trip, and loss offorced reactor coolant flow. The consequences of accidents that causecore overcooling must be evaluated when the MTC is negative.
Suchaccidents include sudden feedwater flow increase and steam line break.In order to ensure a bounding accident
- analysis, the MTC is assumed tobe its most limiting value for the analysis conditions appropriate to eachaccident.
The bounding value is determined by considering rodded andunrodded conditions, whether the reactor is at full or zero power, andwhether it is the BOC or EOC life. The most conservative combination appropriate to the accident is then used for the analysis (Ref. 2).MTC values are bounded in reload safety evaluations assuming steadystate conditions at BOC and EOC. An EOC measurement orMcGuire Units 1 and 2 B3132Rvso o 3B3.1.3-2Revision No. 136 MTCB83.1.3BASESAPPLICABLE SAFETY ANALYSES (continued) analytical check (Ref. 5) of the EOC MTC is conducted at conditions when the RCS boron concentration reaches approximately 300 ppm. Themeasured or calculated value may be extrapolated to project the EOCvalue, in order to confirm reload design predictions.
MTC satisfies Criterion 2 of 10 CFR 50.36 (Ref. 4). Even though it is notdirectly observed and controlled from the control room, MTC isconsidered an initial condition process variable because of itsdependence on boron concentration.
LCO LCO 3.1.3 requires the MTC to be within specified limits of the COLR toensure that the core operates within the assumptions of the accidentanalysis.
During the reload core safety evaluation, the MTC is analyzedto determine that its values remain within the bounds of the originalaccident analysis during operation.
Assumptions made in safety analyses require that the MTC be lesspositive than a given upper bound and more positive than a given lowerbound. The MTC is most positive at or near BOC; this upper bound mustnot be exceeded.
This maximum upper limit occurs at or near BOC, allrods out (ARO), hot zero power conditions.
For some core designs, theburnable absorbers may burnout faster than the fuel depletes early in thecycle. This may cause the boron concentration to increase with burnupearly in the cycle and the most positive MTC not occur at BOC, butsomewhat later in the cycle. For these core designs, the predicted distance between the BOC MTC, and the most positive MTC is used toadjust the BOC measured MTC to ensure that the MTC remains less thanthe limit during the entire cycle. At EOC the MTC takes on its mostnegative value, when the lower bound becomes important.
This LCOexists to ensure that both the upper and lower bounds are not exceeded.
During operation, the condition of the upper LCO limit at BOC is ensuredthrough measurement.
The lower LCO limit at EOC is ensured eitheranalytically or through measurement.
The Surveillance checks at BOOand EOC on MTC provide confirmation that the MTC is behaving asanticipated so that the acceptance criteria are met.The LCO establishes a maximum positive value that cannot be exceeded.
The BOO positive limit and the EOC negative limit are established in theCOLR to allow specifying limits for each particular cycle. This permits theunit to take advantage of improved fuel management and changes in unitoperating schedule.
McGuire Units 1 and 2 B3133Rvso o 3B 3.1.3-3Revision No. 136 MTCB 3.1.3BASESAPPLICABILITY Technical Specifications place both LCO and SR values on MTC, basedon the safety analysis assumptions described above.In MODE 1, the limits on MTC must be maintained to ensure that anyaccident initiated from THERMAL POWER operation will not violate thedesign assumptions of the accident analysis.
In MODE 2 with the reactorcritical, the upper limit must also be maintained to ensure that startup andsubcritical accidents (such as the uncontrolled control rod assembly orgroup withdrawal) will not violate the assumptions of the accidentanalysis.
The lower MTC limit must be maintained in MODES 2 and 3, inaddition to MODE 1, to ensure that cooldown accidents will not violate theassumptions of the accident analysis.
In MODES 4, 5, and 6, this LCO isnot applicable, since no Design Basis Accidents using the MTC as ananalysis assumption are limiting when initiated from these MODES.ACTIONS A.1If the BOO MTC limit is violated, administrative withdrawal limits forcontrol banks must be established to maintain the MTC within its limits.The MTC becomes more negative with control bank insertion anddecreased boron concentration.
A Completion Time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> providesenough time for evaluating the MTC measurement and computing therequired bank withdrawal limits.Using physics calculations, the time in cycle life at which the calculated MTC will meet the LCO requirement can be determined.
At this point incore life Condition A no longer exists. The unit is no longer in theRequired Action, so the administrative withdrawal limits are no longer ineffect.B.._If the required administrative withdrawal limits at BOC are not established within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the unit must be brought to MODE 2 with keff < 1.0 toprevent operation with an MTC that is more positive than that assumed insafety analyses.
The allowed Completion Time of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> is reasonable, based onoperating experience, for reaching the required MODE from full powerconditions in an orderly manner and without challenging plant systems.C...1Exceeding the EOC MTC limit means that the safety analysisassumptions for the EOC accidents that use a bounding negative MTCvalue may be invalid.
If the EOC MTC limit is exceeded, the plant mustMcGuire Units 1 and 2 B3134Rvso o 3B 3.1.3-4Revision No. 136 MTCB 3.1.3BASESACTIONS (continued) be brought to a MODE or condition in which the LCO requirements arenot applicable.
To achieve this status, the unit must be brought to at leastMODE 4 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.The allowed Completion Time is reasonable, based on operating experience, for reaching the required MODE from full power conditions inan orderly manner and without challenging plant systems.SURVEILLANCE SR 3.1.3.1REQUIREMENTS This SR requires measurement of the MTC at BOC prior to enteringMODE 1 in order to demonstrate compliance with the positive MTC LCO.Meeting the limit prior to entering MODE 1 ensures that the limit will alsobe met at higher power levels.The BOC MTC value for ARO will be inferred from isothermal temperature coefficient measurements obtained during the physics testsafter refueling.
If appropriate, the ARO value is adjusted to account forany increase in the MTC early in the cycle. The ARO value can then bedirectly compared to the BOC MTC limit of the LCO. If required, measurement results and predicted design values can be used toestablish administrative withdrawal limits for control banks.SR 3.1.3.2In similar fashion, the LCO demands that the MTC be less negative thanthe specified value for EOC full power conditions.
This measurement may be performed at any THERMAL POWER, but its results must beextrapolated to the conditions of RTP and all banks withdrawn in order tomake a proper comparison with the LCO value. Because the RTP MTCvalue will gradually become more negative with further core depletion andboron concentration reduction, a 300 ppm SR value of MTC shouldnecessarily be less negative than the EOC LCO limit. The 300 ppm SRvalue is sufficiently less negative than the EOC LCO limit value to ensurethat the LCO limit will be met when the 300 ppm Surveillance criterion ismet.SR 3.1.3.2 is modified by three Notes that include the following requirements:
- a. The SR is not required to be performed until 7 effective full powerdays (EFPD) after reaching the equivalent of an equilibrium RTP allrods out (ARO) boron concentration of 300 ppm for the reasonsdiscussed above. Measurement of the MTC may be suspended for the current operating cycle provided the benchmark criteriaMcGuire Units 1 and 2 B3135Rvso o 3B 3.1.3-5Revision No. 136 MTC8 3.1.3BASESSURVEILLANCE REQUIREMENTS (continued) specified in DPC-NE-1 007-PA and the Revised MTC Prediction specified in the COLR are satisfied.
- b. If the 300 ppm Surveillance limit is exceeded, it is possible that theEOC limit on MTC could be reached before the planned EOC.Because the MTC changes slowly with core depletion, theFrequency of 14 EFPD is sufficient to avoid exceeding the EOClimit.c. The Surveillance limit for RTP boron concentration of 60 ppm isconservative.
If the measured MTC at 60 ppm is more positivethan the 60 ppm Surveillance limit, the EOC limit will not beexceeded because of the gradual manner in which MTC changeswith core burnup.REFERENCES
- 1. 10 CFR 50, Appendix A, GDC 11.2. UFSAR, Chapter 15.3. UFSAR, Section 15.4.4. 10 CFR 50.36, Technical Specifications, (c)(2)(ii).
- 5. DPC-NE-1 007-PA, "Conditional Exemption of the EOC MTCMeasurement Methodology.
McGuire Units 1 and 2831-6RvsoNo16 B3.1.3-6Revision No. 136