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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
[Table view] |
Text
- Duke Energy Date: :lllQLZQUi Distribution:
Document Transmittal
- TR-NUC-MC-QQ3<>46
- 1. Gardner, Troy R DOCUMENTTRANSMITTALFORM Purpose: W.LH:. 2. Mc Ginnis, Vickie L 3. Mccree, Victor M Released By: 4. OPS HUMAN PERFORMANCE
-Facility:
Mt!:Z!.!IBli N!.!tLliAB SIAIIQN limm1i 5. OPS TRNG MGR. SUBJECT 13225 RQild 6. QATS-MNS Tes;h Sw;:s; 3,2,3 QQ1 142
- 7. RESIDENT NRC INSPECT MGQ2DM 8. SERV BLDG FILE ROOM -Huntuiiilli:, Nt 28QZ8 9. U S NU C REG WASHINGTO N , DC l'!1
- 10. USNRC 11. WESTINGHOUSE ELECTRIC CO LLC Page 1of1 Document ID 1 2 3 4 5 6 7 8 9 10 11 LICN -MC -MNS-TSB-B 3.9.3 -001 -ISSUED FYIIE FYIIE
- FYIIE FYIIE R&AIE FYIIE R&AILP FYIIE R&A I E R&AIE R&AIE Remarks:
- Nuclear Instrumentation B 3.9.3 B 3.9 REFUELING OPERATIONS B 3.9.3 Nuclear Instrumentation BASES BACKGROUND The source range neutron flux monitors are used during refueling operations to monitor the core reactivity condition.
The installed source range neutron flux monitors are part of the Nuclear Instrumentation System (NIS) while the Wide Range Neutron Flux Monitoring System (Gamma-Metrics) are not. Source range indication is provided via the NIS source range channels and the Gamma-Metrics shutdown monitors using detectors located external to the reactor vessel. These detectors monitor neutrons leaking from the core. Neutron flux indication for these monitors are provided in counts per second. The NIS Source Range Channels, utilizing fission chamber detectors, have a range of 0.1 to 1 E6 cps. The Wide Range (Gamma-Metrics) channels are fission chambers with a range of 0.1 to 1 ES cps (in the startup range). The NIS source range channels and the Gamma-Metrics shutdown monitors provide continuous visible count rate indication in the control room and a high flux control room alarm to alert operators to any unexpected positive reactivity additions.
Since TS 3.9.2 requires isolation of unborated water sources, the shutdown monitors (Gamma-Metrics) audible alarm, NIS source range audible indication and audible alarm are not required for OPERABILITY in Mode 6. The NIS source range detectors and the Gamma-Metrics are designed in accordance with the criteria presented in Reference
- 1. APPLICABLE Two OPERABLE source range neutron flux monitors (any combination of SAFETY ANALYSES the two NIS source range monitors and the two Gamma-Metrics wide range monitors) are required to provide an indication to alert the operator to unexpected changes in core reactivity such as with a boron dilution accident (Ref. 2) or an improperly loaded fuel assembly.
LCO The source range neutron flux monitors satisfy Criterion 3 of 10 CFR 50.36 (Ref. 3). This LCO requires that two source range neutron flux monitors be OPERABLE to ensure that redundant monitoring capability is available to detect changes in core reactivity.
To be operable, each monitor must provide a visual indication in the Control Room. The visual indication can be, but not limited to, either a gauge, chart recorder, CRT, or some other recording device. The two required source range neutron flux monitors may consist of any combination of the two NIS source range monitors and the two Gamma-Metrics wide range shutdown monitors.
- McGuire Units 1 and 2 B 3.9.3-1 Revision No. 142
APPLICABILITY ACTIONS Nuclear Instrumentation B 3.9.3 As required by LCO 3.9.2, "Unborated water source isolation valves", all isolation valves for reactor makeup water sources containing unborated water that are connected to the Reactor Coolant System (RCS) must be closed to prevent unplanned boron dilution of the reactor coolant during MODE 6 and thus avoid a reduction in shutdown margin. As such, the required source range monitors OPERABILITY includes only a visual monitoring function.
A high flux alarm is not a required function for OPERABILITY.
In MODE 6, the source range neutron flux monitors must be OPERABLE to determine changes in core reactivity.
There are no other direct means available to check core reactivity levels. In MODES 2, 3, 4, and 5, the NIS source range detectors and circuitry are also required to be OPERABLE by LCO 3.3.1, "Reactor Trip System (RTS) Instrumentation." The Gamma-Metrics wide range shutdown monitors do not provide an automatic reactor trip protective function . A.1 and A.2 With only one required source range neutron flux monitor OPERABLE, redundancy has been lost. Since these instruments are the only direct means of monitoring core reactivity conditions, CORE ALTERATIONS and introduction of coolant into the RCS with boron concentration less than required to meet the minimum boron concentration of LCO 3.9.1 must be suspended immediately.
Suspending positive reactivity additions that could result in failure to meet the minimum boron concentration limit is required to assure continued safe operation.
Introduction of coolant inventory must be from sources that have a boron concentration greater than that which would be required in the RCS for minimum refueling boron concentration.
This may result in an overall reduction in RCS boron concentration, but provides acceptable margin to maintaining subcritical operation.
Performance of Required Action A.1 shall not preclude completion of movement of a component to a safe position.
B.1 With no required source range neutron flux monitor OPERABLE, action to restore a monitor to OPERABLE status shall be initiated immediately.
Once initiated, action shall be continued until a source range neutron flux monitor is restored to OPERABLE status. B.2 With no required source range neutron flux monitor OPERABLE, there are no direct means of detecting changes in core reactivity.
However, since CORE AL TERA TIONS and positive reactivity additions are not to be made, the core reactivity condition is stabilized until the source range neutron flux monitors are OPERABLE.
This stabilized condition is McGuire Units 1 and 2 B 3.9.3-2 Revision 142 *
- BASES Nuclear Instrumentation B 3.9.3 ACTIONS (continued) determined by performing SR 3.9.1.1 to ensure that the required boron concentration exists. The Completion Time of once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is sufficient to obtain and analyze a reactor coolant sample for boron concentration and ensures that unplanned changes in boron concentration would be identified.
The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Frequency is reasonable, considering the low probability of a change in core reactivity during this time period. SURVEILLANCE SR 3.9.3.1 REQUIREMENTS REFERENCES SR 3.9.3.1 is the performance of a CHANNEL CHECK, which is a comparison of the parameter indicated on one channel to a similar parameter on other channels.
It is based on the assumption that the two indication channels should be consistent with core conditions.
Changes in fuel loading and core geometry can result in significant differences between source range channels, but each channel should be consistent with its local conditions.
The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program. SR 3.9.3.2 SR 3.9.3.2 is the performance of a CHANNEL CALIBRATION.
The CHANNEL CALIBRATION ensures that the monitors are calibrated.
This SR is modified by a Note stating that neutron detectors are excluded from the CHANNEL CALIBRATION.
The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program. 1. 10 CFR 50, Appendix A, GDC 13, GDC 26, GDC 28, and GDC 29. 2. UFSAR, Sections 4.2, 15.4.6. 3. 10 CFR 50.36, Technical Specifications, (c)(2)(ii) . McGuire Units 1 and 2 B 3.9.3-3 Revision 142
- Duke Energy Date: :lllQLZQUi Distribution:
Document Transmittal
- TR-NUC-MC-QQ3<>46
- 1. Gardner, Troy R DOCUMENTTRANSMITTALFORM Purpose: W.LH:. 2. Mc Ginnis, Vickie L 3. Mccree, Victor M Released By: 4. OPS HUMAN PERFORMANCE
-Facility:
Mt!:Z!.!IBli N!.!tLliAB SIAIIQN limm1i 5. OPS TRNG MGR. SUBJECT 13225 RQild 6. QATS-MNS Tes;h Sw;:s; 3,2,3 QQ1 142
- 7. RESIDENT NRC INSPECT MGQ2DM 8. SERV BLDG FILE ROOM -Huntuiiilli:, Nt 28QZ8 9. U S NU C REG WASHINGTO N , DC l'!1
- 10. USNRC 11. WESTINGHOUSE ELECTRIC CO LLC Page 1of1 Document ID 1 2 3 4 5 6 7 8 9 10 11 LICN -MC -MNS-TSB-B 3.9.3 -001 -ISSUED FYIIE FYIIE
- FYIIE FYIIE R&AIE FYIIE R&AILP FYIIE R&A I E R&AIE R&AIE Remarks:
- Nuclear Instrumentation B 3.9.3 B 3.9 REFUELING OPERATIONS B 3.9.3 Nuclear Instrumentation BASES BACKGROUND The source range neutron flux monitors are used during refueling operations to monitor the core reactivity condition.
The installed source range neutron flux monitors are part of the Nuclear Instrumentation System (NIS) while the Wide Range Neutron Flux Monitoring System (Gamma-Metrics) are not. Source range indication is provided via the NIS source range channels and the Gamma-Metrics shutdown monitors using detectors located external to the reactor vessel. These detectors monitor neutrons leaking from the core. Neutron flux indication for these monitors are provided in counts per second. The NIS Source Range Channels, utilizing fission chamber detectors, have a range of 0.1 to 1 E6 cps. The Wide Range (Gamma-Metrics) channels are fission chambers with a range of 0.1 to 1 ES cps (in the startup range). The NIS source range channels and the Gamma-Metrics shutdown monitors provide continuous visible count rate indication in the control room and a high flux control room alarm to alert operators to any unexpected positive reactivity additions.
Since TS 3.9.2 requires isolation of unborated water sources, the shutdown monitors (Gamma-Metrics) audible alarm, NIS source range audible indication and audible alarm are not required for OPERABILITY in Mode 6. The NIS source range detectors and the Gamma-Metrics are designed in accordance with the criteria presented in Reference
- 1. APPLICABLE Two OPERABLE source range neutron flux monitors (any combination of SAFETY ANALYSES the two NIS source range monitors and the two Gamma-Metrics wide range monitors) are required to provide an indication to alert the operator to unexpected changes in core reactivity such as with a boron dilution accident (Ref. 2) or an improperly loaded fuel assembly.
LCO The source range neutron flux monitors satisfy Criterion 3 of 10 CFR 50.36 (Ref. 3). This LCO requires that two source range neutron flux monitors be OPERABLE to ensure that redundant monitoring capability is available to detect changes in core reactivity.
To be operable, each monitor must provide a visual indication in the Control Room. The visual indication can be, but not limited to, either a gauge, chart recorder, CRT, or some other recording device. The two required source range neutron flux monitors may consist of any combination of the two NIS source range monitors and the two Gamma-Metrics wide range shutdown monitors.
- McGuire Units 1 and 2 B 3.9.3-1 Revision No. 142
APPLICABILITY ACTIONS Nuclear Instrumentation B 3.9.3 As required by LCO 3.9.2, "Unborated water source isolation valves", all isolation valves for reactor makeup water sources containing unborated water that are connected to the Reactor Coolant System (RCS) must be closed to prevent unplanned boron dilution of the reactor coolant during MODE 6 and thus avoid a reduction in shutdown margin. As such, the required source range monitors OPERABILITY includes only a visual monitoring function.
A high flux alarm is not a required function for OPERABILITY.
In MODE 6, the source range neutron flux monitors must be OPERABLE to determine changes in core reactivity.
There are no other direct means available to check core reactivity levels. In MODES 2, 3, 4, and 5, the NIS source range detectors and circuitry are also required to be OPERABLE by LCO 3.3.1, "Reactor Trip System (RTS) Instrumentation." The Gamma-Metrics wide range shutdown monitors do not provide an automatic reactor trip protective function . A.1 and A.2 With only one required source range neutron flux monitor OPERABLE, redundancy has been lost. Since these instruments are the only direct means of monitoring core reactivity conditions, CORE ALTERATIONS and introduction of coolant into the RCS with boron concentration less than required to meet the minimum boron concentration of LCO 3.9.1 must be suspended immediately.
Suspending positive reactivity additions that could result in failure to meet the minimum boron concentration limit is required to assure continued safe operation.
Introduction of coolant inventory must be from sources that have a boron concentration greater than that which would be required in the RCS for minimum refueling boron concentration.
This may result in an overall reduction in RCS boron concentration, but provides acceptable margin to maintaining subcritical operation.
Performance of Required Action A.1 shall not preclude completion of movement of a component to a safe position.
B.1 With no required source range neutron flux monitor OPERABLE, action to restore a monitor to OPERABLE status shall be initiated immediately.
Once initiated, action shall be continued until a source range neutron flux monitor is restored to OPERABLE status. B.2 With no required source range neutron flux monitor OPERABLE, there are no direct means of detecting changes in core reactivity.
However, since CORE AL TERA TIONS and positive reactivity additions are not to be made, the core reactivity condition is stabilized until the source range neutron flux monitors are OPERABLE.
This stabilized condition is McGuire Units 1 and 2 B 3.9.3-2 Revision 142 *
- BASES Nuclear Instrumentation B 3.9.3 ACTIONS (continued) determined by performing SR 3.9.1.1 to ensure that the required boron concentration exists. The Completion Time of once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is sufficient to obtain and analyze a reactor coolant sample for boron concentration and ensures that unplanned changes in boron concentration would be identified.
The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Frequency is reasonable, considering the low probability of a change in core reactivity during this time period. SURVEILLANCE SR 3.9.3.1 REQUIREMENTS REFERENCES SR 3.9.3.1 is the performance of a CHANNEL CHECK, which is a comparison of the parameter indicated on one channel to a similar parameter on other channels.
It is based on the assumption that the two indication channels should be consistent with core conditions.
Changes in fuel loading and core geometry can result in significant differences between source range channels, but each channel should be consistent with its local conditions.
The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program. SR 3.9.3.2 SR 3.9.3.2 is the performance of a CHANNEL CALIBRATION.
The CHANNEL CALIBRATION ensures that the monitors are calibrated.
This SR is modified by a Note stating that neutron detectors are excluded from the CHANNEL CALIBRATION.
The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program. 1. 10 CFR 50, Appendix A, GDC 13, GDC 26, GDC 28, and GDC 29. 2. UFSAR, Sections 4.2, 15.4.6. 3. 10 CFR 50.36, Technical Specifications, (c)(2)(ii) . McGuire Units 1 and 2 B 3.9.3-3 Revision 142