Letter Sequence Other |
---|
|
|
MONTHYEARBSEP 02-0010, Response to Request for Additional Information Re Request for License Amendments - Frequency of Performance Based Leakage Rate Testing2002-01-31031 January 2002 Response to Request for Additional Information Re Request for License Amendments - Frequency of Performance Based Leakage Rate Testing Project stage: Response to RAI BSEP 02-0032, Response to Request for Additional Information Regarding Request for License Amendments - Frequency of Performance-Based Leakage Rate Testing2002-02-0505 February 2002 Response to Request for Additional Information Regarding Request for License Amendments - Frequency of Performance-Based Leakage Rate Testing Project stage: Response to RAI BSEP 02-0035, Revised Request for License Amendments, Frequency of Performance-Based Leakage Rate Testing2002-02-11011 February 2002 Revised Request for License Amendments, Frequency of Performance-Based Leakage Rate Testing Project stage: Request ML0205101402002-02-19019 February 2002 Safety Evaluation Input - ONE-TIME Extension of Appendix J Type a Integrated Leakage Rate Test Interval for Brunswick Steam Electric Plant, Units 1 & 2 Project stage: Approval ML0206706842002-03-0606 March 2002 Issuance of Amendment, Allows One-Time Interval Increase for Type a, Integrated Leakage Rate Test for No More than 3 Years, 2 Months Project stage: Approval ML0207004862002-03-0606 March 2002 Technical Specification Pages for Amendment No. 216 for Brunswick, Unit 1 Project stage: Other 2002-02-19
[Table View] |
|
---|
Category:Technical Specification
MONTHYEARRA-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-22-0110, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf.2022-03-25025 March 2022 Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf. 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-21-0272, Supplement to 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 4b2021-11-0101 November 2021 Supplement to 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-18-0183, 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 4b2021-04-0101 April 2021 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 ML20342A3472021-03-0404 March 2021 Issuance of Amendment Nos. 303 and 331 Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control Enhancements RA-19-0431, Application to Revise Technical Specifications to Adopt TSTF 564, Safety Limit MCPR2020-03-0909 March 2020 Application to Revise Technical Specifications to Adopt TSTF 564, Safety Limit MCPR 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-19-0157, Supplement to Request for License Amendment Technical Specification 3.8.3, Diesel Fuel Oil, One-Time Extension of Main Fuel Oil Storage Tank Completion Time2019-03-26026 March 2019 Supplement to Request for License Amendment Technical Specification 3.8.3, Diesel Fuel Oil, One-Time Extension of Main Fuel Oil Storage Tank Completion Time ML18298A0782018-12-0303 December 2018 2nd Correction to Issuance of Amendments to Adopt Technical Specifications Task Force 542, Revision 2, Reactor Pressure Vessel Water Inventory Control RA-18-0079, Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO2018-08-14014 August 2018 Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO BSEP 18-0045, Request for License Amendment: Technical Specification 3.8.3, Diesel Fuel Oil, One-Time Extension of Main Fuel Oil Storage Tank Completion Time2018-04-25025 April 2018 Request for License Amendment: Technical Specification 3.8.3, Diesel Fuel Oil, One-Time Extension of Main Fuel Oil Storage Tank Completion Time BSEP 18-0012, Application to Revise Technical Specifications to Adopt TSTF-208, Revision 0, Extension of Time to Reach Mode 2 in LCO 3.0.32018-01-23023 January 2018 Application to Revise Technical Specifications to Adopt TSTF-208, Revision 0, Extension of Time to Reach Mode 2 in LCO 3.0.3 BSEP 18-0001, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2018-01-23023 January 2018 Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements BSEP 18-0013, Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control2018-01-23023 January 2018 Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control 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 ML16252A2202016-08-29029 August 2016 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 BSEP 16-0067, Technical Specification Bases, Rev 882016-08-0303 August 2016 Technical Specification Bases, Rev 88 ML16224A2832016-08-0303 August 2016 Technical Specification Bases, Rev 88 BSEP 16-0047, Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee-Controlled Program2016-06-29029 June 2016 Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee-Controlled Program 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 ML15175A4452015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 4 of 6 ML15175A4482015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 6 of 6 ML15175A4472015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 5 of 6 ML15175A4422015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 3 of 6 RA-15-0006, Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 2 of 62015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 2 of 6 ML12237A0532012-08-14014 August 2012 Technical Specification Bases, Brunswick Steam Electric Plant, Unit 1 - Renewed Facility Operating License DPR-71, Revision 80 BSEP 12-0090, Technical Specification Bases, Brunswick Steam Electric Plant, Unit 2 - Renewed Facility Operating License DPR-62, Revision 762012-08-14014 August 2012 Technical Specification Bases, Brunswick Steam Electric Plant, Unit 2 - Renewed Facility Operating License DPR-62, Revision 76 ML11270A3712011-12-21021 December 2011 Issuance of Amendments Regarding Adoption of TSTF-514 BSEP 10-0057, Request for License Amendments - Addition of Analytical Methodology Topical Report to Technical Specification 5.6.5, Core Operating Limits Report2010-04-29029 April 2010 Request for License Amendments - Addition of Analytical Methodology Topical Report to Technical Specification 5.6.5, Core Operating Limits Report BSEP 10-0052, Request for License Amendments - Addition of Analytical Methodology Topical Report to Technical Specification 5.6.5, Core Operating Limits Report2010-04-29029 April 2010 Request for License Amendments - Addition of Analytical Methodology Topical Report to Technical Specification 5.6.5, Core Operating Limits Report BSEP 08-0145, Renewed Facility Operating License, Technical Specification Bases, Revision 572008-10-30030 October 2008 Renewed Facility Operating License, Technical Specification Bases, Revision 57 ML0832204692008-10-30030 October 2008 Renewed Facility Operating License, Technical Specification Bases, Revision 60 ML0828301372008-10-0606 October 2008 License Amendment Request to Eliminate Work Hour Controls to Support Compliance with Revised 10 CFR 26 BSEP 08-0082, Request for License Amendment - Adoption of TSTF-475, Revision 1 - Revision of Control Rod Notch Surveillance Test Frequency and a Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process2008-06-19019 June 2008 Request for License Amendment - Adoption of TSTF-475, Revision 1 - Revision of Control Rod Notch Surveillance Test Frequency and a Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process ML0727101412007-09-27027 September 2007 Tech Spec Pages for Amendments 242 and 270 Related to Main Fuel Oil Storage Tank BSEP 07-0082, Submittal of Technical Specification Bases Revisions2007-08-14014 August 2007 Submittal of Technical Specification Bases Revisions BSEP 07-0080, Request for License Amendment Re Technical Specification 3.3.1.2, Source Range Monitor (SRM) Instrumentation.2007-08-13013 August 2007 Request for License Amendment Re Technical Specification 3.3.1.2, Source Range Monitor (SRM) Instrumentation. BSEP-07-0064, Request for License Amendments, Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program2007-08-0606 August 2007 Request for License Amendments, Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program BSEP 07-0058, Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process2007-07-17017 July 2007 Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process BSEP 07-0048, Submittal of Technical Specification Bases Revisions2007-05-28028 May 2007 Submittal of Technical Specification Bases Revisions BSEP 06-0129, Request for License Amendments Regarding Linear Heat Generation Rate and Core Operating Limits Report References for Areva Np Fuel2007-01-22022 January 2007 Request for License Amendments Regarding Linear Heat Generation Rate and Core Operating Limits Report References for Areva Np Fuel BSEP 06-0101, Submittal of Technical Specification Bases Revisions2006-09-14014 September 2006 Submittal of Technical Specification Bases Revisions BSEP 06-0044, Submittal of Technical Specification Bases Revisions2006-04-13013 April 2006 Submittal of Technical Specification Bases Revisions BSEP 05-0109, Submittal of Technical Specification Bases Revisions2005-08-16016 August 2005 Submittal of Technical Specification Bases Revisions BSEP 05-0102, Request for License Amendment Revised Main Steam Isolation Valve Leakage Limit2005-08-11011 August 2005 Request for License Amendment Revised Main Steam Isolation Valve Leakage Limit BSEP 05-0094, Request for License Amendments - Appendix J Leakage Rate Testing Instrumentation Accuracy, Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program2005-08-11011 August 2005 Request for License Amendments - Appendix J Leakage Rate Testing Instrumentation Accuracy, Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program ML0518001622005-06-28028 June 2005 Technical Specification Page 3.4-10 RCS Ld Instrumentation (Tac No. MC7216, MC7217) ML0518001552005-06-28028 June 2005 Technical Specification Page 3.4-10 Re RCS Ld Instrumentation (Tac No. MC7216, MC7217) BSEP 05-0082, Submittal of Technical Specification Bases Changes2005-06-22022 June 2005 Submittal of Technical Specification Bases Changes 2023-02-16
[Table view] Category:Amendment
MONTHYEARRA-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-22-0110, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf.2022-03-25025 March 2022 Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf. ML20342A3472021-03-0404 March 2021 Issuance of Amendment Nos. 303 and 331 Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control Enhancements 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 ML18298A0782018-12-0303 December 2018 2nd Correction to Issuance of Amendments to Adopt Technical Specifications Task Force 542, Revision 2, Reactor Pressure Vessel Water Inventory Control RA-18-0079, Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO2018-08-14014 August 2018 Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO BSEP 18-0045, Request for License Amendment: Technical Specification 3.8.3, Diesel Fuel Oil, One-Time Extension of Main Fuel Oil Storage Tank Completion Time2018-04-25025 April 2018 Request for License Amendment: Technical Specification 3.8.3, Diesel Fuel Oil, One-Time Extension of Main Fuel Oil Storage Tank Completion Time BSEP 18-0012, Application to Revise Technical Specifications to Adopt TSTF-208, Revision 0, Extension of Time to Reach Mode 2 in LCO 3.0.32018-01-23023 January 2018 Application to Revise Technical Specifications to Adopt TSTF-208, Revision 0, Extension of Time to Reach Mode 2 in LCO 3.0.3 BSEP 18-0001, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2018-01-23023 January 2018 Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements ML16252A2202016-08-29029 August 2016 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 ML11270A3712011-12-21021 December 2011 Issuance of Amendments Regarding Adoption of TSTF-514 BSEP 10-0057, Request for License Amendments - Addition of Analytical Methodology Topical Report to Technical Specification 5.6.5, Core Operating Limits Report2010-04-29029 April 2010 Request for License Amendments - Addition of Analytical Methodology Topical Report to Technical Specification 5.6.5, Core Operating Limits Report BSEP 10-0052, Request for License Amendments - Addition of Analytical Methodology Topical Report to Technical Specification 5.6.5, Core Operating Limits Report2010-04-29029 April 2010 Request for License Amendments - Addition of Analytical Methodology Topical Report to Technical Specification 5.6.5, Core Operating Limits Report ML0828301372008-10-0606 October 2008 License Amendment Request to Eliminate Work Hour Controls to Support Compliance with Revised 10 CFR 26 BSEP 08-0082, Request for License Amendment - Adoption of TSTF-475, Revision 1 - Revision of Control Rod Notch Surveillance Test Frequency and a Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process2008-06-19019 June 2008 Request for License Amendment - Adoption of TSTF-475, Revision 1 - Revision of Control Rod Notch Surveillance Test Frequency and a Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process ML0727101412007-09-27027 September 2007 Tech Spec Pages for Amendments 242 and 270 Related to Main Fuel Oil Storage Tank BSEP 07-0080, Request for License Amendment Re Technical Specification 3.3.1.2, Source Range Monitor (SRM) Instrumentation.2007-08-13013 August 2007 Request for License Amendment Re Technical Specification 3.3.1.2, Source Range Monitor (SRM) Instrumentation. BSEP-07-0064, Request for License Amendments, Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program2007-08-0606 August 2007 Request for License Amendments, Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program BSEP 05-0094, Request for License Amendments - Appendix J Leakage Rate Testing Instrumentation Accuracy, Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program2005-08-11011 August 2005 Request for License Amendments - Appendix J Leakage Rate Testing Instrumentation Accuracy, Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program BSEP 05-0102, Request for License Amendment Revised Main Steam Isolation Valve Leakage Limit2005-08-11011 August 2005 Request for License Amendment Revised Main Steam Isolation Valve Leakage Limit ML0518001622005-06-28028 June 2005 Technical Specification Page 3.4-10 RCS Ld Instrumentation (Tac No. MC7216, MC7217) ML0518001552005-06-28028 June 2005 Technical Specification Page 3.4-10 Re RCS Ld Instrumentation (Tac No. MC7216, MC7217) ML0414003262004-05-17017 May 2004 Enclosure 1, Amendments No. 232 & 259 ML0409000422004-03-26026 March 2004 Issuance of Amendment No. 231, Minimum Critical Power Ratio Safety Limit BSEP 03-0150, Request for License Amendments Technical Specification 3.1.8, Scram Discharge Volume (SDV) Vent and Drain Valves, Using the Consolidated Line Item Improvement Process2003-12-15015 December 2003 Request for License Amendments Technical Specification 3.1.8, Scram Discharge Volume (SDV) Vent and Drain Valves, Using the Consolidated Line Item Improvement Process BSEP 02-0159, Application for Technical Specification Change Regarding Elimination of Post Accident Sampling System Requirements2002-11-13013 November 2002 Application for Technical Specification Change Regarding Elimination of Post Accident Sampling System Requirements BSEP 02-0124, Application for Amendment to Licenses DPR-71 & DPR-62 to Revise Technical Specifications Section 3.1.7 to Reflect Modifications as Result of Transition to GE14 Fuel Design2002-07-24024 July 2002 Application for Amendment to Licenses DPR-71 & DPR-62 to Revise Technical Specifications Section 3.1.7 to Reflect Modifications as Result of Transition to GE14 Fuel Design ML0208807632002-03-22022 March 2002 Technical Specification Page (Paper Copy) ML0208106382002-03-19019 March 2002 Technical Specification Pages - Amendment 219 and 245 ML0208002542002-03-14014 March 2002 Technical Specification Pages (Paper) ML0207400562002-03-0808 March 2002 Technical Specifications Pages for Amendment Nos. 217 & 243, Brunswick, Units 1 & 2 ML0207004862002-03-0606 March 2002 Technical Specification Pages for Amendment No. 216 for Brunswick, Unit 1 ML0206706842002-03-0606 March 2002 Issuance of Amendment, Allows One-Time Interval Increase for Type a, Integrated Leakage Rate Test for No More than 3 Years, 2 Months 2023-02-16
[Table view] |
Text
Programs and Manuals Programs and Manuals 5.5 5.5 Programs and Manuals Primary Containment Leakage Rate Testing Program (continued)
- a. Compensation of instrument accuracies applied to the primary containment leakage total in accordance with ANSI/ANS 56.8-1987 instead of ANSI/ANS 56.8-1994;
- b. Following air lock door seal replacement, performance of door seal leakage rate testing with the gap between the door seals pressurized to 10 psig instead of air lock testing at P as specified in Nuclear Energy Institute Guideline 94-01, Revision 0;
- c. Reduced duration Type A tests may be performed using the criteria and Total Time method specified in Bechtel Topical Report BN-TOP-1, Revision 1.
- d. Performance of Type C leak rate testing of the hydrogen and oxygen monitor isolation valves is not required; and
- e. Performance of Type C leak rate testing of the main steam isolation valves at a pressure less than P instead of leak rate testing at Pa as specified in ANSI/AN9 56.8-1994.
- f. NEI 94 1995, Section 9.2.3: The first Type A test performed after the February 15, 1991, Type A test shall be performed no later than April 15, 2004.
The peak calculated primary containment internal pressure for the design basis loss of coolant accident, Pa, is 49 psig.
The maximum allowable primary containment leakage rate, La, shall be 0.5% of primary containment air weight per day at Pa.
Leakage rate acceptance criteria are:
- a. Primary containment leakage rate acceptance criterion is
< 1.0 La. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are < 0.60 La for Type B and C tests and
- 0.75 La for Type A tests.
- b. Air lock testing acceptance criteria are:
- 1) Overall air lock leakage rate is
- 0.05 La when tested at ! Pa.
(continued)
Brunswick Unit 1 5.0-16 Amendment No. 216 1
Programs and Manuals 5.5 5.5 Programs and Manuals Primary Containment Leakage Rate Testing Program (continued)
- 2) For each air lock door, leakage rate is
- 5 scfh when the gap between the door seals is pressurized to psig. S10 The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program frequencies.
Brunswick Unit 1 5.0-17 Amendment No. 216 I
Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4.
5.6.1 Occupational Radiation Exposure Report
NOTE ------------------------------
A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.
A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors), for whom monitoring was performed, receiving an annual deep dose equivalent > 100 mrem and their associated collective deep dose equivalent (reported in person-rem) according to work and job functions (e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling). This tabulation supplements the requirements of 10 CFR 20.2206. The dose assignments to various duty functions may be estimated based on pocket dosimeter, thermoluminescent dosimeter (TLD), electronic dosimeter or film badge measurements. Small exposures totalling < 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total deep dose equivalent received from external sources should be assigned to specific major work functions. The report, covering the previous calendar year, shall be submitted by April 30 of each year.
5.6.2 Annual Radiological Environmental Operating Report
------------------ NOTE ------------------------------
A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.
The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with (continued) 5.0-18 Amendment No. 216 I Brunswick Unit 1
Reporting Requirements 5.6 5.6 Reporting Requirements Environmental Operating Report (continued) 5.6.2 Annual Radiological Manual the objectives outlined in the Offsite Dose Calculation IV.B.3, I, Sections IV.B.2, (ODCM), and in 10 CFR 50, Appendix and IV.C.
Report shall The Annual Radiological Environmental Operating all radiological environmental include the results of analyses of taken samples and of all environmental radiation measurements locations specified in the table during the period pursuant to the as summarized and tabulated and figures in the ODCM, as well format of results of these analyses and measurements in the Position, Table 3 in the Radiological Assessment Branch Technical In the event that some individual Revision 1, November 1979. the results are not available for inclusion with the report, for and explaining the reasons report shall be submitted noting in a the missing results. The missing data shall be submitted supplementary report as soon as possible.
5.6.3 Radioactive Effluent Release Report
.NOTE NOT --------....................
station. The A single submittal may be made for a multiple unit sections common to all units at the submittal shall combine station. .
the operation of The Radioactive Effluent Release Report covering prior to the unit during the previous year shall be submitted The report May 1 of each year in accordance with 10 CFR 50.36a.
radioactive liquid shall include a summary of the quantities of the unit. The and gaseous effluents and solid waste released from objectives outlined material provided shall be consistent with the in conformance in the ODCM and the Process Control Program and I,Section IV.B.1.
with 10 CFR 50.36a and 10 CFR Part 50, Appendix 5.6.4 Monthly Operating Reports experience, Routine reports of operating statistics and shutdown main steam including documentation of all challenges to the a monthly basis no safety/relief valves, shall be submitted on month the calendar later than the 15th of each month following covered by the report.
(continued)
Amendment No. 216 1 Brunswick Unit 1 5.0-19
Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.5 CORE OPERATING LIMITS REPORT (COLR)
- a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:
- 1. The AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) for Specification 3.2.1;
- 2. The MINIMUM CRITICAL POWER RATIO (MCPR) for Specification 3.2.2;
- 3. The Allowable Value for Function 2.b, APRM Flow Biased Simulated Thermal Power-High, for Specification 3.3.1.1; and
- 4. The Allowable Values and power range setpoints for Rod Block Monitor Upscale Functions for Specification 3.3.2.1.
- b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
- 1. NEDE-24011-P-A, "General Electric Standard Application for Reactor Fuel" (latest approved version).
- 2. NEDO-32339-A, "Reactor Stability Long Term Solution:
Enhanced Option I-A," July 1995.
- 3. NEDC-32339-P Supplement 1, "Reactor Stability Long Term Solution: Enhanced Option I-A ODYSY Computer Code,"
March 1994 (Approved in NRC Safety Evaluation dated January 4, 1996).
- 4. NEDO-32339 Supplement 3, "Reactor Stability Long Term Solution: Enhanced Option I-A Flow Mapping Methodology," August 1995 (Approved in NRC Safety Evaluation dated May 28, 1996).
(continued) 5.0-20 Amendment No. 216 1 Brunswick Unit 1
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)
- c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.
- d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.
5.6.6 Post Accident Monitoring (PAM) Instrumentation Report When a report is required by Condition B or F of LCO 3.3.3.1, "Post Accident Monitoring (PAM) Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause schedule for restoring the of the inoperability, and the plans and instrumentation channels of the Function to OPERABLE status.
5.0-21 Amendment No. 216 I Brunswick Unit 1
High Radiation Area 5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 High Radiation Area As provided in paragraph 20.1601(c) of 10 CFR Part 20, the following controls required by shall be applied to high radiation areas in place of the controls paragraph 20.1601(a) and (b) of 10 CFR Part 20:
5.7.1 High Radiation Areas with Dose Rates not exceeding 1.0 rem/hour surface (at 30 centimeters from the radiation sources or from any penetrated by the radiation)
- a. Each accessible entryway to such an area shall be barricaded and conspicuously posted as a high radiation area. Such barricades may be opened as necessary to permit entry or exit of personnel or equipment.
- b. Access to, and activities in, each such area shall be controlled by means of a Radiation Work Permit (RWP) or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.
and
- c. Individuals qualified in radiation protection procedures personnel continuously escorted by such individuals may be exempted from the requirement for an RWP or equivalent while performing their assigned duties provided that they are following plant radiation protection procedures for entry to, exit from, and work in such areas.
- d. Each individual or group entering such an area shall possess:
- 1. A radiation monitoring device that continuously displays radiation dose rates in the area ("radiation monitoring and indicating device"); or
- 2. A radiation monitoring device that continuously integrates the radiation dose rates in the area and alarms when the device's dose alarm setpoint is reached
("alarming dosimeter"), with an appropriate alarm setpoint; or
- 3. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area; or (continued) 5.0-22 Amendment No. 216 I Brunswick Unit 1
High Radiation Area 5.7 5.7 High Radiation Area 5.7.1 High Radiation Areas with Dose Rates not exceeding 1.0 rem/hour (at 30 centimeters from the radiation sources or from any surface penetrated by the radiation) (continued)
- 4. A self-reading dosimeter and, (a) Be under the surveillance, as specified in the RWP or equivalent, of an individual at the work site, qualified in radiation protection procedures, equipped with a radiation monitoring and indicating device who is responsible for controlling personnel radiation exposure within the area, or (b) Be under the surveillance, as specified in the RWP or equivalent, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area.
- e. Except for individuals qualified in radiation protection procedures, entry into such areas shall be made only after dose rates in the area have been established and entry personnel are knowledgeable of them.
(at 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour 30 centimeters from the radiation source or from any surface (at 1 penetrated by the radiation), but less than 500 rads/hour by meter from the radiation source or from any surface penetrated the radiation)
- a. Each accessible entryway to such an area shall be be conspicuously posted as a high radiation area and shall provided with a locked door, gate, or guard that prevents unauthorized entry, and in addition:
- 1. All such door and gate keys shall be maintained under the administrative control of the shift superintendent or the radiation control supervisor or designated representative; and
- 2. Doors and gates shall remain locked or guarded except during periods of personnel or equipment entry or exit.
(continued) 5.0-23 Amendment No. 216 I Brunswick Unit 1
High Radiation Area 5.7 5.7 High Radiation Area 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour (at 30 centimeters from the radiation source or from any surface penetrated by the radiation), but less than 500 rads/hour (at 1 meter from the radiation source or from any surface penetrated by the radiation) (continued)
- b. Access to, and activities in, each such area shall be controlled by means of an RWP or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.
- c. Individuals qualified in radiation protection procedures may be exempted from the requirement for an RWP or equivalent while performing radiation surveys in such areas provided that they are following plant radiation protection procedures for entry to, exit from, and work in such areas.
- d. Each individual (whether alone or in a group) entering such an area shall possess:
- 1. An alarming dosimeter with an appropriate alarm setpoint; or
- 2. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area with the means to communicate with and control every individual in the area; or
- 3. A direct-reading dosimeter and, (a) Be under the surveillance, as specified in the RWP or equivalent, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring and indicating device who is responsible for controlling personnel exposure within the area, or (b) Be under the surveillance, as specified in the RWP or equivalent, by means of closed circuit television, of personnel qualified in radiation (continued)
Brunswick Unit I 5.0-24 Amendment No. 216 1
High Radiation Area 5.7 5.7 High Radiation Area 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour (at 30 centimeters from the radiation source or from any surface penetrated by the radiation), but less than 500 rads/hour (at 1 meter from the radiation source or from any surface penetrated by the radiation) (continued) protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with and control every individual in the area; or
- 4. A radiation monitoring and indicating device in those cases where the options of Specifications 5.7.2.d.2 and 5.7.2.d.3, above, are impractical or determined to be inconsistent with the "As Low As is Reasonably Achievable" principle.
- e. Except for individuals qualified in radiation protection procedures, entry into such areas shall be made only after dose rates in the area have been established and entry personnel are knowledgeable of them.
- f. Such individual areas that are within a larger area that is controlled as a high radiation area, where no enclosure exists for purpose of locking and where no enclosure can reasonably be constructed around the individual area need not be controlled by a locked door or gate, but shall be barricaded and conspicuously posted as a high radiation area, and a conspicuous, clearly visible flashing light shall be activated at the area as a warning device.
Amendment No. 216 I Brunswick Unit 1 5.0-25