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| {{#Wiki_filter:Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.15 Safety Function Determination Program (SFDP) (continued) | | {{#Wiki_filter:Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.15 Safety Function Determination Program (SFDP) (continued) |
| : b. A required system redundant to the system(s) in turn supported by the inoperable supported system is also inoperable; or c. A required system redundant to the support system(s) for the supported systems (a) and (b) above is also inoperable. | | : b. A required system redundant to the system(s) in turn supported by the inoperable supported system is also inoperable; or |
| The SFDP identifies where a loss of safety function exists. If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered.5.5.16 Containment Leakage Rate Testing Program a. A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. | | : c. A required system redundant to the support system(s) for the supported systems (a) and (b) above is also inoperable. |
| This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," dated September 1995, as modified by the following exceptions: | | The SFDP identifies where a loss of safety function exists. If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered. |
| : 1. The visual examination of containment concrete surfaces intended to fulfill the requirements of 10 CFR 50, Appendix J, Option B testing, will be performed in accordance with the requirements of and frequency specified by ASME Section XI Code, Subsection IWL, except where relief has been authorized by the NRC.2. The visual examination of the steel liner plate inside containment intended to fulfill the requirements of 10 CFR 50, Appendix J, Option B, will be performed in accordance with the requirements of and frequency specified by ASME Section Xl Code, Subsection IWE, except where relief has been authorized by the NRC.3. The ten-year interval between performance of the integrated leakage rate (Type A) test, beginning May 4, 1994, for Unit 1 and April 30, 1993, for Unit 2, has been extended to 15 years.b. The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 47 psig.c. The maximum allowable containment leakage rate, La, at Pa, shall be 0.10% of containment air weight per day.(continued) | | 5.5.16 Containment Leakage Rate Testing Program |
| DIABLO CANYON -UNITS 1 & 2 5.0-24 Unit 1 -Amendment No..1-35, 1-50, 4-72, 197 Unit 2 -Amendment No. 4,35, 450, 4-74, 198 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.16 Containment Leakage Rate Testing Program (continued) | | : a. A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," dated September 1995, as modified by the following exceptions: |
| : d. Leakage rate acceptance criteria are: 1. Containment overall 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 L, for the Type B and Type C tests and _< 0.75 La for Type A tests;2. Air lock testing acceptance criteria are: a) Overall air lock leakage rate is < 0.05 La when tested at > Pa.b) For each door, leakage rate is < 0.01 La when pressurized to > 10 psig.e. The provisions of SR 3.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program.f. The provisions of SR 3.0.3 are applicable to the Containment Leakage Rate Testing Program.5.5.17 Battery Monitoring and Maintenance Program This Program provides for restoration and maintenance, based on the recommendations of IEEE Standard 450, "IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications," or of the battery manufacturer, of the following: | | : 1. The visual examination of containment concrete surfaces intended to fulfill the requirements of 10 CFR 50, Appendix J, Option B testing, will be performed in accordance with the requirements of and frequency specified by ASME Section XI Code, Subsection IWL, except where relief has been authorized by the NRC. |
| : a. Actions to restore battery cells with float voltage < 2.13 V, and b. Actions to equalize and test battery cells that have been discovered with electrolyte level below the top of the plates.(continued) | | : 2. The visual examination of the steel liner plate inside containment intended to fulfill the requirements of 10 CFR 50, Appendix J, Option B, will be performed in accordance with the requirements of and frequency specified by ASME Section Xl Code, Subsection IWE, except where relief has been authorized by the NRC. |
| DIABLO CANYON -UNITS 1 & 2 5.0-24a Unit 1 -Amendment No. 4-72, 197 Unit 2 -Amendment No. 4-74, 198}} | | : 3. The ten-year interval between performance of the integrated leakage rate (Type A) test, beginning May 4, 1994, for Unit 1 and April 30, 1993, for Unit 2, has been extended to 15 years. |
| | : b. The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 47 psig. |
| | : c. The maximum allowable containment leakage rate, La, at Pa, shall be 0.10% of containment air weight per day. |
| | (continued) |
| | DIABLO CANYON - UNITS 1 & 2 5.0-24 Unit 1 - Amendment No..1-35, 1-50, 4-72, 197 Unit 2 - Amendment No. 4,35, 450, 4-74, 198 |
| | |
| | Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.16 Containment Leakage Rate Testing Program (continued) |
| | : d. Leakage rate acceptance criteria are: |
| | : 1. Containment overall 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 L, for the Type B and Type C tests and _<0.75 La for Type A tests; |
| | : 2. Air lock testing acceptance criteria are: |
| | a) Overall air lock leakage rate is < 0.05 La when tested at > Pa. |
| | b) For each door, leakage rate is < 0.01 La when pressurized to > 10 psig. |
| | : e. The provisions of SR 3.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program. |
| | : f. The provisions of SR 3.0.3 are applicable to the Containment Leakage Rate Testing Program. |
| | 5.5.17 Battery Monitoring and Maintenance Program This Program provides for restoration and maintenance, based on the recommendations of IEEE Standard 450, "IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications," or of the battery manufacturer, of the following: |
| | : a. Actions to restore battery cells with float voltage < 2.13 V, and |
| | : b. Actions to equalize and test battery cells that have been discovered with electrolyte level below the top of the plates. |
| | (continued) |
| | DIABLO CANYON - UNITS 1 & 2 5.0-24a Unit 1 - Amendment No. 4-72, 197 Unit 2 - Amendment No. 4-74, 198}} |
Letter Sequence Other |
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TAC:MD3977, Containment Structural Integrity (Approved, Closed) TAC:MD3978, Containment Structural Integrity (Approved, Closed) |
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Category:Technical Specifications
MONTHYEARDCL-24-018, License Amendment Request 24-01 Revision to Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2024-02-28028 February 2024 License Amendment Request 24-01 Revision to Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) ML23012A2172023-02-0909 February 2023 Issuance of Amendment Nos. 244 and 245 Revision to Technical Specifications to Adopt TSTF-569, Revision 2, Revise Response Time Testing Definition ML21242A2162022-12-21021 December 2022 Issuance of Amendment Nos. 243 and 244 Technical Specifications and Revised License Conditions for the Permanently Defueled Condition (EPID: L-2020-LLA-0261 DCL-22-059, License Amendment Request 22-03 Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions2022-07-26026 July 2022 License Amendment Request 22-03 Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions ML21188A3452021-07-0808 July 2021 Issuance of Amendment No. 238 Revision to TS 3.7.8, Auxiliary Saltwater (Asw) System (Emergency Circumstances) ML21188A0372021-07-0707 July 2021 Attachment 1 TS_3_7_8 (Marked Up Pages) ML21188A0352021-07-0707 July 2021 Attachment 2 TS_3_7_8 (Retype Pages) ML21188A0342021-07-0707 July 2021 Attachment 3-TS Bases Section 3_7_8 (Marked-up Pages) DCL-19-094, License Amendment Request 19-02 to Relocate Technical Specification 5.3, Unit Staff Qualifications, to the Updated Final Safety Analysis Report2019-12-0505 December 2019 License Amendment Request 19-02 to Relocate Technical Specification 5.3, Unit Staff Qualifications, to the Updated Final Safety Analysis Report DCL-18-100, License Amendment Request 18-02 - License Amendment Request to Revise Technical Specification 5.6.5b1 Core Operating Limits Report (COLR) for Full Spectrum Loss-of-Coolant Accident Methodology2018-12-26026 December 2018 License Amendment Request 18-02 - License Amendment Request to Revise Technical Specification 5.6.5b1 Core Operating Limits Report (COLR) for Full Spectrum Loss-of-Coolant Accident Methodology ML16330A6722017-01-0505 January 2017 Issuance of Amendment Nos. 228 and 230, Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation ML16139A0082016-12-21021 December 2016 Issuance of Amendment Nos. 227 and 229, Digital Replacement of the Process Protection System Portion of the Reactor Protection System and Engineered Safety Features Actuation System ML16035A4412016-04-14014 April 2016 Issuance of Amendment Nos. 225 and 227, Adopt National Fire Protection Association NFPA 805, Performance-Based Standard for Fire Protection for LWR Generating Plants (2001 Edition) ML16083A5642016-03-23023 March 2016 License Amendment Request 16-02, License Amendment Request to Revise Technical Specification 3.4.12., Low Temperature Overpressure Protection (Ltop) System. DCL-16-028, Technical Specifications B.4.17., Steam Generator (SG) Tube Integrity, LTOP Orifice-Key Design Features, and Additional Information2016-03-23023 March 2016 Technical Specifications B.4.17., Steam Generator (SG) Tube Integrity, LTOP Orifice-Key Design Features, and Additional Information ML16055A3592016-03-0909 March 2016 Issuance of Amendment Nos. 224 and 226, Revise Updated Final Safety Analysis Report for Beacon Power Distribution Monitoring System Methodology and TS 5.6.5 (COLR) Paragon and Nexus Methodologies ML16032A0062016-02-19019 February 2016 Redacted, Issuance of Amendment Nos. 223 and 225, Revise UFSAR Section 15.4.2.2 to Incorporate Pressurizer Filling Analysis for Major Rupture of a Main Feedwater Pipe Accident Into Licensing Basis ML15245A5422015-09-30030 September 2015 Issuance of Amendment Nos. 220 and 222, Request to Revise Operating License Condition Related to Cyber Security Plan Milestone H Full Implementation Date ML15204A2222015-08-27027 August 2015 Issuance of Amendment Nos. 219 and 221, Adopt Technical Specifications Task Force Traveler TSTF-432, Revision 1, Change in Technical Specification End States (WCAP-16294) ML15162A8822015-07-0101 July 2015 Issuance of Amendment Nos. 218 and 220, Revise Surveillance Requirements in TS 3.8.1, AC Sources, Related to Diesel Generator Testing DCL-15-052, Response to NRC Request for Additional Information Regarding License Amendment Request 14-01, Revision to Technical Specification 3.8.1, AC Sources - Operating.2015-04-29029 April 2015 Response to NRC Request for Additional Information Regarding License Amendment Request 14-01, Revision to Technical Specification 3.8.1, AC Sources - Operating. ML14042A1932014-02-27027 February 2014 Issuance of Amendment Nos. 217 and 219, Editorial and Clarifying Changes to Technical Specification (TS) 3.7.10, Control Room Ventilation System (CRVS) and TS 5.6.5, Core Operating Limits Report (COLR) (TAC MF1959-MF1960) ML13130A2252013-05-10010 May 2013 Technical Specification 3.5.2 Safety Injection Pump 2-1 Issue Information ML13267A1352013-01-31031 January 2013 Attachment 6 to DCL-13-016, LTR-RAM-1-13-002 NP-Attachment, Revision 0, Justification for the Application of Technical Specifications Changes in WCAP-14333 and WCAP-15376 to the Tricon/Als Process Protection System at the Diablo Canyon Powe DCL-12-107, Supplement to PG&E Letter DCL-11-059, License Amendment Request 11-04, Revision to Technical Specification (TS) 3.6.6, 'Containment Spray and Cooling Systems,' TS 3.7.5, 'Auxiliary Feedwater (AFW) System,' TS 3.8.1, 'Ac.....2012-11-0101 November 2012 Supplement to PG&E Letter DCL-11-059, License Amendment Request 11-04, Revision to Technical Specification (TS) 3.6.6, 'Containment Spray and Cooling Systems,' TS 3.7.5, 'Auxiliary Feedwater (AFW) System,' TS 3.8.1, 'Ac..... DCL-12-057, Supplement to PG&E Letter DCL-12-017, Response to NRC Request for Additional Information: NRC Question 12012-05-31031 May 2012 Supplement to PG&E Letter DCL-12-017, Response to NRC Request for Additional Information: NRC Question 1 DCL-11-097, License Amendment Request 11-05, Evaluation Process for New Seismic Information and Clarifying the Diablo Canyon Power Plant Safe Shutdown Earthquake2011-10-20020 October 2011 License Amendment Request 11-05, Evaluation Process for New Seismic Information and Clarifying the Diablo Canyon Power Plant Safe Shutdown Earthquake DCL-11-059, Diablo Canyon Units 1 & 2, License Amendment Request 11-04, Revision to Technical Specification 3.6.6, Containment Spray and Cooling Systems, TS 3.7.5, Auxiliary Feedwater System, TS 3.8.1, AC Sources-Operating, TS 3.8.9, Distribution Sys2011-06-0101 June 2011 Diablo Canyon Units 1 & 2, License Amendment Request 11-04, Revision to Technical Specification 3.6.6, Containment Spray and Cooling Systems, TS 3.7.5, Auxiliary Feedwater System, TS 3.8.1, AC Sources-Operating, TS 3.8.9, Distribution Syste DCL-11-055, Supplement to License Amendment Request 11-02, Revision to Technical Specification 3.7.1, Main Steam Safety Valves (Mssvs).2011-04-21021 April 2011 Supplement to License Amendment Request 11-02, Revision to Technical Specification 3.7.1, Main Steam Safety Valves (Mssvs). DCL-11-018, License Amendment Request 11-02, Revision to Technical Specification 3.7.1, Main Steam Safety Valves (Mssvs)2011-02-17017 February 2011 License Amendment Request 11-02, Revision to Technical Specification 3.7.1, Main Steam Safety Valves (Mssvs) DCL-10-028, Emergency License Amendment Request 10-02, One Time Revision to Technical Specification 3.8.1, AC Sources - Operating.2010-03-11011 March 2010 Emergency License Amendment Request 10-02, One Time Revision to Technical Specification 3.8.1, AC Sources - Operating. DCL-10-028, Diablo Canyon, Units 1 and 2, Emergency License Amendment Request 10-02, One Time Revision to Technical Specification 3.8.1, AC Sources - Operating.2010-03-11011 March 2010 Diablo Canyon, Units 1 and 2, Emergency License Amendment Request 10-02, One Time Revision to Technical Specification 3.8.1, AC Sources - Operating. DCL-10-018, License Amendment Request 10-01, Revision to Technical Specification 3.8.1, AC Sources - Operating.2010-02-24024 February 2010 License Amendment Request 10-01, Revision to Technical Specification 3.8.1, AC Sources - Operating. DCL-09-062, Emergency License Amendment Request 09-04 Revision to Technical Specification 3.7.1, Main Steam Safety Valves (Mssvs) for Unit 2 Cycle 15.2009-09-0303 September 2009 Emergency License Amendment Request 09-04 Revision to Technical Specification 3.7.1, Main Steam Safety Valves (Mssvs) for Unit 2 Cycle 15. ML0919601772009-07-0303 July 2009 License Amendment Request 09-02, Revision to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation, Operability Requirements and Actions for RCS Leakage Detection Instrumentation DCL-09-009, License Amendment Request 09-01 - Revision to Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, Deletion of the High Negative Rate Trip Function2009-02-24024 February 2009 License Amendment Request 09-01 - Revision to Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, Deletion of the High Negative Rate Trip Function DCL-08-100, Supplement to License Amendment Request 07-03, Revision to Technical Specification 3.7.10, Control Room Ventilation System (CRVS)2008-11-25025 November 2008 Supplement to License Amendment Request 07-03, Revision to Technical Specification 3.7.10, Control Room Ventilation System (CRVS) ML0824102622008-10-30030 October 2008 Issuance of Amendment Nos. 200 and 201, Technical Specifications Change to Relocate Surveillance Test Intervals to a Licensee-Controlled Program (Risk-Informed Initiative 5b) DCL-07-097, License Amendment Request 07-04, Proposed Technical Specifications Change to Relocate Surveillance Test Intervals to a Licensee-Controlled Program (Risk Informed Technical Specifications Initiative 5b)2007-10-15015 October 2007 License Amendment Request 07-04, Proposed Technical Specifications Change to Relocate Surveillance Test Intervals to a Licensee-Controlled Program (Risk Informed Technical Specifications Initiative 5b) DCL-07-075, Supplement to License Amendment Request 07-01, Revision to Technical Specifications to Support Steam Generator Replacement, and Response to Request for Additional Information2007-08-0909 August 2007 Supplement to License Amendment Request 07-01, Revision to Technical Specifications to Support Steam Generator Replacement, and Response to Request for Additional Information ML0713707332007-06-26026 June 2007 Tech Spec Pages for Amendment Nos. 197 and 198 TS 5.5.16, Containment Leakage Rate Testing Program, for Consistency with 10 CFR 50.55a(g)(4) ML0709900742007-06-25025 June 2007 Units, 1 and 2, Tech Spec Page for Amendments 196 and 197 Administrative Changes to the Technical Specification 5.5.8, Inservice Testing Program. ML0703500522007-04-17017 April 2007 Tech Spec Pages for Amendment Nos. 195 and 196 TS 3.4.1 Reactor Coolant System Pressure, Temperature, & Flow Departure from Nucleate Boiling Limits & TS 5.6.5 Core Operating Limits Report. ML0704404942007-03-21021 March 2007 Tech Spec Pages for Amendments 194 and 195 Regarding Steam Generator Tube Integrity Technical Specifications ML0701902142007-01-19019 January 2007 Units, 1 and 2 - Tech Spec Pages for Amendments 192 and 193 Technical Specification 1.1 Definitions and Technical Specification 3.4.16 Reactor Coolant System Specific Activity DCL-06-143, License Amendment Request 06-10 Revision to Technical Specification 5.5.8, Inservice Testing Program2006-12-29029 December 2006 License Amendment Request 06-10 Revision to Technical Specification 5.5.8, Inservice Testing Program DCL-06-136, License Amendment Request 06-05 Revision to Technical Specification 3.4.1, Reactor Coolant System Pressure, Temperature, and Flow Departure from Nucleate Boiling Limits, and Technical Specification 5.6.5, Core Operating....2006-12-29029 December 2006 License Amendment Request 06-05 Revision to Technical Specification 3.4.1, Reactor Coolant System Pressure, Temperature, and Flow Departure from Nucleate Boiling Limits, and Technical Specification 5.6.5, Core Operating.... DCL-06-142, License Amendment Request 06-09, Revision to Technical Specification 5.5.16, Containment Leakage Rate Testing Program (TSTF-343)2006-12-29029 December 2006 License Amendment Request 06-09, Revision to Technical Specification 5.5.16, Containment Leakage Rate Testing Program (TSTF-343) ML0635500312006-12-20020 December 2006 Tech Spec Pages for Amendment 192 Regarding TS 5.6.5, Core Operating Limits Report. DCL-06-129, Special Report 06-03 - 180 Day Report for Steam Generator Technical Specification Task Force 449, Thirteenth Refueling Outage2006-11-17017 November 2006 Special Report 06-03 - 180 Day Report for Steam Generator Technical Specification Task Force 449, Thirteenth Refueling Outage 2024-02-28
[Table view] |
Text
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.15 Safety Function Determination Program (SFDP) (continued)
- b. A required system redundant to the system(s) in turn supported by the inoperable supported system is also inoperable; or
- c. A required system redundant to the support system(s) for the supported systems (a) and (b) above is also inoperable.
The SFDP identifies where a loss of safety function exists. If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered.
5.5.16 Containment Leakage Rate Testing Program
- a. A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," dated September 1995, as modified by the following exceptions:
- 1. The visual examination of containment concrete surfaces intended to fulfill the requirements of 10 CFR 50, Appendix J, Option B testing, will be performed in accordance with the requirements of and frequency specified by ASME Section XI Code, Subsection IWL, except where relief has been authorized by the NRC.
- 2. The visual examination of the steel liner plate inside containment intended to fulfill the requirements of 10 CFR 50, Appendix J, Option B, will be performed in accordance with the requirements of and frequency specified by ASME Section Xl Code, Subsection IWE, except where relief has been authorized by the NRC.
- 3. The ten-year interval between performance of the integrated leakage rate (Type A) test, beginning May 4, 1994, for Unit 1 and April 30, 1993, for Unit 2, has been extended to 15 years.
- b. The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 47 psig.
- c. The maximum allowable containment leakage rate, La, at Pa, shall be 0.10% of containment air weight per day.
(continued)
DIABLO CANYON - UNITS 1 & 2 5.0-24 Unit 1 - Amendment No..1-35, 1-50, 4-72, 197 Unit 2 - Amendment No. 4,35, 450, 4-74, 198
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.16 Containment Leakage Rate Testing Program (continued)
- d. Leakage rate acceptance criteria are:
- 1. Containment overall 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 L, for the Type B and Type C tests and _<0.75 La for Type A tests;
- 2. Air lock testing acceptance criteria are:
a) Overall air lock leakage rate is < 0.05 La when tested at > Pa.
b) For each door, leakage rate is < 0.01 La when pressurized to > 10 psig.
- e. The provisions of SR 3.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program.
- f. The provisions of SR 3.0.3 are applicable to the Containment Leakage Rate Testing Program.
5.5.17 Battery Monitoring and Maintenance Program This Program provides for restoration and maintenance, based on the recommendations of IEEE Standard 450, "IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications," or of the battery manufacturer, of the following:
- a. Actions to restore battery cells with float voltage < 2.13 V, and
- b. Actions to equalize and test battery cells that have been discovered with electrolyte level below the top of the plates.
(continued)
DIABLO CANYON - UNITS 1 & 2 5.0-24a Unit 1 - Amendment No. 4-72, 197 Unit 2 - Amendment No. 4-74, 198