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| {{#Wiki_filter:5.5 Programs and Manuals Programs and Manuals 5.5 5.5.12 Primary Containment Leakage Rate Testing Program (continued) | | {{#Wiki_filter:Programs and Manuals 5 .5 5 .5 Programs and Manuals 5 .5 .12 Primary Containment Leakage Rate Testing Program (continued) |
| : 2. NEI 94 1995, Section 9.2.3: The first Unit 3 Type A test performed after the July 14, 1994, Type A test shall be performed no later than July 13, 2009. b. The peak calculated primary containment internal pressure for the design basis loss of coolant accident, P a , is 43.9 psig. c. The maximum allowable primary containment leakage rate, L a , at P a , is 3% of primary containment air weight per day. d. Leakage rate acceptance criteria are: 1. Primary containment overall leakage rate acceptance criterion is <_ 1.0 L a. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are <_ 0.60 L a for the combined Type B and Type C tests, and <_ 0.75 L a for Type A tests. 2. Air lock testing acceptance criteria is the overall air lock leakage rate is <_ 0.05 L a when tested at _> Pa. e. The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program. 5.5.13 Battery Monitoring and Maintenance Program This Program provides for restoration and maintenance, based on the recommendations of IEEE Standard 450-1995, "IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications," including the following: a. Actions to restore battery cells with float voltage < 2.13 V, and b. Actions to equalize and test battery cells that had been discovered with electrolyte level below the minimum established design limit. (continued) | | : 2. NEI 94 1995, Section 9 .2 .3 : The first Unit 3 Type A test performed after the July 14, 1994, Type A test shall be performed no later than July 13, 2009 . |
| Dresden 2 and 3 5.5-12 Amendment No. | | : b. The peak calculated primary containment internal pressure for the design basis loss of coolant accident, P a , is 43 .9 psig . |
| 5.5 Programs and Manuals 5.5.14 Control Room Envelope Habitability Pr oqram Programs and Manuals 5.5 A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Emergency Ventilation (CREV) System, CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge. The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident (DBA) conditions without personnel receiving radiation exposures in excess of 5 rem total effective dose equivalent (TEDE) for the duration of the accident. The program shall include the following elements: a. The definition of the CRE and the CRE boundary. b. Requirements for maintaining the CRE boundary in its design condition including configuration control and preventive maintenance. c. Requirements for (i) determining the unfiltered air inleakage past the CRE boundary into the CRE in accordance with the testing methods and at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors," Revision 0, May 2003, and (ii) assessing CRE habitability at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0. d. Measurement, at designated locations, of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation by the CREV system, operating at the flow rate required by the VFTP, at a Frequency of 24 months. The results shall be trended and used as part of the 24 month assessment of the CRE boundary. e. The quantitative limits on unfiltered air inleakage into the CRE. These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph | | : c. The maximum allowable primary containment leakage rate, La , |
| : c. The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences. Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis. f. The provisions of SR 3.0.2 are applicable to the Frequencies for assessing CRE habitability, determining CRE unfiltered (continued)
| | at Pa , is 3% of primary containment air weight per day . |
| Dresden 2 and 3 5.5-13 Amendment No. | | d . Leakage rate acceptance criteria are : |
| 5.5 Programs and Manuals 5.5.14 Control Room Envelope Habitability Program (continued) | | : 1. Primary 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 La for the combined Type B and Type C tests, and <_ 0 .75 La for Type A tests . |
| Programs and Manuals 5.5 inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively. Dresden 2 and 3 5.5-14 Amendment No.}}
| | : 2. Air lock testing acceptance criteria is the overall air lock leakage rate is <_ 0 .05 La when tested at _> Pa . |
| | : e. The provisions of SR 3 .0 .3 are applicable to the Primary Containment Leakage Rate Testing Program . |
| | 5 .5 .13 Battery Monitoring and Maintenance Program This Program provides for restoration and maintenance, based on the recommendations of IEEE Standard 450-1995, "IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications," including the following : |
| | : a. Actions to restore battery cells with float voltage |
| | < 2 .13 V, and |
| | : b. Actions to equalize and test battery cells that had been discovered with electrolyte level below the minimum established design limit . |
| | (continued) |
| | Dresden 2 and 3 5 .5-12 Amendment No . |
| | |
| | Programs and Manuals 5 .5 5 .5 Programs and Manuals 5 .5 .14 Control Room Envelope Habitability Pr oqram A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Emergency Ventilation (CREV) System, CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge . The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident (DBA) conditions without personnel receiving radiation exposures in excess of 5 rem total effective dose equivalent (TEDE) for the duration of the accident . The program shall include the following elements : |
| | : a. The definition of the CRE and the CRE boundary . |
| | : b. Requirements for maintaining the CRE boundary in its design condition including configuration control and preventive maintenance . |
| | : c. Requirements for (i) determining the unfiltered air inleakage past the CRE boundary into the CRE in accordance with the testing methods and at the Frequencies specified in Sections C .1 and C .2 of Regulatory Guide 1 .197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors," Revision 0, May 2003, and (ii) assessing CRE habitability at the Frequencies specified in Sections C .1 and C .2 of Regulatory Guide 1 .197, Revision 0 . |
| | : d. Measurement, at designated locations, of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation by the CREV system, operating at the flow rate required by the VFTP, at a Frequency of 24 months . The results shall be trended and used as part of the 24 month assessment of the CRE boundary . |
| | : e. The quantitative limits on unfiltered air inleakage into the CRE . These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph c . The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences . Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis . |
| | : f. The provisions of SR 3 .0 .2 are applicable to the Frequencies for assessing CRE habitability, determining CRE unfiltered (continued) |
| | Dresden 2 and 3 5 .5-13 Amendment No . |
| | |
| | Programs and Manuals 5 .5 5 .5 Programs and Manuals 5 .5 .14 Control Room Envelope Habitability Program (continued) inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively . |
| | Dresden 2 and 3 5 .5-14 Amendment No .}} |
|
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Category:Technical Specifications
MONTHYEARML24183A1082024-08-0808 August 2024 – Issuance of Amendment Nos. 302 and 298 Adoption of Tstf-505, Provide Risk Informed Extended Completion Times – RITSTF Initiative 4b ML24136A1322024-07-30030 July 2024 Transmittal Letter for Renewed License ML24138A0572024-06-26026 June 2024 – Issuance of Amendment Nos. 285 and 278 Application to Adopt TSTF-564, Safety Limit MCPR ML23340A1552024-03-15015 March 2024 – Issuance of Amendment Nos. 299 and 295 Adoption of TSTF-564, Safety Limit MCPR ML23349A1622023-12-17017 December 2023 Issuance of Amendment Nos. 298 and 294 Increase Completion Time in Technical Specification 3.8.1.B.4 (Emergency Circumstances) RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs ML23144A3142023-07-0606 July 2023 Issuance of Amendment Nos. 281 and 274 Transition to GNF3 Fuel (EPID L-2022-LLA-0121) - Nonproprietary ML23032A3602023-03-22022 March 2023 Issuance of Amendment Nos. 279 and 272 New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies ML22217A0442022-12-0707 December 2022 Issuance of Amendment Nos. 292 and 288 Control Rod Scram Times RS-22-065, License Amendment Request Regarding Transition to GNF3 Fuel2022-08-18018 August 2022 License Amendment Request Regarding Transition to GNF3 Fuel ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for2022-04-0404 April 2022 Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V RS-22-006, Request to Expand Applicability of Prime Methods to Evaluate Fuel Centerline Melt and Cladding Strain Compliance for Framatome Fuel2022-01-20020 January 2022 Request to Expand Applicability of Prime Methods to Evaluate Fuel Centerline Melt and Cladding Strain Compliance for Framatome Fuel ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML21179A0432021-06-21021 June 2021 4 to Final Safety Analysis Report, Chapter 16, Technical Specifications ML21033A5302021-04-0101 April 2021 Issuance of Amendments to Adopt Technical Specifications Task Force TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML21013A0052021-02-0404 February 2021 Issuance of Amendments to Adopt Technical Specifications Task Traveler TSTF-568, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 RS-20-016, County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems2020-04-13013 April 2020 County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems RS-20-046, Emergency License Amendment Request - Increase Technical Specifications Allowable MSIV Leakage Rates in TS 3.6.1.32020-04-0101 April 2020 Emergency License Amendment Request - Increase Technical Specifications Allowable MSIV Leakage Rates in TS 3.6.1.3 ML18137A2712018-06-29029 June 2018 Issuance of Amendments Regarding Permanent Extension of Type a and Type C Leak Rate Test Frequencies (Cac. Nos. MF9687 and MF9688; EPID L-2017-LLA-0228) (RS-17-060) RS-18-020, Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement2018-06-15015 June 2018 Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement ML17311A1622017-12-0101 December 2017 Issuance of Amendments Regarding Permanent Extension of Type a and Type C Leak Rate Test Frequencies RS-17-126, Quad Cities Nuclear Power Station, Units 1 & 2, Technical Requirements Manual2017-10-19019 October 2017 Quad Cities Nuclear Power Station, Units 1 & 2, Technical Requirements Manual ML17298A4422017-10-19019 October 2017 Technical Requirements Manual ML17238A1222017-08-26026 August 2017 Transmittal of Previously Omitted Proposed Technical Specification Page 3.1-2, and Figures 2.1.1, 3.3.1, 3.3.2, 3.5.1, 3.6.1 ML17180A1212017-06-21021 June 2017 Technical Specification Bases RS-17-082, Dresden Nuclear Power Station, Units 2 & 3, Technical Specification Bases2017-06-21021 June 2017 Dresden Nuclear Power Station, Units 2 & 3, Technical Specification Bases ML17151A8002017-05-31031 May 2017 Amendment No. 82, Section 1.1 Safety Limit Bases ML16111A1042016-05-11011 May 2016 Issuance of Amendments to Revise the Reactor Steam Dome Pressure in Technical Specification 2.1.1, Reactor Core SLs (CAC Nos. MF6640-MF6644) ML15343A1262016-04-29029 April 2016 Issuance of Amendments to Amend Facility Operating License Nos. DPR-19 and DPR-25 to Revise Technical Specifications to Support Use of a New Nuclear Criticality Safety Analysis Methodology RS-16-035, County, and Quad Cities - Request for License Amendment to Address Secondary Containment Access Openings2016-02-0303 February 2016 County, and Quad Cities - Request for License Amendment to Address Secondary Containment Access Openings ML15324A4392015-12-17017 December 2015 Issuance of Amendments (CAC Nos. MF5471-MF5476) ML15268A4862015-10-0606 October 2015 Correction of Amendments Adopting Technical Specification Task Force Traveler TSTF-523 (TAC Nos. MF4436-MF4446) ML15183A3512015-08-0505 August 2015 Issuance of Amendments Concerning Adding Topical References to Technical Specifications (TAC Nos. MF3359, MF3363, MF3361, and MF3362)(RS-13-288) ML15141A0582015-07-28028 July 2015 Issuance of Amendments Regarding Emergency Action Level Schemes (TAC Nos. MF4232-MF4251) ML15106A9472015-04-24024 April 2015 Correction to Amendments Regarding Battery Surveillance Requirements (TAC Nos. MF4589 and MF4590) ML14323A5222015-04-0808 April 2015 Issuance of Amendments Regarding the Emergency Plan Definition of Annual Training ML15056A7722015-03-30030 March 2015 Issuance of Amendments Regarding ML14085A5322014-07-21021 July 2014 Issuance of Amendments Adoption of TSTF-522 Ventilation System Surveillance Requirements RS-13-288, Request for License Amendment to Technical Specifications Section 5.6.5. Core Operating Limits Report.2013-12-19019 December 2013 Request for License Amendment to Technical Specifications Section 5.6.5. Core Operating Limits Report. RS-13-137, Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Item Improvement Process2013-09-0303 September 2013 Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Item Improvement Process RS-13-165, Request for License Amendment to Revise Battery Surveillance Requirements2013-06-10010 June 2013 Request for License Amendment to Revise Battery Surveillance Requirements RS-11-180, Quad Cities, Unit 2 - Request for Technical Specification Change for Safety Limit Minimum Critical Power Ratio2011-11-22022 November 2011 Quad Cities, Unit 2 - Request for Technical Specification Change for Safety Limit Minimum Critical Power Ratio ML1132603482011-11-22022 November 2011 Request for Technical Specification Change for Safety Limit Minimum Critical Power Ratio ML0926704882009-10-21021 October 2009 Issuance of Amendments Risk Informed Modification to Selected Required Action End States for BWR Plants ML0925101522009-10-20020 October 2009 License Amendments, Modify the Technical Specifications to Risk-informed Requirements Regarding Selected Required Action End States as Provided in Technical Specification Task Force (TSTF) Change Traveler TSTF-423, Revision 0 RS-09-036, Request for License Amendment to Technical Specification (TS) 3.4.5, RCS Leakage Detection Instrumentation, TS 5.6.5, Core Operating Limits Report (Color), and Renewed Facility Operating License2009-04-0707 April 2009 Request for License Amendment to Technical Specification (TS) 3.4.5, RCS Leakage Detection Instrumentation, TS 5.6.5, Core Operating Limits Report (Color), and Renewed Facility Operating License ML0824703052008-08-28028 August 2008 Technical Specifications, TSTF Change Traveler TSTF-479 & TSTF-497 ML0824015232008-08-22022 August 2008 Tech Spec Pages for Emergency Amendment 221 Regarding Drywell Floor Drain Sump Monitoring System 2024-08-08
[Table view] |
Text
Programs and Manuals 5 .5 5 .5 Programs and Manuals 5 .5 .12 Primary Containment Leakage Rate Testing Program (continued)
- 2. NEI 94 1995, Section 9 .2 .3 : The first Unit 3 Type A test performed after the July 14, 1994, Type A test shall be performed no later than July 13, 2009 .
- b. The peak calculated primary containment internal pressure for the design basis loss of coolant accident, P a , is 43 .9 psig .
- c. The maximum allowable primary containment leakage rate, La ,
at Pa , is 3% of primary containment air weight per day .
d . Leakage rate acceptance criteria are :
- 1. Primary 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 La for the combined Type B and Type C tests, and <_ 0 .75 La for Type A tests .
- 2. Air lock testing acceptance criteria is the overall air lock leakage rate is <_ 0 .05 La when tested at _> Pa .
- e. The provisions of SR 3 .0 .3 are applicable to the Primary Containment Leakage Rate Testing Program .
5 .5 .13 Battery Monitoring and Maintenance Program This Program provides for restoration and maintenance, based on the recommendations of IEEE Standard 450-1995, "IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications," including the following :
- a. Actions to restore battery cells with float voltage
< 2 .13 V, and
- b. Actions to equalize and test battery cells that had been discovered with electrolyte level below the minimum established design limit .
(continued)
Dresden 2 and 3 5 .5-12 Amendment No .
Programs and Manuals 5 .5 5 .5 Programs and Manuals 5 .5 .14 Control Room Envelope Habitability Pr oqram A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Emergency Ventilation (CREV) System, CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge . The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident (DBA) conditions without personnel receiving radiation exposures in excess of 5 rem total effective dose equivalent (TEDE) for the duration of the accident . The program shall include the following elements :
- a. The definition of the CRE and the CRE boundary .
- b. Requirements for maintaining the CRE boundary in its design condition including configuration control and preventive maintenance .
- c. Requirements for (i) determining the unfiltered air inleakage past the CRE boundary into the CRE in accordance with the testing methods and at the Frequencies specified in Sections C .1 and C .2 of Regulatory Guide 1 .197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors," Revision 0, May 2003, and (ii) assessing CRE habitability at the Frequencies specified in Sections C .1 and C .2 of Regulatory Guide 1 .197, Revision 0 .
- d. Measurement, at designated locations, of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation by the CREV system, operating at the flow rate required by the VFTP, at a Frequency of 24 months . The results shall be trended and used as part of the 24 month assessment of the CRE boundary .
- e. The quantitative limits on unfiltered air inleakage into the CRE . These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph c . The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences . Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis .
- f. The provisions of SR 3 .0 .2 are applicable to the Frequencies for assessing CRE habitability, determining CRE unfiltered (continued)
Dresden 2 and 3 5 .5-13 Amendment No .
Programs and Manuals 5 .5 5 .5 Programs and Manuals 5 .5 .14 Control Room Envelope Habitability Program (continued) inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively .
Dresden 2 and 3 5 .5-14 Amendment No .