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| | number = ML071720254 | | | number = ML071720254 |
| | issue date = 06/15/2007 | | | issue date = 06/15/2007 |
| | title = H. B. Robinson Steam Electric Plant, Unit 2 - Technical Specifications Changes Related to Containment Peak Pressure (TAC No. MD2682) | | | title = H. B. Robinson Steam Electric Plant, Unit 2 - Technical Specifications Changes Related to Containment Peak Pressure |
| | author name = | | | author name = |
| | author affiliation = NRC/NRR/ADRO/DORL/LPLII-2 | | | author affiliation = NRC/NRR/ADRO/DORL/LPLII-2 |
Revision as of 11:11, 10 February 2019
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MONTHYEARML0717202542007-06-15015 June 2007 Technical Specifications Changes Related to Containment Peak Pressure Project stage: Acceptance Review ML0710701702007-06-15015 June 2007 Issuance of an Amendment for Containment Peak Pressure Technical Specifications Changes Project stage: Approval ML0726102012007-09-19019 September 2007 Technical Specification, Correction to Technical Specification Page Issued with Amendment No. 215 Issued on June 15, 2007 Project stage: Approval ML0725702252007-09-19019 September 2007 Correction to Technical Specification Pages Issued with Amendment No. 215 Issued on June 15, 2007 Project stage: Approval 2007-06-15
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Category:Technical Specifications
MONTHYEARML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 RA-23-0029, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range)2023-01-30030 January 2023 Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range) ML22329A2982023-01-19019 January 2023 Issuance of Amendment No. 274 Regarding Revision of Technical Specification 3.8.1 Surveillance Requirement 3.8.1.16 ML22294A0922022-12-15015 December 2022 Issuance of Amendment No. 273 Regarding Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML22159A2952022-08-0303 August 2022 Issuance of Amendment No. 271 Regarding Correction to Non-Conservative Technical Specifications Figure 3.4.3-2, Pressure/Temperature Limit Cooldown Curves ML19158A3072019-08-15015 August 2019 Issuance of Amendment No. 265, Regarding Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5b RA-19-0308, Clean Technical Specifications Pages Regarding Application to Adopt TSTF-425, Revision 32019-07-16016 July 2019 Clean Technical Specifications Pages Regarding Application to Adopt TSTF-425, Revision 3 ML18200A0422018-08-16016 August 2018 Issuance of Amendment No. 260 Regarding Request to Revise Technical Specification Reactor Coolant System Pressure and Temperature Limits to Reflect 24-Month Fuel Cycles RA-17-0001, Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules2017-07-18018 July 2017 Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules ML17066A3742017-04-26026 April 2017 Issuance of Amendments Re. Application to Revise TSs to Adopt TSTF-427, Rev. 2, Using the Consolidated Line Item Improvement Process (CAC Nos. MF8039 Through MF8049) RNP-RA/17-0019, Supplemental Submittal to Correct Marked Up Technical Specifications (TS) Pages Transmitted with Application for Technical Specification Task Force (TSTF)-339, Relocate TS Parameters to the COLR Consistent with WCAP-14483, Revision 22017-03-0808 March 2017 Supplemental Submittal to Correct Marked Up Technical Specifications (TS) Pages Transmitted with Application for Technical Specification Task Force (TSTF)-339, Relocate TS Parameters to the COLR Consistent with WCAP-14483, Revision 2 RA-15-0042, Application to Revise Technical Specifications to Adopt Methodology Report DPC-NE-3008-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis.2015-11-19019 November 2015 Application to Revise Technical Specifications to Adopt Methodology Report DPC-NE-3008-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis. ML15222B1752015-09-0808 September 2015 Issuance of Amendment to Modify Technical Specification 3.8.1, Diesel Generator Testing Requirements RA-15-0031, Application to Revise Technical Specifications for Methodology Report DPC-NE-1008-P, Revision 0, Nuclear Design Methodology Using CASMO-5/Simulate-3 for Westinghouse Reactors.2015-08-19019 August 2015 Application to Revise Technical Specifications for Methodology Report DPC-NE-1008-P, Revision 0, Nuclear Design Methodology Using CASMO-5/Simulate-3 for Westinghouse Reactors. RNP-RA/15-0026, Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring (PAM) Instrumentation Report, 14-Day Report for the Inoperability of Pressurizer Power Operated Relief Valves Position Indication2015-04-0101 April 2015 Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring (PAM) Instrumentation Report, 14-Day Report for the Inoperability of Pressurizer Power Operated Relief Valves Position Indication RNP-RA/13-0117, License Amendment Request to Modify Technical Specification 3.3.1, Reactor Protection System (RPS) Instrumentation2014-02-10010 February 2014 License Amendment Request to Modify Technical Specification 3.3.1, Reactor Protection System (RPS) Instrumentation ML13198A3672013-08-29029 August 2013 Issuance of an Amendment to Revise the Steam Generator Program Inspection Frequencies and Tube Sample Selection and Application of Permanent Alternate Repair Criteria (H*) RNP-RA/13-0089, Supplemental Submittal to Correct TS Pages Re Request for Revision to Steam Generator Program Inspection Frequencies & Tube Sample Selection & Application of Permanent Alternate Repair Criteria2013-08-22022 August 2013 Supplemental Submittal to Correct TS Pages Re Request for Revision to Steam Generator Program Inspection Frequencies & Tube Sample Selection & Application of Permanent Alternate Repair Criteria RNP-RA/13-0002, License Amendment Request to Modify Technical Specification 3.1.7 to Delete the Monthly Rod Position Indication Surveillance Requirements2013-06-0707 June 2013 License Amendment Request to Modify Technical Specification 3.1.7 to Delete the Monthly Rod Position Indication Surveillance Requirements ML12339A0672012-12-18018 December 2012 Issuance of License Amendments Regarding Cyber Security RNP-RA/12-0057, License Amendment Request for Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection and Application of Permanent Alternate Repair Criteria (H*)2012-08-29029 August 2012 License Amendment Request for Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection and Application of Permanent Alternate Repair Criteria (H*) ML11342A1652011-12-29029 December 2011 Issuance of an Amendment on Technical Specifications Related to Use of Areva'S M5 Advanced Alloy in Fuel Cladding and Fuel Assembly Components RNP-RA/10-0096, Request for Technical Specifications Change Regarding Use of M5 Alloy Fuel2010-10-20020 October 2010 Request for Technical Specifications Change Regarding Use of M5 Alloy Fuel ML1008303302010-03-25025 March 2010 Issuance of Amendment Regarding Technical Specifications Changes Related to the Chemical and Volume Control System RNP-RA/10-0024, Request for Emergency Technical Specifications Change to Section 3.4.17, Chemical and Volume Control System (CVCS)2010-03-22022 March 2010 Request for Emergency Technical Specifications Change to Section 3.4.17, Chemical and Volume Control System (CVCS) RNP-RA/10-0001, Request for Technical Specification Changes to Section 3.3.2, Engineered Safety Feature, Actuation System (ESFAS) Instrumentation, and Section 3.3.6, Containment Ventilation Isolation Instrumentation2010-03-0505 March 2010 Request for Technical Specification Changes to Section 3.3.2, Engineered Safety Feature, Actuation System (ESFAS) Instrumentation, and Section 3.3.6, Containment Ventilation Isolation Instrumentation ML0936312122009-12-16016 December 2009 Request for Technical Specifications Change Regarding Steam Generator Alternate Repair Criteria RNP-RA/09-0024, Transmittal of Technical Specifications Bases Revisions2009-04-16016 April 2009 Transmittal of Technical Specifications Bases Revisions ML0813403232008-07-23023 July 2008 Issuance of Amendment Regarding the Incorporation of Technical Specification Task Force Standard Technical Specification Change Traveler, TSTF-448, Revision 3, Control Room Habitability. ML0815402792008-06-19019 June 2008 Tech Spec Pages for Amendment 218 Regarding Administrative Changes to the Operating License and Technical Specifications ML0803300542008-01-29029 January 2008 Tech Spec Pages for Amendment 217 to Make a One-time Change to Technical Specification (TS) 3.1.7 Rod Position Indication. ML0726102012007-09-19019 September 2007 Technical Specification, Correction to Technical Specification Page Issued with Amendment No. 215 Issued on June 15, 2007 ML0725706282007-09-18018 September 2007 Correction to Technical Specification Pages Issued with Amendment No. 216 Issued on July 16, 2007 RNP-RA/07-0095, Correction to Technical Specifications Page in Amendment 2162007-09-12012 September 2007 Correction to Technical Specifications Page in Amendment 216 ML0720102362007-07-16016 July 2007 Tech Spec Pages for Amendment 216 to Adopt Technical Specifications Task Force (TSTF) Standard TS Change Traveler, TSTF-447, Using the Consolidated Line Item Improvement Process ML0717202542007-06-15015 June 2007 Technical Specifications Changes Related to Containment Peak Pressure ML0709900232007-04-0404 April 2007 Technical Specifications, Changes Surveillance Requirement (SR) 3.5.2.6 RNP-RA/07-0032, Additional Information Pertaining to Proposed Technical Specifications Changes Regarding Steam Generator Tube Repair Criteria2007-03-22022 March 2007 Additional Information Pertaining to Proposed Technical Specifications Changes Regarding Steam Generator Tube Repair Criteria RNP-RA/07-0023, Response to NRC Request for Additional Information Pertaining to Proposed Technical Specifications Changes Regarding Steam Generator Tube Repair Criteria2007-03-13013 March 2007 Response to NRC Request for Additional Information Pertaining to Proposed Technical Specifications Changes Regarding Steam Generator Tube Repair Criteria ML0628404592006-10-0404 October 2006 Tech Spec Pages for Amendment 208 Regarding Emergency Diesel Generator or Automatic Trips Bypass TS 3.8.1 ML0627100222006-09-22022 September 2006 Technical Specification Amendment No. 210 - H.B. Robinson, Unit 2 - Issuance of Amendment and Partial Denial Reactor Protection System and Engineered Safety Feature Actuation System Instrumentation Tables ML0627005192006-09-20020 September 2006 Technical Specifications, Amendment, Methodology for Large Break Loss-of-Coolant Accident RNP-RA/06-0048, Request for Technical Specifications, Change Related to Containment Peak Pressure2006-07-17017 July 2006 Request for Technical Specifications, Change Related to Containment Peak Pressure ML0621900412006-07-11011 July 2006 Technical Specifications, Alternate Source Term for the loss-of-coolant RNP-RA/06-0046, Request for Technical Specifications Change to Section 3.5.2. Emergency Core Cooling System2006-06-0101 June 2006 Request for Technical Specifications Change to Section 3.5.2. Emergency Core Cooling System RNP-RA/06-0028, Request for Technical Specifications Change Regarding Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process2006-05-30030 May 2006 Request for Technical Specifications Change Regarding Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process ML0610805222006-04-11011 April 2006 H. B. Robinson, Unit 2 - Request for Technical Specification Change to Core Operating Limits Report References RNP-RA/06-0027, ANP-2512(NP), Loss of Forced Reactor Coolant Flow Analysis.2006-03-31031 March 2006 ANP-2512(NP), Loss of Forced Reactor Coolant Flow Analysis. ML0524205242005-08-25025 August 2005 Tech Spec Pages for Amendment 206 DC Sources - Operation and Shutdown RNP-RA/05-0062, Response to Request for Additional Information Regarding Technical Specifications Change Request to Section 3.8.4 DC Sources - Operating2005-07-13013 July 2005 Response to Request for Additional Information Regarding Technical Specifications Change Request to Section 3.8.4 DC Sources - Operating 2023-08-29
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-3-neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required;D. Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components; E. Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by operation of the facility.3. This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations:
10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Section 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below: A. Maximum Power Level The licensee is authorized to operate the facility at a steady state reactor core power level not in excess of 2339 megawatts thermal.B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 215 are hereby incorporated in the license.The licensee shall operate the facility-in accordance with the Technical Specifications.
(1) For Surveillance Requirements (SRs) that are new in Amendment 176 to Final Operating License DPR-23, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 176. For SRs that existed prior to Amendment 176, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 176.Renewed Facility Operating License No. DPR-23 Amendment No.21 5 Isolation Valve Seal Water System 3.6.8 3.6 CONTAINMENT SYSTEMS 3.6.8 Isolation Valve Seal Water (IVSW) System LCO 3.6.8 APPLICABILITY:
The IVSW System shall be OPERABLE.MODES 1. 2, 3, and 4.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. IVSW system A.1 Restore IVSW system 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable, to OPERABLE status.B. Required Action B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and associated Completion Time AND not met.B.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.8.1 Verify IVSW tank pressure is > 46.2 psig. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.6.8.2 Verify the IVSW tank volume is 31 days 85 gallons.(continued)
I HBRSEP Unit No. 2 3.6-20 Amendment No. 215 Isolation Valve Seal Water System 3.6.8 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.6.8.3 Verify the opening time of each air In accordance operated header injection valve is within with the limits. Inservice Testing Program SR 3.6.8.4 Verify each automatic valve in the IVSW 18 months System actuates to the correct position on an actual or simulated actuation signal.SR 3.6.8.5 Verify the IVSW dedicated nitrogen 18 months bottles will pressurize the IVSW tank to k 46.2 psig.SR 3.6.8.6 Verify IVSW seal header flow rate is: 18 months a. 5 52.00 cc/minute for Header A, b. 5 16.50 cc/minute for Header B, c. 32.50 cc/minute for Header C, and d. 23.00 cc/minute for Header D.I HBRSEP Unit No. 2 3.6-21 Amendment No. 215 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.16 Containment Leakage Rate Testing Program This program provides controls for implementation of 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 for Type A testing. 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 exception:
- a. NEI 94-01 -1995, Section 9.2.3: The first Type A test performed after the April 9, 1992, Type A test shall be performed no later than April 9, 2007.Type B and C testing shall be implemented in the program in accordance with the requirements of 10 CFR 50, Appendix J, Option A.The peak containment pressure, Pa, is specified as the containment design pressure of 42 psig, which exceeds the peak calculated containment internal pressure for the design basis loss of coolant accident.The maximum allowable containment leakage rate. La, at Pa, shall be 0.1% of the containment air weight per day.Leakage rate acceptance criteria are: a. Containment leakage rate acceptance criteria 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 Type B and Type C tests, and s 0.75 La for Type A tests.The provisions of SR 3.0.3 are applicable to the Containment Leakage Rate Testing Program.HBRSEP Unit No. 2 5.0-24 Amendment No.215 HBRSEP Unit No. 2 5.0-24 Amendment No.215