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MONTHYEARNL-08-096, Request for Relief to Extend Inservice Inspection Interval for the Reactor Vessel Weld Examination and Request for License Amendment for Submittal of ISI Information and Analyses2008-07-0808 July 2008 Request for Relief to Extend Inservice Inspection Interval for the Reactor Vessel Weld Examination and Request for License Amendment for Submittal of ISI Information and Analyses Project stage: Request ML0820307962008-07-21021 July 2008 License Amendment Request for License Condition to Support Implementation of Extended In-Service Inspection Interval Project stage: Request ML0827603842008-10-0101 October 2008 Attachment 2, Marked Up Tech Spec Pages for License Amendment Request: Reporting of Reactor Vessel In-Service Inspection Information and Analyses in Support of Code Relief Request for Extension of Reactor Vessel.. Project stage: Request ML0827603832008-10-0101 October 2008 Attachment 1, Evaluation of the Proposed Change to License Amendment Request: Reporting of Reactor Vessel In-Service Inspection Information and Analyses in Support of Code Relief Request for Extension of Reactor Vessel.. Project stage: Request CP-200900009, Request for Relief to Extend the Unit 1 & 2 Inservice Inspection Interval for the Reactor Vessel Weld Examination and License Amendment Request 09-004 to Add License Condition for Submittal of ISI Information and Analyses2009-03-0404 March 2009 Request for Relief to Extend the Unit 1 & 2 Inservice Inspection Interval for the Reactor Vessel Weld Examination and License Amendment Request 09-004 to Add License Condition for Submittal of ISI Information and Analyses Project stage: Request ML0918907412009-07-0808 July 2009 Withdrawal of License Amendment Request: Reporting of Reactor Vessel Inservice Inspection Information and Analyses in Support of Code Relief Request for Extension of Reactor Vessel In-Service Inspection Interval Project stage: Withdrawal 2CAN100902, Request for Alternative ANO2-ISI-004 - Proposed Alternative to Extend the Third 10-Year Inservice Inspection Interval for Reactor Vessel Weld Examinations2009-10-29029 October 2009 Request for Alternative ANO2-ISI-004 - Proposed Alternative to Extend the Third 10-Year Inservice Inspection Interval for Reactor Vessel Weld Examinations Project stage: Request TMI-09-142, Request to Extend the Inservice Inspection Interval for Reactor Vessel Weld and Internal Examinations - Relief Requests RR-09-01 and RR-09-022009-10-29029 October 2009 Request to Extend the Inservice Inspection Interval for Reactor Vessel Weld and Internal Examinations - Relief Requests RR-09-01 and RR-09-02 Project stage: Request RC-11-0117, Request to Use Alternatives to ASME Code Requirements in VCSNS 3rd Ten Year Inservice Inspection Interval (RR-III-07) Risk-Informed Extension of Reactor Vessel In-Service Inspection Interval2011-08-16016 August 2011 Request to Use Alternatives to ASME Code Requirements in VCSNS 3rd Ten Year Inservice Inspection Interval (RR-III-07) Risk-Informed Extension of Reactor Vessel In-Service Inspection Interval Project stage: Other 2CAN041303, Additional Reactor Vessel Closure Head Weld Request for Alternative ANO2-ISI-004 Proposed Alternative to Extend the Third 10-Year Inservice Inspection Interval for Reactor Vessel Weld Examinations2013-04-24024 April 2013 Additional Reactor Vessel Closure Head Weld Request for Alternative ANO2-ISI-004 Proposed Alternative to Extend the Third 10-Year Inservice Inspection Interval for Reactor Vessel Weld Examinations Project stage: Request 2CAN111305, Unit 2, Response to Request for Additional Information Related to Relief Request ANO2-ISI-0042013-11-11011 November 2013 Unit 2, Response to Request for Additional Information Related to Relief Request ANO2-ISI-004 Project stage: Response to RAI AEP-NRC-2018-51, Request to Extend the Inservice Inspection Interval for Reactor Vessel Weld Examination - Relief Request ISIR-4-082018-08-0101 August 2018 Request to Extend the Inservice Inspection Interval for Reactor Vessel Weld Examination - Relief Request ISIR-4-08 Project stage: Request 2009-03-04
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Category:Technical Specifications
MONTHYEARML23158A1952023-08-30030 August 2023 R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications ML23180A2362023-06-29029 June 2023 Correction of Errors on Technical Specification Pages 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 ML22067A0772022-03-31031 March 2022 Correction of License Amendment Nos. 337 and 315 to Revise Response Time Testing Definition 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 ML19165A2472019-08-26026 August 2019 Issuance of Amendment Nos 330 and 308 Relocation and Consolidation the Emergency Operations Facility and Joint Information Center for the Calvert Cliffs Nuclear Power Plant ML18365A3732019-01-22022 January 2019 Issuance of Amendment Nos. 328 and 306 to Extend Completion Time of Required Action D.3 of Technical Specification 3.8.1 to 14 Days ML18270A1302018-10-30030 October 2018 Issuance of Amendment Nos. 326 and 304 to Add Risk-Informed Completion Time Program ML17129A5062017-05-12012 May 2017 Plants, Units 1 and 2 - Correction to Technical Specification Pages 1.1-2, 1.1-3, and 1.1-4 to Correct Errors Introduced During the Issuance of Amendment Nos. 286 and 263 ML15352A1642016-03-17017 March 2016 Calvert Cliffs, Units 1 & 2 and Independent Spent Fuel Storage Installation; Nine Mile, Units 1 & 2 and R. E. Ginna - Issuance of Amendments Regarding the Emergency Plan Requalification Training Frequency for Emergency Response Organization Personnel ML15279A1912015-12-30030 December 2015 Issuance of Amendment Revision to Pressurizer Safety Valve Technical Specifications ML15211A0052015-08-17017 August 2015 Amendment Adoption of TSTF-425, Relocate Specific Surveillance Frequencies to a Licensee Controlled Program ML15223B2502015-08-14014 August 2015 and Nine Mile Point Nuclear Station, Unit No. 2- Copy of License Amendment Nos. 313, 291, 118, and 150 ML15161A3802015-07-30030 July 2015 R. E. Ginna and Nine Mile Point, Unit 2 - Issuance of Amendments Regarding Implementation of Technical Specification Task Force Traveler 523, Generic Letter 2008-01, Managing Gas Accumulation (TAC Nos. MF4405 - MF4409) ML15133A1442015-07-23023 July 2015 Amendment Regarding New Technical Specification 3.7.18 for Atmospheric Dump Valves ML15154A6612015-07-16016 July 2015 Amendment License Amendment Request to Extend Containment Leakage Rate Test Frequency ML14307A8422015-01-14014 January 2015 Issuance of Amendment Regarding the Adoption of Technical Specification Task Force (TSTF) 426, Revision 5, Revise or Add Actions to Preclude Entry Into LCO (Limiting Condition of Operation) 3.0.3 ML14280A5222014-10-21021 October 2014 Amendment Enhancements to Diesel Generator Surveillance Requirements (Tac Nos. ME9832 and ME9833) ML14239A4912014-10-21021 October 2014 Issuance of Amendments Regarding the Adoption of Technical Specification Task Force 501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (TAC Nos. ME9794-95) ML14153A5622014-05-30030 May 2014 Response to Request for Additional Information Regarding Enhancements to Diesel Generator License Amendment Request ML14091A2972014-04-0101 April 2014 Issuance of Amendments to Conform the Renewed Facility Operating Licenses and Materials License to Reflect the Direct Transfer of Operating Authority (TAC Nos. MF2584, MF2585, and L24780) ML13308A3872013-10-31031 October 2013 Application for Technical Specification Improvement to Adopt TSTF-510-A, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection. ML13030A1332013-01-28028 January 2013 License Amendment Request Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML1134104612012-01-11011 January 2012 Amendment Technical Specification Task Force Traveler 487-A, Revision 1, Relocate DNB Parameters to the COLR ML1129406452011-12-20020 December 2011 Technical Specification Interpretation for Calvert Cliffs Nuclear Power Plant Units 1 & 2 on Limiting Condition for Operation (LCO) Applicability (LCO) 3.0.5 ML1103902242011-02-18018 February 2011 License Amendment, Transition from Westinghouse Nuclear Fuel to Areva Nuclear Fuel ML1030101702010-10-25025 October 2010 License Amendment Request: Revision of Limiting Condition for Operation 3.0.5 ML1026505292010-09-22022 September 2010 9/22/10 E-Mail to P. S. Furio from J. Goshen Calvert Amendment 9 Tech Specs Page 5 ML1026605642010-09-17017 September 2010 Technical Specification Bases, Revisions 38 & 39, Section B 3.8 - Electrical Power Systems ML1009700702010-04-0505 April 2010 License Amendment Request: Section 5.0, Administrative Controls, Personnel Title Revisions & Administrative Changes ML0933500992009-11-23023 November 2009 License Amendment Request - Transition from Westinghouse Nuclear Fuel to Areva Nuclear Fuel ML0827603842008-10-0101 October 2008 Attachment 2, Marked Up Tech Spec Pages for License Amendment Request: Reporting of Reactor Vessel In-Service Inspection Information and Analyses in Support of Code Relief Request for Extension of Reactor Vessel.. ML0824706232008-08-29029 August 2008 License Amendment Request: Appendix K Measurement Uncertainty Recapture - Power Uprate Request ML0824106932008-08-28028 August 2008 Attachment (2), Marked Up Technical Specification Pages for License Amendment Request: Application for Technical Specification Change TSTF-491 ML0824806762008-08-27027 August 2008 License Amendment Request: Replacement of the Trisodium Phosphate Buffer with a Sodium Tetraborate Buffer, Attachment (2) Markup of Technical Specifications Pages ML0821104652008-07-29029 July 2008 Technical Specifications, Amendment Regarding Control Room Habitability ML0816503472008-06-11011 June 2008 Additional Information Control Room Habitability ML0805303882008-03-24024 March 2008 Units, 1 and 2 - Tech Spec Pages for Amendments 285 and 262 Addition of Limiting Condition of Operation 3.0.8 for Inoperable Snubbers ML0732004702007-12-20020 December 2007 Tech Spec Pages for Amendment Nos. 283 and 260 Use of Lead Fuel Assemblies and Change to Core Operating Limits Report Analytical Methods ML0734706402007-12-13013 December 2007 Supplement to Application for Technical Specification Change to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process ML0724202032007-08-29029 August 2007 Tech Spec Pages for Amendments 281 and 258 Implementation of Alternative Radiological Source Term ML0712703712007-05-0202 May 2007 License Amendment Request Add LCO 3.0.9 on the Unavailability of Barriers Using the Consolidated Line Item Improvement Process ML0712002852007-04-25025 April 2007 Technical Specifications 3.1 and 3.2, Appendix B, Reporting Related to National Pollutant Discharge Elimination System (NPDES) Permit ML0708701102007-03-22022 March 2007 Request for Additional Information Regarding Implementation for Alternative Source Term ML0706103572007-02-27027 February 2007 License Amendment Request: Change to the Core Operating Limits Report Analytical Methods List ML0706104142007-02-27027 February 2007 License Amendment Request: Use of Lead Fuel Assemblies ML0703305992007-02-0101 February 2007 License Amendment Request: Revise Containment Sump Surveillance Requirement to Verify Strainer Integrity ML0632500502006-11-16016 November 2006 License Pages and Technical Specifications, Calvert Cliffs Units 1 & 2 2023-08-30
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ATTACHMENT (2)
MARKED UP TECHNICAL SPECIFICATION PAGES Renewed Operating License Page 4 (Unit 1)
Renewed Operating License Page 5 (Unit 2)
Calvert Cliffs Nuclear Power Plant, Inc.
October 1, 2008
- c. Identification of process sampling points ;
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- d. Proce9ure for recording and management of data; i
- e. Procedures defining corrective act ions for off control point chemistry condi tions ; and 1 .
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- f. A procedure identifying the authority responsible for the interpretation of the data and the sequence and timin g of administrative eve nts required to initiate corrective act ion .
i (5) . Mitigation Strategy I
The Calvert d liffs Nuclear Power Plant, Inc., sha ll deve lop and ma intain strategies for ~ddressing large fires and explosions that include the following key areas :
I I
(a) Fire fighting response strategy with the following elements:
- 1. Pre-defined coordinated fire response strategy and guidance
- 2. Assessment of mutual aid fire fighting assets
- 3. Designated staging areas for equi pment and mate rials
- 4. Command and control
- 5. I Training of respo nse person nel I
(b) Operations to mitigate fuel damage considering the following:
- 1. : Protection and use of personnel assets
- 2. ! Communications
- 3. ! Minimizing fire spread
- 4. i Procedures for implementing integrated fire response I strategy
- 5. .! Identification of readily ava ilable pre -staged equipment
- 6. I Training on integrated fire response strategy
- 7. I Spent fuel pool mitigation measures i .
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(c) Acti~ns to m inimize release to include consideration of:
I*i
- 1. i . Water spray scrubbing
- 2. ! Dose to onsite respo nders JtJ::>f-P.-r'\A /~
D. The licensee shall fu,lyimplement and maintain in effect all provisions of the Commission-approved phys ical security, training and qua lification, and safeguards continqency plans, including amendments made pursua nt to provisions of the Mis~llaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 278 17 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans , which conta in Safeguards Information protected under .10 CFR 73.21, is entitled: "Calvert Cliffs Nuclear Power !Plant Security Plan, Training and Qua lifica tion Plan, and Safeguards Conting~ncy Plan, Revision 1" subm itted May 19, 2006 .
Amendment No. 273 Revised by letter dated July 11, 2007
- 4. .Procedures for implementing integrated fire response lstrateqy
- 5. ! Identification of readily available pre-staged equ ipment
- 6. T raini ng on integrated fire response strategy
- 7. [Spent fue lpool mitigation measures (c) Actions to m inimize release to include consideration of:
i
- 1. !W ater spray scrubbing
- 2. !Dose to ons ite responders
}useer \\ 8 i l ) ,
D. Th e licensee shall fully implement and maintain in effect all provisions of the Co rnrnission-approved physical security, training and qua lification, and safeguards conti nqency plans , including amendments ma de pursuan t to provisions of the Miscell aneous A me ndments and Sea rch Req uirements revisions tot 0 CFR 7~ .55 (5 1 FR 27817 and 27822) and the autho rity of 10 CFR 50 .90 and 10 CFR 50 J54(p). Th e combined set of plans, which con ta in Safeguards Inform ation protected under 10 CFR 73.21, is entitled : "Calvert Cliffs Nuclear Power pl ant Security Plan, Training and Quali fication Plan, and Safeguards Continge ncy Plan , Revision 1" submitted date d May 19, 2006.
I E. T he Calvert Cliffs Nuclear Power Plant , Inc., sha ll im plem ent and ma inta in in effect all provisions ofithe approved fir e protection program as describe d in the Updated Final Safety Analysis Report fo r the facility and as approved in the SER dated September 14,1 979, and Supplements dated October 2, 1980; March 18, 1982; and September;27, 1982; and Exemptio ns dated A ugust 16,1 982; Ap ril 21, 1983; March !1 5, 1984; August 22, 1990; and April 7, 1999 subject to the following provision: Th e Ca lvert Cliffs Nuclear Power Plant, Inc. may make changes to the approved fi re protection prog ram without prior approval of th e Co mm ission only if th ose changes would not adversely affect the ability to achieve and maintain !s afe shutdown in the event of a fi re.
F. At the time of the next scheduled update to the FSAR required pursuan t to 10 CFR 50.71(e)(4) fdllowing the issuance of this renewed license, the licensee sha ll update the FSA~ to include the FSAR supplement su bm itted pursuant to 10 CFR 54.2 1(d), as amended and supplemented by th e program descriptio ns in Appendix E to .the Saf.ety Eva luation Re port, NU REG-1 705. Until th at FSAR update is complete, the lice nsee may make changes to the programs described in Appendix E withoutiprior Com miss ion approval, provided that the licensee eva luates eac h such th ange pursuant to the criteria set forth in 10 CFR 50 .59 and otherwise co mplies I with th e requirements in that section.
i G. Any future actio ns listed in Appendix E to the Safety Eva luation Report, NUREG-1705, sha ll be included in the FSAR. The licen see sha ll complete these actions by August 13, i2016.
Amendment No. 250 Revised by lett er dated July 11, 2007
INSERT A (6) Reactor Vessel In-Service Inspection Interval Extension As part of Calvert Cliffs Nuclear Power Plant's relief request to extend the reactor vessel In-Service Inspection interval (if approved), Calvert Cliffs shall submit to the NRC the information and analyses specified in paragraph (e) of the proposed 10 CFR 50.61a given in 72 FR 56275, following completion of each American Society of Mechanical Engineers (ASME) Code,Section XI, Category B-A and B-D reactor vessel weld inspection. The information and analyses shall be submitted within one year of the completion of each inspection. Once the final 10 CFR 50.61a is effective, the required information and analyses specified in paragraph (e) of the final 10 CFR 50.61a shall be the information submitted to the NRC .
lNSERT B (8) Reactor Vessel In-Service Inspection Interval Extension As part of Calvert Cliffs Nuclear Power Plant's relief request to extend the reactor vessel In-Service Inspection interval (if approved), Calvert Cliffs shall submit to the NRC the information and analyses specified in paragraph (e) of the proposed 10 CFR 50.61a given in 72 FR 56275, following completion of each American Society of Mechanical Engineers (ASME) Code, Section Xl, Category B-A and B-D reactor vessel weld inspection. The information and analyses shall be submitted within one year of the completion of each inspection . Once the final 10 CFR 50.61a is effective, the required information and analyses specified in paragraph (e) of the final 10 CFR 50.61a shall be the information submitted to the NRC.