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MONTHYEARML0235800042002-12-23023 December 2002
Memorandum to Richard Laufer, Integrated Leak Rate Test (ILRT) Extension Request
Project stage: Other
ML0306408802003-03-0505 March 2003
Issuance of Amendment Nos. 254 & 134, Respectively, Revising TS, Section 6.17 to Allow a One-Time 5-Year Extension to the Current 10-Year Test Interval for the Containment Integrated Leak Rate Test
Project stage: Approval
ML0306509012003-03-0505 March 2003
TSs Pages Amendments 254 & 134
Project stage: Other
2002-12-23
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Category:Technical Specifications
MONTHYEARL-24-038, License Amendment Request to Remove the Expired One-Time Action for Valve Leak Repair in Technical Specification (TS) 3.5.2 and to Correct Core Operating Limits Rep Ort (COLR) References2024-09-17017 September 2024
License Amendment Request to Remove the Expired One-Time Action for Valve Leak Repair in Technical Specification (TS) 3.5.2 and to Correct Core Operating Limits Rep Ort (COLR) References
ML23198A3592023-10-0202 October 2023
Issuance of Amendment Nos. 322 and 212 Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident (EPID L-2022-LLA-0129) - Nonproprietary
ML22210A0102022-09-16016 September 2022
Energy Harbor Fleet- Issuance of Amendments Regarding Adoption of TSTF 554, Revise Reactor Coolant Leakage Requirements
ML22095A2352022-05-10010 May 2022
Issuance of Amendment Nos. 316 and 206 Revise Technical Specification 5.6.3, Core Operating Limits Report (COLR)
ML21334A0302021-11-22022 November 2021
3 to Updated Final Safety Analysis Report, Chapter 15, Technical Specifications and Bases
ML21197A0092021-11-0101 November 2021
Issuance of Amendment Nos. 313 and 203 Reactor Coolant System, Pressure and Temperature Limits Report
ML21214A2752021-10-15015 October 2021
Issuance of Amendment Nos. 312 and 202 Atmospheric Dump Valves
ML21075A1132021-04-16016 April 2021
Issuance of Amendment Nos. 311, 200, and 302 to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff, Into the Technical Specifications
ML21070A0002021-03-22022 March 2021
Issuance of Amendment 310, Revise Technical Specification 5.5.5.1, Unit 1 SG Program, to Defer Spring 2021 Refueling Outage Steam Generator Inspections to Fall 2022 Refueling Outage
ML20346A0222021-03-10010 March 2021
Issuance of Amendment Nos. 309 and 199 to Change Technical Specifications to Implement New Surveillance Methods for the Heat Flux Hot Channel Factor
ML20335A0522021-02-18018 February 2021
Issuance of Amendment Nos. 308 and 198 to Modify Certified Fuel Handler Related Technical Specifications for Permanently Defueled Condition
ML21027A2282021-01-27027 January 2021
License Amendment Request for One-time Deferral of Steam Generator Inspections
ML20335A1292020-11-23023 November 2020
5 to Updated Final Safety Analysis Report, Chapter 16, Technical Specifications
L-20-298, Supplement to License Amendment Request: Proposed Change to Technical Specifications Sections 1.1, Definitions, and 5.0, Administrative Controls, for Permanently Defueled Condition2020-11-0909 November 2020
Supplement to License Amendment Request: Proposed Change to Technical Specifications Sections 1.1, Definitions, and 5.0, Administrative Controls, for Permanently Defueled Condition
ML20213A7312020-09-23023 September 2020
Issuance of Amendment Nos. 305 and 195 to Modify Primary and Secondary Coolant Activity Technical Specifications
ML20160A0742020-05-20020 May 2020
2 to Updated Final Safety Analysis Report, Chapter 15, Technical Specifications and Bases
ML18022B1162018-03-0101 March 2018
Issuance of Amendment Nos. 302 and 191 Regarding the Use of Optimized Zirlo Fuel Rod Cladding (CAC Nos. MF9580 and MF9581; EPID L-2017-LLA-0201)
ML17291A0812018-01-22022 January 2018
Issuance of Amendments Transition to NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (CAC Nos. MF3301 and MF3302; EPID L-2013-LLF-0001)
ML17216A5702017-10-12012 October 2017
Issuance of Amendments Emergency Action Level Scheme Changed Based on NEI 99-01, Revision 6 (CAC Nos. MF8448 and MF8449; EPID L-2016-LLA-0011)
ML17221A2802017-08-16016 August 2017
Issuance of Amendments to Adopt Technical Specifications Task Force (TSTF) Traveler 547, Revision 1
ML16040A0842016-06-0707 June 2016
FENOC, Beaver Valley Power Station, Unit Nos. 1 and 2; and Davis-Besse Nuclear Power Station, Unit No. 1 - Issuance of Amendments Revision to Technical Specification 5.3.1, Unit Staff Qualifications
ML15294A4392015-12-16016 December 2015
Issuance of Amendments License Amendment Request to Revise Steam Generator Technical Specifications (CAC Nos. MF6054 and 6055)
ML15086A2512015-05-20020 May 2015
Issuance of Amendment Revise Technical Specification 4.3.2, Spent Fuel Storage Minimum Inadvertent Drainage Elevation
L-15-026, License Amendment Request to Steam Generator Technical Specifications2015-04-0101 April 2015
License Amendment Request to Steam Generator Technical Specifications
ML14322A4612015-03-0606 March 2015
Issuance of Amendments Request for Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force Initiative 5b.
L-14-300, Response to Request for Additional Information Regarding License Amendment to Adopt Technical Specification Task Force Traveler 4252014-09-21021 September 2014
Response to Request for Additional Information Regarding License Amendment to Adopt Technical Specification Task Force Traveler 425
ML14245A1512014-09-17017 September 2014
Issuance of Amendments Regarding Technical Specification 3.1.3, Moderator Temperature Coefficient Measurement
L-12-271, License Amendment Request to Modify Technical Specification 3.1.3, Moderator Temperature Coefficient Measurement (Mtc), to Provide an Exemption Under Certain Conditions2012-07-25025 July 2012
License Amendment Request to Modify Technical Specification 3.1.3, Moderator Temperature Coefficient Measurement (Mtc), to Provide an Exemption Under Certain Conditions
L-11-269, Technical Specification 5.6.6.2.1 - Steam Generator Inspection Report2011-09-20020 September 2011
Technical Specification 5.6.6.2.1 - Steam Generator Inspection Report
ML1119401232011-07-28028 July 2011
License Amendment, Issuance of Amendment Regarding Approval of the First Energy Nuclear Operating Company Cyber Security Plan
L-11-141, License Amendment Request No. 10-021, Replacement of Beaver Valley Power Station Unit No. 1 Spray Additive System by Containment Sump Ph Control System2011-05-27027 May 2011
License Amendment Request No. 10-021, Replacement of Beaver Valley Power Station Unit No. 1 Spray Additive System by Containment Sump Ph Control System
ML1108001222011-03-18018 March 2011
Supplement to Spent Fuel Pool Rerack Amendment Request
L-11-103, Supplement to Spent Fuel Pool Rerack Amendment Request2011-03-18018 March 2011
Supplement to Spent Fuel Pool Rerack Amendment Request
ML1103501622011-02-24024 February 2011
License Amendment, Issuance of Amendment Regarding the Revised Steam Generator Inspection Scope Using F* Inspection Methodology
L-10-275, License Amendment Request for Spent Fuel Pool Rerack2010-10-18018 October 2010
License Amendment Request for Spent Fuel Pool Rerack
L-10-063, License Amendment Request No. 09-005, Revised Steam Generator Inspection Scope2010-02-26026 February 2010
License Amendment Request No. 09-005, Revised Steam Generator Inspection Scope
ML0929503052009-11-0505 November 2009
Technical Specifications, Appendices a, B, and C
ML0527202912009-11-0505 November 2009
Current Facility Operating License No. DPR-66, Technical Specifications, Revised 03/02/2018
ML0929200562009-11-0505 November 2009
Renewed Facility Operating License, Appendices a, B, and D
L-09-025, ISFSI, and Perry, Application for Technical Specification (TS) Change for Adoption of TSTF-511 Revision 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26.2009-03-25025 March 2009
ISFSI, and Perry, Application for Technical Specification (TS) Change for Adoption of TSTF-511 Revision 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26.
L-08-236, License Amendment Request No. 08-006, Replacement of Beaver Valley Unit No. 2 Spray Additive System by Containment Sump Ph Control System2008-09-24024 September 2008
License Amendment Request No. 08-006, Replacement of Beaver Valley Unit No. 2 Spray Additive System by Containment Sump Ph Control System
ML0807300272008-03-11011 March 2008
Technical Specifications to Amend 164
ML0805103742008-02-15015 February 2008
Tech Spec Pages for Amendments 281 and 163 Control Room Envelope Habitibility in Accordance with Technical Specification Task Force Traveler 448
ML0728200762007-10-0505 October 2007
Technical Specifications, Issuance of Amendment Changes to the Recirculation Spray System Pump Start Signal Due to the Containment Sump Screen Modification
L-07-074, Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3 (License Amendment Request No. 07-008)2007-08-30030 August 2007
Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3 (License Amendment Request No. 07-008)
ML0717202522007-06-14014 June 2007
Beaver and Perry, Technical Specifications, Issuance of Amendments Modification of Technical Specification Requirements for Inoperable Snubbers
ML0703902842007-02-21021 February 2007
Improved Technical Specifications
L-07-017, License Amendment Requests Nos. 334 and 2052007-02-0909 February 2007
License Amendment Requests Nos. 334 and 205
L-07-006, Technical Specification 6.9.7 - Steam Generator Inspection Report2007-02-0202 February 2007
Technical Specification 6.9.7 - Steam Generator Inspection Report
L-06-172, Units 1 and 2, License Amendment Requests to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process2007-01-11011 January 2007
Units 1 and 2, License Amendment Requests to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process
2024-09-17
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Text
ADMINISTRATIVE CONTROLS OFFSITE DOSE CALCULATION MANUAL (ODCM) (Continued)
- c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented.
6.16 Moved to the PROCESS CONTROL PROGRAM.
6.17 Containment Leakage Rate Testing Program 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, except that the next Type A test performed after the May 29, 1993 Type A test shall be performed no later than May 28, 2008.
The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 40.0 psig.
The maximum allowable containment leakage rate, La, at Pa, shall be 0.10% of containment air weight per day.
Leakage Rate acceptance criteria are:
- a. Containment leakage rate acceptance criterion is < 1.0 La for the overall Type A leakage test and < 0.60 La for the Type B and Type C tests on a minimum pathway leakage rate (MNPLR) basis. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are < 0.60 La on a maximum pathway leakage rate (MXPLR)(2) basis for Type B and Type C tests and < 0.75 La for Type A tests.
(1) Exemptions to Appendix J of 10 CFR 50 dated November 19, 1984, December 5, 1984, and July 26, 1995.
(2) For penetrations which are isolated by use of a closed valve(s), blind flange(s), or de-activated automatic valve(s),
the MXPLR of the isolated penetration is assumed to be the measured leakage through the isolation device(s).
BEAVER VALLEY - UNIT 1 6-25 Amendment NO.- 254
ADMINISTRATIVE CONTROLS 6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM)
Changes to the ODCM:
- a. Shall be documented and records of reviews performed shall be retained in accordance with the applicable record retention provision of the quality assurance program description included in the Updated Final Safety Analysis Report. This documentation shall contain:
- 1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and
- 2) A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
- b. Shall become effective after review and acceptance by the OSC and the approval of the plant manager, predesignated alternate or a predesignated manager to whom the plant manager has assigned in writing the responsibility for review and approval of specific subjects.
- c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented.
6.16 Moved to the PROCESS CONTROL PROGRAM.
6.17 CONTAINMENT LEAKAGE RATE TESTING PROGRAM 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, except that the next Type A test performed after the November 10, 1993 Type A test shall be performed no later than November 9, 2008.
(1) Exemptions to Appendix J of 10 CFR 50, as stated in the operating license.
BEAVER VALLEY - UNIT 2 6-25 Amendment No. 134