Similar Documents at Ginna |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML17250B3061999-10-20020 October 1999 Proposed Tech Specs,Consisting of 1999 Changes to TS Bases ML17265A6941999-06-28028 June 1999 Proposed Tech Specs,Revising ITS Associated with RCS Leakage Detection Instrumentation,As Result of Commitment Submitted as Part of Staff Review of Application of leak-before-break Status to Protions of RHR Piping ML17265A5911999-03-0101 March 1999 Proposed Tech Specs Change Revising Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6) ML17265A4661998-11-24024 November 1998 Proposed Tech Specs 4.2.1,revising Description of Fuel Cladding Matl & Updating List of References Provided in TS 5.6.5 for COLR ML17265A3151998-06-0404 June 1998 Proposed Tech Specs Basis Re Main Steam Isolation Setpoint ML17265A2941998-05-21021 May 1998 Tech Specs Consisting of Submittal Changes for 1998 ML17265A2461998-04-27027 April 1998 Proposed Tech Specs Revising Requirements Associated W/Sfp to Reflect Planned Mod to Storage Racks & Temporarily Addressing Boraflex Degradation within Pool ML17264B0671997-10-0808 October 1997 Proposed Tech Specs,Correcting & Clarifying Info Re RCS Pressure & Temp Limits Rept Administrative Controls Requirements ML17264B0441997-09-29029 September 1997 Proposed Tech Specs Revising Adminstrative Controls W/ Respect to Reactor Coolant Sys Pressure & Temp Limits Rept ML17264B0391997-09-29029 September 1997 Proposed Tech Specs Revising Allowable Value & Trip Setpoint for High Steam Flow Input Into LCO Table 3.3.2-1,Function 4d (Main Steam Isolation) to Address Issues Identified in Rev Revised Setpoint Analysis Study ML17264A9991997-08-19019 August 1997 Proposed Tech Specs Correcting Specified Accumulator Borated Water Volume Values in SR 3.5.1.2 to Match Associated Accumulator Percent Level Values ML17264B0031997-08-19019 August 1997 Proposed Tech Specs Allowing Testing of Three ECCS motor- Operated Valves in Mode 4 Which Currently Requires Entry Into LCO 3.0.3 ML17264A9241997-06-0303 June 1997 Proposed Tech Specs Clarifying Issues Re Low Temperature Overpressure Protection ML17264A8671997-04-24024 April 1997 Proposed Tech Specs,Revising Rcs,Pt & Administrative Control Requirements ML17264A8491997-03-31031 March 1997 Proposed Tech Specs 3.7.12 Re Spent Fuel Pool Boron Concentration ML17264A7601996-12-16016 December 1996 Proposed Annual TS Bases ML17264A7131996-10-29029 October 1996 Proposed Tech Specs Re Actions for Inoperable Channels Associated with Auxiliary Feedwater Pump ML17264A6001996-09-13013 September 1996 Proposed Tech Specs Re RCS Pressure & Temp Limits Rept ML17264A5301996-06-0303 June 1996 Proposed Tech Specs Re Update to Correction of Typographical Error Request ML17264A5111996-05-29029 May 1996 Proposed Tech Specs Pages 3.3-18 & 3.3-19,reflecting Revs to LCO 3.3.1 ML17264A4711996-05-0808 May 1996 Proposed Tech Specs,Correcting Typos ML17264A4081996-03-20020 March 1996 Proposed Tech Specs 3.9.3,Containment Penetrations Re Use of Roll Up Door & Associated Encl Building for LCO 3.9.3 Requirements ML17264A4051996-03-15015 March 1996 Proposed Tech Specs Changing Section 5.6.6 Page 5.0-22 to Incorporate Methodology for Determining RCS P/T & LTOP Limits Into Administrative Controls Section for RCS P/T Limits Rept ML17264A3451996-02-0909 February 1996 Proposed Tech Specs,Revising Setpoints for SG Water Level High Feedwater Isolation Function ML17264A3401996-02-0909 February 1996 Proposed Tech Specs Re LTOP Limits Using Util Proposed Methodology ML17264A3341996-02-0909 February 1996 Proposed Tech Specs Containment Requirements During Mode 6 Cost Beneficial Licensing Action ML17264A3231996-01-26026 January 1996 Proposed Tech Specs Re Nuclear Fuel Cycle for NRC Approval ML17264A2811995-12-0808 December 1995 Proposed Tech Specs Re Changes to Current RCS Pressure & Temp Limits for Heatup,Cooldown,Criticality & Hydrostatic Testing ML17264A2531995-11-27027 November 1995 Proposed Tech Specs for Implementation of 10CFR50,App J, Option B ML17264A2571995-11-20020 November 1995 Proposed Tech Specs,Discussing Changes to TS Instrumentation Requirements & Conversion to Improved TS ML17264A2491995-11-20020 November 1995 Proposed Tech Specs Re Ventilation Filter Testing Program ML17264A1511995-08-31031 August 1995 Proposed Tech Specs Implementing WCAP-10271,its Assoc Suppls & Other Re Changes W/Respect to RTS & ESFAS ML17263A9781995-03-13013 March 1995 Proposed Tech Specs to Revise TS 4.4.2.4.a,replacing Specific Leakage Testing Frequencies for Containment Isolation Valves ML17263A7901994-09-27027 September 1994 Proposed TS Section 6.0, Administrative Controls. ML17263A7281994-07-15015 July 1994 Proposed Tech Specs Providing NRC W/Opportunity to Communicate at Early Stage Any Concerns W/Respect to Differences from NUREG-1431 ML17263A6581994-05-23023 May 1994 Proposed Tech Specs,Increasing Allowable Reactor Coolant Activity Levels ML17263A6431994-05-13013 May 1994 Proposed Tech Specs Administrative Section 6.0 ML17263A3701993-08-20020 August 1993 Corrected Proposed TS Page 5.1-1,changing Word Released to Leased ML17263A3571993-08-0606 August 1993 Proposed Tech Specs Re Alternative Requirements for Snubber Visual Insp Intervals ML17263A3191993-07-15015 July 1993 Proposed Tech Specs,Removing Containment Isolation Valve Table 3.6-1 from TS ML17263A2101993-04-0505 April 1993 Proposed TS Table 3.6-1, Containment Isolation Valves. ML17262B1191992-12-17017 December 1992 Proposed Tech Specs Sections 3.2 & 3.3 Re Acid Storage Tank Boron Concentration Reduction Study ML17309A5021992-11-30030 November 1992 Proposed Tech Specs Reflecting Removal of Table of Containment Isolation Valves ML17262B0441992-10-0808 October 1992 Proposed TS 3.7.1 Re Auxiliary Electrical Sys ML17262B0211992-09-15015 September 1992 Proposed Tech Specs Sections 3.1.1.4,3.1.1.6 & 4.3.4, Addressing GL 90-06, Resolution of Generic Issue 70, 'Porv & Block Valve Reliability' & Generic Issues 94, 'Addl LTOP for Lwrs.' ML17262A9141992-06-22022 June 1992 Proposed TS 4.3.1 Re Reactor Vessel Matl Surveillance Testing ML17262A8321992-04-23023 April 1992 Proposed Tech Specs Re Snubber Visual Insp Schedule ML17262A8221992-04-21021 April 1992 Proposed Tech Specs Re Fire Protection Program ML17262A7871992-03-23023 March 1992 Proposed Tech Spec Revising Section 6.5.1 Re Plant Operations Review Committee Function ML17262A7911992-03-20020 March 1992 Proposed Tech Specs Revising 6.9.1.2 & 6.9.2.5 1999-06-28
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17250B3061999-10-20020 October 1999 Proposed Tech Specs,Consisting of 1999 Changes to TS Bases ML17265A6941999-06-28028 June 1999 Proposed Tech Specs,Revising ITS Associated with RCS Leakage Detection Instrumentation,As Result of Commitment Submitted as Part of Staff Review of Application of leak-before-break Status to Protions of RHR Piping ML17265A6401999-05-12012 May 1999 Rev 11 to Technical Requirements Manual for Ginna Station. ML17265A6261999-04-18018 April 1999 Rev 10 to Technical Requirements Manual (Trm), for Ginna Station ML17311A0701999-04-14014 April 1999 Rev 10 to AP-PRZR.1, Abnormal Pressurizer Pressure. ML17309A6521999-04-14014 April 1999 Rev 14 to AP-RCS.1, Reactor Coolant Leak. ML17309A6531999-04-13013 April 1999 Rev 1 to FIG-2.0, Figure Sdm. with 990413 Ltr ML17265A6111999-03-26026 March 1999 Rev 9 to Technical Requirements Manual for Ginna Station. ML17265A5911999-03-0101 March 1999 Proposed Tech Specs Change Revising Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6) ML17265A5571999-02-25025 February 1999 Rev 4 to Technical Requirements Manual (Trm). ML17265A5491999-02-12012 February 1999 to EOP FR-H.5, Response to SG Low Level. ML17265A5481999-02-12012 February 1999 to EOP ATT-22.0, Attachment Restoring Feed Flow. ML17265A5461999-02-12012 February 1999 0 to EOP AP-TURB.1, Turbine Trip Without Rx Trip Required. ML17309A6481999-01-25025 January 1999 Revised Ginna Station Emergency Operating Procedures. with 990125 Ltr ML17265A5151999-01-14014 January 1999 Revised Emergency Operating Procedures,Including Rev 14 to AP-SW.1,rev 3 to ATT-5.2,rev 5 to ATT-8.0,rev 1 to ATT-14.6, Rev 17 to E-1,rev 16 to ECA-1.1,rev 26 to ES-1.3,rev 4 to FR-Z.2 & Index ML17265A5081999-01-0808 January 1999 Rev 7 to Technical Requirements Manual, for Ginna Station ML17265A4961998-12-18018 December 1998 Rev 6 to Technical Requirements Manual. ML20198C0361998-12-14014 December 1998 Rev 11 to ECA-0.2, Loss of All AC Power Recovery with SI Required ML20198C0121998-12-14014 December 1998 Rev 10 to AP-RCS.2, Loss of Reactor Coolant Flow ML20198C0581998-12-14014 December 1998 Rev 5 to FR-Z.1, Response to High Containment Pressure ML20198C0411998-12-14014 December 1998 Rev 16 to FR-C.1, Response to Inadequate Core Cooling ML20198C0521998-12-14014 December 1998 Rev 13 to FR-S.1, Response to Reactor Restart/Atws ML17265A4661998-11-24024 November 1998 Proposed Tech Specs 4.2.1,revising Description of Fuel Cladding Matl & Updating List of References Provided in TS 5.6.5 for COLR ML20155G0301998-10-30030 October 1998 Rev 13 to EOP AP-CCW.1, Leakage Into Component Cooling Loop ML17265A4091998-08-24024 August 1998 Rev 13 to AP-SW.1, Svc Water Leak. W/980824 Ltr ML17265A3721998-07-16016 July 1998 Rev 14 to EOP AP-CW.1, Loss of Circ Water Pump. W/980716 Ltr ML17265A3151998-06-0404 June 1998 Proposed Tech Specs Basis Re Main Steam Isolation Setpoint ML17265A2941998-05-21021 May 1998 Tech Specs Consisting of Submittal Changes for 1998 ML17265A2861998-05-0606 May 1998 Rev 19 to EOP ECA-3.2, SGTR W/Loss of Reactor Coolant Saturated Recovery Desired & Updated ECA Index.W/980506 Ltr ML17265A2461998-04-27027 April 1998 Proposed Tech Specs Revising Requirements Associated W/Sfp to Reflect Planned Mod to Storage Racks & Temporarily Addressing Boraflex Degradation within Pool ML17265A1821998-02-20020 February 1998 Rev 1 to EWR 5111, MOV Qualification Program Plan, Calculation Assumption Verification Criteria. ML17265A1491997-12-31031 December 1997 Rev 1 to Inservice Testing Program. ML17264B0731997-10-14014 October 1997 Rev 4 to Technical Requirements Manual (TRM) for Ginna Station. ML17264B0671997-10-0808 October 1997 Proposed Tech Specs,Correcting & Clarifying Info Re RCS Pressure & Temp Limits Rept Administrative Controls Requirements ML17264B0441997-09-29029 September 1997 Proposed Tech Specs Revising Adminstrative Controls W/ Respect to Reactor Coolant Sys Pressure & Temp Limits Rept ML17264B0391997-09-29029 September 1997 Proposed Tech Specs Revising Allowable Value & Trip Setpoint for High Steam Flow Input Into LCO Table 3.3.2-1,Function 4d (Main Steam Isolation) to Address Issues Identified in Rev Revised Setpoint Analysis Study ML17265A1541997-09-16016 September 1997 Rev 1 to DA EE-92-089-21, Design Analysis Ginna Station Instrument Loop Performance Evaluation & Setpoint Verification. ML17264B0031997-08-19019 August 1997 Proposed Tech Specs Allowing Testing of Three ECCS motor- Operated Valves in Mode 4 Which Currently Requires Entry Into LCO 3.0.3 ML17264A9991997-08-19019 August 1997 Proposed Tech Specs Correcting Specified Accumulator Borated Water Volume Values in SR 3.5.1.2 to Match Associated Accumulator Percent Level Values ML17264A9791997-08-0505 August 1997 Rev 7 to AP-RCS.3, High Reactor Coolant Activity. ML17264A9781997-08-0505 August 1997 Rev 12 to AP-RCS.1, Reactor Coolant Leak. ML17264A9771997-08-0505 August 1997 Rev 11 to AP-RCP.1, RCP Seal Malfunction. ML17264A9751997-08-0505 August 1997 Rev 14 to AP-ELEC.1, Loss of 12A & 12B Busses. ML17264A9851997-08-0404 August 1997 Rev 2 to Summary Description of Compliance w/10CFR73 Amend Protection Against Malevolent Use of Vehicles at Nuclear Power Plants. ML17264A9391997-07-0707 July 1997 Rev 3 to Technical Requirements Manual for Ginna Station, Inserting New Tabs Accordingly Per Previous Transmittal for Rev ML17264A9341997-07-0101 July 1997 to Technical Requirements Manual (TRM) & inter-office Correspondence Dtd 970624 ML17264A9461997-06-20020 June 1997 to Inservice Insp (ISI) Program. ML17264A9241997-06-0303 June 1997 Proposed Tech Specs Clarifying Issues Re Low Temperature Overpressure Protection ML17311A0471997-05-22022 May 1997 Revised Eops,Including Procedures Index,Rev 5 to ATT-15.0, Rev 3 to ATT-15.2,rev 3 to AP-ELEC.3,rev 13 to ECA-0.1 & Rev 9 to ECA-0.2.W/970522 Ltr ML17264A8671997-04-24024 April 1997 Proposed Tech Specs,Revising Rcs,Pt & Administrative Control Requirements 1999-06-28
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Attachment A Revise the Technical Specifications as follows:
- 1. Replace Sections 3.13, 4.2, and 4.14, and page 6.10-2 with the enclosed proposed sections.
8iii270i58 "Biii24 PDR ADOCK 05000244I
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3.13 Snubbers A licabilit Applies to the operability of all safety-related snubbers listed in the Inservice Inspection Program.
~Ob 'ctive To specify the requirements for operability of snubbers.
S ecif ication 3.13.1 Whenever the reactor is above cold shutdown, all snubbers listed in the Inservice Inspection Program shall be operable. In addition, snubbers which support systems which are required to be operable at cold or refueling shutdown shall be operable.
3.13.2 If one or more snubbers are inoperable when required to be operable, then restore the inoperable snubber(s) to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or declare the supported system inoperable and take the appropriate actions for that system.
Basis Snubbers are required to be operable to ensure that the structural integrity of the reactor coolant system and all other safety related systems is maintained during and following a seismic or other event initiating dynamic loads.
3 ~ 13 1 Amendment No. 14 Proposed
4.2 Inservice Ins ection A licabilit Applies to the inservice inspeciton of Quality Groups A, B and C Components, High Energy Piping Outside of Containment, Steam Generator Tubes, and Snubbers.
To provide assurance of the continuing structural and operational integrity of the structures, components and systems in accordance with the rec,uirements of 10 CFR 50.55a(g).
4.2.1 S ecification The inservice inspection program for Quality Groups A, B and C Components, High Energy Piping Outside of Containment, Steam Generator tubes and snubbers shall be in accordance with Appendix B of'he Ginna Station Quality Assurance Manual. This inservice inspection program shall define the specific requirements of the edition and Addenda of the ASME Boiler and Pressure Vessel Code,Section XI, which are applicable for the forty month period of the ten year inspection interval.
The program ten year inspection intervals shall be f
based on the following commencing dates.
4.2.1.1 The inspection interval for Quality Group A Components shall be ten year intervals of service commencing on January 1, 1970.'he 4.2.1.2 inspection intervals for Quality Group B and C Components shall be ten year intervals of service with the first interval commencing with May 1, 1973, and with subsequent intervals commencing January 1, 1980.
4.2-1 Amendment No. 13 Proposed
0 I The inspection intervals for the High Energy Piping Outside of Containment shall be ten year intervals of service commencing with May 1, 1973. The inspection program during each third of the first inspection interval provides for examination of all welds at design basis break locations and one-third of all welds at locations where a weld failure would result in unacceptable consequences. During each succeeding inspection interval, the program shall provide for an examination of each of the design basis break location welds, and each of the welds at locations where a weld failure would result in unacceptable consequences.
The inspection intervals for Steam Generator Tubes shall be specified in the "Inservice Inspection Program" for the applicable forty month period commencing with May 1, 1973.
Inservice Inspection of ASME Code Class 1, Class 2 and Class 3 components (Quality Groups A, B and C) shall be performed in .accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by the
-NRC pursuant to 10 CFR 50, Section 50.55a(g) (6) (i).
The inspection intervals for snubbers shall be as specified in the Inservice Inspection Program.
4.2-2 Amendment No. 13 Proposed
C' Basis The inservice inspection program provides assurance for the continued structural integrity of the structures, components and systems of Ginna Station. The program complies with the AShlE Boiler and Pressure Vessel Code Section XI "Rules for Inservice Inspection of Nuclear Power Plant Components" as practicable, with due consideration. to the design and physical access of the structures, components and systems as manufactured and constructed.
This compliance will constitute an acceptable basis for satisfying the requirements of General Design Criterion 32, Appendix A of 10 CFR Part 50 and the requirements of Section 50.55a, paragraph g of 10 CFR Part 50.
4.2-3 Amendment No. 13 Proposed
P Deleted.
4.14-1 Proposed
c ~ Records of plant radiation and contamination surveys.
- d. Records of off-site environmental monitoring surveys.
- e. Record 'of radiation exposure of all plant personnel, in-cluding all contractors and visitors to the plant who enter radiation control areas.
Records of radioactivity in liquid and gaseous material released to the environmental and radioactive waste shipments.
Records of transient or operational cycles for those facility components designed for limited number of transients or cycles.
- h. Records of training and qualification for current station technical and operations staff members.
1~ Records of in-service inspections performed pursuant to these Technical Specifications.
Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR Section 50.59.
- k. Records of meetings of the PORC and the NSARB.
Records of Quality Assurance activities as required by the QA Manual.
- m. Records for Environmental Qualification which are covered under the provisions of paragraph 6.14.
- n. Records of the service lives of all hydraulic and mechanical snubbers listed in the Inservice Inspection Program including the date at which the service life commences and associated installation and maintenance records.
6.10-2 Change No. 17 Order dated Oct. 24, 1980 Proposed