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
[Table view] |
Text
3.13 Shock vnressors (Snubbers)
A licabilit Applies to the operability of all safety-related shock suppressors (snubbers) listed in Table 3.13-1.
To specify the reauirements for operabilitv of shock suppressors (snubbers).
S ecifications:
3.13.1 The reactor shall not be made critical unless (1) all shock suppressors (snubbers) listed in Table 3.13.1 are operable.
3.13.2 Continued hot shutdown or power operation is permitted for a period up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> without the conditions of 3.13.1 being met. If the conditions of 3.13-1 are not met in that 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> period, then the reactor shall be in a cold shutdown condition within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
Basis Shock suppressors (snubbers) are recruired 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.
Snubbers may be replaced by rigid structural supports (bumpers) provided an analysis is performed to demonstrate that, appropriate acceptance criteria are satisfied for design basis seismic and pipe break events and provided that the bumpers are inspected periodically in a manner appropriate for rigid structural supports.
3 ~ 13 1 Proposed 8805200120 880513
,'PDR AQOCK 05000244
'P DCD
ATTACHMENT B t
The upper portion of the two steam generators at Ginna Station are currently restrained against lateral seismic and pipe break loads by eight large (532,000 lb. capacity) hydraulic shock arrestors (snubbers). The intent of the proposed amendment to the Technical Specifications is to permit replacement of six of the eight snubbers (per steam generator) with rigid structural members, or bumpers. A pair of existing snubbers will remain in the upper support configuration for each steam generator. The snubbers to be replaced were installed to mitigate the dynamic effects of seismic events and postulated pipe ruptures. The proposed configuration, allowing the use of bumpers, retains high safety margins under postulated loading conditions. A description of the changes and a summary report were previously provided to the NRC Staff by letters dated September 22, 1987, November 20, 1987 and December 15, 1987. is a revised report, "Steam Generator Hydraulic Snubber Replacement Program", May 1988, Rev. 2, summarizing the analyses performed for the modified upper support configuration to determine the loads on RCS piping and component supports due to postulated seismic events and pipe breaks. This report confirms the applicability of previously approved leak-before-break analyses and incorporates the guidance of Generic Letter 87-11 for elimination of arbitrary intermediate breaks. The results of the analyses determined that the RCS, with the proposed modified steam generator upper lateral support configuration, will meet acceptance criteria for resulting loads from postulated seismic and other design basis events.
This proposed change to the Technical Specifications adds a statement in the bases to Section 3.13, allowing the substitution of rigid structural members for snubbers provided that the modified configuration has been analyzed and found to be acceptable. The specific inspection criteria and surveillance requirements for snubbers do not apply to the bumpers. The maintenance inspection of the bumpers will be visual and of a type appropriate to rigid supports, in accordance with the established RG&E ISI program. The benefits of this change will include reduced worker radiation exposures and lower maintenance costs.
Granting this request would not affect the design basis of the ECCS or containment and compartment structures, nor change the equipment qualification basis of any engineered safety feature response.
This proposed amendment has been reviewed against the three factors of 10 CFR 50.92.
amendment does not involve It has been determined that the a significant hazards consideration for the following reasons.
- 1. This change will not result in a significant increase in the probability or consequences of -
an accident previously evaluated.
The proposed modification involves replacing six of the eight snubbers in each steam generator's upper lateral support with rigid structural supports. The lateral restraints limit the displacement of the steam generators due to the dynamic effects of postulated seismic and pipe break events. The analyses of the modified. steam generator upper support configuration provided in the enclosed report demonstrates that high safety margins will be maintained under postulated loading conditions, including normal loads, thermal expansion, design basis seismic events, postulated pipe ruptures at the steam generator secondary-side terminal ends (Main Steam and, Feedwater) and reactor coolant loop auxiliary line nozzles (Pressurizer surge, SI accumulator, and RHR). The postulated break locations are conservatively appropriate based upon the application of leak-before-break technology and the relaxation of arbitrary intermediate pipe rupture requirements in accordance with Generic Letter 87-11 and Standard Review Plan Section 3.6.2. The NRC has determined that the probability or consequences of an accident are not increased when leak-before-break technology is properly applied. Through proper application of leak-before-break technology, it has been demonstrated that advanced fracture mechanics analysis is an acceptable alternative to the use of structures and components, including snubbers, to mitigate the consequences of dynamic effects of postulated pipe ruptures. Dynamic effects of postulated ruptures in the main coolant loop piping have been eliminated from the design basis for Ginna through application of a leak-before-break technology consistent with GDC-4 and previously approved for the RG&E Ginna plant in a letter dated September 9, 1986. The elimination of arbitrary intermediate breaks in the main steam and feedwater lines has been previously discussed and agreed upon with the NRC as documented in an RGRE letter dated December 15, 1987 and in Sections 2.1.2 and 4.3 of Enclosure 1. Because adequate safety margins, based on the Updated .Final Safety Analysis Report allowable stresses, are maintained with 'the "modified configuration as shown in Enclosure 1, there is no increase in the probability or consequences of an accident previously evaluated.
In addition, this change will not modify the design basis of other structures, systems and components, nor modify the equipment qualification basis or any engineered safety feature response.
- 2. This change will not create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed modification replaces snubbers with a different type of support, rigid bumpers. These supports are designed to restrain steam generator displacement upon a seismic or pipe break event. As shown in the enclosed report, the reactor coolant system, with the modified steam generator upper lateral support configuration, will continue to satisfy design basis requirements with high safety margins. Accordingly, this change will not create the possibility of a new or different kind of accident from any accident previously evaluated. In addition, there is no possibility that the credible failure of any portion of the modified upper lateral support configuration could produce any new initiating event.
- 3. This change does not involve a significant reduction in a mar in of safet The enclosed report documents the evaluation of the modified support configuration under design basis loading conditions.
This report concludes that the acceptance criteria for RCS piping stresses and component support loads are'atisfied. These acceptance criteria incorporate conservatisms such that by satisfying the criteria the established margins of safety are maintained. Furthermore, Tables 4 and 7 of the enclosed report indicate that the actual stress or load as a fraction of the allowable load remains the same as, or decreases, for the modified support configuration. Therefore, there are no significant reductions in the margins of safety.
