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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 Make the following changes in the Technical Specfication.
Remove Xnsert Page 3.11-1 to 3.11-4 Page 3.11-1 to 3.11-4 Page 4.11-1 Page'.11-1 1
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Fuel Handlin in the Auxilia Buildin A licabilit Applies to limitations while moving irradiated fuel in the operating floor area of the auxiliary building.
To limit doses in the event an irradiated fuel assembly is damaged significantly.
S ecification During handling of fuel assemblies in the auxiliary building when either the fuel being handled or the fuel stored in the spent fuel storage pool has decayed less than 60 days since irradiation, the following conditions shall be satisfied:
a ~ One auxiliary building main exhaust fan shall be operating.
- b. The auxiliary building exhaust fan 1C, which takes suction from the spent fuel storage pool area, shall be operating.
c ~ All doors, windows, and other I
direct openings 4
between the operating floor area and the outside shall be closed excep't that the personnel door w
may be opened'or access as required.
d ~ Roughing filters shall be installed at the inlet to the adsorbers.
3 ~ 11 1 Proposed
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- e. Charcoal absorbers shall be installed in the ventilation system exhaust from the spent fuel storage pool area and shall be operable.
3.11.2 Radiation levels in the spent fuel storage area shall be monitored continuously.
3.11.3 A load in excess of one fuel assembly and its handling tool shall never be stationed or permitted to pass over storage racks containing spent fuel.
3.11.4 The spent fuel pool temperature shall be limited to 150 F.
Basis:
Charcoal adsorbers will reduce significantly the consequences of ll a refueling accident which considers the clad failure of a single irradiated fuel assembly. Therefore, charcoal adsorbers should be employed whenever recently irradiated fuel is being handled.
This requires that the ventilation system should be operating and drawing air through the adsorbers. The only exception to the requirement occurs when the fuel being handled, or any fuel in the storage pool, has decayed at least 60 days since irradition.
The consequences of a fuel handling accident, in this case without operation of the charcoal absorbers is significantly less than the guidelines of 10CFR100.
Amendment No.10 3 ~ 11 2 Proposed
The desired air flow path, when handling irradiated fuel, is from the outside of the building into the operating floor area, toward the spent fuel storage pool, into the area exhaust ducts, through the adsorbers, and out through the ventilation system exhaust to the facility vent. Operation of a main auxiliary building exhaust fan assures that. air discharged into the main ventilation system exhaust duct will go through a HEPA and be discharged to the facility vent. Operation of the exhaust fan for the spent fuel storage pool area causes air movement on the operating floor to be toward the pool. Proper operation of the fans and setting of dampers would result in a negative pressure on the operating floor which will cause air leakage to be into the building.
Thus, the overall air flow is from the location of low activity (outside the building) to the area of highest activity (spent fuel storage pit). The exhaust air'flow would be through a roughing filter and charcoal before being discharged from the
,I facility. The roughing 'filter protects the adsorber, from becoming fouled with dirt; the adsorber removes iodine, the isotope of highest radiological signficance, resulting from a fuel handling accident. The effectiveness of charcoal for removing iodine is assured by having a high throughput and a high removal efficiency.
The throughput is attained by operation of the exhaust fans. The high removal efficiency is attained by minimizing the amount of iodine that bypasses the charcoal and having charcoal with a high potential for removing the iodine that does pass through the charcoal.
3 ~ 11 3 Proposed
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The spent fuel pool temperature is limited to 150'F because if the spent fuel pool cooling system is lost at that temperature, sufficient time (approximately 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />) is available to provide back-up cooling, assuming the maximum anticipated heat load (full core discharge 6 previously stored fuel), until a temperature of 180'F is reached, the temperature at which the structural integrity of the pool was analyzed and found acceptable.
References (1) FSAR Section 9.3-1 (2) ANS-5.1 (N 18.6), October 1973 (3) Letter, J.A. Zwolinski, (USNRC) to R.W. Kober, (RG6E),
November 14, 1984.
, 3.11-4'roposed
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4.11 Refuelin A l icabilit
,- Applies to refueling and to fuel handling in the spent fuel pool.
S ecification
- 4. 11. 1 Spent Fuel Pit Charcoal Absorber System 4.11.1.1 Within 60 days prior to any operation of the spent fuel pool charcoal absorber system as required by Section 3.11, the following conditions shall be demonstrated.
After the conditions have been demonstrated, the occurrence of painting, fire, or chemical release in any ventilation zone communicating with the spent fuel pool charcoal absorber system shall require that the following conditions be redemonstrated, before fuel handling may continue, if operation of the spent fuel fuel pool charcoal absorber system, is required per section 3.11 a 0 The total air flow rate from the charcoal absorbers shall be at least 75% of that measured with a complete set of new absorbers; b.' In-place Freon testing, under ambient conditions, shall show at least 99% removal.
~ The results of laboratory analysis on a carbon sample shall show 90$ or greater radioactive methyl iodide removal when tested at least 150'F and 95% RH and at 1.5 to 2.0 mg/m 3 loading with tagged CH I.
- 4. 11-1 Proposed
V A Attachment B The proposed change to the Technical Specification deletes the requirement for operation of the charcoal filters when moving fuel in the auxiliary building when the fuel has decayed 60 days since irradiation, and when fuel stored in the pool has decayed at least 60 days.
In response to a request for expansion of the spent fuel storage pool capacity, the NRC SER documented the NRC staff evaluation of the radiological consequences of a tornado missile impact on Region 2 of the spent, fuel storage racks. In this analysis, a cooldown time of 60 days and damage to nine fuel assemblies was assumed. No credit was taken for operation of charcoal filters. For this case the offsite radiological con-sequences were calculated to be 2 rem thyroid and 0.1 rem whole body.
Adjusting these calculated results for damage to only one fuel assembly corresponding to a fuel handling accident, yields resulting doses of approximately 0.2 rem thyroid and 0.01 rem whole body. These consequences are well within the guidelines of 10CFR100 and are significantly less than doses previously considered by the NRC to be acceptable.
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Attachment C In accordance with 10CFR 50.91 this change to the Technical Specifications has been evaluated against three criteria to determine if the operation of the facility in accordance with the proposed amendment would:
- 1. involve a significant, increase in the probability or consequences of an accident previously evaluated; or
- 2. create the possibility of a new or different kind of accident from any accident previously evaluated; or
- 3. involve a significant reduction in a margin of safety.
Reference 1 provides an evaluation by the NRC of the limiting thyroid dose that would result from damage to fuel that had decayed 60 days since irradition. As discussed in Attachment B, these results can be used to evaluate the consequences of a fuel handling accident inside the auxiliary building with no credit for iodine removal due to operation of the charcoal filters. The resulting thyroid dose of 0.2 Rem is well within the guidelines of 10CFR 100 and is less than that which was previously considered to be acceptable by the NRC.
Therefore, a no significant hazards finding is warranted because: i the probability of a fuel handling accident is unchanged and the consequences are, less than those previously evaluated, t Jp
- 2) the possibility of a new or different kind of accident is not created, and
- 3) the margin of safety is not reduced due to the resulting dose being less than that previously considered acceptable.
References (1) Letter, Mr. J.A. Zwolinski, NRC, to Mr. R.N. Kober, RG&E, November 14, 19S4.
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