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] |
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Attachment A
- 1. Make the following changes in the Technical Specifications.
Remove Insert pages 3.11-2 through 3.11-3 pages 3.11-2 through 3.11-3 3.11-5 8401250301 840ii8 r PDR ADOCK 05000244 PDR j
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- e. Charcoal adsorbers shall be installed in the ventilation system exhaust from the spent fuel storage pit area and shall be operable.
3.11.2 Radiation levels in the spent fuel storage area shall be monitored continuously.
3.11.3 The trolley of the auxiliary building crane 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.
3.11.5 The spent fuel shipping cask shall not be carried by the auxiliary building crane, pending the evaluation of the spent fuel cask drop accident and the crane design by RGGE and NRC review and approval.
Basis:
Charcoal adsorbers will reduce significantly the consequences of a refueling accident which considers the clad failure of a single irradiated fuel assembly. Therefore, charcoal adsorbers should be employed whenever irradiated fuel is being handled. This requires that the ventilation system should be operating and drawing air through the adsorbers.
The desired air flow path, when handling irradiated fuel, is from I'
the outside of the building into the operating floor area, toward the spent fuel storage pit, 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 Amendment No. , 4, 6 3.11-2 proposed
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 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 pit area causes air movement on the operating floor to be towards the pit. Pioper operation of the fans and setting of dampers would result in a negative pre'ssure 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 facility. The roughing filter protects the adsorber from becoming fouled with dirt; the adsorber removes iodine, the isotope of highest radiological significance, resulting from a fuel handling accident. The effectiveness of charcoal foi 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 potenti;al for'removing the iodine that 'does pass through the charcoal.
Amendment No. P1, P6 3 ~ 11 3 Proposed
Attachment B In 1976, Rochester Gas & Electric replaced the original R. E. Ginna spent fuel storage racks, increasing the storage capacity of the pool by decreasing the center-to-center spacing of the storage locations.
In evaluating the radiological consequences of missiles, RG&E proposed a spent fuel storage pattern whereby the probability of a missile impact on spent fuel that had decayed less than 60 days was not increased. Therefore, the density of fission product inventory maintained in any local area was less than that which had been stored in the original storage racks. This was accepted by the NRC and the required storage pattern was incorporated into the Technical Specifications (Reference 1).
Because of anticipated requirements upon the storage capacity of the racks, RG&E requested U.S. Tool & Die (USTD) to perform an analysis of the effect of a vertical and horizontal impact of the missile with the greatest potential for damage to the rack and contained fuel assemblies (attached). Design values for tornado .
wind speed and missile characteristics were those established in '-.
the NRC review of Systematic Evaluation Program (SEP) Topics III-2, Wind and Tornado Loadings, and III-4.A, Tornado Missiles (Ref. 4 and 5). This missile is characterized as a 1490 lb. wood pole, 35 ft. in length with a diameter of 13.5 inches. USTD assumed a tornado wind velocity of 132 mph and accounted for the drag effects of the pool water above the racks using Reference 3.
The results of this analysis indicated that vertical defor-mation would be no greater than 1.40 inches and there would be no deformation from a horizontal impact. This limited deformation does not change appreciably for higher tornado wind speeds.
Additional margins are available to accommodate higher tornado wind speeds. For example, calculations performed assuming a tornado wind speed of 200 mph yield a vertical deformation of 1.8 inches and at worst a small amount of localized plastic deformation for a horizontal impact.
These results are conservative for the following reasons:
- 1. The energy absorbed by the pole is neglected.
that .upon impact the pole, would, split,.along the Itgrain is likely reducing the fraction of total energy absorbed by the rack.
- 2. It is assumed that the missile enters the water at an orientation exposing the minimum cross sectional area perpendicular to the direction of travel. For a vertical impact in the 132 mph case, a change in the missile orientation of only decrease the kinetic energy on impact from 79,000 5'ould ft./lb. to approximately 12,000 ft./lb. Similar reductions would occur at higher wind speeds also.
- 3. For a horizontal impact, the increase in the distance that the missile must travel through water relative to a vertical impact was neglected.
In October 1981, the NRC completed an evaluation of the consequences of a postulated fuel handling accident inside contain-ment (Reference 2). In 'this evaluation the staff calculated the offsite dose consequences assuming damage to all the rods of one fuel assembly occurring 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> after shutdown, and 100% of the activity released from the pool was released to the atmosphere.
The resulting calculated dose at the EAB was 96 rem.
sec/m 3 corres-4.
This analysis used a X/Q value of 4.8 x 10 ponding to a probability level of .5%. The RG&E submittal of June 30, 1981 for SEP Topic II-2.C determined that5the direction dependent X/Q at. a 5% probability level is 6 x 10 sec/m . This value is still very conservative and more appropriate given the high winds and excellent dispersion associated with tornado conditions.
If the 5% X/Q value was used, the dose at the (Exclusion5 Area boundary) EAB would be reduced by a factor of 8 (6 x 10 /4.4 x 10 ) resulting in a value of 12 rem for damage to all rods of =.
one fuel assembly 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> after shutdown.
The worst position for impact of a missile would be centered on a fuel storage location where, because of the 13.5 inch missile radius compared to a diagonal dimension of the box of 11.9 inches, the corners of four other fuel storage locations would be damaged.
Because of the limited deformation of the storage box, difficult to postulate damage beyond the equivalent of it one is assembly.
However, even assuming that all 5 fuel assemblies were severely damaged, and that all fuel assemblies could be moved to the spent fuel pool within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, and that all 5 fuel assemblies were peak power assemblies, the upper bound on the dose at the EAB would be 5 x 12 or 60 rem. This result is well within the guide-lines of 10CFR 100 (300 rem) and is less than what the NRC previously considered acceptable and approved for Ginna for the postulated fuel handling accident inside containment.
Therefore it is acceptable to delete the restriction on storage of recently discharged fuel in the spent fuel pool.
References
- 1. Letter, A. Schwencer, USNRC to L. D. White, RGSE, November 15, 1976.
- 2. Letter, D. M. Crutchfield, USNRC, to J. E. Maier, RG&E, October 7, 1981.
- 3. D. R. Miller, W. A. Williams, "Tornado Protection for the Spent Fuel Storage Pool," General Electric APED-5696, November 1968.
- 4. Letter, D. M. Crutchfield, USNRC to J. E. Maier, RG&E, August 22, 1983.
- 5. NUREG-0821, Supplement No. 1, Integrated Plant Safety Assessment, Systematic Evaluation Program, August 1983.
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