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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
TABLE 3.5-1 (Continued PROTECTION SYSTEM INSTRUMENTATION 5
OPERATOR ACTION TOTAL NO. of MIN. PERMISSIBLE IF CONDITIONS OF CEDHNEL NO. of KDHNELS OPERABLE BYPASS COLUMN 1 OR 3 OPERABLE NO. FUNCTIONAL UNIT CHANNELS TO TRIP KiANNELS CONDITIONS CANNOT BE MET ABOVE
- 19. Degraded Voltage 2/bus 2/bus 1/bus T = 350 F 480V Safeguards Bus
- 20. Automatic Trip Logic Note 4 14 Note 5 Including Reactor Trip Breakers NOTE 1: When block condition exists, maintain normal operation.
NOTE 2: Channels should be operable at all modes below the bypass condition with the reactor trip system breakers in the closed position and control rod drive system capable of rod withdrawal.
NOTE 3: Channels shall be operable at all modes below the bypass condition except during refueling defined to be when fuel is in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.
NOTE 4: One reactor trip breaker may be bypassed for surveillance testing provided the other reactor trip breaker is operable.
NOTE 5: Channels shall be operable at all modes above refueling when the control rod drive system is capable of rod withdrawal unless both reactor trip breakers are open.
F.P. Full Power SS'01270014 890117 PDR ADOCK 05000244 P PNU
- 12. With the number of operable channels less than the Total Number. of Channels, operation may proceed provided the inoperable channel is placed in the tripped, condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Should the next Channel Functional Test require the bypass of an inoperable channel to avoid the generation of an actuation. signal, operation may proceed until this Channel Functional. Test. At the time of this Channel Functional Test, or. if at any "time the number of operable channels is less than the Minimum Operable Channels required, be at hot shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and at an RCS temperature less than. 350'F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
- 13. With the number of operable channels less than the Minimum Operable Channels required, operation may continue provided the containment purge and exhaust valves are
-
maintained closed.
- 14. Should one reactor trip breaker or channel of trip logic be inoperable the. plant must not be in the operating mode following a six, hour time period, and the breaker must be open.
If one of the (undervoltage diverse reactor trip breaker trip features or shunt trip attachment) on one breaker is inoperable, restore it to operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or, declare breaker inoperable. If at. the end of the 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period one trip feature is inoperable it must be repaired or the plant must not be in. the operating mode, and the reactor trip breaker must be open, following an additional six hour time period. The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required for performing maintenance to restore the breaker to operable status.
Amendment No. 3.5-15 Proposed
TABLE 4. 1-1 (CONTINUED)
Channel Descri tion Check Calibrate Test Remarks
- 25. Containment Pressure R M Narrow range containment pressure
(-3.0, +3 psig) excluded
- 26. Steam Generator Pressure
- 27. Turbine First Stage Pressure
- 28. Emergency Plan Radiation M Instruments
- 29. Environmental Monitors M NA NA
- 30. Loss of Voltage/Degraded NA Voltage 480 Volt Safeguards Bus
- 31. Trip of Main Feedwater Pumps NA NA
- 32. Steam Flow 33 ~ T.
- 34. Chlorine Detector, Control Room NA Air Intake
- 35. Ammonia Detector, Control Room NA Air Intake
- 36. Radiation Detectors, Control Room NA Air Intake
- 37. Reactor Vessel Level NA Indication System 38a. Trip Breaker NA NA Notes 1, 2 and 3 Logic Channel Testing 38b. Trip Breaker NA NA Note 1 Logic Channel Testing
TABLE 4. 1-1 (CONTINUED)
Channel Descri tion Check Calibrate Test Remarks
- 39. Reactor Trip Breakers NA NA Function test - Includes independent testing of both undervoltage and shunt trip attachment of reactor trip breakers. Each of the two reactor trip breakers will be tested on alternate months.
Note 2 40 'anual Reactor Trip NA NA Includes independent testing of both undervoltage and shunt trip circuits. The test shall also verify the operability of the bypass breaker.
41a. Reactor Trip Bypass Breaker NA NA Using test switches in the reactor protection rack manually trip the reactor trip bypass breaker using the shunt trip coil.
41b. Reactor Trip Bypass Breaker NA NA Automatically trip the under-voltage trip attachment.
NOTE 1: Logic trains will be tested on alternate months corresponding to the reactor trip breaker testing.
Monthly logic testing will verify the operability of all sets of reactor trip logic actuating contacts on that train (See Note 3). Refueling shutdown testing will verify the operability of all sets of reactor trip actuating contacts on both trains. In testing, operation of one set of contacts will result in a reactor trip breaker trip; the operation of all other sets of contacts will be verified by the use of indication circuitry.
NOTE 2: Testing shall be performed monthly, unless the reactor trip breakers are open, or shall be performed prior to startup if testing has not been performed within the last 30 days.
NOTE 3= The source range trip logic may be excluded from monthly testing provided prior to startup.
it is tested within 30 days
ATTACHMENT B This proposed Technical Specification change reflects the request made in the January 9, 1987 NRC letter from Dominic C. DiIanni to Roger W. Kober concerning the "Review of Design for Automatic Shunt Trip for Reactor Trip Breakers (Generic Letter 83-28 Item 4.3)".
The proposed changes incorporate on-, line reactor trip breaker testing into the Technical Specifications. A detailed description of all the changes is presented on Table 1.
This change in Technical Specifications clearly is not a request for a change in the authorized power level as it is related only to operational and testing requirements of the reactor trip breakers within the plant. Further, the major possible consequence of this change that can be foreseen. at this time is that over a period of time additional plant trips may occur through actions taken during monthly testing of the reactor trip breakers. However, occasional trips are considered within the normal operating conditions at a power plant.
A significant hazards analysis has been accomplished against the criteria in 10CFR50.92. Because the proposed changes constitute additional limitations and control on both operation and testing they do not:
(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.
Therefore, Rochester Gas and. Electric submits that the issues associated with this amendment request 'warrant a no significant hazards finding.
L l
1 1
TABLE, 1 Detailed Technical S ecification Chan es Location Descri tion of Chan e Reason for Chan e
- p. 3.5-8, Add Item 20 - Automatic Trip This change reflects new Table 3.5-1 Logic including Reactor Trip operating condition require-Page 3 of 3 Breakers. ments for the Reactor Trip Breakers and reactor trip logic.
Change Note 3 - the fifth Correct typographical error.
word of sentence should be changed from "of" to "at".
Add Note 4 to the bottom of This Note is needed to this page. explain the bypass condition in the new Item 20.
- p. 3.5-15 Add Number 14 to the bottom This note is required to Action Statement of this page. explain fully the operator actions required if the requirement of column 3 for line 20 of Table 3.5-1 cannot be met.
- p. 4.1-7 Add Items 38a and 38b con- This addition reflects new Table 4.1-1 cerning logic testing on a testing requirements in monthly and refueling outage response to NRC letter basis. '3-28.
- p. 4.1-7a Add Item. 39 concerning the This addition reflects new Table 4.1-1 testing of Reactor Trip testing requirements in Breakers. response to NRC letter 83-28.
Add Item 40 concerning the This addition reflects new testing of the manual testing requirements in tripping of the Reactor response to NRC letter Trip Breakers. 83-28.
Add Items 41a and 41b con- This addition reflects new cerning the testing of the testing requirements in Reactor Trip Bypass Breaker. response to NRC letter 83'"28.
Add Notes 1, 2, 3 These notes are required to explain the testing requirements of the logic associated with the Reactor Trip Breakers.
'I t
~ ~ ~
Table 1 (Cont'd)
Lines in the margins showing changes indicate changes in the Technical Specifications as currently approved by the NRC. The substance of this submittal is the same as that of our January 26, 1988 letter which was supplemented by our August 26, 1988 letter. Both were of the. same subject.
This letter does reflect the fact that Amendment No. 30 was approved and thus if one compares this submittal with the August submittal, one would find the item numbers on Table 4.1-1 changed from 37a, 37b, 38, 39, 40a and 40b to 38a, 38b, 39, 40, 41a and 41b, respectively. In addition, the above table has been changed to accurately detail these numbering changes.