Similar Documents at Ginna |
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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]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML17265A6401999-05-12012 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
ML17309A6521999-04-14014 April 1999
Rev 14 to AP-RCS.1, Reactor Coolant Leak.
ML17311A0701999-04-14014 April 1999
Rev 10 to AP-PRZR.1, Abnormal Pressurizer Pressure.
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.
ML17265A5571999-02-25025 February 1999
Rev 4 to Technical Requirements Manual (Trm).
ML17265A5481999-02-12012 February 1999
to EOP ATT-22.0, Attachment Restoring Feed Flow.
ML17265A5491999-02-12012 February 1999
to EOP FR-H.5, Response to SG Low Level.
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.
ML20198C0581998-12-14014 December 1998
Rev 5 to FR-Z.1, Response to High Containment Pressure
ML20198C0361998-12-14014 December 1998
Rev 11 to ECA-0.2, Loss of All AC Power Recovery with SI Required
ML20198C0521998-12-14014 December 1998
Rev 13 to FR-S.1, Response to Reactor Restart/Atws
ML20198C0411998-12-14014 December 1998
Rev 16 to FR-C.1, Response to Inadequate Core Cooling
ML20198C0121998-12-14014 December 1998
Rev 10 to AP-RCS.2, Loss of Reactor Coolant Flow
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
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
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.
ML17265A1541997-09-16016 September 1997
Rev 1 to DA EE-92-089-21, Design Analysis Ginna Station Instrument Loop Performance Evaluation & Setpoint Verification.
ML17264A9751997-08-0505 August 1997
Rev 14 to AP-ELEC.1, Loss of 12A & 12B Busses.
ML17264A9771997-08-0505 August 1997
Rev 11 to AP-RCP.1, RCP Seal Malfunction.
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.
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.
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
ML20140B8291997-03-24024 March 1997
Rev 3 to EOP ATT-12.0, Attachment N2 Porvs
ML17264A8221997-02-0606 February 1997
Rev 15 to FR-P.1, Response to Imminent Pressurized Thermal Shock Condition.
ML17264A8201997-02-0606 February 1997
Rev 7 to AP-RCC.2, Rcc/Rpi Malfunction.
ML17264A8081997-01-23023 January 1997
Revised Emergency Operating Procedures,Including Rev 14 to E-1,Rev 19 to E-3,Rev 14 to ECA-2.1,Rev ECA-3.3,Rev 20 to ES-1.3,Rev 13 to FR-C.1,Rev 12 to FR-C.2 & Rev 14 to FR-P.1
ML20133N3351997-01-10010 January 1997
Rev 7 to FR-C.3, Response to Saturated Core Cooling
ML17264A8881996-10-10010 October 1996
Rev 9 to ODCM for Ginna Station.
ML20128N0681996-10-0303 October 1996
Revised Emergency Operating Procedures,Including Rev 5 to Att-10.0, Attachment Faulted S/G & Rev 6 to Att-16.0, Attachment Ruptured S/G
ML17264A5311996-05-31031 May 1996
Revised Emergency Operating Procedures,Including Rev 10 to AP-RCP.1,Rev 12 to ECA-0.1,Rev 12 to ECA-2.1,Rev 3 to FR-H.2,Rev 3 to FR-H.4,Rev 7 to FR-I.1,Rev 12 to FR-P.1,Rev 10 to FR-S-1 & Rev 6 to FR-S.2
ML17264A5161996-05-22022 May 1996
Rev 2 to Technical Requirements Manual (TRM)
ML17264A4581996-04-0808 April 1996
Rev 7 to ODCM for Ginna Station.
ML17264A4371996-04-0101 April 1996
Rev 1 to Technical Requirements Manual (TRM)
ML17264A4391996-04-0101 April 1996
Rev 1 to Updated Technical Requirements Manual (TRM)
ML17264A4191996-02-24024 February 1996
Rev 0 to Technical Requirements Manual (Trm).
ML17264A6901996-02-23023 February 1996
Rev 0 to Inservice Testing Program.
1999-05-12
[Table view] |
Text
GlNNA STAmpg UNlT ¹S COMPt Eon OATE:-
ROCHESTER GAS AND ELECTRIC CORPORATIO T!IVIE;
'GINNA STATION CONTROLLED COPY NUMBER PROCEDURE NO. J A-25.4 REV. NO. 8 REACTOR POST TRIP REVIEW TECHNICAL REVIEW PORC REVIEW DATE QO REVIEW PLANT S ERINTENDENT EFFECTIVE DATE QA~ NON-QA CATEGORY 1.0 REVIEWED BY:
THIS PROCEDURE CONTAINS 7 PAGES S509>00077 S50903'-
.".. P.: ",PDR PDR "ADOCK,05000244'
i 1
1
A-25 ':1 A-25.4 REACTOR POST TRIP REVIEW 1~0 PURPOSE:
To define duties and responsibilities for the conduct of a reactor post trip review. This review will be conducted to determine the causes of all unplanned reactor trips (i.e. opening of trip breakers without all control rods fully inserted) at Ginna Station.
1~2 To define the scope of the review and the records that must be reviewed to perform this assessment.
2 '
REFERENCES:
2.1 Facility Technical Specifications 2.2 A-25 "Reporting of Unusual Plant Conditions" 2 ' A-25.1 "Ginna Station Event Report" 2 ' ,0-9.3 "NRC Immediate Notification" 2.5 Internal NRC Memo From R.W. Starostecki, Director, .DPRP
3.0 INSTRUCTIONS
3.1 Control Room 0 erator 3~1~1 Submit an A-25.1, "Unusual Event Report"'.
3 ~ 1.2 Inform Shift Supervisor of unusual conditions or observations made during the event.
3 ' Shift Technical Advisor 3.2.1 The Shift Technical Advisor shall perform a preliminary assessment of the event. This shall be documented by completion of the attached Post-Trip Review Form.
A-25 ~ 4 2 3 ' ' Upon completion of the form, forward it to the Shift Supervisor for inclusion with the A-25.4 Review.
3.2.3 The Shift Technical Advisor will also, upon request of the Shift Supervisor, assist with the Shift Supervisor's assessment.
3.3 Other Plant Personnel 3 ~ 3 ~ 1 Any other plant personnel that are involved with the event (Auxiliary Operators, I&C Techs, Electricians, etc.) should make themselves available to the Shift Supervisor to answer any question(s) about their involvement in the event.
3 ' Shift Su ervisor 3 '.1 The Shift Supervisor is to review the A-25.1 report, Operator notes, the Shift Technical Advisors assessment and any other information available to make a prelim-inary assessment of the cause of the Reactor Trip. The Shift Supervisor may call upon the Shift Technical Advisor and any other plant personnel to assist him in his assessment. The Shift Superviso'r Assessment and material used in the assessment will be passed to the Duty Engineer after the Shift Supervisor completes his assessment.
3.4.2 The Shift Supervisor shall review the event and assign one of the following classifications to the event. (Mark other classifications N/A) .
3 ' '.1 Condition One the cause of the trip is positively known. All safety-related and other important equipment functioned properly during the trip.
3 ' '.2 Condition Two - the cause of the trip is positively known. Some sa fety-related and/or other important equipment functioned in an abnormal or degraded manner.
3.4.2 ' Condition Three - the cause of the trip is not positively known.
A-25.4:3 3 ' Dut En ineer 5~1 The Duty Engineer shall review the Shift Supervisor's 3 ~
"assessment of the eve'nt.
review'rintout is available Ifit shall the computer post trip also be review-ed. The Duty Engineer shall make an assessment of the cause of the event. The Duty Engineer shall forward all materials, including his assessment, to the Plant Superintendent.
3.5.2 The Duty Engineer shall review the event classificat-ion. If the Duty Engineer does not concur with the Shift Supervisor's classification, the PORC will review the event and classify it.
3.6 Plant Su erintendent 3.6 ~ 1 The Plant Superintendent shall schedule a meeting of the Plant Operations Review Committee (PORC) with the purpose of reviewing the event.
3 ~ 6.2 All events regardless of classification shall be reviewed by the PORC and the Plant Superintendent's permission granted before the Reactor may be restarted.
- 3. 6.3 In the event that the cause of the trip is positively known and all Safety Related equipment functioned properly, the Plant Superintendent may authorize the Reactor restart prior to completion of all the attachments to this procedure.
3 ' PORC 3.7.1 Reports shall be presented by Subcommittee Chairman as identified on Attachment B.
3.7 ' PORC shall review the event and either concur with the assessment presented to it or initiate its own investigation into the cause of the event. Attachment C identifies necessary criteria for plant restart.
I 3 ' ' PORC shall determine stions are resolved.
if all safety or Tech Spec. que-3.7.4 PORC shall recommend to the Plant Superintendent whether or not to allow a Reactor restart.
l A-25.4:4 3 ' 0 erations Mana er 3.8 ~ 1 Operations Manager or his alternate shall review this material and concur with PORC's assessment prior to taking the reactor critical.
3.9 Corrective Actions 3.9.1 Any member of the plant staff may initiate corrective action by bringing the matter to the attention of plant management or the Shift Supervisor.
3.9 ' The plant shall not be made critical after a trip until the event has been reviewed and the cause is known.
4.0 RECORDS
4.1 Records of the review shall be noted in the minutes of the PORC meeting.
4.2 The PORC minutes shall be the permanent record of the review.
4.3 All material used in the Post Trip Review to shall be attached to this procedure and forwarded Central Records.
COMPLETION DATE COMPLETED BY:
OPERATIONS MANAGER:
A-25.4:5 REACTOR POST TRIP REVIEW (Refer to A-25.4 for Instructions)
A-25.4 TIME OF TRIP: DATE:
II. DESCRIPTION OF EVENT:
III. ACTIONS PERFORMED BY STA:
a) Procedures referred to:
b) Parameters observed:
c) Recognition/Diagnosis reached:
d) Advice given to Shift Supervisor:
IV. CAUSE OF EVENT:
V. ADDITIONAL COMMENTS:
SHIFT TECHNICAL ADVISOR:
A-25.4:6 ATTACHMENT B PORC SUBCOMMITTEE CHAIRMAN ASSIGNMENTS Evaluation of Safet Technical and Tech. S ec. uestions and Review A ainst A licable Information from the UFSAR and Prior Transients Technical Manager alternates: Nuclear Engineer Duty Engineer Evaluation of E i ment Malfunctions and Re air Plans Maintenance Manager alternates: I&C Supervisor Maintenance Supervisor Post Tri Review Cause Identification A-25.4 Re ort Summar P
Operations Manager alternates: Operations Supervisor Duty Engineer Startu Plans and Se uence Planner
A-25 ':7 ATTACHMENT C PORC REVIEW CRITERIA Root cause of problem(s) has been identified.
2 ~ A clear sequence of events has been determined.
3 ~ All near term corrective actions have been taken to resolve the root cause of the trip.
4 ~ Long term corrective actions are outline and a method for tracking them has been established.
5 ~ All ma j or sa fety systems and other important equipment responded properly or the root cause of the problem(s) found and circumstances reviewed to assure that no new potential safety concerns were identified.
- 6. Operation of plant systems during the trip was consistent to any applicable information provided in the UFSAR.
7 ~ Where possible, comparison with previous similar events has been made and no unexplained differences in operation of plant systems occurred.
- 8. Failure of any items from g5 shall be compared against A-25.4 reports and if necessary equipment history files to determine if any failures are repetitive in nature or involve common mode failures. Separate tracking documents may be initiated to follow corrective action on these items.
Items 6, 7, and 8 should include the information being used for comparison.
