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
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~~OCUL& 'tO RSSP-1. 5 ' 7 '0 .
VALVE INTERLOCK VERIFICATION FEEDNATER ISOLATION T:-(." CC.4L ~=a ~=;i
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RSSP-1.5:1 RSSP-1.5 VALVE INTERLOCK VERIFICATION " FEEDWATER ISOLATION
1.0 PURPOSE
To describe the steps necessary to perform the valve interlock verification for feedwater isolation.
2.0 TEST REQUIREHENTS:
2.1 To verify interlocks associated with high steam generator levels, system Tavg..and turbine trip.
3.0
REFERENCE:
3.1 Foxboro Instrument Block Diagrams BD18 and BD19 4.0 INITIAL CONDITIONS:
4 1
~ Plant in either hot or cold shutdown PRECAUTIONS:
.5. 1 If secondary side condensate system is pressurized, the guard valves before the Steam Generator flow control, main and bypass (I,oop A 6 B) valves must be maintained closed.
5.2 If test is conducted during hot shutdown, the Steam Dump Proportional Unit (steam dump cabinet) must be placed on manual.
5.3 If test is performed when plant maintenance is being performed verify that conductance of test will not conflict with maintenance work or comprimise safety of maintenance people.
5.4 If plant is in hot shutdown, any feedwater make up to steam generators is to be supplied by Auxiliary Feedwater system.
6.0 INSTRUCTIONS
6.1 Prior to checking F.W. valve interlocks, check the valves for operability as follows:
6.1.1 Verify that Hain Feedwater valves have been manually cranked to the neutral position.
6 .1.2 Verify that air supply is turned on to valve positioner.
6.1.3 Verify feedwater isolation reset at Control Board.
6.2 -Ensure that the following RC system level control bistables are energized.
RSSP-1.5:2 6.2.1 LC-461 A/B bistable (Loop A steam generator) 6.2.2 LC-462 B/C bistable (Loop A steam generator) 6.2.3 LC-463 C/D bistable (Loop A steam generator) 6.2.4 LC-471 A/B bistable (Loop B steam generator) 6.2.5 LC-472 B/C bistable (Loop B steam generator) 6.2.6 LC-473 C/D bistable (Loop B steam generator)
Note: To be energized, the water level in S/G's must be less than 70%. If level is high (greater 70'/) than a DC current generator must be utilized at the test jacks of the concerned channels and a simulated input injected.
6.3 Place C.B. Hand-automatic transfer station for the following main feedwater controllers on manual.
6.3.1 HC-466 Loop "A" LCV 6.3.2 HC-476 I,oop "B" LCV 6.4 Place CB Hand-automatic transfer station for the following by-pass Controllers on manual.
6.4.1 HC-480 Loop "A" by-pass' 6.4..2.. HC-. 481. Loop "B" by-pass 6.5 Stroke the following main and by-pass feedwater valves for Loop A 6 B through full cycle and then leave in open position.
Note: Valve action should be verified by visual observation.
cycled left open 6.5.1 FCV-466 Loop A 6.5.2 FCV-480 6.5.3 FCV-476 Loop B 6.5.4 FCV-481 6.6 To verify action Hi level override, establish a 2/3 logic by placing the following bistables in the trip mode (proving switch in protection racks).
6.6.1 LC-461A Loop A tripped 6.6.2 LC-462B 6.6.3 LC-471A Loop B 6.6.4 LC-472B 6.7 Verify visually that all FCV's have automatically stroked to their closed positions.
6 '.1 FCV-466 closed FCV-480 FCV-476 FCV-481 NOTE: Verification of remaining logic combination need not be done at this .time as a subsequent test (at safeguard test panel) will prove out this capability.
RSSP-1.5:3 6.8 Return the bistable proving switches for the following bistables position and verify that the valves open automatically. Reset to'ormal by-pass valves if necessary.
valve open 6.8.1 LC-461A 1 FCV-466 6.8.2 LC-462B ) FCV-480 6.8.3 LC"471A FCV-476 6.8.4 LC-472B ) FCV-481 6.9 Disconnect field input terminals to temperature control bistable to TC 401F (Steam Dump rack at li.C.B.)
6.10 Connect DC current generator to input terminals of TC 401F bistable and inject a signal equivalent to that which corresponds to a T avg.
temperature greater than 554 F (approx. 556 F) 6.11 Place the following CB tfain F.W. Hand-automatic transfer stations in the auto position and verify that the valves are open:
6.11.1 HC-466 Loop A LCV 6.11.2 HC-476 Loop A LCV 6.12 By-pass valve controllers were left on hand control from previous step. Verify that the following valves are open:
6.12.1 LCV-480 Loop A 6.12.2 LCV-481 Loop B 6.13 Decrease input signal, to TC 401F bistable equivalent to that which corresponds to a T avg. temperature less than 554 F (approx. 552 F) 6.14 Verify that the following valves have stroked automatically to the closed position.
6.14.1 FCV-466 Loop A 6.14.2 FCV-480 6.14.3 FCV-476 Loop B 6.14.4 FCV-481 6.15 Simulate turbine operation condition by blocking open two of the 63 AST auto stop oil pressure mercoids..
6.16 Verify that the following valves have stroked automatically to their open position:
RSSP"1.5:4 6.17.1 FCV-466 I,oop A 6.17.2 FCV-480 6.17.3 FCV-476 I,oop B 6.17.4 FCV-481 6.18 Unblock the two 63 AST.mercoids which were blocked in step 6.16 above.
- 6. 19 Verify that the following valves have stroked automatically to their closed positions:
6.19.1 LCV-466 Loop A 6.19.2 LCV-480 6.19.3 LCV-476 Loop B 6.19.4 LCV-481 6.20 Increase input to,temperature control bistable TC 401F to that which corresgonds to a T avg. temperature greater than 554 0 F (approx. 556 F) 6.21 Verfiy that the following valves have stroked automatically to their open position:
6.21.1 LCV-466 Loop A 6.21.2 I,CV-480 6.21.3 LCV-476 I,oop B 6.21.4 LCV-481 6.22 Jog switch on controllers HC-466 and HC-476 from Auto to manual several times to decrease controller output to 0% and verify that the following valves remain in the open position: (Observe small indicators above controllers for Q 6.22.1 FCV-466 Valve open 6.22.2 FCV-476 Valve open 6.22.3 FCV-466) FCV-467 Auto 6.23 Vith by-pass valve controller HC-481 and HC-480 on manual position, adjust output to 0/ and verify the following valves rem'ain in the open position:
6.23.1 FCV-480 Valve open 6.23.2 FCV-481 Valve open 6.24 Place the following Hand-automatic transfer controllers to the manual position (HCB) and reduce manual control setting to zero.
6.24.1 HC-466 Loop A,; manual position 6.24.2 HC-476 Loop B manual position 6.25 Verify that the following valves have automatically stroked to their closed position:
RSSP-1.5:5 6.25.1 FCV-466 Loop A Valve closed 6.25.2 FCV-480 6.25.3 FCV-476 Loop B 6.25.4 FCV-781 6.26 Remove DC current generator from temperature control bistable TC 401F and reconnect field wiring to input terminals; wire connected.
6.27 If DC current generators had been connected to test jacks at steam generator level channels remove from service to restore channel to normal.
6.27.1 LC-461 restored to normal 6.27.2 LC-462 restored to normal 6.27.3 LC-463 restored to normal 6.27.4 LC-471 restored to normal 6.27.5 LC-472 restored to normal 6.27.6 LC-473 restored to normal 6.28 Realign system and valves as required for subsequent operation.
CO>iPLETED BY:
DATE COHPLETED:
SHIFT FOREHAN:
RESULTS 6 TEST REVIEW: DATE:
