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
EOP: TITLE REV: 9 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 1 of 8 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE PLANT SUPERINTENDENT EF EC VE DATE CATEGORY 1.0 REVIEWED BY:
9206160409 05000244 920605'DR ADOCK P . PDR
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2 I
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EOP: TITLE:
REV' AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 2 of 8 A. PURPOSE This procedure provides the steps necessary to respond to a loss of CCW while the plant is at power.
B. ENTRY CONDITIONS/SYMPTOMS
- 1. SYMPTOMS The symptoms of LOSS OF CCW DURING POWER OPERATION are; a Annunciator A-13 COMP COOLING SURGE TANK LO LEVEL 41.24,
~
lit, or
- b. Annunciator A-22 CCW PUMP DISCHARGE LO PRESS 60 PSI, lit, or
- c. Annunciator A-17, MOTOR OFF, RCP, CCP, lit, or Annunciator d.
15 GPM, lit A-9, or RHR PUMP COOLING WATER OUTLET LO FLOW
- e. Annunciator A-6, FLOW 15 GPM, lit or CONT SPRAY PUMP COOLING WATER OUT LOW Annunciator A-14, SAFETY INZ PUMPS COOLING WATER OUT LO FLOW 25 GPM, lit or gi Annunciator A-7 (A-15),
OR LO FLOW 165 GPM RCP 125'F, litlAor(1B) CCW RETURN HI TEMP
- h. Annunciator A-24 (A-32), RCP lA (1B) OIL LEVEL +'.25, lit.
C 4 EOP: TITLE:
REV 9 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 3 of 8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- CAUTION IF CCW FLOW TO A RCP IS INTERRUPTED FOR GREATER THAN 2 MINUTES OR IF EITHER RCP MOTOR BEARING TEMPERATURE EXCEEDS 200'F, THEN CCW SHOULD BE CONSIDERED LOST TO THAT RCP, REFER TO STEP 3.
1 Check CCW Pump Status: Perform the following:
o Annunciator A-17, Motor Off RCP a. Verify auto start of standby CCW CCP - EXTINGUISHED pump or start manually.
o Both CCW pump breaker white b. IF Annunciator A-22, CCW pump disagreement lights discharge lo press 60 psi LIT, EXTINGUISHED THEN check closed CCW to RHR HXs (MOV-738A and MOV-738B).
EOP: TITLE REV: 9 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 4 of 8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: CCW surge tank level should be verified locally in the Aux Bldg, if possible.
2 Verify CCW Surge Tank Level Normal:
- a. CCW surge tank level a. Open RMW to CCW surge tank APPROXIMATELY 50% AND STABLE (MOV-823) and start a RMW pump and perform the following:
IF surge tank level is stable or increasing, THEN go to Step 3.
IF surge tank level can NOT be maintained greater than 10%,
THEN 0
- 1) Trip the Rx.
- 2) Trip the RCPs.
- 3) Place both CCW pumps in pull stop.
- 4) Go to E-O, REACTOR TRIP or SAFETY INJECTION.
~e EOP: TITLE:
REV: 9 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 5 of 8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION IF AN RCP(S) IS TRIPPED DUE TO A LOSS OF CCW, SEAL INJECTION SHOULD BE MAINTAINED TO THE IDLE RCP(S) UNTIL RCS TEMPERATURE IS LESS THAN 200'F, OR UNTIL CCW IS RESTORED.
3 Check CCW To Both RCPs: IF CCW lost to RCP(s), THEN:
o Annunciator A-7 (A-15), RCP 1A a. Trip the Rx.
(1B) CCW return Hi temp or low flow 165 gpm 125'F alarm- b. Trip affected RCP(s).
EXTINGUISHED
- c. Go to E-O, REACTOR TRIP or o RCP motor bearings temperature SAFETY INJECTION.
(PPCS address GD-RCPS OR RCP temperature monitor RK-30A recorder) - 5 200'F 4 Check CCW Valve Alignment Align CCW valves as necessary.
NORMAL (Refer to Attachment CONTROL ROOM CCW ALIGNMENT DURING POWER OPERATION)
M 'E I
Cs
EOP:
REV: 9 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 6 of 8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: o An evaluation must be made to determine if operation may continue while investigating a CCW leak in containment.
o Operation may continue with the reactor support coolers isolated.
If this occurs, notify higher supervision.
5 Check For CCW Leakage In CNMT:
- a. CNMT sump A levels - NOT a. IF abnormal increase in CNMT INCREASING NOTICEABLY sump level, THEN:
l) Direct HP Tech to sample sump A for chromates.
- 2) Prepare to make CNMT entry to check for CCW leak.
- b. RCP oil levels - NOT INCREASING b. IF any RCP oil level increasing uncontrollably, THEN:
- 1) Close CCW to and from affected RCP(s), (MOVs 749A and 759A for "A" RCP; MOVs 749B and 759B for "B" RCP).
- 2) Trip Rx.
- 3) Trip affected RCP(s).
- 4) Go to E-O, REACTOR TRIP or SAFETY INJECTION.
l J
I
EOP:
REV: 9 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 7 of 8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Check For CCW Leakage In AUX IF no leakage indicated in AUX BLDG: BLDG, THEN:
o Aux Bldg sump pump - INCREASED a. Direct HP Tech to sample CCW Hx START FREQUENCY SW outlet for chromates,
-OR- b. Go to step 10.
o Waste holdup tank level UNEXPLAINED INCREASE
-OR-o Aux Bldg - VISUAL LEAKAGE IDENTIFIED 7 Establish - THE SOURCE OF THE CCW LEAKAGE AND ISOLATE 8 Verify CCW Surge Tank Level IF CCW surge tank level NOT Normal: approximately 50%, THEN open RMW to CCW surge tank, MOV-823, and start o CCW surge tank level APPROXIMATELY 50%
a RMW pump to fill to approximately 50%.
CCW surge tank 9 Direct HP To Sample For Chromates 10 Verify CONDITIONS PERMIT IF shutdown required, THEN refer to CONTINUED POWER OPERATION, 0-2.1, NORMAL SHUTDOWN TO HOT (Refer to Technical SHUTDOWN.
Specification Section 3.3.3).
i EOP:
REV: 9 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 8 of 8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Refer to 0-9.3, NRC STATE AND COUNTIES IMMEDIATE NOTIFICATION, for reporting requirements.
11 Complete NOTIFICATION TO HIGHER SUPERVISION 12 Establish Further Guidance:
- a. Problem or leakage - CORRECTED a. IF problem NOT corrected or leakage NOT found or isolated, THEN return to Step 4.
- b. Return to -APPROPRIATE OPERATING PROCEDURE
-END-
EOP:
REV: 9 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 1 of 1 ATTACHMENT CONTROL ROOM CCW ALIGNMENT DURING POWER OPERATION o CCW to RHR Hx A MOV-738A Closed o CCW to RHR Hx B MOV-738B Closed o CCW from RCP 1A Thermal Barrier AOV-754A Open o CCW from RCP 1B Thermal Barrier AOV-754B Open o CCW from Ex Ltdn Hx Isol Vlv AOV-745 Closed o CCW Surge Tk Vent RCV-017 Open o CCW to CNMT Isol Vlv MOV-817 Open o CCW to Rx Supp Clrs Isol Vlv MOV-813 Open o CCW from Rx Supp Clrs Isol Vlv MOV-814 Open o CCW to RCP 1A Isol Vlv MOV-749A Open o CCW to RCP 1B Isol Vlv MOV-749B Open o CCW from RCP 1A Isol Vlv MOV-759A Open o CCW from RCP 1B Isol Vlv MOV-759B Open o NRHX Ltdn Outlet Temp (Controller) TCV-130 Auto
t' gfg, \
