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
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REV: 5
.ATT-10.0 ATTACHMENT FAULTED S/G PAGE 1 of 2 Responsible Manager WA4 ! t Date /d-3-$
/
Dispatch AO with locked valve key to complete local isolation of faulted S/G as follows:
NQTE: Intermediate Building environment should be assessed for radiological I or other personnel safety concerns.
-1. Request identification of faulted S/G from Control Room.
NOTE: Steps may be done in any order, ,
1
- 2. Verify faulted S/G MSIV bypass valve closed (INT BLDG steam header area) o S/G A, V-3615
-O R-o S/G B, V-3614
- 3. Isolate steamlines for the faulted S/G:
o Steam sampling system (INT BLDG steam header area) o S/G A, close V 3413A O R-0 S/G B, close V-3412A o Support heating steam (INT BLDG steam header area) o S/G A, close V-3669 O R-0 S/G B, close V 3668 o Upstream trap'3 (TURB BLDG east of MFW regulating valves) o S/G A, close V-3521 OR-0 S/G B, close V 3520 9610160282 961003 PDR ADOCK 05000244 Y PDR
. goes ritLE:
REV: 5 - 1 i '
ATTACHMENT FAULTED S/G I
$TT-10.0
- PAGE 2 of 2 O ..............................................................
CAUTION CONTROL ROOM SHOULD BE NOTIFIED BEFORE ISOLATING TDAFW PUMP l STEAM OR FEED FLOW.
- 4. '..,cally CLOSE TDAFW pump steam root valves o S/G A, V-3505
-O R-0 S/G B, V-3504
- 5. Locally close TDAFW pump feed header isolation valve for affected S/G:
o S/G A, V-4005 (steam header west end on catwalk by CNMT wall)
I -O R-0 S/G B, V-4006 (Main steam header east end by stairs)
- 6. Locally close MFW regulating valve and bypass valve outlet isolation valves for the faulted S/G:
o S/G A, V-3987 and V ,991
-O R-o S/G B, V-3986 and V-3990
k3 l
. go : rirtt: l REVi 6
'ATT-16.0 ATTACHMENT RUPTURED S/G PAGE 1 of 3 O
Responsible Manager Lov/[L J Date /d-3-9/,
/ ,
1 NOTE: Intermediate Building environment should be assessed for radiological ;
and other personnel safety concerns.
PART A. Dispatch AO with locked valve key to complete localisolation of l ruptured S/G as follows:
l NOTE: Steps may be done in any order for PART A.
l CAUTION l CONTROL ROOM SHOULD BE NOTIFIED BEFORE ISOLATING TDAFW PUMP l STEAM OR FEED FLOW.
- 1) Verify BOTH S/G MSIV bypass valves closed (INT BLDG steam header area):
o S/G A, V-3615 o S/G B, V-3614 l
l 2) Locally close TDAFW pump steam root valves o S/G A, V-3505
-O R-O S/G B, V 3504 l 3) Locally close the following steam valves from the ruptured S/G:
l o Steam to sampling system valve (INT BLDG steam header area):
S/G A, close V-3413A O R-S/G B, close V 3412A l
l 0 Support heating steam valve (INT BLDG steam header area):
I S/G A, close V 3669
-O R-
>0 s'o 8.ci v see8 l
' REV: 6 i
$TT-16.0 i
ATTACHMENT RUPTURED S/G PAGE 2 of 3 ;
f~
\ o Upstream trap isolation valve (TURB BLDG near MFW reg vivs):
S/G A, close V-3521
-O R-S/G B, close V 3520
- 4) Locally close TDAFW pump manual feedwater isolation valve to ruptured S/G (INT BLDG steam header area):
S/G A, V 4005
-O R-S/G B, V-4006 ;
k
- 5) Bypass condensate polishing demineralizers as follows:
1
- 1. Place AVT bypass valve controller in MANUAL (east end of AVT :
panel). I
- 2. Open bypass valve.
- 3. Isolate _A.LLiinservice demineralizers as follows:
a) Place the Mixed Bed Service Selector switch to override AND select the bed to be removed from service. j b) Place the 4 position selector switch for the selected bed to OFF. l c) Repeat steps a and b for each inservice bed.
]
i
- 6) Locally place TURB RM WALL EXH FAN switches to CLOSE. !
- 7) Locally place TURB RM ROOF VENT switches to CLOSE.
.............................................................. l CAUTION ;
l PART B OF THIS ATTACHMENT SHOULD ONLY BE PERFORMED IF RUPTURED S/G MSIV CANNOT BE CLOSED.
)
.............................................................. 1 PART B. Dispatch AO to locally perform the following when ruptured S/G MSIV cannot be closed, if areas are accessible: l l
- 1) Close Air Ejector / Gland steam root valve, V-3540 (Main steam header TURB j BLOG).
- 2) Close flange heating isolation valves, MOV-3601 A and MOV 3602A.
, ., tops ilfLE:
REW 6 ATT-16.0 -
ATTACHMENT RUPTURED S/G
. PAGE 3 of 3 l
\ 3) Notify Control Room that main flowpaths are isolated, THEN complete isolation by closing the following valves:
NOTE: Substeps may be done in any order.
a) MFW regulating valve and bypass valve manualisolation valves for both S/Gs:
o S/G A, V-3985 and V-3989 l o S/G B, V-3984 and V-3988 l b) Reheat steam chain valves: l l
l 0 1 A MSR, V-3551 l 0 18 MSR, V-3550 0 2A MSR, V-3553 ,
o 28 MSR, V-3552 l c) Steam dump header isolation and bypass valves (Main steam header l TURB BLDG on platform overhead) o V-3532 and V-3659 o V-3533 and V-3658 d) Reheat steamline warmup valves (warmup vivs located east end of 1 A
, and 2A MSRs TURB BLDG middle floor):
l o V-3645 o V-3646 o V 3647 o V-3648 e) Reheat steamline common vent, V-8500 (at condenser north of 1 A l MSR).
l f) Steam to trap header isolation valves o V-8513 (Main steam header TURB BLDG) o V-8529 (south side EH skid) o V-8510 (south side EH skid) s l
-.