Similar Documents at Zion |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20216G1351999-09-23023 September 1999
Rev 5 to Chapter 12 of Zion Annex Odcm
ML20209F8321999-06-30030 June 1999
Rev 4,Chapter 12 of ODCM for Zion Annex
ML20211C3311999-04-30030 April 1999
Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood
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Rev 3 to Zion Nuclear Station Recovery Plan
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ML20140D8071997-06-0606 June 1997
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Rev 1 to Zion Nuclear Station Recovery Plan
ML20148B7371997-05-0808 May 1997
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Rev 1.9 to Chapter 10, Zion Annex Index & Rev 1.8 to Chapter 12, Radioactive Effluent Technical Stds
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Amend 4 to Zion Station Fire Protection Rept
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Proposed Tech Specs Using Guidance in NUREG-1431 to Produce Improved TSs
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Proposed Tech Specs Re Rquirements Governing RCS Pressure & Temp Limits
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Proposed Tech Specs Modifying F* Distance Definition
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Pump & Valve Inservice Testing Plan for Zion Nuclear Generating Station Units 1 & 2
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1999-09-23
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20216G1351999-09-23023 September 1999
Rev 5 to Chapter 12 of Zion Annex Odcm
ML20209F8321999-06-30030 June 1999
Rev 4,Chapter 12 of ODCM for Zion Annex
ML20211C3311999-04-30030 April 1999
Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood
ML18068A7121998-07-31031 July 1998
Rev 3 to Chapter 12 of Zion Station Odcm.
ML20217N9661998-03-31031 March 1998
Revs to ODCM for Zion Station,Including Rev 2 to Chapters 10 & 12
ML20216G8981998-03-16016 March 1998
Certified Fuel Handler Training & Retraining Program
ML20216H9041997-10-31031 October 1997
Revs to OCDM for Zion Station,Including Rev 1.9 to Chapter 10,rev 1.1 to Chapter 11,rev 1.9 to Chapter 12 & Rev 1.1 to App F
ML20212B4421997-10-22022 October 1997
Rev 3 to Zion Nuclear Station Recovery Plan
ML20212B4471997-10-22022 October 1997
Rev 3 to Zion Nuclear Station Recovery Program,Scope Mgt Guideline
ML20212B4601997-10-22022 October 1997
Rev 3 to Zion Nuclear Station Recovery Program,Sys Readiness Review
ML20212B4761997-10-22022 October 1997
Rev 3 to Zion Nuclear Station Recovery Program,Dept Start- Up Readiness Assessment Guideline
ML20211B4831997-09-0505 September 1997
Restart Action Plan
ML20140C4151997-06-0505 June 1997
Rev 1 to Zion Nuclear Station Recovery Plan
ML20137B4691997-01-31031 January 1997
Rev 1.9 to Chapter 10, Zion Annex Index & Rev 1.8 to Chapter 12, Radioactive Effluent Technical Stds
ML20216E6041997-01-31031 January 1997
Amend 4 to Zion Station Fire Protection Rept
ML20134H4591996-10-31031 October 1996
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ML20129E5621996-09-30030 September 1996
Rev 1.1 to Chapter 11 to Odcm,Zion Annex Index
ML20129J4891995-10-0404 October 1995
On-Site Review for ODCM Revision
ML20058E8751993-09-0303 September 1993
Revised AOP-6.3, Loss of RHR Shutdown Cooling
ML20056H0281993-08-20020 August 1993
Errata to Chapter 12 to ODCM, Including Revised Table 12.2-1,12.2-3 & 12.5-1
ML20056G8131993-06-30030 June 1993
Pump & Valve Inservice Testing Plan for Zion Nuclear Generating Station Units 1 & 2
ML20058E8351993-06-10010 June 1993
Revised AOP-7.4, Control Room Inaccessibility
ML20127D0691992-12-30030 December 1992
Corporate Emergency Response Organization Required Reading Package 92-11
ML20245L7651989-08-0707 August 1989
Rev 0 to Offsite Dose Calculation Manual
ML20235T6421987-12-31031 December 1987
Rev 11A to Offsite Dose Calculation Manual. Rev 11B to Table of Contents Also Encl
ML20237F6641987-02-27027 February 1987
Revised Procedure PT-18, Control Room Charcoal Booster Fans Test
ML20210U0861987-01-27027 January 1987
Procedure 91-614-04-123, Human Factors Integration of Zion Nuclear Generating Station Reg Guide 1.97 Program
ML20236R9811986-08-28028 August 1986
Ae Project Plan for Evaluation of Pressurizer Safety & Relief Valve Discharge Piping Subsystem
ML20205F8061986-07-25025 July 1986
Rev 0 to Procedure TSGP-47, Control Room Ventilation Sys Ductwork In-Leakage Test
ML20206J6961986-06-17017 June 1986
Rev 2 to Inservice Insp & Test Program Second Interval
ML20203L3551986-04-30030 April 1986
Rev 0 to Comm Ed Training Program Description for Station Control Room Engineer/Shift Technical Advisor
ML20210A5651985-12-27027 December 1985
Rev 0 to Emergency Procedure ES-1.1, SI Termination
ML20136G3371985-11-0808 November 1985
Suppl 4 to NUREG-0737 Suppl 1 Dcrdr Program Plan
ML20207N3261985-08-12012 August 1985
Rev 0 to 2L-517 E, Steam Generator a Level Channel Electronics
ML20207N3201985-08-0606 August 1985
Rev 0 to 2L-517 T, Steam Generator a Level Transmitter
ML20140D0761985-06-30030 June 1985
Rev 11 to Sections 7.2 & 8.0 of Offsite Dose Calculation Manual
ML20127K1211985-04-27027 April 1985
Rev 0 to Procedure Zap 6-52-5, Zion Station Equipment Technical Info Control Program
ML20237F7271985-03-26026 March 1985
Revised TSS 15.6.14C, Activated Carbon Filters Lab Analysis
ML20237F6791985-03-26026 March 1985
Revised TSS 15.6.14A, Activated Carbon Filter In-Place Leak Test
ML20237F6931985-03-26026 March 1985
Revised TSS 15.6.14B, HEPA Filter Banks In-Place Leak Tests
ML20140G0341984-04-25025 April 1984
Rev 10 to Procedure TSS 15.6 10A, Type a Containment Leak Rate Test
ML20062F1691982-07-22022 July 1982
Public Version of Revised Page 8 to Revision 3 to Emergency Plan Implementing Procedure EPIP 700-1, Corporate Command Ctr Group Directory
ML20062F1511982-07-22022 July 1982
Public Version of Revision 5 to Emergency Plan Implementing Procedure EPIP 110-1, Station Director
ML20054M5921982-06-22022 June 1982
Public Version of Revision 7 to Emergency Plan Implementing Procedure 320-1, Activation of Generating Station Emergency Plan Station Group. Revised Index & Revision 8 to Table of Contents Encl
ML20054M3391982-06-22022 June 1982
Public Version of Revision 4 to Emergency Plan Implementing Procedure EPIP 700-1, Corporate Command Ctr Group Directory. Revision 7 to Table of Contents Encl
ML20055B2391982-06-15015 June 1982
Public Version of Revision 2 to Emergency Plan Implementing Procedure EPIP 130-1, Technical Director
ML20054M3921982-06-15015 June 1982
Public Version of Revision 2 to Emergency Plan Implementing Procedure EPIP 140-1, Maint Director. Revised Table of Contents Encl
ML20054M3781982-06-15015 June 1982
Public Version of Revision 3 to Emergency Plan Implementing Procedure EPIP 110-1, Station Director. Revision 5 to Table of Contents Encl
ML20054K6891982-06-15015 June 1982
Public Version of Revision 2 to Emergency Plan Implementing Procedure EPIP 120-1, Operations Director. Revised Table of Contents Encl
ML20054K9601982-06-15015 June 1982
Public Version of Revision 3 to Emergency Plan Implementing Procedure EPIP 700-1, Emergency Phone List. Revised Table of Contents Encl
1999-09-23
[Table view] |
Text
- . .. _- . . = - - - - .. . .. ._ - .. .
i ES-1.1 SI TERMINATION Rev. 0 12-27-85 1
- STEP -
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED A. PURPOSE This procedure provides the necessary_ instructions to terminate safety injection and stabilize plant conditions.
B. SYMPTOMS OR ENTRY CONDITIONS This procedure is entered from:
- 1) E-0, REACTOR TRIP OR SAFETY INJECTION, and E-1, LOSS OF REACTOR OR SECONDARY COOLANT, when specified termination criteria are satisfied.
i
- 2) FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, after secondary heat sink has been reestablished and SI is terminated.
870$O50113 870428 PDR q ADOCK 05000295 PDR 0516E 1
ES-1.1 SI TERMINATION Rev. 0 12-27-85
- STEP - ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- If offsite power is lost after SI reset, *
- manual action will be required to restart *
- some safeguards equipment.
- Foldout page should be open.
- A discretion of Shift Supervisor, steps 21 through 23 may be performed at any time as conditions allow. These steps secure DGs running unloaded, check Source Range detectors energized, and shutdown unnecessary plant equipment.
- 1. Reset SI:
- a. Verify safeguards breaker targets a. Match targets.
- MATCHED
- b. Depress both SI RESET pushbuttons
- c. Verify the following: c. Locally place both trains of safeguards in TEST.
- SAFETY INJECTION ACTIVATED annunciator blue light - OUT
- AUTO SAFETY INJECTION BLOCKED annunciator blue light - ON
- 2. Reset Containment Spray / Isolation Phase B, IF Actuated
\
l 0516E 2
i ES-1.1 SI TERMINATION Rev. O 12-27-85
- STEP -
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 3. Establish Instrument Air To Containment:
- a. Verify an air compressor - a. Start air compressors as RUNNING necessary,
- b. Open valves FCV-IA01A and B
- 4. Stop All Charging Pumps But One ,
Centrifugal i
- 5. Check RCS Pressure - STABLE OR Perform the following:
I INCREASING .
- 1) Operate charging and SI pumps l as necessary.
- 2) Go to ES-1.2 POST-LOCA C00LDOWN AND DEPRESSURIZATION.
- 6. Close Appropriate IVSW Valves:
- a. Check containment conditions: a. Perform the following:
Containment radiation - NORMAL 1) Close IVSW injection valves to MOV-VC8100
- Containment pressure - NORMAL and A0V-VC8152 and 8153:
- Containment temperature - NORMAL FCV-IWO8 FCV-IW12 FCV-IWO9 FCV-IW13
- 2) Go to step 7.
- b. Close all IVSW injection valves:
FC WO8 FCV-IW13 F 09 FCV-IW14 j F 10 FCV-IW15 FCV-IW11 FCV-IW16
- FCV-IW12 FCV-IW17 i
l 0516E 3
ES-1.1 SI TERMINATION Rev. 0 12-27-85
- STEP -
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 7. Establish Normal Charging Flow:
- a. Verify charging pump miniflow a. Open valves.
valves MOV-VC8110 and 8111 -
OPEN
- b. Close BIT inlet isol. valves MOV-SI8803A and B
- c. Close BIT discharge isol. valves MOV-SI8801A and B
- d. Open charging header isolation valves MOV-VC8105 and 8106
- e. Open RCP seal water return containment isolation valve MOV-VC8100
- f. Check RCP LBRTH AP - BETWEEN f. Adjust RCP LBRTH AP 20 AND 60 INCHES control valve HCV-182.
- 8. Control Charging Flow to Maintain - IF PZR level continues to PZR Level - BETWEEN 20% AND 50% decrease, THEN:
(BETWEEN 50% AND 80% FOR ADVERSE CONTAINMENT) 1) Isolate normal charging flow path and realign charging flow path through BIT.
- 2) Go to ES-1.2, POST-LOCA C00LDOWN AND DEPRESSURIZATION.
- IF PZR level is greater than 50%
(80% for adverse containment),
, THEN align letdown using step 13 WHILE continuirg with step 9.
0516E 4
ES-1.1 SI TERMINATION Rev. O
- 12-27-85 1
! - STEP -
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 9. Check If SI Pumps Should Be Stopped:
! a. RCS pressure: a. Perform the following:
STABLE OR INCREASING 1) E any SG is faulted, THEN do NOT proceed until AND faulted SG depressurization stops.
GREATER THAN 1600 PSIG (1900 PSIG for ADVERSE CONTAINMENT) 2) E EITHER:
NO SG is faulted.
QE
- Criteria for stopping SI pumps can NOT be satisfied after faulted SG depressurization 4 stops.
i THEN go to ES-1.2, POST-LOCA COOLDOWN AND
- DEPRESSURIZATION.
- b. Stop both SI pumps i 10. Align RHR Pumps:
- a. Stop both RHR pumps
- b. Close MOV-CC9412A and B
- 11. Verify ECCS Flow Not Required: Perform the following:
- a. RCS subcooling - 1) Operate charging and SI GREATER THAN 30*F (RCS PRESSURE - pumps as necessary.
HOT LEG TEMPERATURES ABOVE FIGURE ON FOLDOUT PAGE FOR 2) Go to ES-1.2, POST-LOCA ADVERSE CONTAINMENT) C00LDOWN AND DEPRESSURIZATION..
- b. PZR level - GREATER THAN 4%
(30% for ADVERSE CONTAINMENT) 4 0516E 5 (.( 2 7 ,.u l .)
.-- _
