(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Similar Documents at Zion |
---|
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 ML20205Q8801999-04-13013 April 1999 Proposed Tech Specs Page 5-9,replacing Operational TSs with Permanently Defueled TSs ML20154E3441998-10-0202 October 1998 Proposed Tech Specs Pages Re Amends to Licenses DPR-39 & DPR-48,eliminating License Conditions No Longer Applicable & Replacing Existing Operational Custom TS with Permanently Defueled TS ML18068A7121998-07-31031 July 1998 Rev 3 to Chapter 12 of Zion Station Odcm.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 ML20217H9451998-03-30030 March 1998 Proposed Tech Specs Restoring Plant Custom TS Replaced W/ Improved TS by Previous Amend & Reinstating License Condition Deleted by That Previous Amend ML20216G8981998-03-16016 March 1998 Certified Fuel Handler Training & Retraining Program ML20202H3641997-11-28028 November 1997 Proposed Improved TSs Using Guidance Provided in NUREG-1431 ML20199D6251997-11-10010 November 1997 Proposed Improved TS Bases Changes & Supporting Info & Final Proposed TS Bases for Section 3.3,including Revised Table of Contents & List of Effective Pages 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 ML20212B4761997-10-22022 October 1997 Rev 3 to Zion Nuclear Station Recovery Program,Dept Start- Up Readiness Assessment Guideline ML20212B4601997-10-22022 October 1997 Rev 3 to Zion Nuclear Station Recovery Program,Sys Readiness Review 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 ML20211B4831997-09-0505 September 1997 Restart Action Plan ML20211B9941997-08-0606 August 1997 Proposed Improved Tech Specs Re Draft SER for Zion Station Conversion,Per NUREG-1431 ML20196G8781997-07-18018 July 1997 Proposed Tech Specs,Meeting Administrative Commitment Resulting from from Plant TS Improvement Program ML20140D8071997-06-0606 June 1997 Proposed Tech Specs Using Guidance Provided in NUREG-1431,to Produce Set of Improved TS for Plant ML20140C4151997-06-0505 June 1997 Rev 1 to Zion Nuclear Station Recovery Plan ML20148B7371997-05-0808 May 1997 Proposed Tech Specs Re Addition of Discussion of Position & Duties of Licensed Operators & Senior Licensed Operators to Section 5.3, Qualification ML20134J2971997-02-0303 February 1997 Proposed Tech Specs Suppl to 960920 Application for Amend to Licenses DPR-39 & DPR-48,providing Annotated & Clean Copies of ITS Pp Affected by Proposed Amend 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 ML20134G0991997-01-27027 January 1997 Proposed Tech Specs Re Revising TS Such That Use of Entire Abb/Ce TR,CEN-629-P,would Be Authorized as Governing Document for Installing CE Sleeves in SG Tubes ML20133D0901997-01-0202 January 1997 Proposed Tech Specs Using Guidance in NUREG-1431 to Produce Improved TSs ML20132B8331996-12-11011 December 1996 Proposed Tech Specs Completely Revising TS Using Guidance Provided in NUREG-1431, Std Ts,Westinghouse Plants ML20134J3641996-11-0808 November 1996 Proposed Tech Specs Re Rquirements Governing RCS Pressure & Temp Limits ML20134G3401996-11-0707 November 1996 Proposed Tech Specs 4.3.1.A.4.b Re Surveillance Requirement ML20134G4141996-11-0707 November 1996 Proposed Tech Specs Table 3.7-1 Re Reduced Power Range Neutron Flux High Setpoint Trip ML20134G5921996-11-0707 November 1996 Proposed Tech Specs 3.13.1.A Re Limiting Operation for Operation ML20129J7731996-11-0101 November 1996 Proposed Tech Specs Modifying Section 3.15.2.A & Section 4.15.2.A of TS ML20134H4591996-10-31031 October 1996 Rev 1.8 to Chapter 10 Odcm,Zion Annex Index ML20128Q8891996-10-14014 October 1996 Proposed Tech Specs 3.3.2.G Re Limiting Condition for Operation & 4.3.2.G Re Surveillance Requirements ML20128H3011996-10-0404 October 1996 Proposed Tech Specs,Clarifying & Adding Mode of Applicability for Rod Position Indicator Channels to TS ML20128L7831996-10-0404 October 1996 Proposed Tech Specs Modifying F* Distance Definition ML20128L8371996-10-0404 October 1996 Proposed Tech Specs Re Implementation of Option B to 10CFR50,App J 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 ML20059H5811994-01-19019 January 1994 Proposed Tech Specs Revising RCS Temperature Required for Reactor Criticality,In Addition to Editorial Changes in Affected Specifications ML20058C3031993-11-19019 November 1993 Proposed Tech Specs Changing LTOP of Reactor Vessel ML20058A2651993-11-10010 November 1993 Proposed Tech Specs Re Limitations on Radioactive Matl Released in Liquid & Gaseous Effluents & New 10CFR21 ML20059H9541993-11-0404 November 1993 Proposed Tech Specs Revising Surveillance Frequency & Acceptance Criteria ML20058E8751993-09-0303 September 1993 Revised AOP-6.3, Loss of RHR Shutdown Cooling ML20056F7291993-08-23023 August 1993 Proposed Tech Specs for Implementation of Latest Rev to 10CFR20, Stds for Protection Against Radiation 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 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 Rev 1.8 to Chapter 10 Odcm,Zion Annex Index 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 .)
.-- _