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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML18066A6641999-09-30030 September 1999
Proposed Tech Specs Re Surveillance Implementation
ML18066A6501999-09-17017 September 1999
Final Clean Copies of ITS & Bases Pages Incorporating Proposed Changes,Editorial Changes & Bases Clarifications as Result of Ongoing Reviews to ITS LCOs 3.5.2,3.6.3,3.6.6, 3.7.5 & 3.7.7 & 3.7.8
ML18066A5911999-07-30030 July 1999
Proposed Tech Specs Sections 3.3,3.5 & 3.6,converting to Its,Per NUREG-1432
ML18066A5691999-07-19019 July 1999
Proposed Tech Specs Section 3.7, Plant Systems, Converting to ITS
ML18066A5011999-06-11011 June 1999
Proposed Tech Specs Pages Re 980126 Submittal & Replacement Pages for Sections 3.3,3.4 & 3.9
ML18068A5851999-05-0303 May 1999
Proposed Tech Specs Section 3.5,converting to ITS
ML18066A4551999-04-0707 April 1999
Proposed ITS Pages 3.1.4-2 & 3.1.4-8,revising Completion Time for Action D.1
ML18066A4431999-03-30030 March 1999
Proposed Tech Specs Section 3.7,converting to ITS
ML18066A4251999-03-22022 March 1999
Revised TS Pages for ITS Section 3.4
ML20207B2501999-03-0101 March 1999
Proposed Tech Specs Sections 2.0,3.1 & 3.2,converting to ITS
ML18066A3281998-11-0909 November 1998
Proposed Tech Specs,Deleting CVCS Operability Requirements Currenty in LCOs 3.2 3.17.6 & Associated Testing Requirements Currently in SRs 4.2 & 4.17
ML20195E4451998-11-0909 November 1998
Proposed Tech Specs,Converting to Its,Consistent with NUREG-1432,Rev 1,in Response to 980824 RAI
ML20154N2901998-10-12012 October 1998
Proposed Tech Specs Sections 1.0,3.0,4.0 & 5.0,converting to Improved Tech Specs
ML18066A3021998-09-14014 September 1998
Proposed Tech Specs Markups of Previously Submitted Pages & Revised ITS Submittal Pages
ML20151Z8111998-09-14014 September 1998
Proposed Tech Specs Converting to Improved Tss, Consistent with NUREG-1432,Rev 1
ML18066A2011998-06-17017 June 1998
Proposed Tech Specs,Reflecting Reduced Min Reactor Vessel Flow Rate Assumption in Accident Analyses
ML18066A1841998-06-10010 June 1998
Simulator Four-Year Test Rept & Schedule for Performance Testing for Next Four-Year Period.
ML18068A3451998-04-29029 April 1998
Rev 9 to EI-9, Offsite Radiological Monitoring.
ML18068A3441998-04-28028 April 1998
Rev 3 to EI-6.6, Gamma E Determination.
ML18065B2271998-04-21021 April 1998
Reactor Vessel Neutron Fluence Methodology.
ML20217C3101998-03-24024 March 1998
Palisades,Review of Actual Fluence Determination
ML18065B1801998-03-13013 March 1998
Proposed Tech Specs Allowing Installation of Plant Mod W/O Requiring Plant Shutdown
ML18065B2021998-03-10010 March 1998
Rev 7 to Relocated TS Per GL 89-09.
ML18067A8161998-01-26026 January 1998
Proposed Tech Specs Converting to Improved Ts,Consistent W/ NUREG-1432,Rev 1.Includes Vols 1-20
ML18066A4901998-01-20020 January 1998
Proposed Tech Specs Re Partial Response to 990126 Request RAI for ITS Section 3.6, Containment.
ML20197G3851997-12-17017 December 1997
Rev 17 to Palisades Nuclear Plant Suitability,Training & Qualification Plan
ML18065B2321997-10-24024 October 1997
Rev 5 to Procedure HP 10.10, Palisades Radiological Environ Program Sample Collection & Shipment.
ML18067A7071997-10-0101 October 1997
Proposed Tech Specs,Stating That TS Flywheel Insp Period Be Lengthened to Ten Years & Deleting Note of Insp at End of Cycle 12
ML18067A6731997-09-0303 September 1997
Proposed Tech Specs,Updating TS to Reflect Capabilities of Installed CR Ventilation Equipment & to Emulate Std TS, CE Plants - NUREG 1432 Requirements for That Sys
ML18067A6771997-09-0303 September 1997
Proposed Tech Specs,Deleting Snubber Operability Requiements in LCO 3.20 & Snubber Testing Requirements Currently in SR 4.16
ML18067A6001997-06-27027 June 1997
Proposed Tech Specs Revising Electrical Power Systems
ML18067A4701997-03-28028 March 1997
Proposed Tech Specs Pp Supporting Completion of Administrative Control Changes Proposed in 951211 Safety Evaluation for Amend 174
ML20137H5901997-03-27027 March 1997
Proposed Tech Specs Change Request Re Change in Co Name
ML18067A4531997-03-26026 March 1997
Proposed Tech Specs,Allowing Entry Into Air Lock to Perform Repairs on Inoperable Air Lock Door & Thereby Avoid Potential for Unnecessary Plant Shutdown
ML18067A5151997-02-11011 February 1997
Rev 5 to Health Physics Procedure HP 10.10, Palisades Radiological Environ Program Sample Collection & Shipment.
ML18065B2011996-12-24024 December 1996
Rev 11 to Offsite Dose Calculation Manual.
ML18065B0861996-11-27027 November 1996
Corrected Pages 14 & 15 to Rev 18 to EM-09-02, Inservice Testing Program Relief Request Valve Relief Request 20.
ML20134P4071996-11-19019 November 1996
Suitability,Training & Qualification Plan, Rev 16
ML20137G3871996-10-29029 October 1996
Rev 6 to Relocated TS Per NRC GL 89-09
ML18065B0331996-10-25025 October 1996
Proposed Tech Specs Change Request,Revising Administrative Controls Sections of Plant TS
ML18065B0171996-10-18018 October 1996
Proposed Tech Specs,Providing Info Necessary for Completion of Review & Approval Process Re Writting Commitment Be Made That Description of Palisades Operating Requirements Manual Will Be Added to FSAR
ML18065A9551996-10-0202 October 1996
Proposed Tech Specs 4.6.1 Re Safety Injection sys,4.6.2 Re Containment Spray sys,4.6.3 Re Pumps & 4.6.4 Re Valves
ML18065A9111996-09-0404 September 1996
Proposed Tech Specs 3.7, Electrical Power Systems.
ML20117K9581996-09-0303 September 1996
Proposed Tech Specs,Revising Administrative Control & Resolution of NRC Comments
ML18065A8631996-08-14014 August 1996
Proposed TS Table 4.3.2 Re Miscellaneous Surveillance Items
ML18065A7661996-06-10010 June 1996
Expired Temporary Change O-96-044 to Rev 17 to SOP-17A, Clean Radwaste Sys.
ML18065A7651996-06-10010 June 1996
Cancelled Tcn O-96-045 to Rev 17 to SOP-17B, Dirty Radwaste Sys.
ML18065A5861996-03-29029 March 1996
Proposed Tech Specs,Upgrading Plant TS & Bases to Emulate STS for Combustion Engineering Plants,NUREG-1432,Rev 1
ML18065A8021996-02-21021 February 1996
Rev 2 to EM-09-13, ISI Pressure Testing Program.
ML20137G3631996-02-16016 February 1996
Rev 10 to Offsite Dose Calculation Manual
1999-09-30
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML18068A3451998-04-29029 April 1998
Rev 9 to EI-9, Offsite Radiological Monitoring.
ML18068A3441998-04-28028 April 1998
Rev 3 to EI-6.6, Gamma E Determination.
ML18065B2271998-04-21021 April 1998
Reactor Vessel Neutron Fluence Methodology.
ML18065B2021998-03-10010 March 1998
Rev 7 to Relocated TS Per GL 89-09.
ML20197G3851997-12-17017 December 1997
Rev 17 to Palisades Nuclear Plant Suitability,Training & Qualification Plan
ML18065B2321997-10-24024 October 1997
Rev 5 to Procedure HP 10.10, Palisades Radiological Environ Program Sample Collection & Shipment.
ML18067A5151997-02-11011 February 1997
Rev 5 to Health Physics Procedure HP 10.10, Palisades Radiological Environ Program Sample Collection & Shipment.
ML18065B2011996-12-24024 December 1996
Rev 11 to Offsite Dose Calculation Manual.
ML18065B0861996-11-27027 November 1996
Corrected Pages 14 & 15 to Rev 18 to EM-09-02, Inservice Testing Program Relief Request Valve Relief Request 20.
ML20134P4071996-11-19019 November 1996
Suitability,Training & Qualification Plan, Rev 16
ML20137G3871996-10-29029 October 1996
Rev 6 to Relocated TS Per NRC GL 89-09
ML18065A7661996-06-10010 June 1996
Expired Temporary Change O-96-044 to Rev 17 to SOP-17A, Clean Radwaste Sys.
ML18065A7651996-06-10010 June 1996
Cancelled Tcn O-96-045 to Rev 17 to SOP-17B, Dirty Radwaste Sys.
ML18065A8021996-02-21021 February 1996
Rev 2 to EM-09-13, ISI Pressure Testing Program.
ML20137G3631996-02-16016 February 1996
Rev 10 to Offsite Dose Calculation Manual
ML20137G3581996-02-15015 February 1996
Rev 6 to CPC Pnp Process Control Program
ML18064A8141995-06-29029 June 1995
Procedure EOF App B, INPO Emergency Response Assistance Agreement, Dtd 950426
ML20100H2621995-06-18018 June 1995
Rev 2 to Reactor Vessel Exam Program Plan Interval 2,Period 3 & Interval 3,Period 1
ML18064A8881995-03-16016 March 1995
Rev 0 to Palisades Nuclear Power Plant Third Interval ISI Program for Class 1,2 & 3 Components & Supports, Vols I & II
ML18064A6301995-03-0303 March 1995
Rev 7 to App H, Emergency Planning EOF Training Matrix.
ML18064A6341995-02-27027 February 1995
Project Plan,Alloy 600,Palisades Nuclear Plant, Rev 1,dtd 950227
ML20072K7741994-07-15015 July 1994
Rev 0 to Palisades Performance Enhancement Plan
ML20072K7641994-07-0606 July 1994
Rev 1 to Palisades Plant Restart Plan from 1994 Forced Outage
ML18059B0481994-06-0303 June 1994
Attachment 4 to Procedure EM-09-13,Rev 1, ISI Pressure Testing Program Procedure.
ML20069D3081994-05-24024 May 1994
Suitability,Training & Qualification Plan
ML20069G2511994-05-20020 May 1994
Rev 30 to Procedure MO-7A-2, Emergency Diesel Generator 1-2 (K-6B)
ML20069G2391994-05-20020 May 1994
Rev 30 to Procedure MO-7A-1, Emergency Diesel Generator 1-1 (K-6A)
ML20064E4831994-03-0606 March 1994
ASME Section XI Repair Program, 0054-00101-001-100,rev 0
ML20064E5011994-03-0404 March 1994
Procedure for Application & Exam of Weld Overlay Repairs to Austenitic Stainless Steel Piping Systems, 0054-00101-001-101,rev 0
ML18059A6981994-02-23023 February 1994
Reactor Vessel Integrity Project Plan.
ML18059A6881994-02-15015 February 1994
Editorial Changes to Rev 6 to Emergency Implementing Procedure EI-6.13, Protective Action Recommendations for Offsite Populations.
ML18059B0201993-12-31031 December 1993
Methods of Alleviating Adverse Consequences of Fluctuating Water Levels in Great Lakes - St Lawrence River Basin, Rept to Govts of Canada & Us,Dtd 931231
ML18059A5541993-11-19019 November 1993
Rev 4 to Attachment 3 to Procedure REC-1, Recovery Plan Format.
ML18059A4781993-10-27027 October 1993
Rev 5 to Administrative Procedure 9.11, Engineering Analysis.
ML18059A4231993-10-0707 October 1993
Rev 0 to Palisades Plant Pressurizer Safe End Crack Repair Action Plan.
ML20059A5181993-09-30030 September 1993
Public Version of Rev 36 to General Ofc Emergency Planning Procedure,App G, Emergency Telephone Numbers. W/931019 Release Memo
ML18058B7871992-12-15015 December 1992
Rev 3 to HP 10.10, Palisades Radiological Environ Program Sample Collection & Shipment.
ML18058B0341992-05-11011 May 1992
Rev 6 to Odcm.
ML18058A4331992-05-0707 May 1992
Rev 5 to General Ofc Emergency Planning Procedure EOF-4, Communication Support Team, Page 3,reflecting Editorial Changes
ML20090A3401992-02-27027 February 1992
Rev 5 to ODCM
ML18058A1461992-01-27027 January 1992
Rev 45 to General Office Emergency Planning Gort/Eof Procedures Index
ML18058A1471991-12-0909 December 1991
Rev 5 to General Ofc Emergency Planning Procedure EOF-3, Emergency Operations Facility Administrator. Approval Summary Encl
ML18058A1441991-12-0909 December 1991
Rev 5 to General Ofc Emergency Planning Procedure EOF-4, Communication Support Team. Approval Summary Encl
ML18058A1451991-12-0909 December 1991
Rev 6 to General Ofc Emergency Planning Procedure EOF-2, Emergency Operations Facility Director. Approval Summary Encl
ML20091S2361991-12-0909 December 1991
Rev 8 to General Ofc Emergency Planning Procedure GEN-3, On-Shift Sys Power Controller. Approval Summary Encl
ML18058A1421991-12-0909 December 1991
Rev 7 General Office Emergency Planning Procedure GORT-1, General Office Response Team (Gort). Approval Summary Encl
ML18058A1431991-12-0909 December 1991
Rev 10 to General Ofc Emergency Planning Procedure GEN-1, Overview. Approval Summary Encl
ML18057B3281991-10-17017 October 1991
Rev 2 to Procedure EI-15.2, Quarterly Communications Test Telephone Number,Verifications.
ML20086T2811991-09-16016 September 1991
Rev 0 to Functional Description FC-888,covering Replacement of All Four Channels of Reactor Protection Sys Power Supply Assemblies,Trip Unit Assemblies,Interconnection Modules, Bistable Trip Units & Auxiliary Trip Units
ML18057B0221991-05-10010 May 1991
Rev 15 to EM-09-04, Inservice Testing of Selected Safety- Related Pumps, Reflecting Complete Rewrite of Procedure to Omit Vertical Lines
1998-04-29
[Table view] |
Text
ENCLOSURE 2 Consumers Power Company Palisades Plant Docket 50-255 PRESSURIZER SAFE END CRACK ACTION PLAN October 7, 1993
(~
9310120434 931007 PDR ADOCK05000255 5 . . PDR
PALISADES PLANT PRESSURIZER SAFE END CRACK REPAIR ACTION PLAN REVISION 0 10/07/93
Action Plan Revision 0: xS~~h/z_:i Plant General Manager Date PURPOSE:
The purpose of the Pressurizer Safe End Crack Repair Action Plan is to provide a document which identifies responsibilities, ensures necessary actions are completed prior to the plant startup, and ensures assignments for long term actions are made.
The Action Plan may only be modified with the approval of the Plant General Manager or his designated alternate .
- 1. Conduct an engineering evaluation of the failure.
The specific elements of this engineering analysis include the following:
- a. Metallurgical analysis of the failed safe end to identify the cause of the crack.
Metallurgical Analysis Complete and Crack Cause Evaluated NECO Mechanical, Civil, and Structural Manager
- b. Analysis of factors contributing to PWSCC in the pressurizer nozzle safe end. This includes evaluation of material properties and stresses that may have contributed to the failure. Piping stresses and weld residual stresses are being evaluated and will
- be reviewed by an independent third party .
Analysis of Material Properties and Stresses Complete and Third Party Review Complete NECO Mechanical, Civil, and Structural Manager
- c. Evaluation of other nozzles safe ends in the primary coolant system, based on the engineering evaluation of the failure, to identify other locations which may be susceptible to the same failure cause. This evaluation includes both nozzles with Inconel 600 safe ends and other safe end materials. Contributing factors to PWSCC will also be evaluated for the safe ends that are identified as being susceptible to the same failure cause. This will include evaluation of material properties and stresses.
Nozzle Safe End Evaluation Complete
- NECO Mechanical, Civil, and Structural Manager
Page 2 of 5
Evaluation of NDE Predictive Testing Services Supervisor
- 2. Identify corrective actions for the specific safe end that failed.
An engineering evaluation of the repair to the pressurizer safe end, based on the root cause analysis of the failure, has shown that. the lifetime of the repaired safe end well exceeds the length of the next operating cycle.
Corrective Actions of Safe End Failure Identified NECO Mechanical, Civil, and Structural Manager
- 3. Identify corrective actions for other safe ends that may be susceptible to the same failure.
Other safe ends that may be susceptible to the same failure will be inspected for flaws using appropriate non-destructive examination techniques.
NDE for Additional Safe Ends Identified, Documented, and Evaluated Satisfactorily Predictive Testing Services Supervisor
- 4. Complete necessary corrective actions to ensure safe operation of Palisades during the next operating cycle prior to returning the plant to service.
- a. Repair of the failed pressurizer safe end.
Repair Complete Maintenance Manager
- b. Non-destructive examinations of other safe ends potentially susceptible to the same failure cause.
Repair Complete and Acceptance NDE Satisfactory Predictive Testing Services Supervisor
- 5. Identify corrective actions necessary to ensure long term safe operation of Palisades.
- a. Engineering evaluation of additional repairs which may be necessary for long term operation of the pressurizer safe ends will be performed and additional repairs and corrective actions, if required, will be completed by the end of the next refueling shutdown.
Assign Action for the Above Corrective Actions for Next Refueling Outage NECO Mechanical, Civil, and Structural Manager
- b. Further evaluation of non-destructive examination techniques in light of the pressurizer safe end crack will be conducted. Enhanced ultrasonic techniques will be employed in an augmented inspection program for safe ends beginning in the next refueling shutdown. To provide assurance that we are performing the most effective NDE possible the following actions will be completed:
Assign Action to Evaluate NDE Techniques and Employ Them in Augmented Inspection Program in Next Refueling Outage Predictive Testing Services Supervisor
- 6. Technical Report Prepared, Finalized.
NECO Mechanical, Civil and Structural Manager
- 7. Send Report to NRC.
Safety and Licensing Manager
- 8. Hold Meeting with NRC to Review Technical Report.
Safety and Licensing Manager
- 9. Provide NRC with crack tip sample for independent sample analysis.
Predictive Testing Service Supervisor
- 10. PRC Review of Technical Report and Recommended Approvals.
PRC Chairman
- 11. Authorization For Leaving Cold Shutdown.
Plant General Manager
. I
'
- ENCLOSURE 3 Consumers Power Company Palisades Plant Docket 50-255 PRESSURIZER SAFE END CRACK NDE
SUMMARY
October 7, 1993
~
WALL THICKNESS SURFACE PROFILE RT OD ID IGSCC CODE WELD # DIA PIEL SEIF N ID OD CIL PT PT UT UT COMMENTS PORV #1 6" 1.5" 1.8" Smooth Moderate Done Done Done No* No* *Configuration SE TO Bore Transition precludes UT NOZZLE 4-6" .438" 1.5" Taper Heavy Done Done Done No* No* . New Weld WELD #lA Bore Transition *Configuration SE TO PIPE I
precludes UT SPRAY #20 4" .625" .625" As No Done Done No No* No* *Configura-ELBOW TO Welded Transition ti on SE #21 precludes UT
- 21 NOZZLE 4-8" .625" 2. 5" Smooth Heavy Done Done No No* No* *Configura-tion TO SE Bore Transition precludes UT RELIEF VALVES RV-1039 #1 6" 1.3" 1. 6" Smooth Moderate Done Done Done Done No NOZZLE TO Bore Transition IN FLANGE RV-1040 #1 6" 1. 3" 1. 6" Smooth Moderate Done Done Done Done No NOZZLE TO Bore Transition IN FLANGE RV-1041 #1 1. 3" 1. 6" Smooth NOZZLE TO IN FLANGE I 6"
Bore IModerate Transition Done Done Done Done ifo Do = Scheduled But Not Complete P/EL = Pipe or Elbow Done = Completed *
- SE = Safe End No = Decision Made Not To Examine N Nozzle F = Flange Effective as of October 7, 1993
WELD #
-=*
COMMENTS PORV PIPING WELDS WELD #2 4" .438 As- No Done Done No No No New Weld PIPE TO Welded Transition PIPE WELD #3 4" .438 As- No Done Done No No No New Weld PIPE TO Welded Transition ELBOW WELD #4 4" .438 As- No Done Done No No No ELBOW TO Welded Transition PIPE WELD #5 4" .438 As- No Done Done No No No PIPE TO Welded Transition ELBOW WELD #6 4" .438 As- No Done Done No No No ELBOW TO Welded Transition PIPE Do = Scheduled But Not Complete P/EL = Pipe or Elbow Done = Completed SE = Safe End No = Decision Made Not To Examine N Nozzle F Flange Effective as of October 7, 1993
PRESSlJRl2ER ~ELIEF VALVE
~ OZZLE ASSEt16l Y IMCDMNEL 1
1iELD '"1 r: FLANGE j
I I
.
WELD *2 r J.
WELD #6
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r1Jf1Ti'1
---L E(I *,_.,\ \.VELD # 1A c
z Ip~
w w
......
L-~-f ~
r:,...-~ <(
(0 WELD # 1-----.....__ ---
LU
_J N
N 0
_z PORV NOZZLE ASSEMBLE
October 8, 1993 THE ATTACHED TWO DOCUMENTS (ONE OF WHICH IS PROPRIETARY) AR.E REFERENCES LISTED IN CONSUMERS 10/7 /93 LETTER FROM SLADE TO NRC DOCUMENT CONTROL DESK. THESE DOCUMENTS WERE SENT TO NRC AT NRC'S REQUEST AND
- SHOULD BE DOCKETED ALONG WITH THE INCOMING LETTER.
THANK YOU.
,CAROLE JAMERSON, PD3-1
-,* *' :' 504-1337' *, .. ,
, -..: .:* ... :. *:
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' '
OUTLINE
- EST/MA TION OF PARAMETERS
- DEVELOPMENT OF EXTREMAL MODEL
- ESTIMATION OF BOUNDS FOR FIRST FAILURES
- APPL/CATION TO CROM LIFE PREDICT/ON ANALYSIS
PRESENT
- STATUS OF PRESSURIZER NOZZLES
- FIELD FAILURES EVEN IN LEAST SUSCEPTIBLE HEATS
- ONLY INITIAL FAILURE INFORMATION AVAILABLE
- DIFFICULTY IN DEVELOPING OVERALL ASSESSMENT
