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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
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ATTAChWENT 1
Consumers Power Company Palisades Plant Docket 50-255 CRITERIA FOR DETERMINING JUSTIFICATION FOR CONTINUED OPERATION WHEN ENCOUNTERING DISCREPANCIES IN "AS-BUILT" SAFETY-RELATED PIPING November 13, 1989
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CRITERIA FOR DETERMINING JUSTIFICATION t
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DISCREPANCIES IN "AS-BUILT" SAFETY-RELATED PIPING
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CONSUMERS POWER COMPANY PALISADES PLANT
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2.0 CRITERIA . . ..... .. . . .. . . . .. . . . ... . . 1
3.0 CONCLUSION
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1.0 INTRODUCTION
AND SCOPE 1
These criteria are intended to provide the operability determination requirements for safety-related piping and associated supports if it is determined that stresses exceed allowables presented in the Palisades Plant Updated FSAR (Reference 1). These criteria permit operation for an interim period only. Modifications will be made which return the system to within FSAR allowables.
These criteria are intended to be used to expeditiously perform necessary
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evaluations to determine interim operability and not to delay appropriate actions.
2.0 CRITERIA 1.
2.1 Piping Operability Criteria t.
The piping analysis shall be in accordance with ANSI B31.1, 1973 1
1 Edition (Reference 2) with the load combination stress limit defined below. The 1973 Edition of ANSI B31.1 is judged to be a
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comprehensive and updated consolidation of all of the requirements l of earlier editions of B31.1 used at Palisades. This edition constitutes use of a single reference encompassing all licensing requirements and is compatible with current computer software used by Consumers Power Company. The design loading conditions to be l
applied in the analysis shall include the Safe Shutdown Earthquake.
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FollowingLare the pipe stress criteria for justifying. continued sc . operation of the plant ,
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i Where: S tp = Longitudinal Pressure Stress S = Dead Weight Stress ;
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S = Stresses Resulting From Safe Shtitdown Earthquake SSE S = Material Yield Stress (Reference 3 Appendices) '
y Code Case N-411 allows for increased damping values, independent of
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pipe diameter, for seismic analysis. Therefore, increased damping values, in accordance with "+'- ince 4, will be acceptable when performing these analyses to meet operability. If the piping stress analysis exceed the value of 2.0 S , or pipe supports do not ,
meet their operable limits (see Sect. 2.2), then additional iterative
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analysis of the piping may be required. The iterative analysis may l
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use the knowledge that a support is not capable of withstanding the L loads, and can be removed from the analysis. The Code Case N-411 analysis will be an alternativa analysis procedure to that of the original piping seismic design methodology. Analysis employing Code
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Case N-411 will be performed based upon the requirement of US NRC Regulatory Guide 1.84, Rev. 26. (Reference 5) i For cases where piping secondary stresses (stresses induced by !
restraint of free end thermal displacement, thermal anchor movements or seismic anchor movements) are determined to exceed
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FSAR allowables, a specific case by case approach will be used to determine interim operability.
t 2.2 Pipe Support & Hanger Operability Criteria As a first step in evaluating the support, a linear elastic analysis method will be used to determine the stress and forces in the support members. In addition to the loading in Section 2.1, the ,
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support loads must include pipe thermal loads, restraint of free end thermal displacement and anchor motion. The stresses and forces !
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calculated for each support member shall be compared with the allowables in the FSAR, Chapter 5.10.1.2 criteria for the SSE (Reference 1) combination except as modified below, l-i' d J
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t Shear F,, =. 0.72 Sy but f 0.42 Su-
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Combined Stress For axial compression and bending or
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axial tension and bending, use AISC Paragraph 1.6., (Ref. 6)
B. Anchor Bolts Use Factor of Safety of 2 ageinst ultimate tension and shear values, j I
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Hydraulic: Load < manufacturers one time load capacity.
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L D. Springs Load within catalog range without 1 L
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The maximum of the following:
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- 2. When faulted allowables are not given and the factor of safety is specified in the catalog for the normal operating allowable, a design allowable shall be scaled to e safety
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factor of 2.
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- 3. When the catalog item is designed to B31.1 and no safety
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factor is given, a design allowable twice the catalog value, c
- 4. When test data is available, the design allowable shall have a safety factor of 2.0.
- 5. For a simple component item where an analysis can be performed, the allowable shall be 0.5 of the ultimate stresses or strength.
Where: F t
= Allowable Tensile Stress F = Allowable Bending Stress b
Fy = Allowable Shear Stress
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FS = Factor of Safety,
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Note 1: Actual yield strength may be used where CMTR's are
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available for the material.
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If a support fails using the linear elastic method, then a more refined anslysis may be performed using plastic analysis techniques.
The plastic analysis will follow the design rules of ASME Section III, Appendix F, (Ref.1),
3.0 CONCLUSION
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If the above criteria cannot be met, reportability per 10 CFR 50 must be evaluated and system operabi14'y requirements per Plant Technical Specifications must be evaluated and appropriate actions taken.
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4.0 REFERENCES
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- 1. Palisades Plant Updated Final Safety Analysis Report.
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- 2. ANSI B31.1, 1973 Power Piping Code.
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- 3. American Society of Mechanical Engineers, Boiler and Pressure Vessel i '
CodesSection III, 1983 Edition, through Winter 1985 Addenda.
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- 4. American Society of Mechanical Engineers, Boiler and Pressure Vessel
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Codes, Case N-411, Dated 9/17/84.
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- 5. US Nuclear Regulatory Commission Regulatory Guide 1.84, Design and Fabrication Acceptability, ASME Section III, Division 1, July 1989, !
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Rev. 26,
- 6. " Manual of Steel Construction", American Institute of Steel Construction, Inc., Seventh Edition, 1980.
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