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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
- Date Entered: Apr 28, 1998 TO: USNRC/WASHINGTON JMCKNIGHT Copy Number: 145 PROCEDURE NUMBER: El-6.6 TITLE: GAMMA E DETERMINATION TRANSMITTAL: LISTED BELOW ARE NEW/REVISED PROCEDURES WHICH MUST BE
" IMMEDIATELY INSERTED INTO OR DISCARDED FROM YOUR PROCEDURE MANUAL.
Action Required Section or Description REMOVE AND DESTROY El-6.6, R/3, ENTIRE PROCEDURE REPLACE WITH El-6.6, R/3, ENTIRE PROCEDURE EDITORIAL AND APPLICABILITY SIGN, DATE, AND RETURN THE ACKNOWLEDGEMENT FORM WITHIN 10 DAYS TO THE PALISADES PLANT DOCUMENT CONTROL.
SIGNATURE OR INITIALS u .'\Jv~t0
. . . ,- .-, r- 'l I
.i
~-'"
.. Revision 3 Issued Date 4/23/97
- PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: GAMMA E DETERMl~ATION
- Procedure Sponsor NKBrott Technical Reviewer Date User Reviewer Date
- PALISAPES NUCLEAR PLANT. Proc No El-6.6
- EMERGENCY IMPLEMENTING PROCEDURE Revision 3 Page i
- TITLE: GAMMA E DETERMINATION Table of Contents 1.0 PERSONNEL RESPONSIBILITY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 2.0 PURPOSE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1
- 3. 0 REFERENCES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 3.1 SOURCE DOCUMENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . 1
- 3. 2 REFERENCE DOCUMENTS . . . . . . . . . . . . . . . . . . . . . . .. . . 1 4.0 INITIAL CONDITIONS ANP/OR REQUIREMENTS ................ 2 5.0 PROCEPURE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 I e
- 5. 1 E DETERMINATION . . . . . . . . . . . . . . .. . . . . . . . . . . . . . 2
- 6.0 ATTACHMENTS AND RECORDS . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 6.1 6;2 ATTACHMENTS . . . . . . . . . . . . . . . . . : . . . . . . . . . . . . . . 3 RECORDS . . . . . . . . . . . . . . . . . . . . . . . . *. . . . . . . . . . . . 4 7.0 SPECIAL REVIEWS . . . . . . . . . . . . . . . . . . . . . . . . . . *. . . . . . . . . . . 4 le ATTACHMENTS Attachment 1, "Energy per Disintegration Versus Decay Time Prior to Release for Noble Gas" Attachment 2, "Gamma i:: Determination Worksheet"
. \
- PALISADES NUCLEAR PLANT. Proc No El-6.6 EMERGENCY IMPLEMENTING PROCEDURE Revision 3 Page 1 of 4
- TITLE: GAMMA E DETERMINATION USER ALERT INFORMATION USE PROCEDURE Th.e activities covered by this procedure may be performed from memory.
1.0 PERSONNEL RESPONSIBILITY The Health Physics Support Group Leader shall implement this procedure.
In the absence of a Health Physics Support Group ~eader, the Site Emergency Director shall delegate this responsibility.
2.0 PURPOSE This procedure provides a gamma i= (average gamma energy per disintegration) for input into offsite dose calculations. _
.* This procedure provides a manual backup to the gamma i= calculation performed in the automated dose assessment program, "Offsite."
3.0 REFERENCES
3.1 SOURCE DOCUMENTS 3.1 .1
- 3. 2 REFERENCE DOCUMENTS 3.2.1 Emergency Implementing Procedure El-6.0, "Offsite Dose Calculation and Recommendations for Protective Actions" 3.2.2 Emergency Implementing Procedure El-11.0, "Determination of Extent of Core Damage" 3.2.3 Palisades Administrative Procedure. 10.46, "Plant Records"
- PALISADES NUCLEAR PLAN. Proc No Ei-6.6 EMERGENCY IMPLEMENTING PROCEDURE Revision 3 Page*2 of 4 *
4.0 TITLE
GAMMA E DETERMINATION INITIAL CONDITIONS AND/OR REQUIREMENTS
- a.
- This procedure shall be. implemented as required per El-6.0, "Offsite Dose Calculation and Recommendations for Protective Actions."
- b. Data and results from this procedure should be recorded on the Gamma E Determination Worksheet, Attachment 2.
- c. E is dependent on the source of the radionuclide release, the type of accident/release and the time of decay (or time after reactor shutdown). Those parameters should be known prior to performing this procedure. In the event these parameters cannot be e:
determined, the default value for of 0. 7 MeV should be used.
e1 5.o PROCEDURE
- 5. 1 E DETERMINATION USER ALERT INFORMATION USE PROCEDURE The activities covered by this procedure may be performed from memory.
- a. Determine the source of the release.
NOTE: Time of shutdown can be obtained from the TSC Operations Support Group.
- b. Determine the decay time in hours and record on worksheet, Attachment 2.
NOTE: Fuel failure may be determined using Emergency Implementing Procedure El-11, "Determination of Extent of Core Damage."
- c. Determine E from the appropriate section below:
- 1. Release With Fuel Melt or Fuel Failure - Using the time after reactor shutdown as the decay time prior to release, determine E using Attachment 1. *
- Proc No El-6.6 EMERGENCY IMPLEMENTING PROCEDURE Revision 3 Page 3 of 4
-* 2.
TITLE: GAMMA E DETERMINATION Mainsteam and Offgas !Air Ejector) Releases INo Fuel Melt or Failure) - If the release is coming from a primary to secondary leak and fuel failure or fuel melt is involved, determine E from Attachment 1 and use the time after shutdown as decay time prior to release. For all other cases, use an E of 0.134 MeV.
- 3. Release With No Fuel Melt or Failure Surge Tank. Volume Control Tank. and Oegasifier Releases - Use E that corresponds to the six-hour time in Attachment 1 (0.1809 MeV). This corresponds to a release from the Primary Coolant System (excluding mainsteam releases) without fuel damage. This value may be used for any release that involves fresh primary coolant.
- 4. Waste Gas Oecay Tank INo Fuel Melt or Failure) - If the decay time for activity in a Waste Gas Decay Ta.nk is known,
- then E should be determined using Attachment 1 and
- six hours as the starting point for the decay time determination.
For example, if the tank contains activity that has decayed for two days, then the decay time is 48 + 6 = 54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br />.
- 5. Fuel Handling. Sipping. and Cask Prop Releases - If the release is coming from a fresh spent fuel bundle (directly out of the reactor core and less than 30 days old), then determine E using time after reactor shutdown and Attachment 1. If the release is coming from an old fuel bundle, then use an E of 0.035 MeV.
- d. Mark release type and record E on worksheet.
6.0 ATTACHMENTS ANP RECORDS 6.1 ATTACHMENTS 6.1.1 Attachment 1, "Energy per Disintegration Versus Decay Time Prior to
- 6.1.2 Release for Noble Gas" Attachment 2, "Gamma E Determination Worksheet"
- PALISADES NUCLEAR PLAN. . Proc N~ Er:.6.G EMERGENCY IMPLEMENTING PROCEDURE Revision**-3 .,
Page 4 of 4*
6.2 RECORDS TITLE: GAMMA E DETERMINATION I Records generated by this procedure shall be filed in accordance with elI 1.0 Palisades Administrative Procedure 10.46, "Plant Records."
SPECIAL REVIEWS e1 None
J
Page 1 of 1
- ENERGY PER DISINTEGRATION VERSUS DECAY TIME PRIOR TO RELEASE FOR NOBLE GAS
---l!llE~~~1.0 fl
. ._ . E~*IVY per Oiidntqratkln "
.,_.. ~- Decay Time Priof to RelHH
~L-- e
~f===t::::f:~~ttt:==+/-=+/-ffffiH:=__:=_=+--E_:::::t-f:-t:f-t==t-t=t+=Fttfft-F---1--l':::..-L::l:=L1i:it:t:t===+/-=+/-:lu
--- **-- -L- . _ ....
t==t===t=t:t:tjjttlt~;;:+/-=:t:+/-+/--Hl-t-H---+-t-:+-Ft-IH-iFF==+=+::+=t=+:l~~==:t==l=lo.4 11-----111-r~HT1rt---t---t-1HN,:tttt---+-+--t--4-+~~l---+--+--+-+-L-U-ll--_J--1-10.2 0----0----L-- - ~- -~ ----1---1-~11~*-'*-D~~*-----t----t--+---1-~~t*t----t--;r--+--+--l-+-1r+:l----l---l---
~
0.05 0.04 0.01 0.1 .:-....,---4.---4--.£.--'--1.-L..Ll_. _ _ _ -.1_-1_-L...L..L..L.Jl..LL----L--l._L.L.LJU..lJ_ _ _ L_L_.l.o.01 1 0 10.0 100 1000 (At'hlr 720 hrs, UH 0.035 M*V.)
D.ecay Time Prior to ReleHe (Houra)
~
DCC*950*22*06
- Proc No El-6.6 Attachment 2 Revision 3
- GAMMA E DETERMINATION WORKSHEET Page 1 of 1 Decay time 1 ..
- - - - hours
- 2. Source of release ( ) Fuel Melt or Fuel Failure
( ) Main Steam or Offgas (Air Ejector) Releases
( ) Surge Tank, Volume Control Tank, and Degasifier.Releases
( ) Waste Gas Decay Tank Releases
( ) Fuel Handling, Sipping, and Cask Drop Releases E = ---~MeV Date: Time: Completed By:
