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* Date Entered: Apr 28, 1998 TO: USNRC/WASHINGTON JMCKNIGHT Copy Number: 145 PROCEDURE NUMBER: El-6.6 TITLE: GAMMA E DETERMINATION TRANSMITTAL: | * 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 | ||
LISTED BELOW ARE NEW/REVISED PROCEDURES WHICH MUST BE " IMMEDIATELY INSERTED INTO OR DISCARDED FROM YOUR PROCEDURE MANUAL. Action Required REMOVE AND DESTROY | " IMMEDIATELY INSERTED INTO OR DISCARDED FROM YOUR PROCEDURE MANUAL. | ||
'l I . i | 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" | |||
3.1 SOURCE DOCUMENTS 3.1 .1 | . \ | ||
* NU REG 0654, Section I, "Accident Assessment" 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. | * PALISADES NUCLEAR PLANT. Proc No El-6.6 EMERGENCY IMPLEMENTING PROCEDURE Revision 3 Page 1 of 4 | ||
10.46, "Plant Records" | * TITLE: GAMMA E DETERMINATION USER ALERT INFORMATION USE PROCEDURE Th.e activities covered by this procedure may be performed from memory. | ||
* PALISADES NUCLEAR PLAN. | 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. | |||
* 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 | 2.0 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." | ||
Those parameters should be known prior to performing this procedure. | |||
In the event these parameters cannot be determined, the default value for | ==3.0 REFERENCES== | ||
: 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 | |||
3.1 SOURCE DOCUMENTS 3.1 .1 | |||
* NU REG 0654, Section I, "Accident Assessment" | |||
: 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. * | |||
* PALISAPES N,UCLEAR PLANT | * PALISAPES N,UCLEAR PLANT | ||
* | * 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. | * 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 hours. 5. Fuel Handling. | For example, if the tank contains activity that has decayed for two days, then the decay time is 48 + 6 = 54 hours. | ||
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 | : 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 | 6.0 ATTACHMENTS ANP RECORDS 6.1 ATTACHMENTS 6.1.1 Attachment 1, "Energy per Disintegration Versus Decay Time Prior to | ||
* PALISADES NUCLEAR PLAN .. Proc Er:.6.G | * 6.1.2 Release for Noble Gas" Attachment 2, "Gamma E Determination Worksheet" | ||
., Page 4 of 4* TITLE: GAMMA E DETERMINATION | * 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." | ||
* 1 | SPECIAL REVIEWS e1 None | ||
* Revision 3 , Page 1 of 1 | |||
* ENERGY PER DISINTEGRATION VERSUS DECAY TIME PRIOR TO RELEASE FOR NOBLE GAS . ._ . | J | ||
per Oiidntqratkln " .,_.. Decay Time Priof to RelHH --- | * Proc No El-6.6 | ||
* Atta~hme-nt 1 | |||
0----0----L-- | * Revision 3 , | ||
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 | ||
Time: Completed By:}} | ~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: | |||
*}} |
Latest revision as of 14:43, 23 February 2020
ML18068A344 | |
Person / Time | |
---|---|
Site: | Palisades ![]() |
Issue date: | 04/28/1998 |
From: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
To: | |
References | |
EI-6.6, NUDOCS 9805110149 | |
Download: ML18068A344 (9) | |
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
- NU REG 0654,Section I, "Accident Assessment"
- 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. *
- PALISAPES N,UCLEAR PLANT
- 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
- Proc No El-6.6
- Atta~hme-nt 1
- Revision 3 ,
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: