ML021970551
| ML021970551 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 07/07/2002 |
| From: | Consumers Energy |
| To: | Mcknight J Office of Nuclear Reactor Regulation |
| References | |
| EI-6.6, Revision 3 | |
| Download: ML021970551 (9) | |
Text
Date Entered: Jul 07, 2002 TO:
USNRCIWASHINGTON JMCKNIGHT Copy Number:
145 TRANSMITAL NUMBR 221 094 PROCEDURE NUMBER: EI-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 EI-6.6, R/3, ENTIRE PROCEDURE REPLACE WITH EI-6.6, R/3, ENTIRE PROCEDURE EDITORIAL AND APPLICABILITY WORD 2000 CONVERSION SIGN, DATE, AND RETURN THE ACKNOWLEDGEMENT FORM WITHIN 10 DAYS TO THE PALISADES PLANT DOCUMENT CONTROL.
SIGNATURE OR INITIALS DATE
Procedure No EI-6.6 Revision 3 Issued Date 7/7/02 PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: GAMMA E DETERMINATION I
Procedure S orsor
"/
1 Date NKBrott 1/25/98 Technical Reviewer Date User Reviewer Date
PALISADES NUCLEAR PLANT Proc No EI-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 AND/OR REQUIREMENTS..................................................
2 5.0 PROCEDURE.................................................................................................................
2 5.1 E DETERMINATION.......................................................................................
2 6.0 ATTACHMENTS AND RECORDS.............................................................................
4 6.1 ATTACHMENTS..............................................................................................
4 6.2 RECORDS......................................................................................................
4 7.0 SPECIAL REVIEWS...................................................................................................
4 ATTACHMENTS, "Energy per Disintegration Versus Decay Time Prior to Release for Noble Gas", "Gamma E Determination Worksheet"
PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: GAMMA E DETERMINATION Proc No EI-6.6 Revision 3 Page 1 of 4 1.0 PERSONNEL RESPONSIBILITY The Health Physics Support Group Leader shall implement this procedure. In the absence of a Health Physics Support Group Leader, the Site Emergency Director (SED) or the EOF Director shall delegate this responsibility.
2.0 PURPOSE This procedure provides a gamma P- (average gamma energy per disintegration) for input into offsite dose calculations.
This procedure provides a manual backup to the gamma E calculation performed in the automated dose assessment program, "Offsite."
3.0 REFERENCES
3.1 SOURCE DOCUMENTS 3.1.1 NUREG 0654,Section I, "Accident Assessment" 3.1.2 Dose Assessment Basis Document-06, "Palisades Gamma E Calculations" 3.2 REFERENCE DOCUMENTS 3.2.1 Emergency Implementing Procedure EI-6.0, "Offsite Dose Calculation and Recommendations for Protective Actions" 3.2.2 Emergency Implementing Procedure El-1 1, "Determination of Extent of Core Damage" 3.2.3 Palisades Administrative Procedure 10.46, "Plant Records" 3.2.4 Palisades Administrative Procedure 10.41, "Procedure Initiation and Revision" USER ALERT INFORMATION USE PROCEDURE The activities covered by this procedure may be performed from memory.
PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: GAMMA E DETERMINATION Proc No EI-6.6 Revision 3 Page 2 of 4 4.0 INITIAL CONDITIONS AND/OR REQUIREMENTS
- a.
This procedure shall be implemented as required per Emergency Implementing Procedure EI-6o0, "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 determined, the default value for : of 0.7 MeV should be used.
5.0 PROCEDURE 5.1 E DETERMINATION USER ALERT INFORMATION USE PROCEDURE The activities covered by this procedure may be performed from memory.
NOTE:
Time of shutdown can be obtained from the TSC Operations Support Group.
- a.
Determine the decay time in hours and record on worksheet, Attachment 2.
- b.
Determine the source of the release and record on worksheet.
NOTE:
Fuel failure may be determined using Emergency Implementing Procedure El-1 1, "Determination of Extent of Core Damage."
- c.
Determine P-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. This method is used for all release sources when fuel melt or failure is involved.
PALISADES NUCLEAR PLANT Proc No EI-6.6 EMERGENCY IMPLEMENTING PROCEDURE Revision 3 Page 3 of 4 TITLE: GAMMA E DETERMINATION
- 2.
Mainsteam and Offqas (Air Ejector) Releases (No Fuel Melt or Failure)
- If the release originates from the Primary Coolant System with a Primary to Secondary leak, and there is no fuel melt or failure, then use the E that corresponds with the 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> value (0.134 MeV) from.
- 3.
Surge Tank, Volume Control Tank, and Deqasifier Releases (No Fuel Melt or Failure) - Use _ that corresponds to the six-hour time in (0.180 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 Decay Tank Releases (No Fuel Melt or Failure) - If the decay time for activity in a Waste Gas Decay Tank is known, then should be determined using Attachment 1 and six hours as the starting point for the decay time determination. (If decay time is not known, then use 0.180 MeV as a default.)
For example, if the tank contains activity that has decayed for two days, then the "Decay Time Prior to Release" 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 Handlingi, Sipping, and Cask Drop 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 use the time after reactor shutdown as the "Decay Time Prior to Release," and determine E using. If the release is coming from an old fuel bundle, then use an E of 0.035 MeV.
- d.
Record E on the worksheet.
PALISADES NUCLEAR PLANT Proc No EI-6.6 EMERGENCY IMPLEMENTING PROCEDURE Revision 3 Page 4 of 4 TITLE: GAMMA E DETERMINATION 6.0 ATTACHMENTS AND RECORDS 6.1 ATTACHMENTS 6.1.1, "Energy per Disintegration Versus Decay Time Prior to Release for Noble Gas" 6.1.2, "Gamma E Determination Worksheet" 6.2 RECORDS Records generated by this procedure shall be filed in accordance with Palisades Administrative Procedure 10.46, "Plant Records."
7.0 SPECIAL REVIEWS The scope of this procedure does not include activities that require a 50.59 review per Palisades Administrative Procedure 10.41, "Procedure Initiation and Revision."
Therefore, changes to this procedure do not require a 50.59 review.
The scope of this procedure includes activities that require a PRC review per Palisades Administrative Procedure 10.41, "Procedure Initiation and Revision."
Therefore, changes to this procedure require a PRC review.
(
ENERGY PER DISINTEGRATION VERSUS DECAY TIME PRIOR TO RELEASE FOR NOBLE GAS 1.0
.5
.4
.3
.2
.1
.05
.04
.03
.02
.01
.1
.2
,3
.4.5 1
2 3
4 5
10 20 30 40 50 Decay Time Prior'to Release (Hours) 100 200 300 400 500 1000 (After 720 hrs use 0.035 MeV)
Proc No EI-6.6 Revision 3 Page 1 of 1
__I I
-I
.I I
lU.I 0
.S CL I0 U.
ERC*950*22*06 GAMMA E DETERMINATION WORKSHEET Decay time 1.
2.
hours 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 Date:
Time:
Proc No EI-6.6 Revision 3 Page 1 of 1
- 3.
E
_=
MeV Completed By: