ML010450431
| ML010450431 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 10/02/2000 |
| From: | NRC/RGN-III |
| To: | |
| References | |
| -RFPFR | |
| Download: ML010450431 (170) | |
Text
FINAL AS-ADMINISTERED ADMINISTRATIVE JPMs DAVIS BESSE INITIAL EXAM (OCTOBER 2-6, 2000) r.l FIVE JPMs
DAVIS-BESSE NUCLEAR POWER STATION JOB PERFORMANCE MEASURE WORKSHEET JPM NO.: Admin 1-1 Rev. 0 Page 1 of 5 TASK NO.: 336-005-03-0300 TASK DESCRIPTION: Call Out Proper Relief for Replacement of a Safe Shutdown Equipment Operator.
K/A
REFERENCE:
XXX-GEN-2.1.05 2.3/3.4 APPLICABLE METHOD OF TESTING: Actual Performance Control Room Simulator Classroom TIME FOR COMPLETION: 10 minutes APPLICABILITY: [ J RO [X] SRO TASK STANDARDS:
Perform callout of operator to relieve the safe shutdown EO.
Ensure proper turnover is conducted.
REQUIRED MATERIALS:
Shift Manning List Overtime Callout List Fitness for Duty Callout Form GENERAL
REFERENCES:
DB-OP-00000, Conduct of Operations, Revision 03, C-2 DB-OP-00100, Shift Turnover, Revision 03, C-1 NG-IS-00004, Fitness for Duty Program, Revision 06, C-1 FHAR Section 8.3, Revision 16 INITIAL CONDITIONS:
You are the Shift Supervisor the plant is in MODE 1 at 100% power.
INITIATING CUES:
At 1300 Tim Bolton reports to you he is ill and leaves to go home. You are to perform the required actions as the Shift Supervisor. Assume you are on day shift .
JPM Admin 1-1 Page 2 of 5 INITIAL CONDITIONS:
You are the Shift Supervisor the plant is in MODE 1 at 100% power.
INITIATING CUES:N At 1300 Tim Bolton reports to you he is ill and leaves to go home.
You are to perform the required actions as the Shift Supervisor.
Assume you are on day shift .
JPM Admin 1-1 Page 3 of 5 PERFORMANCE INFORMATION NOTE: Critical steps denoted with a "C". Failure to meet any one of these standards for this item constitutes failure. Sequence is NOT critical unless denoted in the "Comments".
START TIME:
- 1. PERFORMANCE STEP: Recognize that the shift is at less than minimum
.C. manning, and an EO callout is needed.
STANDARD: Review DB-OP-00000, Conduct of Operations or Tech. Spec.,
Section 6 for manning requirements.
COMMENTS: The sequence of the next two steps can be done in any order as long as they are done prior to the actual phone call to the relief EO.
NOTE: Hand examinee the shift rooster and the schedule change notice once he has located the equivalent information in the control room.
CUE: None.
SAT UNSAT
- 2. PERFORMANCE STEP: Determine from the schedule change notice the
.C. available people for callout..
STANDARD: Look at shift manning list to determine Walter and Vassello are eligible for callout. May review overtime list for available people CUE: None.
SAT UNSAT
- 3. PERFORMANCE STEP: Fill out Fitness For Duty (FFD) form as required by the FFD Program.
STANDARD: Obtain a FFD form prior to callout of relief operator.
COMMENTS: (If asked) Provide candidate with FFD form.
CUE: None.
SAT UNSAT
JPM Admin 1-1 Page 4 of 5
- 4. PERFORMANCE STEP: Call the EO and fill out the Fitness for Duty form.
STANDARD: Using the Fitness for Duty form, call out the operator.
CUE: The EO informs you that he is fit for duty and will be in within an hour.
SAT UNSAT TERMINATING CUES: This JPM is complete.
END TIME
JPM Admin 1-1 Page 5 of 5 VERIFICATION OF COMPLETION Operator Evaluator SSN __ Date License: [ J RO [ ] SRO [ ] ONL Validated Completion Time: minutes Actual Completion Time: minutes Acceptable Progress Maintained: Yes No N/A Result: [ ] SATISFACTORY [ I UNSATISFACTORY NOTE: An "Unsatisfactory" requires Comment and will require subsequent remedial training.
Comments/Feedback:
/___________________
Date Evaluator' Evaluator's Signature s Signature Date
SHIFT ROOSTER Klein Inside SSA Koch Outside SSA, FC McPherson ROP Sutter ROS Bolton Z3, SEO Pocino Z2, FB Matherly Z1, FB Magers FB Mabie FB
CALL-IN QUESTIONNAIRE IS-005-00 SECTION 1 - GENERAL INFORMATION PERSON CALLED DATE TIME REASON HAS ALCOHOL BEEN CONSUMED WITHIN PREVIOUS 5 HOURS?
LI YES C NO IF YES, COMPLETE SECTIONS 2 AND 3 IF NO, COMPLETE SECTION 3 SECTION 2 - APPROVAL JUSTIFY WHY THE INDIVIDUAL IS NEEDED DUTY PLANT MANAGER APPROVAL (Signature)
(May be obtained by telephone) X C YES []NO IF DUTY PLANT MANAGER DOES NOT APPROVE THE REQUEST, COMPLETE SECTION 3 TRANSPORTATION PROVIDED?
L YES L NO IF NO, WHY NOT?
SUPERVISOR-SECURITY SHIFT NOTIFIED TO PERFORM BAC EXAM (Name)
SECTION 3 - DOCUMENTATION CALL-OUT PERFORMED BY (Print - Name)
SIGNATURE x
POSITION/TITLE WHEN COMPLETE, FORWARD TO ACCESS CONTROL - MAIL STOP 5125
SCHEDULE CHANGE NOTICE WEEK OF 2-Oct-00 thu 8-Oct-00 Revision 0 Pa.e 1 o 3 2-Oct-00 3-Oct-00 4-Oct-00 5-Oct-00 Monday Tuesday Wedueda Thu rsda 2300-07001 0700-15001
_ a_ _ _1500-2300
_ M_ n_ _ 2300-0700
_ _ _ _ 1 0700-1500 u s a 1 1500-2300 2300-0700 1 0700-1500 11500 0 2 0 _0700-5001 1500-2300 h ur da700_ ___
5 3 a 5 I A I I I Reactor Isbell Bechtel Baker Isbell Arebaugh Baker Isbell McPherson Baker Isbell McPherson Bechtel Operator F F F F F F F F F F F F Jones Migot Walter Jones Boss Walter Jones Pocino Walter Jones Pocino Migot F F C F F C F F C F F F McPherson Witt Rowland _--- Witt ---- Witt Sutter Witt Suffer ----
C F Jones C Jones C F C F Isbell BakerJ. Baker, J. BakerJ. Pocino
_ ---- Arebaugh ----
Bechtel Arebaugh Arebaugh F Rowland Equipment Bracken Ferrell Fehrmnann Bracken Matherly Fehrmnann Bracken Bolton Fehrmann Bracken Bolton Operator C F C C F C C F C C F III Fehrman Purk McElhaney Smith Purk Roidl Smith Purk Magers Smith ---- Magers McElhaney F F F F F F F F F Bolton F F Vassello Empcke Empeke Empcke
Matherly Vassello ---- Dudas Vassello ---- Matherly Vassello ---- Empcke F F Roidl F F Bolton F F F Smith Empeke Tiell Empcke Empeke ---- ----
F F F F Pork Matherly Bracken Matherly Matherly
_ Vassello Bracken Equipment Operator Equipment Operator Durnwald - Mabie l-- Mabie Dumnwald I F Mabie F Mabie F F Auxillary Operator lAusdllazyl Operator Justice Boles Justice Wolf Justice Wolf Trainee
'- DENOTES OVERTIME HAS BEEN SCHEDULED
SCHEDULE CHANGE NOTICE WEEK OF 2-Oct-00 thru 8-Oct-00 Revision 0 Page 2 of 3 6-Oct-00 7-Oct-00 8-Oct-00 I _ Friday 2 Saturda 0 S day 2300-0700 0700-1500 1500-2300 2300-0700 0700-1500 1500-2300 2300-0700 0700-1500 11500-2300 5 2 4 2 3 4 2 3 Reactor Isbell McPheson Bechtel Baker McPherson Baker McPherson Bechtel Operator F F F F F F F F Note 2 Jones Pocino Migot Walter Migot Walter Pocino Migot F F F C F C F F Bechtel Bechtel McPherson
Suttr ---- Sutter --- Sutte Rowland Sutter F F Walter F F Migot Baker, J. Sutter Sutter Migot Bechtel Baker, J.
I Note 2 Equipment Bracken Bolton Ferrell Felrmann Bolton Ferrell Felhmarm Bolton Ferell Operator C F F C F F C F F Ill Purk Magers McElhaney Smith Magers McElhaney Smith Magers McElhaney F F F F F F F F F McEthaney Vassello Magers Vassello
Matherly Roidl Vassello ---- ---- Vassello ----
Bolton F F F McElhaneV Fdhmann F Matherly Ferrell Frrell Smith Bolton Smith Bolton Equipment Operator 11 I Equipment Durnwald I Operator l Mabie. Durnwald ------ Mabie Dornwald I Mabie Durnwald I Mabie F F Mabie I F I F Mabie F F lAuxillaryl I Tratoeear Wolf Justice Wolf Justice Wolf TraineeI I II III W.
- DENOTES OVERTIME HAS BEEN SCHEDULED
SCHEDULE CHANGE NOTICE WEEK OF 2-Oct-00 thra 8-Oct-00 Revision 0 Page 3 of 3 Plant Support Vacations & Paid Absences Name From Thrn Time Code 02-Oct-00 103-Oct-00 04-Oct-00 05-Oct-00 06-Oct-00 Monday I Tuesday Wednesdayi Thursday Friday Reactor Arebaugh Arebaugh Operator F F Boss Boss Boss Boss F F F F Other Activities Equipment Empcke Name From Thrn Description Operator F m Matherly Roidl Roidl Roidl F F F Equipment Operatorl Equipment Operator I l Notes:
Auxillary 1. Cannot stand Fire Brigade duties only.
Operator 2. M. Migot to relieve T. Bolton at 1300 lAuxiliaryl Operator Boles Boles Boles Boles Traimeel Training Crew 1 Baldwin Baldwin Baldwin Baldwin Baldwin Cuff Cuff Cuff Cuff Cuff Licensed Lawrence Lawrence Lawrence Lawrence Lawrence Ploeger Ploeger Ploeger Ploeger Ploeger Fox Fox Fox Fox Fox Rohde Rohde Rohde Rohde Rohde Whalen Whalen Whalen Whalen Whalen Non- Dudas In Dudas Dudas Dudas Licensed Tiell Plant Tiell Tiell Tiell Support Prepared By: Date: Approved By: Date:
levin Giesler 9/14/00 Robert Coad 9/14/00 lsigntre on file) (signature on file)
OPERATIONS SECTION MANNING Off-Shift Assignments Operations Support Staff Superintendent, Plant Operations D. M. Imlay Supervisor - Operations D. P. Ricci Reactor Operators Haugh McLain Stallard Ploeger C
Senior Off Shift SRO Bentley McGee Operations Jones, D. Horvath Advisors C Lakis Shift Managers . C
- Wise Melssen SI-11FTASSIGNMENTS I 1 1 2 1 3 1 4 1 5 6 Baker, K Patrick Supervisor Baldwin Bonfigliol Gillig Roberts l Lewis Myers Shift Supervisor C C C C C Admin. Assistants Giesler Cobbledick C
Assistant Cuff Klein Walleman Hartneet Howard Phillips Operations Shift C C C C C C Operations Patton Analyst Fehr Supervisor Fire Protection Lawrence Wadsworth Koch Coon Advisor
_ _ C C C C Baker,A.
Reactor Fox McPherson Bechtel Baker, J. Isbell Arebaugh Operator F,# F,# F# F F,# C,#
Rohde Pocino Migot Walter Jones, M. Boss F,# F,# F,# C,# F,# F,#
Whalen, T. Sutter Rowland Witt . 29 C,# F F,# C :
TRAINING ASSIGNMENTS Equipment Dudas Bolton Ferrell Fehrmann Bracken Empcke Operator F# F,# F# C C,# F,#
III 1 2 3 4 5 6 Tiell Magers McElhaney Smith Purk Matherly Auxilliary F,# F,# F,# F# F.# F# Operator Ager Wolf Gerwin Justice Higgins Boles Trainees Vassello Roidl sRO F,# F Upgrade Havey Back Bonnett Pierson Class F,# C,# F,# CE Equipment Operator l j j j j ___j Equipment Mabie Durnwald Operator l l F,# l F,#
Auxillary Holmes Brown Wagner Levy Johnson Jarra Operator F# F# F F# F# F#
l lSlobocizian l_ l_lRudolph FNic#he l lson Legends:
C - Fire Brigade Captain qualified Approved: Date:
F - Fire Brigade qualified Rev. 29-E0
- - First Aid Team member
DAVIS-BESSE NUCLEAR POWER STATION JOB PERFORMANCE MEASURE WORKSHEET JPM NO.: Admin 1-2 Rev. 0 Page 1 of 7 TASK NO.: 115-036-01-0100, 333-011-01-0300 TASK DESCRIPTION: Perform a Second Check on a Shutdown Margin Calculation and Find Shutdown Margin is < 1% AK/K K/A
REFERENCE:
XXX-GEN-2.1.33 3.4/4.0 APPLICABLE METHOD OF TESTING: Actual Performance Simulator Control Room Classroom TIME FOR COMPLETION: 20 minutes APPLICABILITY: [ ] RO [X] SRO TASK STANDARDS:
- 1. Correctly use RO curves to determine reactivity worths of control rods, fuel, boron, temperature and Flux Redistribution Penalty (FRP) within the stated accuracy bands.
- 2. Successfully check the calculation for a shutdown margin within the stated accuracy band.
- 3. Identify the Shutdown Margin does not meet Technical Specifications and direction the appropriate corrective actions.
REQUIRED MATERIALS:
DB-NE-06202, Reactivity Balance Calculations, Rev. 01 DB-NE-06201, Reactor Operators Curve Book, Rev. 5 GENERAL
REFERENCES:
DB-NE-06202, Reactivity Balance Calculations, Rev. 01
JPM Admin 1-2 Page 2 of 7 INITIAL CONDITIONS:
The plant is in Mode 3 with a reactor startup in progress.
All systems are in their normal lineup.
The START program is not available.
The following conditions exist:
Burnup: 10 EFPD Boron Conc.: 1535 ppmB Tave: 5280 F APSRs at 30i There is NO known stuck rod.
The Reactor Engineer reports reactivity worth due to transient poisons is
-0.79 AK/K and that the correction factor for boron 10 depletion is 0.96. The Reactivity Anomaly is zero.
INITIATING CUES:
The Shift Supervisor has requested you to check the calculation for a shutdown margin per DB-NE-06202, Reactivity Balance Calculations, and DB-NE-06201, Reactor Operator Curve Book.
(Hand a copy of DB-NE-06201, DB-NE-06202 to examinee and the completed Calculation Sheet Attachment 4.)
JPM Admin 1-2 Page 3 of 7 INITIAL CONDITIONS:
The plant is in Mode 3 with a reactor startup in progress.
All systems are in their normal lineup.
The START program is not available.
The following conditions exist:
Burnup: 10 EFPD Boron Conc.: 1535 ppmB Tave: 5280 F APSRs at 30%
There is NO known stuck rod.
The Reactor Engineer reports reactivity worth due to transient poisons is
-0.7% AK/K and that the correction factor for boron 10 depletion is 0.96. The Reactivity Anomaly is zero.
INITIATING CUES:
The Shift Supervisor has requested you to check the calculation for a shutdown margin per DB-NE-06202, Reactivity Balance Calculations, and DB-NE-06201, Reactor Operator Curve Book.
(Hand a copy of DB-NE-06201, DB-NE-06202 to examinee and the completed Calculation Sheet Attachment 4.)
JPM Admin 1-2 Page 4 of 7 PERFORMANCE INFORMATION NOTE: Critical steps denoted with a "C". Failure to meet any one of these standards for this item constitutes failure. Sequence is NOT critical unless denoted in the "Comments".
START TIME:
- 1. PERFORMANCE STEP: Locate correct procedure section.
STANDARD: Identifies Section 8 or Attachment 4 of DB-NE-06202, Reactivity Balance Calculations, as the correct section.
COMMENT: Sequence NOT required for this JPM except for the last step.
Examinee may complete a separate Attachment 4 prior to verifying the initial Attachment 4.
CUE: None.
SAT UNSAT
- 2. PERFORMANCE STEP: Determine reactivity worth of the fuel.
.C.
STANDARD: From Figure 2, determine value of 15.1 +/- .10% AK/K the value on Attachment 4 is 12.6.
COMMENT: The operator should find this mistake and correct it; actual value is 15.1.
CUE: The Shift Supervisor acknowledges that you have found an error and will review the error with the RO.
The Shift Supervisor has directed you to continue with the calculations and make any necessary correction.
SAT UNSAT
- 3. PERFORMANCE STEP: Determine the reactivity worth due to boron.
STANDARD: From Figure 3, determine value of -9.85 +/- .10% AK/K for boron based on B10 correction factor of 0.96; from Figure 4, determine value of 1.004 +/- .002 for the BCF; multiply these two values to obtain between -8.865 and --10.835% AK/K.
COMMENT: Actual values: Boron is -9.835 AK/K, BCF is 1.004, and total boron reactivity worth is -- 9.9% AK/K.
CUE: None.
SAT UNSAT
JPM Admin 1-2 Page 5 of 7
- 4. PERFORMANCE STEP: Utilize the reactivity worth due to transient poisons.
STANDARD: Determine from initial conditions (-0.7% AK/K).
CUE: None.
SAT UNSAT
- 5. PERFORMANCE STEP: Determine the reactivity worth due to temperature.
STANDARD: From Figure 12, determine value of -. 0096 +/- 0.01 AK/K/OF for temperature coefficient, -4 +/-OOF for AT; multiply these two values to obtain +0.0384 AK/K.
COMMENT: Actual values: temperature coefficient is -. 0096 AK/K/OF; AT 0
is -4 F; temperature reactivity worth is +0.0384 AK/K.
CUE: None.
SAT UNSAT
- 6. PERFORMANCE STEP: Determine adjusted rod worth for no known stuck rod.
STANDARD: From Figure 10, determine worth of -5.145 +/- .02% AK/K.
COMMENT: Actual value is 5.145%.
CUE: None.
SAT UNSAT
- 7. PERFORMANCE STEP: Determine APSR worth.
STANDARD: From Figure llA, determine APSR worth of -. 11 +/- 0.010% AK/K.
CUE: None.
SAT UNSAT
- 8. PERFORMANCE STEP: Determine Flux Redistribution Penalty (FRP) using Table 1.
STANDARD: Determine Flux Redistribution Penalty is 0.300% AK/K.
CUE: None.
SAT UNSAT
JPM Admin 1-2 Page 6 of 7
- 9. PERFORMANCE STEP: Determine reactivity anomaly worth.
STANDARD: Determine zero from Initial Conditions.
CUE: None.
SAT UNSAT
- 10. PERFORMANCE STEP: Determine the value for shutdown margin.
C.C STANDARD: Determine that shutdown margin is a value between .374% and
.457t AK/K.
COMMENT: Actual value is .416% AK/K.
CUE: None.
SAT UNSAT
- 11. PERFORMANCE STEP: Identify the Shutdown Margin is less that the
. C........ Technical Specification limit.
STANDARD: Recognize the Shutdown Margin is less than the 1% AK/K Technical Specification limit.
CUE: The Shift Supervisor directs you to direct the appropriate actions to correct the situation.
SAT UNSAT
- 12. PERFORMANCE STEP: Direct the Control Room personnel to begin borating
. C........ the Reactor Coolant System at > 25gpm of 7875ppm[B] or its equivalent.
STANDARD: Call the Control Room and direct them to borate the RCS at
> 25gpm of 7875ppm[B] or its equivalent.
CUE: The Control Room has been notified to borate the RCS.
SAT UNSAT TERMINATING CUES: This JPM is complete.
END TIME
JPM Admin 1-2 Page 7 of 7 VERIFICATION OF COMPLETION Operator Evaluator SSN Date License: [] RO [ SRO [ ONL Validated Completion Time: minutes Actual Completion Time: minutes Acceptable Progress Maintained: Yes No N/A Result: [ I SATISFACTORY [ ] UNSATISFACTORY NOTE: An "Unsatisfactory" requires Comment and will require subsequent remedial training.
Comments/Feedback:
Evaluator's Signature Date
ATTACHMENT 4:
25 SHUTDOWN MARGIN (SDM) WITH Tave 2 500°F -
DB-NE-06202 Revision 01 SECTION 8.0 4I EFPD= CF(Bl0)= . B(RCS)=Jl5ZgppmB Tave= J F APSR= j3C3 Zwd Known stuck rod7 Y No -Yes Data: Date Time Use the critical reference condition for all data.
[-1 X [1x +-99 L+1A] +,63q+-*sL+--,j + 3oo+ o I=Q2,!/Ak/k p(fuel) p(boron) p(tp) p(temp) R p(APSR) FRP p(anom) SDM Where:
p(fuel) is Fuel Worth from Figure 2 based on EFPD p(boron) is Boron Worth= 'l.g .xt.0 = %Ak/k p(BBOL) CF(FBU) p(boron)
Where:
l S3E x = 1. ? ppmB B(RCS) CF(B10) B(ROCB) p(BBOL) is Boron Worth at Beginning of Life from Figure 3 based on B(ROCB) (Critical curve)
CF(FBU) is Correction Factor for Fuel Burnup from Figure 4 based on EFPD (Critical curve) p(tp) is Transient Poison Worth from START program at time of data p(temp) is Temperature Reactivity= .O 601 x = ZAk/k lg aT AT p(temp)
Whe re:
aT is Temperature Coefficient from Figure 12 based on EFPD and B(ROCB)
AT = Tave - 532°F R is Control Rod Worth from Figure 10 based on EFPD and stuck rod condition p(APSR) is APSR Worth from Figure llA based on EFPD and APSR position FRP is Flux Redistribution Penalty from Table 1 of ROCB p(anom) is Reactivity .'F AtvC'lQr 2
Calculated by r*- Dat.e D Time Checked by Date Attachment 4 Page 1 of 1
ATTACHMENT 4:
g r: /
25 SHUTDOWN MARGIN (SDM) WITH Tave 2 500OF - SECTION 8.0 DB-NE-06202 Revision 01 4I EFPD= l CF(B10)= .i o B(RCS)=I53 ppmB Tave= So OF APSR=_3 C wd Known stuck rod? g No Yes Data: Date Time Use the critical reference condition for all data.
[-1] X [1*;I + ' ' + + 3oo+'C 30=,q I)_ZAk/k p(fuel) p(boron) p(tp) p(temp) R p(APSR) FRP p(anom) SDM Where:
p(fuel) is Fuel Worth from Figure 2 based on EFPD p(boron) is Boron Worth= -SS x /, dog = - q, 9 %Ak/k p(BBOL) CF(FBU) p(boron)
Where:
1_3___ x (a = Y73 _ppmB B(RCS) CF(B10) B(ROCB) p(BBOL) is Boron Worth at Beginning of Life from Figure 3 based on B(ROCB) (Critical curve)
CF(FBU) is Correction Factor for Fuel Burnup from Figure 4 based on EFPD (Critical curve) p(tp) is Transient Poison Worth from START program at time of data p(temp) is Temperature Reactivity= -,609 x = , C3& ZAk/k T AT p(temp)
Whe re:
aT is Temperature Coefficient from Figure 12 based on EFPD and T
b s(KUb)
AT = Tave - 5320F R is Control Rod Worth from Figure 10 based on EFPD and stuck rod condition p(APSR) is APSR Worth from Figure llA based on EFPD and APSR position FRP is Flux Redistribution Penalty from Talble I of ROCB p(anom) is Reactivity 1t-1-rt -f Ai(,ninn;~.
Calculated by ___ Ad 3 _>__
C__ Date Time Checked by Date Attachment 4 Page 1 of 1
DAVIS-BESSE NUCLEAR POWER STATION JOB PERFORMANCE MEASURE WORKSHEET JPM NO.: Admin 2 Rev. 0 Page 1 of 5 TASK NO.: 331-012-03-0300 TASK DESCRIPTION: Review and Issue a Clearance K/A
REFERENCE:
XXX-GEN-2.2.13 3.6/3.8 APPLICABLE METHOD OF TESTING: Actual Performance TIME FOR COMPLETION: 10 minutes APPLICABILITY: [ I RO [X] SRO TASK STANSDARDS:
Review and Approve a Clearance REQUIRED MATERIALS:
- 1. NG-DB-00250, Safety Tagging
- 2. DB-OP-00018, Inoperable Equipment Tracking Log
- 2. Work Package
- 3. Clearance Request
- 4. Tags
- 5. Inoperable Equipment Tracking Log sheet GENERAL
REFERENCES:
NG-DB-00250, Safety Tagging, Revision 00, C-3 DB-OP-00018, Inoperable Equipment Tracking Log, Revision 04, C-4 DB-DP-00007, Control of Work, Revision 02, C-3 INITIAL CONDITIONS:
You are the Work Support Center SRO. The plant is in Mode 1, 100% power, normal conditions.
INITIATING CUES:
You have been directed to review the work package for HPI pump 1, and authorize and issue the clearance.
JPM Admin 2 Page 2 of 6 INITIAL CONDITIONS:
You are the Work Support Center SRO. The plant is in Mode 1, 100% power, normal conditions.
INITIATING CUES:
You have been directed to review the work package for HPI pump 1, and authorize and issue the clearance.
JPM Admin 2 Page 3 of 6 PERFORMANCE INFORMATION NOTE: Critical steps denoted with a "C". Failure to meet any one of these standards for this item constitutes failure. Sequence is NOT critical unless denoted in the "Comments".
START TIME:
- 1. PERFORMANCE STEP: Locate correct procedure and section.
STANDARD: Identifies NG-DB-00250, Safety Tagging, as the correct procedure and section.
CUE: None.
SAT UNSAT
- 2. PERFORMANCE STEP: Review the Work Package.
STANDARD: Reviews work package for scope of work.
CUE: (If necessary) Maintenance requires HPI pump 1 be filled with water to perform the checks.
SAT UNSAT
- 3. PERFORMANCE STEP: Review the clearance for completeness.
. C.
STANDARD: Compares work package scope of work and to clearance. Reviews clearance and tags for correct information.
COMMENT: The wrong tag information for HPI breaker should be discovered at this time.
CUE: The Tagging RO has corrected clearance and tag. (Hand examinee the changed clearence form and the replacement tag for AC 111.)
(If necessary) The Shift Supervisor directs you to continue.
SAT UNSAT
- 4. PERFORMANCE STEP: Enter the Reviever's name into the clearence.
STANDARD: Logs on to the NOMS system and enters their name as the Reviewer.
CUE: The NOMS system has been updated and the reviewed block has been filled with your name.
SAT UNSAT
JPM Admin 2 Page 4 of 6
- 5. PERFORMANCE STEP: Evaluate the clearance for impact on current plant conditions for authorization.
STANDARD: Obtain the Inoperable Equipment Tracking Log to determine the impact of removing the HPIpump 1 from service and declaring the system inoperable for Tech. Specs.
COMMENT: Hand examinee the attached page from the Inoperable Equipment Tracking Log.
CUE: None.
SAT UNSAT
- 6. PERFORMANCE STEP: Ensure redundent equipment is operable.
.C.
STANDARD: Indentify that HPI Pump 2 is inoperable due to the removed date and time not being filled in.
COMMENT: The evaluator will have to initial the removed block, on the Inoperable Equipment Tracking Log sheet, as ther Shift Supervisor CUE: The Shift Supervisor has determined that (time)J/j* and (date) Z should have been entered in the removed block.
SAT UNSAT
- 7. PERFORMANCE STEP: Enter the data on the Inoperable Equipment Tracking Log sheet.
.C.
STANDARD: Enter in the Document Number block the work order number.
Enter in the Equipment/Description block " HPI Pump 1: Check couplingI alignment and soft foot" or the equivalent.
Enter in the Tech Spec Entered block " Y" or " Yes."
Enter in L the Date/Time Entered block the current time and date.
COMMENT: The Document Number block entry and Tech Spec Entered block are not critical.
CUE: None.
SAT UNSAT
JPM Admin 2 Page 5 of 6
- 8. PERFORMANCE STEP: Enter approve to render the equipment inoperable.
STANDARD: Enter into FEARMS the approve to render the equipment inoperable.
COMMENT: This may be done prior to making the Inoperable Equipment Tracking Log entry.
CUE: The approval to render the equipment inoperable has been entered into FEARMS.
SAT UNSAT
- 9. PERFORMANCE STEP: Assign a qualified individual to place the tags.
STANDARD: Must assign an E03 or higher.
COMMENT: Only give cue if a qualified individual is assigned.
CUE: An EO-3 has been assigned.
SAT UNSAT TERMINATING CUES: This JPM is complete.
END TIME
JPM Admin 2 Page 6 of 6 VERIFICATION OF COMPLETION Operator Evaluator SSN Date License: [] RO [ SRO [] ONL Validated Completion Time: minutes Actual Completion Time: minutes Acceptable Progress Maintained: Yes No N/A Result: [ ] SATISFACTORY [ ] UNSATISFACTORY NOTE: An "Unsatisfactory" requires Comment and will require subsequent remedial training.
Comments/Feedback:
Evaluator's Signature Date
TECH SPEC 3.5.2 DOCUMENT EQUIPMENT/WORK DESCRIPTION TECH SPEC DATE/TIME DATE/TIME NUMBER ENTERED ENTERED REMOVED (Y/N) INITIALS INITIALS 99-000200-000 High Pressure Injection Pump 1-2: Check alignment of pump Y for CR.__
I.
i I I 1Fi i 1 F 4 -I-i I i F I I-I ~i.
i iF I I t + i i I
i i I I I __ _ _ __ _ _
FEARMS DAVIS-BESSE PLANT =liii! l liii 11111111 11111 liii liii liii 11liil liii P58-1 Work Order 99-000205-000 Subsystem: SUB052-01 Asset: P58-1 HPI PUMP 1-1 Problem Locn: AUXL8_105*_545 Action: ROUTINE MAINTENANCE Work Class:
WO Type: Mat.Acct: 4537.4537.IS.NP13A.DBRX.00000.00 Clearance: Y Printed: 15-AUG-00 15:32 RMP Clearance number: ASca I8 6IQ Quality Class: Q Tech Spec: Y Environmental Qualification: N Test Requirements: Y ASME Component: ASMEXI Lead Craft: MECHANICAL Repair Tag Number: L077 Train:
'ermission ....b reAto Col S B /:::::::::::l02i::illmei:::::ic M ....... Work - _ _ _ _ _ _ _ _ _ _......_ _ _
SiE:I i______i___
iAT Ei yi
,l....i:.......
i,-SSEEE;EEEE...........
................. EEEEE3 EEE]:
- '.. ' EE
- ;;E000SiES:SEECEEE:Ei~g:j~ig~
Requested by: JOSEPH MADISON Phone: 7311 Planner: KEITH A LUTMAN Phone: 8327 Problem
Description:
VIBRATION HAS INCREASED ON THE PUMP OUTBOARD BEARING PLEASE CHECK THE COUPLING FOR ADEQUATE LUBRICATION AND PROPER ASSEMBLY AND WEAR. CHECK COUPLING ALIGNMENT AND SOFT FOOT. ADJUST IF NEEDED. CHECK THAT HOLDDOWN BOLTS ARE TIGHT Work
Description:
CHECK THE COUPLING FOR ADEQUATE LUBRICATION AND PROPER ASSEMBLY AND WEAR. CHECK COUPLING ALIGNMENT AND SOFT FOOT. ADJUST IF NEEDED. CHECK THAT HOLDDOWN BOLTS ARE7 TIGHT Work Order Review Engineering IST Fzji L , DATE 4 SRO . DATE ALARA '<
@ DATE QC Mechanical DATE ANI - DATE X Lead Shop Review / DATE 7/_)/fZe Special Instructions:
Page 1 of 4
FEARMS DAVIS-BESSE PLANT l 1111 liii 111111 11111 11111 11111 11111 11111 liii11111 11liii liii P58-1 Work Order 99-000205-000 T1k Subsystem: SUB052-01 Test Requirements:
Test Test Test Type Function Procedure Craft Signature Date 3 TSC DB-SP-03218 (Note 1) OPER 3 PMT DB-MM-05003 MECH Test Requirements Comments:
TEST REQUIREMENT DB-MM-05003 COMPLETED UNDER SP03218.
note 1: Test codes 'PMT' and 'IST' also apply.
Technical Specifications Equipment Rendered Inoperable:
P58-1, HIGH PRESSURE INJECTION PUMP #1.
Redundant Equipment to Verify:
P58-2, HIGH PRESSURE INJECTION PUMP #2 Effect on Equ1ipment/System
- 1 HIGH PRESSURE INJECTION PUMP WILL BE INOPERABLE DURING PERFORMANCE OF THIS WO.
01 Tech Spec/Applicable Modes: 3.5.2 (1,2,3).
02 Tech Spec/Applicable Modes: 4.0.5 (1,2,3,4,5,6)
Approval to render equipment inoperable SS/SM DATE Comments:
Operability Testing Complete and Satisfactory
- SS/SM V DATE Related Documents DB-MM-05003 DB-MM-09046 Permits RWP RWP Comments 1999-0081 Other Permits Required 9970886 Page 2 of 4
FEARMS DAVIS-BESSE PLANT l liii 11l1 11111 11111 1111 liii11111 11111 11111 11111 1 ill l111 P58-1 Work Order 99-000205-000 T*
Subsystem: SUB052-01 Steps Craft Crew Size Crew Name Hrs 1 MECHANICAL 2 DB MECH UNIT TEAM 1 8 STEP DESCRIPTION: ALIGNMENT AND COUPLING CHECK.
- CONTACT JOE MADISON PRIOR TO START OF WORK.
- DOCUMENT ALL AS FOUND CONDITIONS.
- CHECK COUPLING MATCH MARKING PRIOR TO DISASSEMBLY TO VERIFY PROPER PREVIOUS ASSEMBLY.
- DISASSEMBLE COUPLING AND CHECK FOR ADEQUATE LUBRICATION.
- CLEAN AND INSPECT COUPLING FOR WEAR.
- RELUBE AND REASSEMBLE COUPLING, ENSURING MATCH MARKS LINE UP.
- PERFORM/CHECK SHAFT ALIGNMENT.
- CHECK MOTOR/PUMP FOR SOFT FOOT, ADJUST IF NEEDED.
- CHECK THAT HOLDDOWN BOL'PS ARE TIGHT.
SIGNATURE: DATE:
2 RADIATION TEST 1 1 SUPPORT CRAFT.
SIGNATURE: DATE:
Notes MLD 12-JAN-99 MDT 1 TAG HUNG ON PUMP WALDOWN PERFORMED BY MICHAEL DISTEL APPROVED BY TERRY PLOEGER FAILURE DATE 1/11/99 System 13-AUG-99 PRINT HISTORY 15-AUG-00 15:28 RMP CLOSED 13-AUG-99 07:30 MHS WSC TAGS JNP 14-MAY-99 ROCK HPI #1 MLD 12-JAN-99 WALKDOWN MMTM REVIEWED NEED TO CHECK COUPLING LUBRICATION AND ALIGNMENT FORWARD TO SHOP Closeout Lead Shop / MDT Removed ; Date:
SS/SM Authorization Date:
QC Mechanical _ Date:
Planner Review Date: ___3_of Page 3 of 4
FEARMS DAVIS-BESSE PLANT I11111 lilii liii 111111 11111 11111 liii 11111 liil 111111 11111 11111 liii liNi 11111 P58-1 Work Order 99-000205-000 U Subsystem: SUB052-01 Completion Date: / /__ Completed By:
Notes:
Page 4 of 4
ATTACHMENT 2: CLEARANCE REOUEST EQUIPMENT NAME JOB No.
CLEARANCE REQUEST NG-DB-00250 1= O a Aorse Work Group(s):
\CA O. \X vCt a4 C 4 4 Description of Work:
QcR~e.. 4+-k- C kVL4A4 , aLO1e pUL1-'c 6A-;-0/c-7t 01ACA~-~ -I 'A , 4 AA- £ft Cs 1n4'Mj OL w c Lj' S4'4t C-t.>
16(Yloci4ss cur-r s4?WA~v
-Ag.Ck fty Reference Drawings Requirements (Include recommended components to be tagged and their position)
Olsolated Electrically Q Isolated Mechanically E Grounded E] Vented Ol Drained O Brkr Removed M System Breach El Other RfQUESTER PRINT & SIGN DATE EXT. WORK GROUP OP6RATION'S REVIEW NOTES Page I of I
SUB052-01-016 08/16/2000 08:07 Davis Besse DB-2000- 0 1 - 7 0 0 5 Page 1 of I Equipment ID:
P58-1 Description /Reason Check coupling for proper lubrication and alignment.
Placement Notes Cautions Completion Instructions Attribute Attribute Description Value Containment Penetration? N'o Tagout Type Non-Outage Number Equipment ID I Description 99-ooo205-ooo r58-1 ICheck coupling for proper lube and alignment Status Description User Verification Date Prepared Prepared By Howard, Bob 08/16/2000 08:00 Reviewed Reviewed By 00/00/0000 00:00 Second Reviewed Second Reviewed By .0/00/0000 00:00 Approved Approved By 00/00/0000 00:00 ssued for Work Issued for Work By 00/00/0000 00:00 Restoration Review Restoration Review By 00/00/0000 00:00 Removal Authorized Removal Authorized By 00/00/0000 00:00 Clearance Closed Clearance Closed By 00/00/0000 00:00
Tag List for SUB052-01-016 08/16/2000 08:07 Davis Besse DB-2000-01-70 0 5 Page 1 of I Equipment ID Equipment Equipment Tag Tag Place. Place. Rest. Rest. Notes Description Location Serial Type Config. Seq. Config. Seq.
HIS1524 HPFPUP 1 AXI7-623-50 RW MC Danger Tag Do1 UNTAGED- 2 NP581 HPI PUMP 1 AUXL7 545-105* DangerTag T{AGGED 1 UNTAGGED 2 AD111 HP INJ PMP 1-2 MP-582 AUXL6-585-323* (D1l)#2 High Voltage Switchgear Roomn_
Danger Tag
_ I RACKED OUT KED_
-UNTAGGED 1
Tag List for SUB052-01-016 08/16/2000 08:04 Davis Besse DB-2000-0o1-07005 Page 1 of 1 riace. riace. Nest.
Config. KSL rotes Equipment ID equipment Equipment lag lag Place. Place.
Seq. Rest. Sesq Notes Description Location Serial Type Config. Seq. Conflg. Seq.
HIS1524 HPI PUMP 1 AUXL7-623-505* CTRM Panel C5716 Danger Tag TG1 UNTGGD 2 NP581 HPI PUMP 1 AUXL7-545-105*_ DangerTag TAGGED 1 UNTAGGED 2 AcillHP INJ PMP 1-1 MP-581 AUXL6-585-325*_(C1) #1 High Voltage Switchgear Room I Danger Tag RACKED OUT I 2 RACKEDfIN 1 Component Print Number AC111 OS-3,G-8 AClIl E3,
DAVIS-BESSE NUCLEAR POWER STATION JOB PERFORMANCE MEASURE WORKSHEET JPM NO.: Admin 3 Rev. 0 Page 1 of 5 TASK NO.: 333-008-01-0300 TASK DESCRIPTION: Review a Waste Gas Release with No Radiation Monitors Available K/A
REFERENCE:
XXX-GEN-2.3.08 2.3/3.2 APPLICABLE METHOD OF TESTING: Actual Performance Simulator Control Room Classroom TIME FOR COMPLETION: 12 minutes APPLICABILITY: [ ] RO EX] SRO TASK STANDARDS:
- 1. Review a Waste Gas Release with no REs operable.
- 2. Deny approval of a Waste Gas Release due to the release Rate.
REOUIRED MATERIALS:
- 1. DB-OP-03012, Radioactive Gaseous Batch Release
- a. Sections 4.1, 4.12,4.13, 4.15 completed accordingly for RE 1822 A and B being out of service.
- b. On attachment 1 enter a release rate of 15 in item 9.a and a tenth value of 0.65 in item 9.b
- 2. ODCM GENERAL
REFERENCES:
INITIAL CONDITIONS:
The plant is at 100% power, Waste Gas REs 1822A and 1822B are inoperable.
INITIATING CUES:
You are directed to review and approve a Waste Gas Release Permit.RE's 4598AA and 4598AB should be used for the release.
JPM Admin 3 Page 2 of 5 INITIAL CONDITIONS:
The plant is at 100% power, Waste Gas REs 1822A and 1822B are inoperable.
INITIATING CUES:
You are directed to review and approve a Waste Gas Release Permit.RE's 4598AA and 4598AB should be used for the release .
JPM Admin 3 Page 3 of 5 PERFORMANCE INFORMATION NOTE: Critical steps denoted with a "C". Failure to meet any one of these standards for this item constitutes failure. Sequence is NOT critical unless denoted in the "Comments".
START TIME:
- 1. PERFORMANCE STEP: Locate the correct procedure.
STANDARD: Determine that DB-OP-03012, Radioactive Gaseous Batch Release Procedure, is the correct procedure.
COMMENT: Hand Examinee a copy of DB-OP-03012 with Section 4.1 completed, and Attachment 1 completed up to 4.h.
CUE: None.
SAT UNSAT
- 2. PERFORMANCE STEP: Verify that the permit is approved.
.C.
STANDARD: Verify that item 4.h. of Attachment 1 has been signed.
CUE: None.
SAT UNSAT
- 3. PERFORMANCE STEP: Verify that surveillance requirements are current.
STANDARD: Verify that the surveillances in Step 4.2.2 are completed.
CUE: All surveillances are current except for REs 1822A and 1822B.
SAT UNSAT
- 4. PERFORMANCE STEP: Detemine RE operability.
STANDARD: Circle unsat in item 4.i due to 1822A&B being inoperable.
CUE: None.
SAT UNSAT
2000 06:01:33.01 CAS DAVIS-BESSE STATION SAMPLE TITLE : CHEM - ECASS SAMPLE ID : 200005241002
- SAMPLE TIME SAMPLE GEOMETRY : CHARCART
- SHELF HEIGHT : ABS SAMPLE TYPE : CHEMISTRY
- SAMPLE QUANTITY : 3.82000E+06 CC ACQ DATE & TIME -2000 05:51
- DEADTIME (%) : 0.4%
PRESET LIVE TIME : 0 00:10:00
- DETECTOR : DETECTOR 2 ELAPSED REAL TIME : 602.33 Secs
- DECAY TIME : 0 00:11:14.24 ELAPSED LIVE TIME - 'n no cecs
- LIBRARY : 211 QC CHECK DATE/TIM} 02:20
- ^ ^ ^^ ^^****************************
COLLECTED BY : JN COUNTED BY : DBS REVIEWED BY COMMENTS 19c9&J~
- P* * * * *Report* * ** ***
Post-NID Peak Search Report It Energy Area Bkgnd FWHM Channel Left Pw %Err Fit Nuclides
- 77. 11 150 1278 0.88 205.81 200 29 76.1 2.30E+00 BI-214 PB-214 3 80.34 879 1659 1.35 214.41 200 29 19.4 I-131 1 249.57 257 1059 1.26 665.47 660 11 50.3 2.48E+00 1 284.36 1001 1102 1.24 758.22 753 12 14.7 2. 18E+00 I-131 I-132 1 288.61 386 1307 2 .34 769.54 765 16 43.1 2.34E+00 I-135 1 294.77 513 1048 2 . 04 785.97 780 13 27.0 7. 19E+00 PB-214 1 351.99 555 1197 1.43 938.49 931 16 29.3 1. 92E+00 I-134 PB-214 1 364.51 10291 949 1.17 971.86 965 14 2.3 3.73E-01 CS-138 I-131 CS-138 1 417.46 122 394 1.18 1112.99 1107 10 63.9 2.12E+00 I-132 I-133 I-135 I-133 1 462.95 544 488 1.54 1234.26 1226 16 20.2 1.95E+00 PB-214 CS-138 1 479.52 259 602 7.17 1278.43 1269 23 50.7 2.18E+00 W-187 PB-214 1 511.07 3327 778 2.81 1362.51 1352 28 6.0 1. 69E+00 1 526.60 169 259 1.47 1403.91 1399 23 37.2 1. 09E+00 I-135 1 530.02 11268 240 1.32 1413.04 1399 23 2.0 1
I-133 546.81 387 331 1.39 1457.79 1451 16 23.3 1. 64E+00 I-135-CS-138 I-132 1 554.45 102 198 0.98 1478.14 1474 10 55.4 2.14E-01
JPM Admin 3 Page 4 of 5
- 5. PERFORMANCE STEP: Verify status of RE monitor source check being satisfactory .
STANDARD: Determine that RE's 1822A and 1822B are inoperable per the initial conditions .
CUE: All other RE's monitor source checks were satisfactory SAT UNSAT
- 6. PERFORMANCE STEP: Circle the operable monitors to be used for the release in item 5.b .
STANDARD: Circle RE's 4598AA and 4598AB in item 5.b based on initial conditions CUE: NONE SAT UNSAT
- 7. PERFORMANCE STEP: Return the permit to the Control Room STANDARD: Return the permit to the Control Room .
CUE: The permit is now returned to the Control Room, you are directed to continue with approval of the Waste Gas Release Permit.
SAT UNSAT
- 8. PERFORMANCE STEP: Check the tenth value of the maximum release rate
.C.
STANDARD: Identify that item 9.b is less than 1 SCFM and deny approval of the Waste Gas Release permit.
NOTE: The tenth value in item 9.b is .65 the release should not be performed CUE: NONE SAT UNSAT TERMINATING CUES: This JPM is complete.
END TIME
JPM Admin 3 Page 5 of 5 VERIFICATION OF COMPLETION Operator Evaluator SSN Date License: [ RO []SRO []ONL Validated Completion Time: minutes Actual Completion Time: minutes Acceptable Progress Maintained: Yes No N/A Result: [ ] SATISFACTORY [ ] UNSATISFACTORY NOTE: An "Unsatisfactory" requires Comment and will require subsequent remedial training.
Comments/Feedback:
Evaluator's Signature Date
Jnidentified Energy Lines Page : 4 tample ID : 200005241002 Acquisition date : -2000 05:51:14
?. Energy Area Bkgnd FWHM Channel Left Pw Cts/Sec %Err %Eff Flags 1 249.57 257 1059 1.26 665.47 660 11 4.28E-01 50.3 4.07E+00 1 511.07 3327 778 2.81 1362.51 1352 28 5.54E+00 2.00E+00 44 1 554.45 102 198 0.98 1478.14 1474 10 1.70E-01 1 84E+00 T 1 -
1 ".I '7 n A n A r . Z = - /) ' U 'ID(nC;'1 1 2118.74 32 14 2 . 92 5648.29 5640 18 5.40E- 0 5.31E-01 7Z?4-1 2217.80 80 21 3.30 5912.40 5902 22 1.33E-01 5.20E-01 1 2254.71 20 5 1.86 6010.80 6004 12 3.38E-02 6 5.17E-01 1 2639.14 28 0 1.71 7035.76 7025 17 4.65E-02 4.96E-01c5" 1 2677.79 55 6 2.60 7138.82 7129 18 9.20E-02 4.95E-01'R 1 2753.87 215 3 2.47 7341.65 7332 20 3.58E-01 4.95E-01A -t 2
'lags: "T" = Tentatively associated
PROCEDURE DEVELOPMENT FORM ISHEET PROCEDURE ACTIVITY TRACKING NO.
ED 7635-14 /0Ff . TAnO- n A i (
I SECTION 1 - IDENTITY PROCEDURE NO. / CURRENT REVISION PROPOSED PROPOSED El NEW a CANCELLATION DB-OP-03012 Ro REVISION NO. CHANGE NO. E REVISION 0 INACTIVATION 0 RESTRICTED SUPERSEDES [ ]CHANGE O REACTIVATION ESTIMATED EXPIRATION 0 TEMPORARY APPROVAL (DATE / EVENT)
PROCEDURE TITLE Radioactive Gaseous Batch Release PROCEDURE CLASSIFICATION PAT/ PCR NOS. CLOSED OUT 0 SR El OR E N-OR CHANGE TO? El YES O NO None rl CONTINUED ACTIVITY
SUMMARY
/ PURPOSE Remove references to specific portions of gamma spectral analysis computer printouts which no longer exist with new gamma spectroscopy software.
DOCUMENTATION MANAGEMENT CONTROL COPY El CONTINUED SECTION - CO OWRENI E C CUMENT; OCONTINUED DOCUMENT NO. REVISION E PAT NO./ CHANGE REQUEST SECTION 3 - REVIEW ORGANIZATIONS REQUIRED REQUESTED
^ CONTINUED E CONTINUED PROCEDURE RbPARER \DATE l REVIEVRDATE
- a. k ,>w .. G;A~t 2/10/00 W.lXit SECTION 4 - ATTCHMENTS COMPLETED AND ATTACHED YES N/A YES N/A YES N/A o C/VALIDATION CHECKLIST Ia"0 SAFETY REVIEW 0 E-REVISED CROSS REFERENCES LIST O 3-COMMITMENT VERIFICATION
SUMMARY
E GeOCUMENT REVIEW SHEETS 0 M-PCRS o O'*SAFETY EVALUATION NO. _0 lO-aTHER FINAL QUALI 4DEIWR CONCURR EEATE/
FNL _ _ SECTION 5 - TEMPORARY APPROVAL MANAGEL7 K -e 1DATE/ / APPROVAL AUTHORITY (DATE SECTION 6 - CONCURRENCE / FINAL APPROVAL PRCEDURE0PONSV R( DATE El MANAGER - BUSINESS SERVICES (BSA)DATE o DIRECTOR - SUPPORTS VtIbES (NA) DAT9 0 SRB 9Z DATE E DIRECTOR - TECHNICAL SERV2CES (E&S) DATE 0 PLANT MANAGER DATE o DIRECTOR - WORK MANAGEMENT (WMD) DATE APPROVA TRI L DAT7,.
3 1.4 I _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
SECTION 7 - TRAINING / PROCEDURE EFFECTIVITY TRAINING COMPLETE ALTERATION EFFECTIVE DATE PROCEDURE SPONSOR DATE O YES O N/A
SECTION 1 - IDENTITY (CONTINUED)
SECTION 2 - QUALIFIED PROCEDURE REVIEW (CONTINUED)
SECTION 7 - TRAINING/PROCEDURE EFFECTIVITY (CONTINUED)
Post-NID Peak Search Report (continued) Page : 3 3ample ID : 200005241002 Acquisition date -2000 05:51:14 Energy Area Bkgnd FWHM Channel Left Pw %Err .Fit Nuclides 1 2639.14 28 0 1.71 7035.76 7025 17 42.4 6.36E-01 1 2677.79 55 6 2.60 7138.82 7129 18 32.0 7.05E-01 1 2753.87 215 3 2.47 7341.65 7332 20 14.3 7.70E-01
PROCEDURE DEVELOPMENT FORM IbCit-t1 PROCEDURE ACTIVITY TRACKING NO.
ED 7635-14 I OF I c~I c'?~I~ -~t SECTION 1 - IDENTITY PROCEDURE NO. / CURRENT REVISION PROPOSED O NEW Q CANCELVATION DB-OP-03012 / R02 REVISION NO. CHANGENO. El REVISION U INACTIVATION 0 RESTRICTED SUPERSEDES 0 CHANGE El REACTIVATION ESTIMATED EXPIRATION C-5 E TEMPORARY APPROVAL _
(DATE EVENT)
PROCEDURE TITLE Radioactive Gaseous Batch Release PROCEDURE CLASSIFICATION PAT I PCR NOS. CLOSED OUT 0 SR El OR E N-QR CHANGE TO? El YES 0 NO CR99-0104 4c& g g -0 o O E CONTINUED ACTIVITY
SUMMARY
/ PURPOSE z G44eJtf This change only will incorporate CR99-0104, and as such constitutes an editorial-ehege-lo this procedure.
,:f-TS c o4sJ-LA-ejA.~tr Re r t 9S-00 iu [NAtMN .AANAGEM1LNr l OfiROL CUPY El CONTINUED SECT CON2AOENT tfTVa"MENTS O_CONTINUED DOCUMENT NO. / REVISION PAT NO. I CHANGE REQUEST DB-OP-03012 / R02 Radioactive Gaseous Bat Releas CR99-0104-Cancellation SECTION 3 - REVIEW ORGANIZATIONS REQUIRED REQUESTED E] CONTINUED IE CONTINUED PROCEDURE PREPER DATE QUALIFIED REVIEW DATE
, .7 SECTION 4 - ATTACHMENTS COMPLETED AND ATTACHED YES N/A YES N/A YES N/A o , VALIDATION CHECKLIST 0 q SAFETY REVIEW 3 a REVISED CROSS REFERENCES LIST JX 0 COMMITMENT VERIFICATION
SUMMARY
0 KDOCUMENTREVIEWSHEETS Pt 0 PCRs cj 9-601 54 0 SAFETY EVALUATION NO. (,. g8c053S 0 1
° OTHER FINAL OUALIFIEDREVIEWER CONCURRENCE DATE
____ _ /2 /2co/ 9 SECTION 5 -TEMPORARY APPROVAL MANAGEMENTSRO lDATE IAPPROVAL AUTHORITY DATE SECTION 6 - CONCURRENCE I FINAL APPROVAL Pt OURSPCSO 7 MANAGER - BUSINESS SERVICES (BSA) DATE o DTRECTOR-SUPPORT RVICES (NA) DAtE 0 0 SRB DATE
[ DIRECTOR - TECHNICAL SERVICES (E&S) DATE Q PLANT MANAGER DATE o DIRECTOR - WORK MANAGEMENT (WMD) DATE APPROVAL THORITY< DATE I 6 d) 1 z / LZ/5 SECTION 7 - TRAtNING / PROCADURE EFFECTIVITY TRAINING COMPETE 0 YES N NtA ALTERS rON EFFECTIVE DATE IZ IPR (4
URES IONS f tvtBlMA n DA['- f k .
SECTION 1 - IDENTITY (CONTINUED)
SECTION 2 - QUALIFIED PROCEDURE REVIEW (CONTINUED)
SECTIONI 7 - TRAINING PROCEDURE EFFECTIVITY (CONJTINUED)
ost-NID Peak Search Report (continued) Page : 2 ample ID : 200005241002 Acquisition date : -2000 05:51:14 Energy Area Bkgnd FWHM Channel Left Pw %Err Fit Nuclides 1 609.57 566 225 1.36 1625.09 1619 12 13.5 6.20E-01 BI-214 1 637.11 514 251 1.27 1698.50 1692 14 15.8 5.20E-01 I-131 1 668.13 220 290 1. 57 1781. 18 1774 14 35.5 2.97E+00 I-132 1 686.09 76 159 1.26 1829.06 1824 11 69.1 2.35E+00 W-187 1 706.43 128 276 1.69 1883.27 1875 16 60.5 4.39E-01 I-133 I-134 I-133 1 722.94 66 172 1.52 1927.29 1923 10 78.3 8.57E-01 I-131 1 768.35 108 143 2.17 2048.33 2041 13 49.6 2.67E+00 BI-214 I-133 I-133 772.62 1 237 116 1.74 2059.70 2054 26 22.6 7.11E-01 I-132 W-187 CS-138 776.64 1 111 138 1.74 2070.42 2054 26 49.8 1 810.72 613 294 1.49 2161.27 2152 19 15.7 6.43E-01 I-132 CO-58 836.55 1 188 172 2.14 2230.13 2222 18 35.9 1.05E+00 I-134 I-135 847.23 1 166 138 1.84 2258.59 2251 14 33.9 9.49E-01 MN-56 I-134 857.20 1 89 167 0.99 2285.17 2277 16 69.1 6.98E+00 I-133 I-134 875.37 355 190 1.62 2333.60 2326 16 20.6 2.34E+00 I-133 898.02 1043 183 1.57 2393.97 2385 17 8.6 8.07E-01 RB-88 Y-88 l 1009.75 280 101 1. 83 2691.84 2685 14 19.4 9.72E-01 CS-138 1 1039.06 133 134 1.79 2769.97 2763 16 43.7 1.85E+00 I-135 l 1120.26 103 113 1. 93 2986.41 2978 25 50.1 1.45E+00 BI-214 1 1123.68 68 122 1. 93 2995.53 2978 25 74.6 I-135 l 1131.43 293 148 1. 53 3016.21 3009 16 22.1 1.75E+00 I-135 1 1237.54 259 101 1.35 3299.05 3292 17 20.1 4.78E+01 I-133 BI-214 1 1260.43 432 67 1.66 3360.08 3350 19 13.3 1.52E+00 I-135 1 1298.16 121 90 1.71 3460.66 3450 18 41.5 9.89E-01 I-132 I-132 I-133 L 1318.20 188 85 2.65 3514.09 3503 24 27.0 3.02E+01 I-132 L 1368.55 455 79 1.77 3648.31 3641 20 13.6 7.15E-01 I-135 NA-24 L 1435.69 503 34 1.89 3827.30 3819 17 10.5 2.40E+00 CS-138 L 1457.67 83 112 1.76 3885.90 3881 21 68.4 1.14E+00 I-135 L 1678.60 99 39 2.07 4474.87 4465 17 35.2 2.22E+00 I-135 L 1707.28 49 55 1.03 4551.33 4539 22 80.8 4.78E+00 I-135 L 1764.58 72 21 1.86 4704.09 4695 17 38.7 1.45E+00 BI-214 L 1791.69 81 25 2.23 4776.38 4767 17 36.4 8.36E-01 I-135 L 1836.08 865 21 2.06 4894.70 4884 21 7.4 1.47E+00 RB-88 Y-88 1 2118.74 32 14 2.92 5648.29 5640 18 62.3 7.72E-01 2217.80 80 21 3.30 5912.40 5902 22 36.8 1.23E+00 L 2254.71 20 5 1.86 6010.80 6004 12 63.1 2.01E-01
PROCEDURE DEVELOPMENT FORM I 0Ht IT PROCEDURE ACTIVITY TRACKING NO.
ED 7635-13 1 OF 1 ITAaa-177n SECTION 1 - IDENTITY PROCEDURE NO. / CURRENT REVISION PROPOSED PROPOSED Cl NEW Cl CANCELLATION DB-OP-03012 / R02 REVISION NO. CHANGE NO. O REVISION ] INACTIVATION El RESTRICTED SUPERSEDES C CHANGE El REACTIVATION EXPIRES 3 TEMPORARY APPROVAL (DATE I EVENT)
PROCEDURE TITLE Radioactive Gaseous Batch Release PROCEDURE CLASSIFICATION PAT / PCR NOS. CLOSED OUT 0 SR a QR D N-OR E CHANGE TO? El YES None mNO E CONTINUED ACTIVITY
SUMMARY
/ PURPOSE Update calculation sections due to new software.
A
_________________________MEl _ _I CONTINUED SECTION 2_- COW Ci ENCONTINUED DOCUMENT NO. / REVISION _JE__L__ a" i PAT NO. /_CHANGE REQUEST SECTION 3 - REVIEW ORGANIZATIONS REQUIRED REQUESTED El CONTINUED El CONTINUED PROCEPULE.PREPARER {. DATE QUALIFIED U DATE (CA/ri SECTION 4 - ATTACHMENTS COMPLETED AND ATTACHED YES N/A YES N/A YES N/A IX 0 VALIDATION CHECKLIST y E SAFETY REVIEW [l E REVISED CROSS REFERENCES LIST o K COMMITMENT VERIFICATION
SUMMARY
0 DOCUMENT REVIEW SHEETS Q { PCRs o R( SAFETY EVALUATION NO. _ 0 OTHER FINAL QUALIFIED REVI WER CQNRENCE ) DATE
'SECTION 5 - TEMPORARY APPROVAL MANAGEMENTS DATE APPROVAL AUTHORITY IDATE SECTION 6 - CONCURRENCE / FINAL APPROVAL UR VN DAT 09MANAGER - BUSINESS SERVICES DATE E DIRECTOR -NA JDAE l Q SRB DATE o DIRECTOR - E&S DATE 0 PLANT MANAGER DATE o DIRECTOR. NSS TRAINING COMPLETE DATE ALTERATION EFFECTIVE DATE PROCEDURE SPONSOR APPR "LAUTHO I
7 c___t___
SECTION 7 - TRAINING / PROCEDURE EFFECTIVITY G ,
INY DATE 21 I DATE a-YES El N/A I I
r SECTION 1 - IDENTITY ICONTINUipDi SECTION 2 - QUALIFIED PROCEDURE REVIEW (CONTINUED)
SECTION 7 - TRAINING/PROCEDURE EFFECTIVITY (CONTINUED)
ummary of Nuclide Activity Pagel: 2 ample ID : 200005241001 Acquisition date : 2000 01:49:04
"'al number of lines in spectrum 11 ber of unidentified lines 3 Number of lines tentatively identified by NID 8 72.73%
uclide Type : FISSION GAS Wtd Mean Wtd-Mean Uncorrected Decay Corr Decay Corr 2-Sigma uclide Hlife Decay uCi/CC uci/CC 2-Sigma Error %Error Flags R-41 109. 62M 1.17 1.317E-06 1.547E-06 0.010E-05 6.45 R-85M 4.48H 1.07 4.806E-08 5.134E-08 1.809E-08 35.24 E-133 5.25D 1. 00 4.017E-06 4.027E-06 0.116E-06 2.87 E-133M 2. 19D 1. 01 1.560E-07 1.569E-07 1.688E-07 107.60 E-135 9.11H 1. 03 1.139E-06 1.177E-06 0.041E-06 3.49 Total Activity : 6.677E-06 6. 958E-06 Grand Total Activity : 6.677E-06 6.958E-06 lags: "K" = Keyline not found 'M" = Manually accepted "El = Manually edited "A" = Nuclide specific abn. limit
PROCEDURE DEVELOPMENT FORM jSHEET PROCEDURE ACTIVITY TRACKING NO.
ED 7635-13 1 OF I I (QR_9AOQ1 I I.
SECTION 1 - IDENTITY PROCEDURE NO. I CURRENT REVISION PROPOSED PROPOSED El NEW C CANCELLAION DB-OP-03012/R02 ~REVISION NO. CH-ANGE NO. lCNEAiO DB-OP-03012/R02 O REVISION C3 INACTIVATION El RESTRICTED SUPERSEDES 0 CHANGE El REACTIVATION EXPIRES C-4 E TEMPORARY APPROVAL (DATE /IEVENT)
PROCEDURE TITLE RADIOACTIVE GASEOUS BATCH RELEASE PROCEDURE CLASSIFICATION PAT/ PCR NOS. CLOSED OUT C; 6-22.05 0 SR a OR E N-QR (- CHANGE TO? a YES 0 NO PCR'S: 98-1771,98-1957,98-1313,98-2617 E CONTINUED ACTIVITY RI SMMAAPV I PURPVO VOC Ad WV....... I . -1.1 Changed referenced procedures for Instrument Cal checks to reflect new procedure numbers. Made Editorial enhancements by moving some steps in the procedure to more appropriate locations, in order to allow evolution to flow more smoothly.
Added step to all release sections to review concurrent steps prior to performance. Made various other editorial enhancements and updates to reflect current plant status.
. . CONTINUEF SECTION 2 - CONCURRENT EFFECTIVE DOCUMENTS ElCONTINUED DOCUMENT NO. I REVISION DOCUMENT TITLE PAT NO. I CHANGE REQUEST DB-OP-03012/R02 RADIOACTIVE GASEOUS BATCH RELEASE CR99-0104-ACTIVATION DB-OP-03012/R02 RADIOACTIVE GASEOUS BATCH RELEASE CR98-2205-CANCELLATION
- E C gIA 8 lJ ._ @ _______
RI ~QIREMREQUESTED SYME CHEM RP O NTROL COPY UED_ O El CONTINUED PROCEDURE PREPAR DATE 612/12/98 12/12/98 SECTION 4 - ATTACHMENTS COMPLETED AND ATTACHED YES N/A YES N/A YES N/A
- 05. 0 VALIDATION CHECKLIST 0 SAFETY REVIEW 0 ) REVISED CROSS REFERENCES LIST j: 0 COMMITMENT VERIFICATION
SUMMARY
'DOCUMENT REVIEW SHEETS )d 0 PCRs O t SAFETY EVALUATION NO. .j( pi0 . OTHER OTH FINAL QUALIFIED REVIEWER CONCURRENCE DATB SECTION 5 - TEMPORARY APPROVAL /
MANAGEMENT SRO IDATE _APPROVAL AUTHORITY DATE SECTION 6 - CONCURRENCE I FINAL APPROVAL DATtI 0 MANAGER -BUSINESS SERVICES DATE C DIRECTOR -NA DA+E / QSRB DATE C DIRECTOR - E&S DATE 0 PLANT MANAGER DATE o DIRECTOR - NSS DATE APPROWCCAUTHORI DATE
_ _ _ _ z. r) loli, SECTION 7 - TRAINING / PROCEDURE EFFECTIVITY TRAINING COMPLETE ElYES N/A
]ALTER10i NIEFFECTIVE
&DAT DATPROCE$ESO8SOR(
1 t-
SECTIOU 1 - IDENTTY (CONTlNUED) x 2
C_
n . _
=.
=
l
=_,
v
= ,
a>
(__
- i
- J^_)
- '--E.- .- :-E. ^ . i _--.*.$E' ........ ._E IF :;../D-:'.^ERE^ 'ES.
I I S-7-.N It C:,, . ! z,::,,~
_ l -E-':E-E
_ I I _ _ _;- _ _ _~ _ =_I __=
I 3ummary of Nuclide Activity . _ __ aae ~ r-3ample ID : 200005241002 Acquisition date * -
- )00 05:51:14 Total number of lines in spectrum 54 nber of unidentified lines 8
.. mber of lines tentatively identified by NID 46 85.19s,
- ~9 % _ 00000010-luclide Type
- ACTIVATION
-.--.. ~.
Wtd Mean Wtd Mean Uncorrected Decay Corr Decay Corr 2-Sigma Tuclide Hlife Decay uCi/CC uci/CC 2-Sigma Error %Error Flags TA-24 15.OOH 1.01 7.306E-10 7.398E-10 1.009E-10 13.63 IN-56 2.58H 1.08 1.666E-10 1.792E-10 0.608E-10 33.93 0O-58 70.80D 1.00 5.868E-10 5.869E-10 0.921E-10 15.70 1-187 23.83H 1.01 2.085E-10 2.102E-10 1.452E-10 69.11 Total Activity : 1.693E-09 1.716E-09 ruclide Type : FISSION Wtd Mean Wtd Mean Uncorrected Decay Corr Decay Corr 2-Sigma ruclide Hlife Decay uCi/CC uCi/CC 2-Sigma Error %Error Flags B-88 17.80M 1.87 8.231E-09 1.540E-08 0.113E-08 b ~ ~ 1 I-n s, 7.36 l . ar ULJ j.
- UV l.773E--09_ 0.13E-09z 7-f
'S-138 32.20M 1.42 1.105E-09 1.565E-09 0.165E-09 10.52 1_ E--8__
Total Activity : 1.111E-08 1.874E-0(8 uclide Type : IODINE Wtd Mean Wtd Mean Uncorrected Decay Corr Decay Corr 2-Sigma uclide Hlife Decay uCi/CC uCi/CC 2-Sigma Error %Error Flags
-131 8.04D 1.00 5.287E-09 5.293E-09 0.124E-09 2.35
-132 2.30H 1.08 1.734E-10 1.881E-10 -0.669E-10 35.54
-133 20.80H 1.01 7.973E-09 8.045E-09 0.158E-09 .1.96
-134 52.60M 1.24 1.728E-10 2.139E-10 0.726E-10 33.93
-135 6.61H 1.03 2.243E-09 2.308E-09 0.307E-09 13.31 Total Activity : 1.585E-08 1.605E-08 uclide Type : NATURAL Wtd Mean Wtd Mean Uncorrected Decay Corr Decay Corr 2-Sigma uclide Hlife Decay uCi/CC uci/CC 2-Sigma Error %Error Flags I-214 19.90M 1.75 8.628E-10 1.512E-09 0.205E-09 13.53 B-214 26.80M 1.52 6.015E-10 9.133E-10 2.673E-10 29.26 Total Activity : 1.464E-09 2.426E-09 Grand Total Activity : 3.011E-08 3. 893E-08 lags: "K" = Keyline not found "Ml = Manually accepted "E" = Manually edited "A"-L= Nuclide specific abn. limiE-
PROCEDURE DEVELOPMENT FORM II O I PROCEDURE ACTIVITY TRACKING NO.
ED 7635-12-(W) ISHEET OF (- q 17- I -, -) <
PROCEDURE NO. PROPOSED PROPOSED LINE OCANCELLTION DB-OP-03012 Rc REVISION NO. CHANGE NO. .
.OREVISION 0 INACTIVATION RESTRICTED EXPiRES SUPERSEDES: C-3 ZCHANGE 0 REACTIVATION (DATE/EVENT) 1_TEMPORARY APPROVAL PROCEDURE TITLE RADIOACTIVE GASEOUS BATCH RELEASE PROCEDURE CLASSIFICATION PAT/PCR NOS. CLOSED OUT 0 SR El QR El N-OR CHANGETO? E YES t PCR97-1365, PCR97-1657, PCR97-2898, PCR980163 NO I - %F- c1'Z-0~
-l7- ECONTINUED ACTIVITY
SUMMARY
/ PURPOSE DELETED REFERENCE TO EQUIPMENT LOG REWROTE CTMT PRESS RELEASE SECTION TO ALLOW RELEASES >24 HRS CORRECTED VARIOUS TYPOS ENHANCED CHEMISTRY ATTACHMENTS VARIOUS EDITORIAL ENHANCEMENTS f
- ca-cz-N -Ffi 1< g-e Lc S, I DOCUMENTATION MANAGEMENT
_______ ^alT13a I'aeftif El CONTINUED 7 ;W@ -ION2,tONC JRRE9 V M1&NI - cNUD DOCUMENT NO. /REVISION DOCUMENT TITLE PAT NO. ICHANGE REQUEST
__ _ _ ___ . __O._ . e 9 REQUIRED REQUESTED CHEM SYME RP E CONTINUED El CONTINUED PROEDURE 4REPAER DATE QUALIFIED REVVNW DATE COMPLETED AND ATTACHED)
YES N/A YES N/A YES N/A CO E E
VALIDATION CHECKLIST ij Q SAFETY REVIEW n REVISED CROSS REFERENCES LIST I. COMMITMENT VERIFICATION
SUMMARY
3 Q DOCUMENT REVIEW SHEETS PCRs Q EL SAFETY EVALUATION NO. _ P 5pM TM T DOC1 p TION 0 OTHER-.
FINAL QUALIFIED REVIEWER CONCURRENCE DATE/
MANAGEMENT SRO DATEAPPOVALAUTHR= DATE PI EJ~ DR 6 El SRB-El DIRECTOR - NA- 7] El PLANT MANAGER DATE E DIRECTOR-E&S DATE APPROVAL A! ORITY f DATE El DIRECTOR - NSS DATE SECTIO~N~7 RAININ Pj'[PQR TR AININ COMPLETE ALTERATION EFFECTIVE DATE PROCE RONSOR DATE E YES N/A I/ 2 iSyR 0
SECTION 1 - IDENTITY (CONTINUED).-
SECTION~~~~~~~~~
RCDERVE2_ ULr~ CNIUD SECTIOIONT2- QUALIFIE PRCEUECREVIET (CONTINUED)
~ ~ ..
- & . %4ttOC.k) LI.) Vt&
- 4*
Release Status: Post-Release Critical Path(s): Vegetables, Inhalation, Ground Plane Critical Individual: Child "Number:
Mate:
cu-c Source.
3tal Release Duration: 780 MIN obic Gas Total Body Dose Release Rate Limit: 3.38E+07 CFM oble Gas Skin Dose Release Rate Limit: I .25E+08 CFM dine and Particulates Release Rate Limit: 4.80E+08 CFM tal Curies Released: 4.02E-02 ELEASE CONCENTRATIONS (uCi/ml3 uclide Concentration Nuclide Concentration Nuclide Concentration R41 I .55E-06 C058 5.87E3-10 CS138 1.56E-09 3 2.30E-06 1131 :5.29E-09 1132 i.881E-10 33 8.04E-09 1134 2.14 E- I 1135 2.3 1E-09 R85M 5.13E-08 MN56 1.79E-10 NA24 7.40E- I 0 388 I .54E-08 W187 2.10E-10 XE133 4.03 E-06 E133M I.57E-07 XE135 1. 181E-06 UtalConcentration: 1.58E-06 gCi/ml (excluding H3 and Noble Gases)
Q: 3.01E-07
'Q: 4.80E-09 kDIQIODINE. TRITIUM. PARTICULATE DOSE COMMITMENT (mRemr)
This Release 3 -Day Ouarter Annua!
'ly 6.1IIE-07 2.41 E-04 4.20E-04 4.21E-04 6.52E-07 2.47E-04 4.30E-04 4.3 1E-04 dney 7.35E-07 2.50E-04 4.36E-04 4.37E-04 ne 3.39E-07 1.42E-05 2.47E-05 2.47F.-05 yroid 4.79E-05 2.94E-03 5.1 1E-03 5.12E-03 ng 5.1813-07 2.36E-04 4.12E-04 4.13E-04
-LLI 5.82E-07 2.37E-04 4.13E-04 4.14E-04
)BLE GAS X/Q: I.83E-06
)BLE GAS DOSE COMMITMENT (mRad)
This Release 31-Dav Ouarter Annual ta Air 3.15E-06 1.9 1E-03 3.32E-03 3.56E-03 mma Air 4.57E-06 5.50E-04 9.58E-04 1.02E-03
PROCEDURE DEVELOPMENT FORM PROCED~URE AC~iVTY TAGING NO-RHFF;:T I np I n _e ED 7635-11 -Z--- .--.C Y 7 o 7 7 SECTION 1 - IDENTITY PROCEDURE NO. PROPOSED PROPOSED 0 NEW 0 CANCELLATION D -6 REVISION NO. CHANGE NO. REVISION O INACTIVATION 0 RESTRICTED O
OLDNO.(ForNo.Change) 1C. C 2 CHANGE EOREACTIVATION EXPIRES_____________
0 TEMPORARY APPROVAL (DATE/EVENT)
PROCEDUR;~LE n AL n PROCEDURE CLASSIFICATION PAT/PCR NO,. CLOSED OUT ySR O OR O N-OR CHANGE TO? O YES,4NO 0 CONTINUED ACTIVITY
SUMMARY
/ PURPOSE I a fr -
4d# addX e4 x
_4 i
I ou -T N RGE rr G CONTINUED SECTION 2- CONCpRRENt) T Uf l C CONTINUED DOCUMENT NO./ REVISION DOCUMENT TIT4 PAT NO. / CHANGE REQUEST SECTION 3 - REVIEW ORGANIZATIONS DUE:
ell REQUIRED REQUESTED OECONTINUED OECONTINUED PROCED6E PREPARE~ DATE IQUAL IlD R VIEWVER tXDATE /
_10 k!
StCTION 4- - TTAlT MENTS
/S4tLY z/7 COMPLETED AND ATTACHED YES N/A YES N/A YES NJA O ' VAUDATION CHECKLIST 3l SAFETY REVIEW O S REVISED CROSS REFERENCES LIST
, 1 COMMITMENT VERIFICATION
SUMMARY
[3 DOCUMENT REVIEW SHEETS a > PCRs O A SAFETY EVALUATION OUE O OTHER FINAL OUALIFIED REVIEWER CONCURRENCE DATE SECTION 5 -TEMPORARY APPROVAL MANAGEMENT SRO DATE APPROVAL AUTHORITY DATE f_\ SECTION 6- CONCURRENCE I FINAL APPROVAL P OEDQtISPE t SRB DATE n DIRECTOR - NA O PLANT MANAGER EDA DATE C)DIRECTOR - E&S DATE APPROVAL AUTHORgy DATE I _ _ _ c___ (Z.}1 7 SECTION 7 -TRAINING I PROCEDURE EFFECTIVITY TRAINING COMPLETE ALERATION EFFECTIVE DATE PROCEDURE SPONSOR lDATE OYES R3N/A l Is I 7il,7
DOCUMENT NO. / REVISION DOCUMENT TITLE PAT NO. / CHANGE REQUEST REQUIRED REQUESTED 7- -
- L' JtX.ttJU D/' A fl KtLtA5t Release Status: Pre-Release Critical Path(s): Vegetables, Inhalation, Ground Plane Critical Individual: Child nit Number: ^
'Date:
Source.
ble Gas Total Body Dose Release Rate Limit: 3.38E+u / CFM ble Gas Skin Dose Release Rate Limit: 1.25E+08 CFM ine and Particulates Release Rate Limit: 4.80E+08 CFM al Curies Released: 1.16E-01 LEASE CONCENTRATIONS (uCi/ml)
- lide Concentration Nuclide Concentration Nuclide Concentration 2.30E-06 AR41 1.55E-06 KR85M 5.13E-08 133 4.03E-06 XE133M 1.57E-07 XE135 1.18E-06
.24 7.40E-10 MN56 1.79E-10 C058 5.87E-10 87 2.10E-10 RB88 1.54E-08 CS138 1.56E-09 1 5.29E-09 1132 1.88E-10 1133 8.04E-09 4 2.14E-10 1135 2.31E-09 al Concentration: 1.58E-06 gCi/ml (excluding H3 and Noble Gases) 3.01 E-07 2:
2:4.80E-09 DIOODINE. TRITIUM. -PARTICULATE DOSE COMMITMENT (mRem)
This Release 31-Dav Ouarter Annual al Body 1.76E-06 2.42E-04 4.21E-04 4.22E-04 1.88E-06 2.48E-04 4.31E-04 4.32E-04 2.11E-06 2.51E-04 4.37E-04 4.38E-04 ke 9.76E-07 1.45E-05 2.53E-05 2.53E-05 roid 1.38E-04 2.99E-03 5.20E-03 5.21E-03 g 1.49E-06 2.37E-04 4.13E-04 4.14E-04 LLI 1.67E-06 2.38E-04 4.14E-04 4.15E-04 BLE GAS X/Q: 1.83E-06 BLE GAS DOSE COMMITMENT (mRad)
This Release 31-Day Ouarter Annual i Air 9.05E-06 1.91E-03 3.32E-03 3.57E-03 nima Air 1.31 E-05 5.55E-04 9.67E-04 1.03E-03
PROCEDURE DEVELOPMENT FORM ED 7635-11
- _ _" SHEET OF J PRO A TRA1 NG NO-.
.2v-%o 1 IVN 1 - IlJtN I1 r PROCEDUREN tG.- PROPOSED PROPOSED O NEW 0 CANCELLATION I REISIONN.CAG NORESTRICTED TX-o C~ aREVISIONNO
/ CNGENQ1 3REVISION R30 0 INACTIVATION OLD NO. (For No Change) 1 j KCHANGE o REACTIVATION EXPIRES 1OTEMPORARY APPROVAL (DATE/EVEN-p PROCEDURE TITLE PROCEDURE CLASSIFICATION PAT/PCR NOS. CLOSED OUT pc.R q L, I XSR0 OR O N-OR CHANGE TO S(NO I TA q f, .- I -. 0 CONTINUED ACTIVITY
SUMMARY
/ PURPOSE i17'V '
TCx( - (vaj DOCUMENTATION b T 0AAGENUt CONTINUED SECTION 2 - CON URREI C 1 3 CONTINUED DOCUMENT NO./ REVISION DOCUMEN TI E PAT NO. / CHANGE REQUEST SECTION 3 - REVIEW ORGANIZATIONS DUE:
REQUIRED Bif REQUESTED 5Ys /lit PROCEDURE PREPAfER l 0 CONTINUED 0 CONTINUED DAEA SECTION 4 - ATTACHMENTS YES N1A YES NtA COMPLETED AND ATTACHED Y- NI-
,>3- 03 VAULDATION CHECKST A 0 SAFETY REVIEW 0COMMITME:NT VERIFICATION
SUMMARY
'.D DOCUMENT REVIEW SHEETS 0 '.20 psig. The leakage rate per penetration shall not exceed 0.15 L . (Technical Specification 4 .G.1.2.g).
2.2.3 The special test, as defined in Surveillance Requirement 4 .6.1.2.g, shall be performed for the Containment Purge Supply and Exhaust Isolation valves when the Plant has been in any combination of MODES 3, 4, 5, or 6 for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided that the tests required by Surveillance Requirements 4 . 6 .1.2.g has not been performed in the previous six months. (Technical Specification 4.6.1.2.h)
I- 7-1
,ummary of Nuclide Activity LwNW 10P - C
,ample ID : 200005241002 Acquisition date - -- - )00 05:51:14 Total number of lines in spectrum 54 nber of unidentified lines 8 mm _, 9% X,
...mber of lines tentatively identified by NID 46 85.;o w _
luclide Type : ACTIVATION -I Wtd Mean Wtd Mean Uncorrected Decay Corr Decay Corr 2-Sigma Juclide Hlife Decay uCi/CC uCi/CC 2-Sigma Error %Error Flags TA-24 15.00H 1.01 7.306E-10 7.398E-10 1.009E-10 13.63 IN-56 2. 58H 1.08 1.666E-10 1.792E-10 0.608E-10 33.93
'O-58 70. 80D 1.00 5.868E-10 5.869E-10 0.921E-10 15.70
!-187 23. 83H 1.01 2.085E-10 2.102E-10 1.452E-10 69.11 Total Activity : 1.693E-09 1.716E-09
[uclide Type : FISSION Wtd Mean Wtd Mean Uncorrected E)ecay Corr Decay Corr 2-Sigma ruclide Hli fe Decay uCi/CC uCi/CC 2-Sigma Error %Error Flags B-88 17. 8OM 1.87 8.231E-09 1.540E-08 t ~ ~ 1U71'u r -7Aa 12~ 0.113E-08 7.36 32u. 0 M 1.7-73E 0 O.133E-09 7 7g -
'S-138 32.20M 1.42 1.105E-09 1.565E-09 0.165E-09 10.52 Total Activi..ty : l.lliE-08 1.874E-0-8 uclide Type : IODINE Wtd Mean Wtd Mean Uncorrected Decay Corr Decay Corr 2-Sigma uclide Hlife Decay uCi/CC uCi/CC 2-Sigma Error %Error Flags
-131 8.04D 1.00 5.287E-09 5.293E-09 0.124E-09 2.35
-132 2.30H 1.08 1.734E-10 1.881E-10 0.669E-10 35.54
-133 20.80H 1.01 7.973E-09 8.045E-09 0.158E-09 .1.96
-134 52.60M 1.24 1.728E-10 2.139E-10 0.726E-10 33.93
-135 6.61H 1.03 2.243E-09 2.308E-09 0.307E-09 13.31 Total Activity : 1.585E-08 1.605E-08 uclide Type : NATURAL Wtd Mean Wtd Mean Uncorrected Decay Corr Decay Corr 2-Sigma uclide Hlife Decay uCi/CC uCi/CC 2-Sigma Error *Error Flags I-214 19.90M 1.75 8.628E-10 1.512E-09 0.205E-09 13.53 B-214 26.80M 1.52 6.01SE-10 9.133E-10 2.673E-10 29.26 Total Activity : 1.464E-09 2.426E-09 Grand Total Activity : 3. 011E-08 3. 893E-08 lags: "K" = Keyline not found 'M" = Manually accepted "El = Manually edited "A"-= =-Nuclide specific abn. limit:
11 DB-OP-03012 Revision 02 2.2.4 For WGDT releases:
- WHEN a tank pressure is approximately 140 PSIG, THEN the tank should be isolated AND a release permit should be started.
- Operations should keep the permit until the tank is ready for release.
- WHEN a second WGDT gets to 110 psi, THEN the release permit should be sent to Chemistry for sample AND release approval of the first decay tank.
- Recommende-Jd decay time for a WGDT is at least thirty (30) days.
IF the tank activity is lower than the level calculated for 1% Failed Fuel after 30 days of decay, THEN a shorter decay period may be justified.
o W-hen possible, the first WGDT to be isolated should be released prior to a second WGDT reaching a pressure of approximately 140 PSIG.
This will avoid possible mixing of oxygen and hydrogen into the remaining WGDT.
o It may be possible to reduce the WGDT fill rate by limiting gas generation until the first WGDT is released and/or investigating why WGDT is increasing in pressure.
3.0 PREREQUISITES NOTE 3.1 All references in the body of the procedure to Item numbers are for locations on, Attachment 1, Radioactive Gaseous Batch Release Permit. l 3.1 Administrative INITIALS QjA 3.1.1 Initiate the release by placing the name of the on-shift Shift Supervisor and completing Item 4.a.
LD<3 3.1.2 Indicate the type of release to be performed by checking the appropriate box in Item 1.
12 DB-OP-03012 Revision 02 3.1.3 Designate the operational sections to be performed by placing an "X" in front of the listed sections-below.
X-1S5 Waste Gas Decay Tank (Sections 4.1 through 4.3)
Containment Pressure Reduction (Sections 4.4 through 4.6)
Containment Purge (Sections 4.7 through 4.9)
Containment Integrated Leak Rate Test (ILRT) Pressure Reduction (Section 4.10)
Gas Space Releases from Tanks to Atmospheric Pressure for Maintenance Work (Section 4.11). For example, depressurizing CFT or SG etc.
5 3.1.4 Remove the operational sections for any tank/vessel NOT being released from this procedure package.
Prerequisites completed by Date O V-
ALV 12,UA,C.UU flAk 1.41 Kt2,Ld2,A,t, Release Status: Post-Release Critical Path(s): Vegetables, Inhalation, Ground Plane Critical Individual: Child N'umber:
)ate:
- s..e Source.
i(al Release Duration: 780 MIN blc Gas Total Body Dose Release Rate Limit: 3.38E+07 CFM
>ble Gas Skin Dose Release Rate Limit: 1.25E+08 CFM line and Particulates Release Rate Limit: 4.80E+08 CFM atal Curies Released: 4.02E-02
-LEASE CONCENTRATIONS (tCi/ml)
Aclide Concentration Nuclide Concentration Nuclide Concentration R4l I.55E-06 C058 5.87E-10 CS138 1.56E-09 2.30E-06 1131 :5.29E-09 1132 1.88E-10 33 8.04E-09 1134 2.14E-10 1135 2.31E-09 t85M 5.13E-08 MN56 1.79E-10 NA24 7.40E-10 388 1.54E-08 W187 2.10E-10 XE133 4.03E-06 3133M 1.57E-07 XE135 1.18E-06 tal Concentration: 1.58E-06 )+/-Ci/ml (excluding H3 and Noble Gases)
Q: 3.01 E-07 Q: 4.80E-09
.DIOIODINE. TRITIUM. PARTICULATE DOSE COMMITMENT (mRem)
This Release 3 1-Day Ouarter Annua!
dy 6.1 IE-07 2.4 1E-04 4.20E-04 4.21 E-04 6.52E-07 2.47E-04 4.30E-04 4.3 1E-04 Jney 7.35E-07 2.50E-04 4.36E-04 4.37E-04 ne 3.39E-07 1.42E-05 2.47E-05 2.47F-05 yroid 4.79E-05 2.94E-03 5.1 IE-03 5.12E-03 ng 5.18E-07 2.36E-04 4.12E-04 4.13E-04
- LLI 5.82E-07 2.37E-04 4.13E-04 4.14E-04
)BLE GAS X/Q: I.83E-06
)BLE GAS DOSE COMMITMENT (mRad)
This Release 31-Day Ouarter Annual LaAir 3.15E-06 1.91E-03 3.32E-03 3.56E-03 mma Air 4.57E-06 5.50E-04 9.58E-04 1.02E-03
i3 DB-OP-03012 Revision 02 4.0 PROCEDURE 4.1 Preparing a Waste Gas Decay Tank (WGDT) for Release INITIALS NOTE 4.1.1 Normally two Waste Gas Decay Tanks (WGDT's) will be in service with one lined up to the "SURGE TANK" position and one lined up to the "NITROGEN" position. In some instances if two WGDT's are isolated for release the remaining in service WGDT would be lined up in the "BOTH" position.
4.1.1 Perform the following:
`' 3 a. Denote the WGDT to be released below:
Decay Tank to be released # _
a R b. Circle the WGDT's that will be left in service and the controller position below:
WGDT Controller Controller Position (Circle WGDT's (Circle the controller in service) position)
HS 1823A, WST GAS TSAURGE
/TANITROGEN/BOTH DECAY TANK 1 IN SELECT
- 2 HS 1825A, WST GAS SURGE TANK/NITROGEN/BOTH DECAY TK 2 IN SELECT HS 1827A, WST GAS SURGE TANK~EN BOTH DECAY TK 3 IN SELECT 4.1.2 IF WGDT 1 is to be isolated and released, THEEN perform the following:
DVIa. Place HS 1823A, WST GAS DECAY TK 1 IN SELECT, at the RWCP in the OFF position.
(Continued)
I
1A
-s DB-OP-03012 Revision 02 C-3 4.1.2.d (Continued)
) b. Verify WG 1835, WASTE GAS DECAY TANK 1-1 TO CLEAN WASTE RECEIVER TANKS CONTROL VALVE is closed.
- c. Verify WG 1836, WASTE GAS DECAY TANK 1-1 TO STATION VENT CONTROL VALVE is closed.
- d. Place an Information Tag stating "This WGDT is isolated and will be released" on the following controllers at the RWCP. Refer to DB-OP-00010, Operational Information Tags.
X HS 1823A, WST GAS DECAY TK 1 IN SELECT.
a HIS 1835, DECAY TK 1 TO CLN WST REC TK.
_ o HIS 1836, DECAY TK 1 TO A FLT VLV.
4.1.3 IF WGDT 2 is to be isolated and released, THEN perform the following:
Q a. Place HS 1825A, WST GAS DECAY TK 2 IN SELECT, at the RWCP in the OFF position.
- b. Verify WG 1837, WASTE GAS DECAY TANK 1-2 TO CLEAN WASTE RECEIVER TANKS CONTROL VALVE is closed.
- c. Verify WG 1838, WASTE GAS DECAY TANK 1-2 TO STATION VENT CONTROL VALVE is closed.
- d. Place an Information Tag stating "This WGDT is isolated and will be released" on the following controllers at the RWCP. Refer to DB-OP-00010, Operational Information Tags.
e HS 1825A, WST GAS DECAY TK 2 IN SELECT.
o HIS 1837, DECAY TK 2 TO CLN WST REC TK.
_
- HIS 1838, DECAY TK 2 TO A FLT VLV.
4.1.4 IF WGDT 3 is to be isolated and released, THEN perform the following:
- a. Place HS 1827A, WST GAS DECAY TK 3 IN SELECT, at the RWCP in the OFF position.
(Continued)
-~ '.AA '.JfOL2AU~) LJC A -~. X~tt.~
Release Status: Pre-Release Critical Path(s): Vegetables, Inhalation, Ground Plane Critical Individual: Child
-mit Number: ^'
Date:
.Sourcc.
ble Gas Total Body Dose Release Rate Limit: 3.38E+U / CFM ble Gas Skin Dose Release Rate Limit: 1.25E+08 CFM ine and Particulates Release Rate Limit: 4.80E+08 CFM alCuries Released: 1.16E-01 LEASE CONCENTRATIONS (RCi/ml) clide Concentration Nuclide Concentration Nuclide Concentration 2.30E-06 AR41 1.55E-06 KR85M 5.13E-08 133 4.03E-06 XE133M 1.57E-07 XE135 1.18E-06
.24 7.40E-10 MN56 1.79E-10 C058 5.87E-10 87 2.1OE-10 RB88 1.54E-08 CS138 1.56E-09 1 5.29E-09 1132 1.88E-10 1133 8.04E-09 4 2.14E-I0 1135 2.31E-09 al Concentration: 1.58E-06 1iCi/ml (excluding H3 and Noble Gases) 2: 3.01E-07 4.80E-09 2:
DIOIODINE, TRITIUM. PARTICULATE DOSE COMMITMENT (mRem)
This Release 31-Day Ouarter Annual al Body 1.76E-06 2.42E-04 4.21E-04 4.22E-04 1.88E-06 2.48E-04 4.31E-04 4.32E-04 2.11 E-06 2.51 E-04 4.37E-04 4.38E-04 e 9.76E-07 1.45E-05 2.53E-05 2.53E-05 roid 1.38E-04 2.99E-03 5.20E-03 5.21E-03 g 1.49E-06 2.37E-04 4.13E-04 4.14E-04
_I 1.67E-06 2.38E-04 4.14E-04 4.15E-04 BLE GAS X/Q: 1.83E-06 BLE GAS DOSE COMMITMENT (mRad)
This Release 31-Day Ouarter Annual iAir 9.05E-06 1.91 E-03 3.32E-03 3.57E-03 ima Air 1.31 E-05 5.55E-04 9.67E-04 1.03E-03
15 DB-OP-03012 Revision 02 4.1.4.d (Continued)
- b. Verify WG 1839, WASTE GAS DECAY TANK 1-3 TO CLEAN WASTE RECEIVER TANKS CONTROL VALVE is closed.
___ c. Verify WG 1840, WASTE GAS DECAY TANK 1-3 TO STATION VENT CONTROL VALVE is closed.
- d. Place an Information Tag stating "This WGDT is isolated and will be released" on the following controllers at the RWCP. Refer to DB-OP-OOO10, Operational Information Tags.
p o HS 1827A, WST GAS DECAY TK 3 IN SELECT.
o HIS 1839, DECAY TK 3 TO A CLN WST REC TK.
o HIS 1840, DECAY TK 3 TO A FLT VLV.
4 4.1.5 Complete Item 4.b.
NOTE 4.1.6 This permit shall be maintained in the Control Room until the WGDT is ready for release. l Recommended decay time is at least thirty days. l 4.1. 6 Return this permit to the Control Room.
103 DB-OP-03012 Revision 02 ATTACHMENT 5: ESTIMATED RELEASE RATE (WGDT pressure + 14.7 psig)
WGDT volume = x 1013 ft3 14.7 psi volume A - volume at beginning of period volume B - volume at end of period If monitoring flowrate, THEN document the date, time and release rate only.
VOLUME VOLUME VOLUME ELAPSED A B CHANGE TIME RELEASE RATE DATE TIME ft3 ft3 ft3 min ft3 lmin.
- - + + +/- *1-I I I-
-+ 4 + + 1-4 4 4 4 4- +
4- 4- *I- + 1- 1-Attachment 5 Page 1 of 1
... M. - A,..
16 DB-OP-03012 Revision 02 NOTE 4.1.7 The pressure of the tank is documented on the permit prior to sampling for release of the tank. l The tank pressure shall be provided to Chemistry l when requesting the sample to be collected. l 4.1.7 Request a sample of the isolated WGDT to estimate the decay time for proposed release scheduling AND oxygen/hydrogen concentrations.
Z o Request RP Management to review tank curie content to determine if decay time will be greater than 30 days.
/C'/cz/Z Piop sed date of release A S o IF isolated WGDT sample results indicate a 4%
hydrogen concentration with greater than 2%
oxygen concentration, THEN the Shift Supervisor should evaluate if actions to purge the WGDT with N2 prior to being released are necessary.
REFER TO DB-OP-06131, Gaseous Radioactive Waste System.
4.1.8 WHEN the isolated WGDT is ready to be sampled for release, THEN perform the following:
A a. Prepare DNO tags for the WGDT to be released in accordance with Attachment 2, DNO Tagging List for Gaseous Waste Release. Refer to DB-OP-00015, Safety Tagging.
- b. Hang the DNO tags on the WGDT to be released.
Refer to DB-OP-00015, Safety Tagging.
- c. Complete Item 4.c.
4.1.9 Record the pressure for the WGDT to be released in Item 3.a.
-. j 171:--
102 DB-OP-03012 Revision 02 ATTACHMENT 4: RE READINGS Circle Release Radiation Element used.
RE 4597AA RE 1822A RE 4597BA RE 5052 RE 1822B DATE TIME CPM CPM I 1 4- 4 1-4-I I 4- 4- +
. I v 4- 4- +
-I -I i 4- 4-I I i 4- 4-i I4 I I Attachment 4 Page 1 of 1
17 DB-OP-03012 Revision 02 C-4 P-3 4.1.10 IF the release will be through the absolute and charcoal filter THEN verify Attachments 1 & 2 of DB-OP-06131, Gaseous Radioactive Waste System, are current.
Ž 4.1.11 IF the release willibe through the absolute and charcoal filters, THEN check "YES" in Item 3.c.
OTHERWISE check "NO" in Item 3.c.
4.1.12 IF "NO" is checked in item 3.c, THEN bypass both filters:
- a. To bypass the absolute filter perform the following:
a Verify WG 48, WASTE GAS ABSOLUTE FILTER BYPASS VALVE, is open.
o Verify WG 45, WASTE GAS ABSOLUTE FILTER OUTLET ISOLATION VALVE, is closed.
_
- Verify WG 8, WASTE GAS ABSOLUTE FILTER 1 INLET ISOLATION VALVE, is closed.
- b. To bypass the charcoal filter perform the following:
X c Verify WG 49, WASTE GAS CHARCOAL FILTER BYPASS VALVE, is open.
A Verify WG 46, WASTE GAS CHARCOAL FILTER INLET ISOLATION VALVE, is closed.
_ c Verify WG 47, WASTE GAS CHARCOAL FILTER OUTLET ISOLATION VALVE, is closed.
.. , ,0 To
101 DB-bP-03012 Revision 02 ATTACHMENT 3: GASEOUS RELEASE PERMIT LOG ANALYST RELEASE NO. DATE RELEASE TYPE SIGNATURE
- 2- / o/,/2/a'C7 A
-3~
____________ _ aS__
I I SAMPLE __
I __
i I i I-
. i T ti I I i I
.1I
_____________________ _____________ _________________________________________________ t_____
Attachment 3 Page 1 of 1
n 18 DB-OP-03012 Revision 02 C-4 NOTE 4.1.13 The pre-sample RE operability check conducted by the Shift Supervisor or Assistant Shift Supervisor may be performed by verifying RE status from the Status Board, Turnover Checklist or Unit Log. This check is performed to determine if two samples are required (ODCM Table 3-1). If desired, then verification that the associated surveillance tests are current may also be utilized to hel determi ne operability. It is not necessary to verify surveillance tests at this time. The tests should be re-verified prior to approving the release to ensure RE operability.
i 4.1.13 Perform a pre-sample RE operability check on the following radiation monitors.
CIRCLE STATUS OF RE 4D1S RE 1822A OPERABLE ERAB RE 1822B OPERABL RAB C RE 4598AA INOPERABLE 0 RE 4598BA OPRBEINOPERABLE
_3 4. 1.14 IF the pre-sample RE operability check determines that at least one Station Vent Radiation Monitor (RE 4598AA or RE 4598BA)
AND at least one of the Waste Gas Treatment System Radiation Monitors (RE 1822A or RE 1822B) are operable, THEN complete Item 4.d. by circling "SAT" AND record any inoperable RE in Item 5.a.
OTHERWISE complete Item 4.d. by circling "UNSAT" AND record the required ODCM action statements in Item 5.a.
j_4- 4.1.15 Deliver this procedure to Chemistry and inform them of any required ODCM action statements recorded in Item 5.a.
Section 4.1 completed by q ISn Date
100 DB-OP-03012 Revision 02 ATTACHMENT 2: DNO TAGGING LIST FOR RADIOACTIVE GASEOUS WASTE RELEASE NOTE ATTACHMENT 2 Valves shall be tagged in the CLOSED position. l
_ _ _ _ _ _ _ _ _ _ __ _ _ I
_ 0,
_ 1. Waste Gas Decay Tank 1:
o WG 34, WASTE GAS DECAY TANK 1-1 INLET ISOLATION VALVE o WG 113, WASTE GAS DECAY TANK 1-2 TO STATION VENT ISOLATION o WG 114, WASTE GAS DECAY TANK 1-3 TO STATION VENT ISOLATION.
o WG 115, WASTE GAS DECAY TANK 1-1 TO CLEAN WASTE RECEIVER TANKS ISOLATION
@fL 2. Waste Gas Decay Tank 2:
o WG 35, WASTE GAS DECAY TANK 1-2 INLET ISOLATION VALVE o WG 112, WASTE GAS DECAY TANK 1-1 TO STATION VENT ISOLATION o WG 114, WASTE GAS DECAY TANK 1-3 TO STATION VENT ISOLATION o WG 116, WASTE GAS DECAY TANK 1-2 TO CLEAN WASTE RECEIVER TANKS ISOLATION
/ .. 3. Waste Gas Decay Tank 3:
o WG 36, WASTE GAS DECAY TANK 1-3 INLET ISOLATION VALVE o WG 112, WASTE GAS DECAY TANK 1-1 TO STATION VENT ISOLATION o WG 113, WASTE GAS DECAY TANK 1-2 TO STATION VENT ISOLATION o WG 117, WASTE GAS DECAY TANK 1-3 TO CLEAN WASTE RECEIVER TANKS ISOLATION Attachment 2 Page 1 of 1 I
19 DB-OP-03012 Revision 02 C-4 4.2 Approving a Waste Gas Decay Tank (WGDT) Release INITIALS 4.2.1 Verify the permit has been approved for release as designated by completion of Item 4.h.
NOTE 4.2.2 a The Shift Supervisor or Assistant Shift Supervisor shall verify instrument l operability based on satisfactory completion l of the latest surveillance test on the instruments, with the instrument being in l service and declared operable. All ODCM l action statements shall be recorded in Item 5.a.
- Entering "6.8.4.d***" in the Surveillance l Requirement Section of the Routine Test l Selection Inquiry on DBMMS gives a convenient l listing of release STs.
II 4.2.2 Verify the following surveillance requirements are current.
e DB-MI-03413, RMS Channel Calibration, for RE 4598AA and/or RE 4598BA
- DB-MI-03401, RMS Channel Calibration, for RE 1822A
- DB-MI-03404, RMS Channel Calibration for RE 1822B
- DB-MI-03428, Channel Calibration of 72C-ISF 1821, Waste Gas System Outlet Flow 1.0",
for FT 1821 a DB-MI-03430, Channel Calibration of 72C-ISF 1821A, Waste Gas System Outlet Flow 3/4", for FT 1821A
- DB-MI-03442, Channel Calibration of 32C-ISF 5090, Station Vent Flow, for FT 5090
- DB-MI-03444, Channel Calibration of 32C-ISF 5090A, Station Vent Flow, for FT 5090A (Continued)
I
99 DB-OP-03012 Revision 02 TA99-1770 ATTACHMENT 1: RADIOACTIVE GASEOUS BATCH RELEASE PERMIT (Continued) 117. TOTAL CURIES IN THIS RELEASE*
Total Curies curies 118. DOSE COMMITMENT FOR THIS RELEASE*
Gamma Air Dose mRad Beta Air Dose mRad Iodines & Particulates Dose mRem 119.
Intentionally Left Blank 120. TO DATE QUARTERLY DOSE ANNUAL DOSE DOSE COMMITMENT*
Estimated Estimated Noble Gas Gamma __mRad mRad Noble Gas Beta mRad mRad lodines and Particulates _ mRem mRem 121. 31 DAY PRPTnrO DOSI COMMITMENT
- a. This Item is NOT APPLICABLE as the release was processed through either the Waste Gas Treatment or Ventilation Exhaust Treatment Systems.
_ -/-6-t Signature Date Estimated Actual Estimated Actual
- b. Noble Gas Gamma __ mRad __ mRad Iodine and Particles mRem mRem Noble Gas Beta mRad mRad
- These items may be marked "N/A" if RETSCode printouts are available.
I Attachment 1 Page 4 of 4
20 DB-OP-03012 Revision 02 4.2.2 (Continued)
- DB-OP-03007, Miscellaneous Instrument Daily Checks o DB-SC-03200, Shift Channel Check of the Radiation Monitoring System
- DB-SC-03216, Quarterly Functional Test of RE-4598AA Station Vent Normal Range Radiation Monitor
- DB-SC-03218, Quarterly Functional Test of RE 4598BA Station Vent Normal Range Radiation Monitor
- DB-SC-03225 and/or DB-SC-03226, Quarterly Functional Test of RE 1822A (RE 1822B), Waste Gas System Discharge to Station Vent Radiation Monitor
- DB-SP-03419, Waste Gas System Effluent Flow Transmitter Quarterly Channel Functional Test, for FT 1821 and/or FT 1821A o DB-CH-03008, Station Vent Releases, Weekly Radiological Monitoring, Sampling and Analysis 4.2.3 IF the release instrument operability checks are satisfactory, THEN complete Item 4.i by circling "SAT".
OTHERWISE complete Item 4.i by circling "UNSAT",
AND verify the required ODCM action statement is recorded in Item 5.a.
4.2.4 IF RE 1822A and/or RE 1822B are OPERABLE, THEN perform the following monitor source check(s) for the OPERABLE monitor(s):
- a. Depress and hold the ALARM ACK button.
- b. Depress the CHECK SOURCE (C.S.) button.
- c. Check for an upscale meter response.
- d. Release the C.S. button.
- e. Wait for the meter to indicate below the WARN setpoint.
- f. Release the ALARM ACK button.
98 DB-OP-03012 Revision 02 TA99-1770 ATTACHMENT 1: RADIOACTIVE GASEOUS BATCH RELEASE PERMIT (Continued) l11. GASEOUS RELEASE* RATE LIMITS I I Noble Gas Total Body Dose Release Rate Limit SCFM 1 Noble Gas Skin Dose Release Rate Limit SCFM 2 Iodine & Particulates Release Rate Limit SCFM 3
- 12. 13. 14. 15. j 16.
ESTIMATED l ACTUAL I ERROR l CURIES j CURIES NUCLIDE J uCi/ml ONE SIGMA l RELEASED l RELEASED_
H-3 I _ I _ I _ _
I I I Kr-83M j _ j _ _ I _
Kr-85M I _ I _ I _ _
Kr-85 [ _ [ _ [ _ [
Kr-87 _ I _ I _ I __
Kr-88 £ _ I _ I_ _
Kr-89 I _ I _ I _ _
Xe-131M I _ +/- _ I _ J Xe-133M j _ _ _ _ _ _
Xe-133 J _ _ I _ I _
Xe-135 J _ I _ I _ I Xe-137 I _ 1 _ _ 1 l Xe-138 I _ I _ I _ _
Xe-135M I _ I _ I _ I I I I
_ _ _ _ I _ _ I _ _ I _ _ I _ 1 _ _ _ _ 1 _ __
I I I I
_ _ _ _ I _ _ I _ _ I _ _ I _ _ _ _ _ I _ __
I I I I I I
_ _ _ _ I _ _ I _ _ _ I _ _ I _ _ _ _ _ _ _
I I I I I I
_ _ _ _ _ I _ _ I _ _ _ _ _ _ _ _ _ _
- Items 13 through 16 are not required to be completed if computer printout of analysis is available.
- These items may be marked N/A if RETSCode printouts are available.
I Attachment 1 Page 3 of 4
21 DB-OP-03012 Revision 02 4.2.5 IF the monitor source check was satisfactory for each operable RE, THEN complete Item 4.j.
OTHERWISE N/A Item 4.j AND notify the Shift Supervisor.
4.2.6 Circle the OPERABLE monitors in Item 5.b which will be used for the release.
4.2.7 Return the release permit to the Control Room.
4.2.8 IF the tenth value of the maximum release rate as recorded on Item 9.b is less than 1 SCFM, THEN do NOT perform this release AND notify the Radiation Protection Management.
4.2.9 IF the instrument checks were satisfactory, as indicated by the completion of Items 4.d, 4.i and 4.j on the permit OR the required ODCM action statements are recorded in Item 5.a AND have or will be performed as required, THEN Item 4.k may be signed by the Shift Supervisor to approve the release valve lineup.
4.2.10 IF the permit is approved, THEN return the permit to an assigned operator to perform the release.
Section 4.2 completed by Date
97 DB-OP-03012 Revision 02 C-3 ATTACHMENT 1: RADIOACTIVE GASEOUS BATCH RELEASE PERMTT (Con tinu ed)
- i. Release instrumention operability check performed SAT/UNSAT
- j. Monitor source check performed by
- k. RELEASE VALVE LINEUP APPROVED by SHIFT SUPERVISOR l
- 1. RELEASE APPROVED by SHIFT SUPERVISOR _ _ _ __
- m. RE Channel Check Performed I
- n. Ft Channel Check Performed I
- a. Remarks: Dc Cb C
4Q 7be 3 I c41tc> ,-
+ Q ,3I+Qe-s OurpiQR l r,.O t1 ZfI - ( CtAC,&ll et '<
I~~~~3 < t _c.... _ WWF .1 )v~MW8\Kw
,r1 4 /CQ +/-_Lt o~ ~ Ioe{zt5<t e'c h -Y It '_
RR L822U Rused:0 E A E 8 CF lLS RE 1822A RE 1822B3 RE 5052 RE 4598AA RE 4598%* FIC1821 FIC 1821A ILRT
- 6. RELEASE STARTED ___
date time pressure or psid l 7. RELEASE STOPPED _
date time pressure or psid
- 8. RELEASE TIME MINUTES Delta P psig or psid
- 9. WASTE GAS DECAY TANK
- a. Maximum Release Rate /r__ SCFM
- b. Tenth Value of Maximum Release Rate IoS SCFM l10.CONTAINMENT RELEASES I
- a. I Maximum Containment Purge rate iL4 > SCFM
- b. Maximum Purge Time A, :y hours Attachment 1 Page 2 of 4
22 DB-OP-03012 Revision 02 4.3 Performing a Waste Gas Decay Tank (WGDT) Release INITIALS 4.3.1 Verify that no other radioactive gaseous batch release is in progress.
4.3.2 Inform the Chemistry Laboratory a radioactive gaseous batch release is going to be initiated and that sampling of the Station Ventilation System should not be permitted for other than required action items during the release.
NOTE 4.3.3 In the event both RE's 1822A and 1822B are inoperable the ODCM Table 3-1 requires that two independent verifications of the discharge valving is performed. However the procedure already has independent verifications on valves in the discharge flowpath so no further action is required.
4.3.3 IF RE 1822A AND RE 1822B are INOPERABLE, THEN perform the following:
0 Verify required ODCM actions are recorded in Item 5.a.
o Mark Step 4.3.4 N/A.
96 DB-OP-03012 Revision 02 C-3 ATTACHMENT 1: RADIOACTIVE GASEOUS BATCH RELEASE PERMIT DAVIS-BESSE NUCLEAR POWER STATION RELEASE I RADIOACTIVE GASEOUS BATCH RELEASE PERMIT 2. NUMBER 6
- 1. Type of Release WGDT #1 WGDT #2 .X WGDT #3 _ CONTAINMENT PURGE _
l CONTAINMENT PRESSURE RELEASE ILRT OTHER _
IF OTHER IS CHECKED PLEASE SPECIFY TANK NAME _
- 3. Release Statistics
Pressure S psig For CTMT Pressure Reductions Releases:
l CTMT to Annulus diff. pressure inches H 0
- b. Volume Cu. ft.
- c. Release will be processed through the Gaseous Radwaste or Ventilation I Exhaust Treatment Systems Yes No l
- 4. Signature Date/Time
- a. Release initiated by ] 7eno
- b. WGDT isolated by l / -C i/
C. Tank DNO tags hung l ?y) GYo }._ I4/ y I l d. Pre-sample RE l operability chek I r l .
performed SAT/fltSA) I hDj5/n, j5 ev /lv
- e. Release sampled by _______ __ ___4_'_
_ 0
- f. Release analyzed by j 44 pi/4&41 c
- g. Dose commitment calc. l I performed by l?I i1 I/O/.2fci> t710
- h. Release approved by RP Supervisor [ J1 ,n t k/t, lO/C/o-S (7c~9 1
/ /
Attachment 1 Page 1 of 4
23 DB-OP-03012 Revision 02 NOTE 4.3.4 The preferred method is to have both RE 1822A AND RE 1822B in service during the release.
NOTE 4.3.4 through 4.3.6 The intent of these steps are to have an operator line up the RE, then to have a second operator independently verify the lineup where necessary.
4.3.4 Lineup the operable radiation monitors as follows:
- a. IF RE 1822A is OPERABLE, THEN perform the following:
- 1. Verify WG 140, WASTE GAS TO STATION VENT RADIATION ELEMENT ISOLATION, is open.
(IV)
- 2. Verify WG 139, WASTE GAS TO STATION VENT RADIATION ELEMENT ISOLATION, is open.
(IV)
- 3. Verify WG 138, WASTE GAS TO STATION VENT RADIATION ELEMENT ISOLATION, is open.
(IV)
- 4. Verify WG 137, WASTE GAS TO STATION VENT RADIATION ELEMENT ISOLATION, is open.
(IV)
- 5. Verify WG 131, WASTE GAS TO STATION VENT RADIATION ELEMENT BYPASS, is closed.
(IV)
(Continued)
95 DB-OP-03012 Revision 02 C-3 7.2.14 DB-MI-04500, Radiation Monitoring System Channel Calibration 7.2.15 DB-OP-00008, Operation and Control of Locked Valves 7.2.16 DB-OP-00015, Safety Tagging Procedure 7.2.17 DB-OP-00018, Inoperable Equipment Tracking Log 7.2.18 DB-OP-06131, Gaseous Radioactive Waste System 7.2.19 DB-OP-06412, Process and Area Radiation Systems 7.2.20 DB-OP-06502, Containment H2 Dilution and H2 Purge System 7.2.21 DB-OP-06503, Containment Purge System 7.2.22 DB-OP-06512, Auxiliary Building Radioactive Ventilation System Procedure 7.2.23 DB-PF-03009, Containment Integrated Leak Rate Testing (ILRT) 7.2.24 DB-SC-03227, Quarterly Functional Test of RE 5052 A, B, and C, CTMT Purge Exhaust Radiation Monitor 7.2.25 DB-SC-03200, Shift Channel Check of the Radiation Monitoring System 7.2.26 DB-SC-03216, Quarterly Functional Test of RE 4598AA, Station Vent Normal Range Radiation Monitor 7.2.27 DB-SC-03218, Quarterly Functional Test of RE 4598BA, Station Vent Normal Range Radiation Monitor 7.2.28 DB-SP-03419, Waste Gas System Effluent Flow Transmitters Quarterly Channel Functional Test 7.2.29 DB-SC-03225, Quarterly Functional Test of RE 1822A, Waste Gas System Discharge to Station Vent Radiation Monitor 7.2.30 DB-SC-03226, Quarterly Functional Test of RE 1822B, Waste Gas System Discharge to Station Vent Radiation Monitor 7.2.31 Technical Specification Section 3.9.12, Spent Fuel Pool Emergency Ventilation System
24 DB-OP-03012 Revision 02 C-3 4.3.4.a (Continued)
- 6. Verify WG 129, RADIATION MONITOR SAMPLE FT 1822 RETURN ISOLATION VALVE, is open.
(IV)
Independent Verification by Date
- b. IF RE 1822B is OPERABLE, THEN perform the following:
- 1. Verify WG 133, WASTE GAS TO STATION VENT RADIATION ELEMENT ISOLATION, is open.
(IV)
- 2. Verify WG 134, WASTE GAS TO STATION VENT RADIATION ELEMENT ISOLATION, is open.
(IV)
- 3. Verify WG 142, WASTE GAS TO STATION VENT RADIATION ELEMENT ISOLATION, is open.
(IV)
- 4. Verify WG 141, WASTE GAS TO STATION VENT RADIATION ELEMENT ISOLATION, is open.
(IV)
- 5. Verify WG 132, WASTE GAS TO STATION VENT RADIATION ELEMENT BYPASS, is closed.
(IV)
- 6. Verify WG 129, RADIATION MONITOR SAMPLE FT 1822 RETURN ISOLATION VALVE is open:
(IV)
Independent Verification by Da teP 4.3.5 IF RE 1822A is INOPERABLE, THEN perform the following:
- a. Verify WG 140, WASTE GAS TO STATION VENT RADIATION ELEMENT ISOLATION, is closed.
IV (Continued)
94 DB-OP-03012 Revision 02 7.1.3 Technical Specifications Sections: 3.11.2.5, 3.6.1.4 and 4.6.1.2 Containment Ventilation System.
7.1.4 Nuclear Quality Assurance Manual 7.1.5 Offsite Dose Calculation Manual (ODCM) 7.1.6 M-038 A, B, and C, Gaseous Radioactive Waste System 7.1.7 M-029 E, Containment and Penetration Rooms Ventilation, Sheet 4 7.1.8 M-029B, Containment and Penetration Rooms Ventilation, Sheet 2 7.1.9 M-028A Aux. Bldg. Radwaste Fuel Handling and Access Control Areas, Sheet 1.
7.1.10 OS-030, Sh 1&2, Operation Schematic Gaseous Radwaste System.
7.2 Implementation 7.2.1 NG-NL-00807, Regulatory Reports 7.2.2 DB-CH-00006. Radioactive Gaseous Release Program 7.2.3 DB-CH-01334, Liquid Scintillation Detector Model 443C I 7.2.4 DB-CH-01801, Radiochemistry Gamma Spectral Analysis 7.2.5 DB-CH-01804, Tritium Determination 7.2.6 DB-CH-03008, Station Vent Releases, Weekly Radiological Monitoring, Sampling and Analysis 7.2.7 DB-CH-03009, Secondary Coolant System Radiochemistry 7.2.8 DB-CH-04004, Containment Atmosphere Sampling and Analysis 7.2.9 DB-CH-06002, Sampling System Nuclear Areas 7.2.10 DB-MI-03428, Channel Calibration of 72C-ISF 1821 Waste Gas System Outlet Flow 1.0" 7.2.1. DB-MI-03430, Channel Calibration of 72C-ISF 1821A Waste Gas System Outlet Flow 3/4" 7.2.12 DB-MI-03442, Channel Calibration of 32C-ISF 5090 Station Vent Flow 7.2.13 DB-MI-03444, Channel Calibration of 32C-ISF 5090A Station Vent Flow
25 DB-OP-03012 Revision 02 4.3.5 (Continued)
- b. Verify WG 137, WASTE GAS TO STATION VENT RADIATION ELEMENT ISOLATION, is closed.
IV
- c. Verify WG 132, WASTE GAS TO STATION VENT RADIATION ELEMENT ISOLATION, is closed.
IV
- d. Verify WG 131, WASTE GAS TO STATION VENT RADIATION ELEMENT BYPASS, is open.
IV
- e. Verify WG 129, RADIATION MONITOR SAMPLE FT 1822 RETURN ISOLATION VALVE is open.
IV Independent Verification by Date 4.3.6 IF RE 1822B is INOPERABLE, THEN perform the following:
- a. Verify WG 133, WASTE GAS TO STATION UNIT RADIATION ELEMENT ISOLATION, is closed.
IV
- b. Verify WG 141, WASTE GAS TO STATION UNIT RADIATION ELEMENT ISOLATION, is closed.
IV
- c. Verify WG 131, WASTE GAS TO STATION UNIT RADIATION ELEMENT ISOLATION, is closed.
IV
- d. Verify WG 132, WASTE GAS TO STATION VENT RADIATION ELEMENT BYPASS, is open.
IV
- e. Verify WG 129, RADIATION MONITOR SAMPLE FT 1822 RETURN ISOLATION VALVE is open.
IV Independent Verification by Date i
I
93 DB-OP-03012 Revision 02 The Gaseous Radwaste Treatment System was used to reduce radioactive materials in this batch release prior to discharge OR the air dose to areas at and beyond the SITE BOUNDARY does NOT exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation in a 31 day period.
Verified by ,V jir /-c Date 5.6 The VENTILATION EXHAUST TREATMENT SYSTEM was used to reduce radioactive materials in this batch release prior to discharge OR the projected doses due to gaseous effluent releases to areas at and beyond the SITE BOUNDARY does NOT exceed 0.3 mrem to any organ in a 31 day period.
Verified by J uc/<k L Date / o/f lec 6.0 RECORDS 6.1 The Quality Assurance Records generated by this procedure shall be listed on the Nuclear Records List by Nuclear Records Management. The Non-Quality Assurance Records generated by this procedure may be listed on the Nuclear Records List according to NG-PS-00106, Nuclear Records Management, at the discretion of the Division Director with record copy responsibility. All records shall be captured and submitted to Nuclear Records Management by the transmitting organization according to NG-PS-00106, Nuclear Records Management.
6.1.1 Quality Assurance Records generated by this procedure are as follows:
- a. Radioactive Gaseous Batch Release Permit
- b. Radioactive Gaseous Batch Release Log
- c. Completed sections of DB-OP-03012 6.1.2 Non-Quality Assurance Records generated by this procedure are as follows:
None
7.0 REFERENCES
7.1 Developmental 7.1.1= Regulatory Guide 1.21, Measuring, Evaluating and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquids and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants.
7.1.2 USAR Section 11, Radioactive Waste Management I
26 DB-OP-03012 Revision 02 4.3.7 IF either RE 1822A or RE 1822B will be used for the release, THEN verify the power switch on the electronic readout for FYIS 1822 is ON.
4.3.8 Verify WG 1821, WASTE GAS TO STATION VENT FLOW CONTROL VALVE is closed, using FIC 1821 on the Radioactive Waste Control Panel (RWCP).
IV 4.3.-9 Ver ify WG 1821A, WASTE GAS TO STATION VENT FLOW CON TROL VALVE is closed, using FIC 1821A at the RWCP.
IV Independent Verification by Date 4.3.10 IF Action A of ODCM Table 3-1 is required due to RE inoperability, THEN "N/A" Step 4.3.11.
4.3.11 Request the Control Room perform the following for the OPERABLE RE's:
- a. For RE 1822A:
- 1. Open WG 1819, WASTE GAS TO STATION VENT ISOLATION using HIS 1819 at the RWCP.
- 2. Open WG 1820, WASTE GAS TO STATION VENT ISOLATION using HIS 1820 at the RWCP.
- 3. Depress the TEST pushbutton on the Control Room module for RE 1822A.
- 4. Check annunciator (7-1-C) "WST GAS SYS OUT RAD HI" has alarmed in the Control Room.
- 5. Check computer alarm R910, "WST GAS SYS OUT RAD" has alarmed in the Control Room.
- 6. Verify WG 1819, WASTE GAS TO STATION VENT ISOLATION closes.
- 7. Verify WG 1820, WASTE GAS TO STATION VENT ISOLATION closes.
- 8. Depress the ALARM ACK button on the Control Room module for RE 1822A.
(Continued)
I
92 DB-OP-03012 Revision 02 5.0 ACCEPTANCE CRITERIA 5.1 The release has been sampled and analyzed for tritium and principal gamma emitters.
Verified by 1Ab/fi >- Date t0 5.2 The dose rate, due to radioactive materia released in this batch release from the site to areas at and beyond the SITE BOUNDARY, does not cause the following limits to be exceeded:
- For noble gases: Less than or equal to 500 mrems/year to the total body and less than or equal to 3000 mrems/year to the skin.
AND e For iodine-131, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days:
Less than or equal to 1500 mrems/year to any organ.
Verified by ':jLq A kkrG Date _IONO-19 5.3 The air dose due to noble gases released in this batch release from the site to areas at and beyond the SITE BOUNDARY does not cause the following limits to be exceeded:
c During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, AND e During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.
Verified by FJr.I I Date cd .7c6 5.4 The dose to a MEMBER OF THE PUBLIC from iodine-131, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in this batch release released to areas at and beyond the SITE BOUNDARY does not cause the following limits to be exceeded:
- a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ and,
- b. During any calendar year: Less than or equal to 15 mrems to any organ.
Verified by 9 /S cek/y Date
27 DB-OP-03012 Revision 02 4.3.11 (Continued)
- b. For RE 1822B:
- 1. Open WG 1819, WASTE GAS TO STATION VENT ISOLATION using HIS 1819 at the RWCP.
- 2. Open WG 1820, WASTE GAS TO STATION VENT ISOLATION using HIS 1820 at the RWCP.
- 3. Lower the Warn Alarm Setpoint to l.OOEO1.
REFER TO DB-OP-06412, Process and Area Monitor Operating Procedure.
- 4. Lower the High Alarm Setpoint to 2.OOEO1.
REFER TO DB-OP-06412, Process and Area Monitoring Operating Procedure.
- 5. Check annunciator (7-1-C), WST GAS SYS OUT RAD HI has alarmed in the Control Room.
- 6. Check computer alarm R910, WST GAS SYS OUT RAD has alarmed in the Control Room.
- 7. Verify WG 1819, WASTE GAS TO STATION VENT ISOLATION closes.
- 8. Verify WG 1820, WASTE GAS TO STATION VENT ISOLATION closes.
- 9. Depress the ALARM ACK pushbutton on the Control Room module for RE 1822B.
- 10. Restore the setpoints for the WARN and HIGH alarm to the values listed in the Radiation Monitor Setpoint Manual. REFER TO DB-OP-06412, Process and Area Monitor Operating Procedure.
4.3.12 Select the flow indicating controller (FIC) for this release AND verify the alarm setpoints by performing the following:
- a. IF the tenth value of the maximum release rate as recorded on Item 9.b is greater than or equal to 1 SCFM BUT less than 5 SCFM, THEN use FIC 1821A for the release.
(Continued)
91 DB-OP-03012 Revision 02 4.17 Completed Release Shift Supervisor Review INITIALS 4.17.1 Review the release procedure and permit for completeness.
4.17.2 Remove any attachments from the package not used during the release.
4.17.3 Submit the completed Surveillance Test Procedure to the Technical Specification Planner/Scheduler.
Subsection 4.17 completed by Date
28 DB-OP-03012 Revision 02 C-4 4.3.12 (Continued)
- b. IF the tenth value of the maximum release rate is greater than OR equal to S SCFM BUT less than or equal to 45 SCFM, THEN use FIC 1821 for the release.
- c. Request the Control Room perform the following:
_ 1. IF FIC 1821A will be used for the release, THEN verify computer pt. F910, GASEOUS EFFLUENT HIGH FLOW ALARM is set at 5 SCFM.
_ _ 2. IF FIC 1821 will be used for the release, THEN verify computer pt. F911, GASEOUS EFFLUENT HIGH FLOW ALARM is set at 50 SCFM.
4.3.13 IF the total elapsed time from sample time listed in Item 4.e to time of release is greater than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, THEN perform the following:
- a. Request Chemistry obtain another sample for the tank to be released.
- b. IF this sample indicates a change in activity that invalidates the dose projections of this release, THEN void this release and start a new release permit.
- c. Record the reason for voiding the permit in Item 5.a.
4.3.14 Request the Shift Supervisor approve the release by signing Item 4.1 on the permit.
4.3.15 Open WG 1819, WASTE GAS TO STATION VENT ISOLATION using HIS 1819 at the RWCP.
IV 4.3.16 Open WG 1820, WASTE GAS TO STATION VENT ISOLATION using HIS 1820 at the RWCP.
IV Independent Verification by Date
90 DB-OP-03012 Revision 02 TA99-1770 4.16.4 Make two (2) copies of the completed Attachment 1 and computer printouts:
e Place one in counting room release log book.
c Submit one to ALARA Services.
4.16.5 The Chemistry Supervisor shall submit this test to the Shift Supervisor after review of the Chemistry sections of Attachment 1.
Subsection 4.16 completed by Date
29 DB-OP-03012 Revision 02 C-4 4.3.17 Perform the following:'
- Record the start time, release permit number, WGDT number and pressure in the Unit Log.
- Mark Recorder UJR 5092 in the Control Room for RE 1822A AND/OR RE 1822B with date, time and release permit number.
- Mark the recorder in the Control Room for RE 4598AA AND/OR 4598BA with date, time and release permit number.
e_ Record the start time, date and WGDT pressure in Item 6.
4.3.18 OPEN the outlet valve for the WGDT to be released.
'N/Al the WGDTs not being released. I
- a. For WGDT 1, open WG 1836, WASTE GAS DECAY TANK 1-1 TO STATION VENT CONTROL VALVE using HIS 1836 at the RWCP.
IV
- b. For WGDT 2, open WG 1838, WASTE GAS DECAY TANK 1-2 TO STATION VENT CONTROL VALVE using HIS 1838 at the RWCP.
IV
- c. For WGDT 3, open WG 1840, WASTE GAS DECAY TANK 1-3 TO STATION VENT CONTROL VALVE using HIS 1840 at the RWCP.
IV Independent Verification by Date 4.3.19 To initiate the release, VERIFY FIC selected in Step 4.3.12 is in AUTO AND adjusted to either the tenth value of the maximum release rate as recorded on Item 9.b OR 45 SCFM, whichever is less, OR at a rate directed by the Shift Supervisor which does not exceed Item 9.b.
I
89 DB-OP-03012
'I Revision 02 TA99-1770 4.16.1 (Continued)
I NOTE 4
.16.1.o I I I
1 psi = 27.7 inches of water I I
I_ _ _
I
- o. IF updating a Containment Purge and there was a reduction in containment pressure, THEN update volume where volume is equal to 2.834E6 (14.7 + Delta P from Item 8) 14.7
_ _ _ P . IF updating a Containment Pressure reduction, THEN perform the following:
- 1. Determine the average flowrate by using Attachment 5, if available, or 305 SCFM if Attachment 5 is not available.
- 2. Multiply this flowrate by the actual purge time to obtain the volume purged.
- 3. Enter the volume released.
- 4. Document all calculations in Item 5, Remarks.
__ q- IF updating a Containment Pressure reduction and multiple samples were taken, THEN update isotopic activity to reflect weighed average based on analyses and release volume and attach calculations to this procedure.
- r. Enter duration of release for Item 8.
- s. Select Compute.
- t. Select Save.
_ u. Select Print.
4.16.2 Review the completed computer printout for agreement with the reported nuclides and activities.
4.16.3 Attach the printout to this procedure.
30 DB-OP-03012 Revision 02 4.3.20 Perform the following at the start of the release.
- a. IF either RE 1822A or RE 1822B are OPERABLE, THEN perform a channel check for each OPERABLE radiation monitor as follows:
- 1. For RE 1822A.
a) Verify the ON/OFF switch is in the ON position.
b) Check all ALARM lights are off c) Check the CHECK SOURCE light is off d) Check the digital indicator is responding.
- 2. For RE 1822B.
a) Verify the ON/OFF switch is in the ON position.
b) Check all ALARM lights are off c) Check the CHECK SOURCE light is off d) Check the digital indicator is responding.
- 3. IF the channel check for each operable RE is NOT satisfactory, THEN perform the following:
a) Close WG 1819, WASTE GAS TO STATION VENT ISOLATION VALVE.
b) Close UG 1820, WASTE GAS TO STATION VENT ISOLATION VAlVE.
c) Notify the Shift Supervisor.
- 4. IF the channel check for each operable RE is satisfactory, THEN complete Item 4.m.
- a) IF both RE channels are NOT OPERABLE, THEN enter "N/A" in Item 4.m, AND record required ODCM actions in Item 5a.
(Continued)
. -111-
on DB-OP-03012 Revision 02 TA99-1770 4.16 Calculations for a Completed Release INITIALS NOTE 4.16.1 This section should be completed as soon as l possible after the release and before the end of the current calendar month.
4.16.1 Update RETSCode files as follows:
- a. Select Procedures
- b. Select Gases
- c. Select Batch release
- d. Select Release
- e. Select Open
- f. High-lite release to be updated
- g. Select OK
- h. Select Release
- i. Select Ppen
- j. High-lite release to be updated
- k. Select OK
- 1. Update release date to reflect day release started
- m. Change Release Status to Post-Release
- n. IF updating a WGDT release, THEN enter a pressure equal the Delta P as record in Item 8.
(Continued)
31 DB-OP-03012 Revision 02 4.3.20 (Continued)
- b. Perform a channel check on the flow meter being used for the release as follows.
IF the flow meter is NOT OPERABLE, THEN "N/A" this step AND Item 4.n.
- 1. Verify the indicated flowrate on the meter is in agreement with the flowrate setting on the release flow controller.
- 2. IF the flowrate meter channel check was satisfactory, THEN complete Item 4.n.
1- - - - - - - - - - - - - - - - - - - - - - - - - - - -I NOTE 4.3.20.b.3 If the flowmeter for the release is INOPERABLE l the ODCM Table 3-1 Action B requires that flowrate be estimated at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Since flow is normally estimated once every two hours I during the release per Step 4.3.24 no additional l action is required.
- 3. IF the flowrate meter channel check was not satisfactory, THEN notify the Shift Supervisor.
-I
87 DB-OP-03012 Revision 02 C-4 NOTE 4.15.8 The Shift Supervisor may approve a release that is NOT recommended, if plant conditions require the release, AND the Manager - Radiation l Protection, or designee, concurs.
I- - - - - - - - - - - - - - - - - - - - - - - - - - -
4.15.8 IF the above conditions can be satisfied, THEN recommend approval of this release by signing Item 4.h.
4.15.9 IF the release can NOT be recommended for approval, AND this is a CTMT pressure reduction, AND the Shift Supervisor desires, THEN disconnect the pressure reduction skid in accordance with Step 4.6.36.
NOTE 4.15.10 IF this permit is voided, THEN dispose of this l procedure. Since NO release was made, NO surveillance testing and documentation is required.
ll I
-4.15.10 IF the release can NOT be recommended for approval and the Shift Supervisor AGREES, THEN forward this procedure to Chemistry for record closeout and disposal.
I7II 4.15.11 Verify and signoff Acceptance Criteria 5.2, 5.3, 5.4, 5.5, and 5.6.
rJ 4.15.12 Return this procedure to the Shi .ft Supervisor.
Section 4.15 completed by g-Ijw-
-A, rk-Ar /
v En, 1-1 -7 Date L)JI3ov
DB-OP-03012 Revision 02 C-4 4.3.20 Review Steps 4.3.21 thru 4.3.25.
NOTE 4.3.21 through 4.3.25 l Steps 4.3.21 through 4.3.25 are performed concurrently during the release and are signed off at the completion of the release.
4.3.21 IF the Main Station Exhaust Fan(s) trip during the release, THEN terminate the release by performing the following:
- a. Verify WG 1819, WASTE GAS TO STATION VENT ISOLATION VALVE, is closed.
- b. Verify WG 1820, WASTE GAS TO STATION VENT ISOLATION VALVE, is closed
- c. Notify the Shift Supervisor.
4.3.22 IF a ALERT or HIGH radiation alarm is received from RE 4598AA or RE 4598BA, THEN perform the following:
- a. Verify WG 1819, WASTE GAS TO STATION VENT ISOLATION VALVE, is closed.
- b. Verify WG 1820, WASTE GAS TO STATION VENT ISOLATION VALVE, is closed.
- c. Notify the Shift Supervisor.
4.3.23 IF RE 1822A and/or RE 1822B are operable, THEN perform the following:
- a. Monitor the radiation monitor(s) approximately every hour.
(Continued)
86 DB-OP-03012 Revision 02 NOTE 4.15.5 A Containment Purge is normally assigned a maximum purge time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at greater than 50,000 CFM during which a conservative estimate of all of the airborne activity detected in the sample analysis is released. IF the airborne l activity detected in the sample analysis will not permit a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> purge time, THEN the purge time is reduced and the Containment volume l ratioed to estimate the activity released. l ll
______4.15.5 IF this release is a Containment Purge and the maximum purge rate recorded in Item 10 is less than or equal to 50,000 CFM, THEN the purge rate is at or above 100% of limit and the Containment Purge approval must be recommended by the Manager - Radiation Protection or his designee only.
4 4.15.6 IF the conditions in Steps 4.15.2 - 4.15.4 are NOT met, THEN an investigation shall be conducted by the Radiation Protection Department and documented in Item 5 prior to recommending this release for approval.
4.15.7 IF an investigation is required, THEN the following guidance should be used in determining if the release should be recommended.
- a. Will plant conditions permit a delay in performing the release to allow for further decay?
- b. If radioiodines and particulates are the cause of the unacceptable condition, can the release be routed through charcoal and/or HEPA filters to remove the activity prior to release?
- c. What effect will this release have on the total quarterly and annual limits for the station dose commitment for radioactive gaseous effluent?
- d. Record the results of the investigation in Item 5.
33 DB-OP-03012 Revision 02 C-4 4.3.23 (Continued)
- b. IF a WARN or HIGH radiation alarm is received on RE 1822A or RE 1822B, THEN perform the following:
- 1. Verify WG 1819, WASTE GAS TO STATION VENT ISOLATION VALVE, is closed.
- 2. Verify WG 1820, WASTE GAS TO STATION VENT ISOLATION VALVE, is closed.
- 3. Notify the Shift Supervisor.
4.3.24 IF annunciator alarm (50-2-I), WST GAS SYS RAD MNTR FLOW is received at the RWCP, THEN perform the following:
- a. Increase RE flow by throttling closed WG 130, WASTE GAS TO STATION VENT CONTROL VALVE OUTLET ISOLATION VALVE.
- b. IF the LOW flow alarm can NOT be cleared, THEN perform the following:
- 1. Verify WG 1819, WASTE GAS TO STATION VENT ISOLATION VALVE, is closed.
- 2. Verify WG 1820, WASET GAS TO STATION VENT ISOLATION VALVE, is closed.
- 3. Notify the Shift Supervisor.
4.3.25 Calculate the estimated flowrate every two hours during the release by performing the following.
- a. Enter the WGDT Gas Volume from Item 3.b of Attachment 1.
_ ft 3 (Initial Volume)
(Continued)
85 DB-OP-03012 Revision 02
&.15 Recommendation for Approval
- - - - - - - - - - - - - - - - - - - - - - - - - - - -I NOTE 4.15 Recommendation of a Gaseous Release for approval shall be performed by authorized management personnel only. IF a permit must be recommended during the hours when the authorized management l I personnel are not present, THEN review and recommendation by telephone is permitted. l Documentation of Tel Com person shall be made in Item 4.h.
ll l_ - - - - - - - - - - - - - - - - - - - - - - - - - - -
INITIALS 4 4.15.1 Ensure all sampling and analysis entries are complete.
1- - - - - - - - - - - - - - - - - - - - - - - - - - - -
NOTE 4.15.2 and 4.15.3 The maximum release rate is a calculated value based on the curie content of all the radionuclides in the WGDT which would result in a release equal to the instantaneous release as defined in the ODCM. The tenth value of the l maximum release rate for a WGDT is a safety l l factor to ensure that only a fraction of the l instantaneous release rate is achieved.
l 4.15.2 IF this is a WGDT release, THEN ensure that the tenth value of the maximum release rate as recorded in Item 9b is greater than 25 SCFM.
4.15.3 IF the maximum release rate as recorded in Item 9a is less than or equal to 25 SCFM, THEN the release should be investigated and the investigation documented in Item 5.a.
j 4.15.4 Ensure the estimated iodine and particulate dose for this release is less than 2.0 E-2 mrem.
- ,; to
- . ..Dg_
mL-1...
... I....
34 DB-OP-03012 Revision 02 C-4 4.3.25 (Continued)
- b. Estimate the WGDT gas volume at the time of the calculation.
Estimate Volume - (WGDT pressure at calculation + 14.7) psig x 1013 ft3.
1A.7 psi
- ( + 14.7) x 1013 ft 14.7 psi ft 3 (Estimated Volume)
- c. Calculate the total elapsed release time in minutes.
Time release started Time of calculation Elapsed time minutes
- d. Estimate the release rate.
Estimated Release Rate (Initial volume - Estimate volume)
Minutes elapsed
= ( - ) ft minutes
= _ __ ft 3/minute
- e. Record the estimated release rate and time calculated on Attachment 5, Estimated Release Rate.
- f. Verify the estimated release flowrate is less than or equal to the tenth value of the maximum release rate recorded on Item 9.b or 45 SCFM whichever is less by adjusting FIC 1821 or FIC 1821A as necessary.
4.3.26 WHEN the WGDT pressure is less than 10 psig, OR as directed by the Shift Supervisor, THEN stop the release by closing the appropriate WGDT outlet valve:
- a. For WGDT 1, close WG 1836, WASTE GAS DECAY TANK 1 TO STATION VENT CONTROL VALVE, using HIS 1836 at the RWCP.
(Continued)
84 DB-OP-03012 Revision 02 TA99-1770
.. I NOTE 4.14.16 Enter the following values under the appropriate column:
a Estimated values determined before a release e Actual values determined after a release. l 4.14.16 Record in Item 18 the following dose commitments for this release from ODCM calculations:
- a. Iodine and Particulate Dose
- b. Gamma Air Dose
- c. Beta Air Dose 4.14.17 Record the sums of the dose commitments from this release (Item 18) and the actual dose commitment from current quarter to date releases in Item 20.
4.14.18 Record the sums of the dose commitments from this release (Item 18) and the actual dose commitment from current year to date releases in Item 20.
4.14.19 Sign Item 4.g.
4.14.20 Submit this procedure for release to the Radiation Protection Management for the required recommendation for release.
Section 4.14 completed by Date
35 DB-OP-03012 Revision 02 C-4 4.3.26 (Continued)
- b. For WGDT 2, close WG 1838, WASTE GAS DECAY TANK 2 TO STATION VENT CONTROL VALVE, using HIS 1838 at the RWCP.
- c. For WGDT 3, close WG 1840, WASTE GAS DECAY TANK 3 TO STATION VENT CONTROL VALVE, using HIS 1840 at the RWCP.
NOTE 4.3.26.d DO NOT record time release is stopped here as the l final time in Item 7 unless the release will not be restarted. Intermediate starts and stops, for l purging should be recorded in Item Sa as needed l to track total release time.
- d. Record time release stopped for sample in Item 5.a.
NOTE 4.3.27 l Chemistry personnel shall determine the need to I purge the WGDT after the release has beena I terminated. I I
- - - - - - - - - - - - - - - - - - - - - - - - - -I 4.3.27 Request Chemistry personnel sample the WGDT released for oxygen and hydrogen concentration.
81 DB-OP-03012 Revision 02 C-3 NOTE 4.14 l A hand calculation will normally be performed l only when the computer is out of service when l release calculations are performed prior to the release. The computer should be used for all l calculations on completed releases.
4.14 Hand Calculation INITIALS 4.14.1 IF this is a WGDT release AND BOTH RE's 1822A and 1822B are inoperable THEN the ODCM Table 3-1 Action A requires that two independent verifications of the release rate calculations be performed. To document this the person doing the independent verification shall obtain a copy of this section of the procedure and attachments and attach the completed section and attachments to the release package.
4.14.2 Calculate the release volume in cubic centimeters at standard pressure as follows:
- a. WGDT Releases (1013) x (P + 14.7) x (28317) 1013 x ( ) x 28317 14.7 14.7 cc =
P - WGDT pressure in PSIG
- b. Containment Release cc = (ft3) x (28317) = ( ) x (28317) =
ft3 - release volume in cubic feet from Item 3.b.
e 2.834 E6 ft3 for a Containment Purge o 4.39 E5 ft3 for a Containment pressure release based on fan capacity of 305 CFM for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
36 DB-OP-03012 Revision 02 C-4 4.3.28 IF purging of the WGDT is required, THEN perform the following:
- a. Perform a Temporary Lift AND open the applicable WGDT inlet isolation valve, refer to DB-OP-00015, Safety Tagging.
- 1. For WGDT 1, open WG 34, Waste Gas Decay Tank 1-1 Inlet Isolation Valve.
- 2. For WGDT 2, open WG 35, Waste Gas Decay Tank 1-2 Inlet Isolation Valve.
- 3. For WGDT 3, open WG 36, Waste Gas Decay Tank 1-3 Inlet Isolation Valve.
- 1. For IWGDT 1, open NN 124, N2 SUPPLY TO WGDT 1-1.
- 2. For WGDT 2, open NN 123, N2 SUPPLY TO WGDT 1-2.
- 3. For WGDT 3, open NN 122, N2 SUPPLY TO WGDT 1-3.
- c. Open NN 158, N2 REGULATOR OUTLET.
- d. Open NN 177, N2 REGULATOR INLET.
4 NOTE .3.28.e The maximum pressure from NN 1807 is set at 20 psig.
Il
- e. WHEN the maximum pressure is attained, THEN close the nitrogen supply valve for the WGDT being purged.
- 1. For WGDT 1, close NN 124, N2 SUPPLY TO WGDT 1.
- 2. For WGDT 2, close NN 123, N2 SUPPLY TO WGDT 2.
- 3. For WGDT 3, close NN 122, N2 SUPPLY TO WGDT 3.
(Continued) f.
so DB-OP-03012 Revision 02 TA99-1770
-AA 4.13.9 IF this release is due to ILRT, THEN mark Item 10 N/A.
4.13.10 Sign Item 4.g.
4/ 4.13.11 Verify and sign off Acceptance Criteria 5.1 6L 4.13.12 Submit this procedure to the Radiation Protection for the required recommendation for release per Section 4.15.
Subsection 4.13 completed by A-lt'Z' 1a Jk; A fVs" Date f ;/b 7 I
37 DB-OP-03012 Revision 02 C-4 4.3.28 (Continued)
- f. Close AND Rehang DNO tag on the applicable WGDT inlet isolation valve.
- 1. For WGDT 1, close WG 34, Waste Gas Decay Tank 1-1 Inlet Isolation Valve.
- 2. For WGDT 2, close WG 35, Waste Gas Decay Tank 1-2 Inlet Isolation Valve.
- 3. For WGDT 3, close WG 36, Waste Gas Decay Tank 1-3 Inlet Isolation Valve.
NOTE 4.3.28.q IF the inlet valve for the tank to be purged has NOT been opened, THEN a new release permit is NOT required. IF the inlet valve has been opened, THEN a new release permit shall be initiated AND an investigation shall be conducted to determine when the inlet valve was opened per the requirements of Conduct of Operations, DB-OP-00000.
l - - - - - - - - - - - - - - - - - - - - - - - - - - -
- g. Reinitiate the release by opening the outlet valve for the WGDT being released, and purged.
- 1. For WGDT 1, open WG 1836, WASTE GAS DECAY TANK 2 TO STATION VENT CONTROL VALVE using HIS 1836 at the RWCP.
IV
- 2. For WGDT 2, open WG 1838, WASET GAS DECAY TANK 2 TO STATION VENT CONTROL VALVE using HIS 1838 at the RWCP.
IV
- 3. For WGDT 3, open WG 1840, WASTE GAS DECAY TANK 3 TO STATION VENT CONTROL VALVE using HIS 1840 at the RWCP.
IV
- 4. Record time release restarted with tank pressure in Item 5.a.
Independent Verification by Date
- h. WHEN the pressure of the WGDT being purged is less than 10 psig, THEN close the outlet valve opened in Step 4.3.28.g.
(Continued)
'7a
, DB-OP-03 012 Revision 02 TA99-1770
- 1 NOTE 4.13.7 A Containment Purge is normally assigned a
maximum purge time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during which a
-- v v est-nimate or all or thie airborne activity detected in the sample analysis is released.
t /% &44-13. 7 IF the release is a Containment Purge, THEN enter the maximum purge time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in Item 10.b and the maximum purge rate (smallest release rate limit) in Item 10.a.
OTHERWISE mark this step and Items 10.a and 10.b N/A.
AL 4.13 .8 Attach printout of RETSCode to this procedure.
I
38 DB-OP-03012 Revision 02 C-4 4.3.28 (Continued)
- i. Repeat Step 4.3.28.a-h until Chemistry personnel determines the oxygen and hydrogen concentrations are within limits.
- Record additional start and stop times with corresponding tank pressures in Item 5.a.
- j. Record on Item 5.a that the WGDT was purged with nitrogen following the release to reduce the oxygen concentration.
- k. Close NN 158, N2 Regulator Outlet
- 1. Close NN 177, N2 Regulator Inlet
- m. IF absolute filter and charcoal filter were bypassed in Step 4.1.11, THEN perform the following:
- 1. For the absolute filter:
- Verify WG 45, WASTE GAS ABSOLUTE FILTER OUTLET ISOLATION VALVE, is open.
_ WG 8, WASTE GAS ABSOLUTE FILTER 1 INLET ISOLATION, is open.
- Verify WG 48, WASTE GAS ABSOLUTE FILTER BYPASS VALVE, is closed.
- 2. For the charcoal filter:
- Verify WG 46, WASTE GAS CHARCOAL FILTER INLET ISOLATION VALVE, is open.
- Verify WG 47, WASTE GAS CHARCOAL FILTER OUTLET ISOLATION VALVE, is open.
- Verify WG 49, WASTE GAS CHARCOAL FILTER BYPASS VALVE, is closed.
4.3.29 Close WG 1819, WASTE GAS TO STATION VENT ISOLATION VALVE.
4.3.30 Close WG 1820, WASTE GAS TO STATION VENT ISOLATION VALVE.
78 DB-OP-03012 Revision 02 TA99-1770 1
NOTE 4.13.4 The Radioactive Gaseous Batch release calculation program will now determine the allowable release rate based on the information provided. 4.13.4 Review the completed computer printout for agreement with the identified isotopes and associated values.
4.13.5 IF this is a WGDT release, THEN record the maximum allowable release rate in Item 9.a.
OTHERWISE mark this step and Item 9.a N/A.
NOTE 4.13.6 For WGDT releases the actual release rate will be less than or equal to the tenth value of the maximum release rate or 45 SCFM whichever is less.
CAUTION 4.13.6 IF the result is less than 1 SCFM, THEN the release should be terminated.
4.13.6 IF this is a WGDT release, THEN divide the maximum release rate by ten and record the value or 45 SCFM, whichever is less, in Item 9.b.
OTHERWISE mark this step and Item 9.b N/A.
39 DB-OP-03012 Revision 02 C-4 NOTE 4.3.31 A value of zero is conservative in that it will assume all activity in-the tank has been released.
Il 4.3.31 Perform the following:
- Request the Control Room mark the recorder UJR 5092, for RE1822A AND/OR RE1822B, with the Release Permit number and stop time.
- Request the Control Room mark the Recorder for RE 4598AA AND/OR 4598BA with release permit number and stop time.
- Record the stop time, release permit number, WGDT number and pressure in the Unit Log.
s Record the release final stop time and date on Item 7.
- Record a WGDT pressure of zero on Item 7.
4.3.32 Remove the DNO tags hung in Section 4.1. Refer to DB-OP-00015, Safety Tagging.
4.3.33 Remove the Information Tags hung in Section 4.1.
Refer to DB-OP-00010, Operational Information Tags 4.3.34 Remove the radiation monitor(s) used for this release from service as follows:
- a. To remove RE 1822A from service perform the following:
- 1. Verify WG 140, WASTE GAS TO STATION VENT RADIATION ELEMENT ISOLATION, is closed.
- 2. Verify WG 139, WASTE GAS TO STATION VENT RADIATION ELEMENT ISOLATION, is closed.
- 3. Verify WG 138, WASTE GAS TO STATION VENT RADIATION ELEMENT ISOLATION, is closed.
- 4. Verify WG 137, WASTE GAS TO STATION VENT RADIATION ELEMENT ISOLATION, is closed.
- 5. Verify WG 132, WASTE GAS TO STATION VENT RADIATION ELEMENT BYPASS, is closed.
(Continued)
77a DB-OP-03012 Revision 02 TA99-1770 21t This page is intentionally left blank.
40 DB-OP-03012 Revision 02 C-4 4.3.34.a (Continued)
- 6. Verify WG 129, RADIATION MONITOR SAMPLE FT 1822 RETURN ISOLATION VALVE, is closed.
- 7. Verify WG 13i, WASTE GAS TO STATION VENT RADIATION ELEMENT BYPASS, is closed.
- b. To remove RE 1822B from service perform the following:
_ 1. Verify WG 133, WASTE GAS TO STATION VENT RADIATION ELEMENT ISOLATION, is closed.
__ _ 2. Verify WG 134, WASTE GAS TO STATION VENT RADIATION ELEMENT ISOLATION, is closed.
- 3. Verify WG 142, WASTE GAS TO STATION VENT RADIATION ELEMENT ISOLATION, is closed.
- 4. Verify WG 141, WASTE GAS TO STATION VENT RADIATION ELEMENT ISOLATION, is closed.
- 5. Verify WG 131, WASTE GAS TO STATION VENT RADIATION ELEMENT BYPASS, is closed.
- 6. Verify WG 129, RADIATION MONITOR SAMPLE FT 1822 RETURN ISOLATION VALVE, is closed.
- 7. Verify WG 132, WASTE GAS TO STATION VENT RADIATION ELEMENT BYPASS, is closed.
4.3.35 IF either RE 1822A or RE 1822B was in service for the release, THEN turn the power switch on the electronic readout for FYIS 1822 to OFF.
4.3.36 Perform the following:
- a. Calculate total release time.
Time recorded in Item 7 - Time Recorded in Item 6
- Also subtract start and stop times when purging tank as recorded in Item 5.a if performed.
- b. Calculate Delta P.
Pressure recorded in Item 6 - Pressure recorded in Item 7
- c. Record calculated values in Item 8.
77 DB-OP-03012 4.13.3 (Continued on page 77a)
(Cont:inued)
Revision 02 TA99-1770 i
-4f k. For volume entry
- 1. For WGDT, use calculated value
- 2. For Containment Purge, enter 2.834E+6
- 3. For Containment Pressure reduction, enter 4.39E+5
- 4. For ILRT, enter 2.834E+6
- 5. For Other, enter calculated value as follows:
a) Obtain tank or line pressure from Control Room.
b) Obtain tank or line volume from Control Room or Plant Engineering.
c) Determine "corrected volume" (Line/tank pressure +14.7) x line/tank volume (Line/tank pressure +14.7) x line/tank volume 14.7
- 1. Select yes for processed through Gaseous Radwaste UNLESS this is a ILRT.
- m. Select Sample Analysis
- n. Enter nuclides and activities
- 0. Select OK P - Select Compute
- q. Select Save
- r. Select Print (Continued)
41 DB-OP-03012 Revision 02 C-4 4.3.37 Verify the selected flow control valve (WG 1821 or WG 1821A) used for the release is closed AND set the controller to zero flow.
4.3.38 Return this procedure to the Control Room for processing.
4.3.39 Review the operational portion of this procedure for completeness.
4.3.40 Return the procedure to the Chemistry Department for processing in accordance with Section 4.16.
Section 4.3 completed by Date
76 DB-OP-03012 Revision 02 TA99-1770 4.13 Computer Assisted Calculations INITIALS 4L 4.13.1 IF the computer is not available for calculating release rates, THEN discard this section and GO TO Section 4.14.
OTHERWISE discard Section 4.14 and Attachments 6
through 8.
I 4.13.2 IF this is a WGDT release and BOTH REs 1822A AND 1822B are inoperable THEN the ODCM Table 3-1 Action A requires that two independent verifications of the release rate calculations be performed. To document this the person doing the independent verification shall obtain a copy of this section of the procedure and attach the completed section to the Release Package.
4.13.3 Run the RETSCode program as follows:
- a. Select Procedures
- b. Select Gases
- c. Select Batch release
- d. Select Release A* e. Select New
" 0o_7
- f. Enter Sample Date as Release Date
- g. Select Batch as Release Type
- h. Select Pre-Release as Status
- i. Select Source of Release j.- For Pressure entry
- 1. For WGDT, enter pressure from Item 3.a.
- 2. For Containment Purge, enter N/A
- 3. For Containment Pressure reduction, enter 1
- 4. For ILRT, enter pressure from item 3.a.
- 5. For Other, enter N/A (Continued)
42 DB-OP-03012 Revision 02 C-3 4.4 Preparing a Containment Pressure Reduction Release INITIALS 4.4.1 Notify the Radiation Protection personnel a Containment pressure reduction is necessary AND the discharge for the pressure release skid will be in the Radioactive Waste Ventilation duct in the Auxiliary Building Train Bay.
4.4.2 Verify the following valves are closed:
_ CV 138, HYDROGEN RECOMBINER INLET ISOLATION VALVE.
o CV 139, HYDROGEN RECOMBINER INLET ISOLATION VALVE.
I _
I NOTE 4.4.3 I
I The following will require personnel from the I I MairI tenance, Electrical, Radiation Protection and I Opea *ations Departments.
I__
I4- - - ~I 4.4. 3 Perform the following:
- a. Perform an operability determination for the SFP EVS for opening FD 1174, Radioactive Waste Ventilation System access port Access port FD 1174 surface area is 120 in . REFER TO DB-OP-00018, Inoperable Equipment Tracking Log AND TS 3.9.12, SFP EVS.
- c. Connect the Containment Pressure Release Skid inlet ducting to the flange from which the blank flange was removed.
- d. Open Radioactive Waste Ventilation System access port FD 1174, located above Door 306 in Room 300.
- e. Connect the Containment Pressure Release Skid outlet ducting to the Radioactive Waste Ventilation System duct port FD 1174.
(Continued)
75 DB-OP-03012 Revision 02 TAO0-0315 4.12.14 (Continued)
NOTE 4.12.14.f Photopeaks which, after visual inspection, are not peaks or photopeaks with 50% error or greater are to be lined out and initialed. Other confirmed photopeaks are to be marked with nuclide's name.
- f. For all unidentified photopeaks, identify those with errors less than 50%. I
- g. IF other nuclides are identified from the evaluation of unidentified photopeaks which have NOT already been quantified, THEN determine nuclide's concentration by using the 'ViCi/ml for a single peak" calculation and add the nuclide and its concentration to the analysis portion of the printout.
- h. IF a photopeak is identified as a nuclide not included in the computer library, THEN contact Chemistry Management for guidance.
_____ 4.12.15 IF the computer printout is not available, THEN record the results of the spectral analysis and tritium analysis in the appropriate row of Items 13 and 14.
NOTE 4.12.16 The Chemistry "Tester" may sign the "Reviewed by" line on the printout if Chemistry Supervisor is not available.
4 12.16 1 IF the computer printout is available, THEN attach a copy of all of the analyses to this procedure. I Subsection 4.12 com pleted by __ / __j___
/7-nI Date
.1
/
69 DB-OP-03012 Revision 02 C-4 4.11.13 WHEN the release is completed, :
THEN terminate the release described by the procedure or MWO.
4.11.14 Record the release stop time, date and tank pressure in Item 7.
4.11.15 Calculate the total Release Time and Delta P from Items 6 and 7 AND record on Item 8.
4.11.16 Return this procedure to the Control Room.
I 4.11.17 Review operational portion of this procedure for completeness.
4.11.18 Return the procedure to the Chemistry Department for processing in accordance with Section 4.16.
Section 4.11 completed by Date
ma DB-OP-03012 Revision 02 C-4 I - 1 NOTE 4.12.14 If the computer system is not available, the the spectrum analysis is performed by hand using DB-CH-01801, Radiochemistry Gamma Spectral l
Analysis, for guidance. Pay particular attention to the spectrum and the following:
- a. Presence of isotopes determined in comparison to isotopes normally found by computer analysis of a gaseous release l gamma spectrum.
- b. Are all of the photopeaks shaped correctly, l are they irregular, bent or skewed in one direction?
C. Attach the Hand Calculation Sheets to this procedure.
4.12.14 Review the gamma spectral analysis computer printout, when available, for the following to ensure its correctness:
- a. The sample description includes the type of release and the assigned release number.
jgo ( b. The correct sample volume has been entered.
3{ c. All of the photopeaks identified have been matched with a known possible isotope from the current peak ID library or investigated.
9-J d. There is no indication of an out of energy calibration condition.
- e. There are NO isotopes indicated that due to decay time, type of release, or plant operational mode should not be present.
(Continued)
70 DB-OP-03012 Revision 02 C-3 NOTE 4.12 l Additional copies of attachments to document l
Action Items may be made as required.
4.12 Sampling and Analysis INITIALS IPa> 4.12.1 Upon receipt of this procedure from the Shift Supervisor, assign the next sequential release permit number from the Gaseous Release Permit Log, Attachment 3.
-... 41 I-
- 4. 12 .2 Record the date, type of release, and your name on the Gaseous Release Permit Log, Attachment 3.
X4 4.12 .3 Record the assigned permit number in Item 2.
-- D2 4.12.4 IF this is a WGDT release and both RE's 1822A and 1822B are INOPERABLE, THEN the ODCM Table 3-1 Action A requires that two independent samples are analyzed in accordance with ODCM Table 3-3 for analyses with each batch. To document this the person doing the independent sample analysis shall obtain a copy of this section of the procedure and attach the completed copy to the release package.
73 DB-OP-03012 Revision 02 C-4 (This page intentionally left blank.)
71 DB-OP-03012 Revision 02 NOTE 4.12.5 Special sampling techniques (air sampler, etc) may be required for releases with low pressures.
3 4.12.5 Sample the indicated type of release in Item 1 as follows:
NOTE 4.12.5.a A minimum purge time of at least 5 minutes is required when obtaining the sample. The bypass shall not be used around the sample station.
Purge shall be through the gas sample pressure container.
- a. WGDT, OTHER and ILRT - Refer to DB-CH-06002, Sampling System Nuclear Areas.
- b. Containment Purges or Pressure Reductions -
Refer to DB-CH-04004, Containment Atmosphere Sampling and Analysis.
I2 4.12.6 Complete Item 4.e when the sample is taken.
NOTE 4.12.7 II- - - ormal sample volume for the 12 cc gas vial is Ni I 1t. cc.
(-,-\ -D 4.12. 7 Prepare the required analysis samples.
72 DB-OP-03012 Revision 02 CAUTION 4.12.8 Maximum sample decay times are as follows:
e 12 cc gas vials - 60 minutes
- 4350 cc marinelli - 120 minutes.
Minimum sample count times are as follows:
e 12 cc gas vials - 5000 seconds at 3 cm e 4350 cc marinelli - 2000 seconds on the detector.
Perform a gamma spectral analysis in accordance with f 4.12.8 Perform a gamma spectral analysis in accordance with DB-CH-01801, Radiochemistry Gamma Spectral Analysis.
Performed by _ , -, X . \ _-C>- r\ < Date /^2r/
( 2 ) t
-11 a+/- 4.12.9 Perform a tritium ana ysis in accordance with DB-CH-01804, Tritium Determination.
Pertormed by Date tc-alm/
4.12.10 Record the results of b ltritium analysis on the gamma spec computer printout.
i <_ 4.12.11 IF two independent samples were analyzed AND the difference between nuclide concentration is greater than 25Z for nuclides with activities greater then 1.OE-4 pCi/cc, THEN contact Chemistry Management for resolution.
__ _ 4.12.12 Complete Item 4.f when all sample analysis are performed.
02 4.12.13 IF this release is for a WGDT, THEN verify the WGDT pressure is entered in Item 3.a.
I - 1,- i r,_-,
72 DB-OP-03012 Revision 02 CAUTION 4.12.8 Maximum sample decay times are as follows:
e 12 cc gas vials - 60 minutes s 4350 cc marinelli - 120 minutes.
Minimum sample count times are as follows:
- 12 cc gas vials - 5000 seconds at 3 cm e 4350 cc marinelli - 2000 seconds on the detector.
Perform a gamma spectral analysis in accordance with 4.12.8 Perform a gamma spectral analysis in accordance with DB-CH-01801, Radiochemistry Gamma Spectral Analysis.
Performed by _ 2111 ,
Is-A b Date 1 1,'r19.1 H a 4.12.9 Perform a tritium analysis in accordance with DB-CH-01804, Tritium Determination.
Performed by rD j
l f -
,v,5 _ __ Date i4 Oh&-l
/ ?
i1e 4.12.1 0 Record the results of the tritium analysis on the gamma spec computer printout.
TkZ 4.12.11 IF two independent samples were analyzed AND the difference between nuclide concentration is greater than 25% for nuclides with activities greater then 1.OE-4 yCi/cc, THEN contact Chemistry Management for resolution.
4.12.12 Complete Item 4.f when all sample analysis are performed.
4.12.13 IF this release is for. a WGDT, THEN verify the WGDT pressure is entered in Item 3.a.
71 DB-OP-03012 Revision 02 NOTE 4.12.5 Special sampling techniques (air sampler, etc) may be required for releases with low pressures. l 4.12.5 Sample the indicated type of release in Item 1 as follows:
1- - - - - - - - - - - - - - - - - - - - - - - - - - - -I NOTE 4.12.5.a A minimum purge time of at least 5 minutes is required when obtaining the sample. The bypass shall not be used around the sample station. l
[ Purge shall be through the gas sample pressure I container.
- a. WGDT, OTHER and ILRT - Refer to DB-CH-06002, Sampling System Nuclear Areas.
- b. Containment Purges or Pressure Reductions -
Refer to DB-CH-04004, Containment Atmosphere Sampling and Analysis.
3I1 4.12.6 Complete Item 4.e when the sample is taken.
NOTE 4.12.7 Normal sample volume for the 12 cc gas vial is 10 cc.
j jj 4 .12.7 Prepare the required analysis samples.
73 DB-OP-03012 Revision 02 C-4 (This page intentionally left blank.)
I
70 DB-OP-03012 Revision 02 C-3 NOTE 4.12 Additional copies of attachments to document Action Items may be made as required.
4.12 Samplinq and Analvsis INITIALS 4.12 .1 Upon receipt of this procedure from the Shift Supervisor, assign the next sequential release permit number from the Gaseous Release Permit Log, Attachment 3.
4 .12.2 Record the date, type of release, and your name on the Gaseous Release Permit Log, Attachment 3.
- 44 412.3 Record the assigned permit number in Item 2.
2 4.12.4 IF this is a WGDT release and both RE's 1822A and 1822B are INOPERABLE, THEN the ODCM Table 3-1 Action A requires that two independent samples are analyzed in accordance with ODCM Table 3-3 for analyses with each batch. To document this the person doing the independent sample analysis shall obtain a copy of this section of the procedure and attach the completed copy to the release package.
74 DB-OP-03012 Revision 02 I C-4 NOTE 4.12.14 l If the computer system is not available, the the spectrum analysis is performed by hand using DB-CH-01801, Radiochemistry Gamma Spectral Analysis, for guidance. Pay particular attention to the spectrum and the following:
- a. Presence of isotopes determined in comparison to isotopes normally found by computer analysis of a gaseous release gamma spectrum.
- b. Are all of the photopeaks shaped correctly, are they irregular, bent or skewed in one direction?
- c. Attach the Hand Calculation Sheets to this procedure.
I- - - - - - - - - - - - - - - - - - - - - - - - - - - -1 4.12.14 .Review the gamma spectral analysis computer printout, when available, for the following to ensure its correctness:
-i2fs- a. The sample description includes the type of release and the assigned release number.
2Xb. The correct sample volume has been entered.
All of the photopeaks identified have been matched with a known possible isotope from the current peak ID library or investigated.
- d. There is no indication of an out of energy calibration condition.
1i e There are NO isotopes indicated that due to decay time, type of release, or plant operational mode should not be present.
(Continued)
' w -- - Y-
69 DB-OP-03012 Revision 02 C-4 4.11.13 WHEN the release is completed, THEN terminate the release described by the procedure or MWO.
4.11.14 Record the release stop time, date and tank pressure in Item 7.
4.11.15 Calculate the total Release Time and Delta P from Items 6 and 7 AND record on Item 8.
4.11.16 Return this procedure to the Control Room.
4.11.17 Review operational portion of this procedure for completeness.
4.11.18 Return the procedure to the Chemistry Department for processing in accordance with Section 4.16.
Section 4.11 completed by Date
75 DB-OP-03012 Revision 02 TAOO-0315 4.12.14 (Continued)
NOTE 4.12.14.f I Pholtopeaks which, after visual inspection, are I not peaks or photopeaks with 50% error or greater are to be lined out and initialed. Other conjEirmed photopeaks are to be marked with nuc'lide's name.
I___'
L 3- f. For all unidentified photopeaks, identify those I
with errors less than 50%.
- g. IF other nuclides are identified from the evaluation of unidentified photopeaks which have NOT already been quantified, THEN determine nuclide's concentration by using the "pLCi/ml for a single peak" calculation and add the nuclide and its concentration to the analysis portion of the printout.
- h. IF a photopeak is identified as a nuclide not included in the computer library, THEN contact Chemistry Management for guidance.
X2Sf 4.12.15 IF the computer printout is not available, THEN record the results of the spectral analysis and tritium analysis in the appropriate row of Items 13 and 14.
NOTE 4.12.16 I The Chemistry "Tester" may sign the "Reviewed by" I linea on the printout if Chemistry Supervisor is I not available.
I__
4.12.16 IF the computer printout is available, THEN attach a copy of all of the analyses to this procedure.a Subsection 4.12 cornpleted by / - I Date (0
ok Ol DB-OP-03012 Revision 02 C-3 NOTE 4.14 l A hand calculation will normally be performed l only when the computer is out of service when release calculations are performed prior to the l release. The computer should be used for all l calculations on completed releases.
4.14 Hand Calculation INITIALS 4.14.1 IF this is a WGDT release AND BOTH RE's 1822A and 1822B are inoperable THEN the ODCM Table 3-1 Action A requires that two independent verifications of the release rate calculations be performed. To document this the person doing the independent verification shall obtain a copy of this section of the procedure and attachments and attach the completed section and attachments to the release package.
4.14.2 Calculate the release volume in cubic centimeters at standard pressure as follows:
- a. WGDT Releases (1013) x (P + 14.7) x (28317) 1013 x ( ) x 28317 14.7 14.7 cc =
P - WGDT pressure in PSIG
- b. Containment Release cc = (ft3) x (28317) = ( ) x (28317) =
ft3 - release volume in cubic feet from Item 3.b.
o 2.834 E6 ft3 for a Containment Purge o 4.39 E5 ft3 for a Containment pressure release based on fan capacity of 305 CFM for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
76 DB-OP-03012 Revision 02 TA99-1770 4.13 Computer Assisted Calculations INITIALS 4.13.1 IF the computer is not available for calculating release rates, THEN discard this section and GO TO Section 4.14.
OTHERWISE discard Section 4.14 and Attachments 6
through 8.
4.13.2 IF this is a WGDT release and BOTH REs 1822A AND 1822B are inoperable THEN the ODCM Table 3-1 Action A requires that two independent verifications of the release rate calculations be performed. To document this the person doing the independent verification shall obtain a copy of this section of the procedure and attach the completed section to the Release Package.
4.13.3 Run the RETSCode program as follows:
- a. Select Procedures
- b. Select Gases
- c. Select Batch release
- d. Select Release 4&LL e. Select New
- f. Enter Sample Date as Release Date g- Select Batch as Release Type
- h. Select Pre-Release as Status
- i. Select Source of Release j.- For Pressure entry
- 1. For WGDT, enter pressure from Item 3.a.
- 2. For Containment Purge, enter N/A
- 3. For Containment Pressure reduction, enter 1
- 4. For ILRT, enter pressure from item 3.a.
- 5. For Other, enter N/A (Continued)
80 DB-OP-03012 Revision 02 Alm- IF this release is due to ILRT, TA99-1770 I
4.13. 9 THEN mark Item 10 N/A.
4.13.10 Sign Item 4.g.
4.13.11 Verify and sign off Acceptance Criteria 5.1 4.13.12 Submit this procedure to the Radiation Protection for the required recommendation for release per Section 4.15.
Subsection 4.13 completed by &little Date e 0
77 DB-OP-03012 (Continued on page 77a) Revision 02 TA99-1770 I, 4.13.3 (Continued) g k. For volume entry
- 1. For WGDT, use calculated value
- 2. For Containment Purge, enter 2.834E+6
- 3. For Containment Pressure reduction, enter 4.39E+5
- 4. For ILRT, enter 2.834E+6
- 5. For Other, enter calculated value as follows:
A/AS a) Obtain tank or line pressure from Control Room.
b) Obtain tank or line volume from Control Room or Plant Engineering.
_ c) Determine "corrected volume" (Line/tank pressure +14.7) x line/tank volume (Line/tank pressure +14.7) x line/tank volume 14.7 S 1. Select yes for processed through Gaseous Radwaste UNLESS this is a ILRT.
- m. Select Sample Analysis J/ n. Enter nuclides and activities
-AL o. Select OK 6 p. Select Compute J X q. Select Save Jo r. Select Print (Continued) w
An DB-OP-03012 Revision 02 TA99-1770 NOTE 4.13.7 A Containment Purge is normally assigned a maximum purge time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during which a
conservative estimate of all of the airborne activity detected in the sample analysis is I released.
I
-Z// W4.13.7 IF the release is a Containment Purge, THEN enter the maximum purge time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in Item 10.b and the maximum purge rate (smallest release rate limit) in Item 10.a.
OTHERWISE mark this step and Items 10.a and 10.b N/A.
6L4 4 .13 .8 Attach printout of RETSCode to this procedure.
I I
77a DB-OP-03012 Revision 02 TA99-1770 I This page is intentionally left blank.
78 DB-OP-03012 Revision 02 TA99-1770 i
NOTE 4.13.4 The Radioactive Gaseous Batch release calculation program will now determine the allowable release rate based on the information provided.
4.13.4 Review the completed computer printout for agreement with the identified isotopes and associated values.
4.13.5 IF this is a WGDT release, THEN record the maximum allowable release rate in Item 9.a.
OTHERWISE mark this step and Item 9.a N/A.
NOTE 4.13.6 For WGDT releases the actual release rate will be less than or equal to the tenth value of the maximum release rate or 45 SCFM whichever is less.
I I I CAUTION 4.13.6 1 l IF the result is less than 1 SCFM, THEN the I I release should be terminated. I I I 4.13.6 IF this is a WGDT release, THEN divide the maximum release rate by ten and record the value or 45 SCFM, whichever is less, in Item 9.b.
OTHERWISE mark this step and Item 9.b N/A.
DAVIS-BESSE NUCLEAR POWER STATION JOB PERFORMANCE MEASURE WORKSHEET JPM NO.: Admin 4 Rev. 0 Page 1 of 7 TASK NO.: 334-011-05-0300; 334-004-05-0300; 334-005-05-0300 TASK DESCRIPTION: Perform an Off-Site Dose Calculation and Upgrade to a General Emergency K/A
REFERENCE:
XXX-GEN-2.4.41 2.3/4.1 APPLICABLE METHOD OF TESTING: Actual Performance Control Room Simulator Time Critical TIME FOR COMPLETION: 30 minutes APPLICABILITY: [J RO EX] SRO TASK STANDARDS:
Determine off-site TEDE dose rates and PARs.
Identify the proper EAL for upgrading.
REQUIRED MATERIALS:
RA-EP-01500, Emergency Classification RA-EP-02245, Protective Action Guidelines HS-EP-02240, Offsite Dose Assessments RA-EP-01900, General Emergency RA-EP-02110, Emergency Notification Offsite Dose Assessment Nomogram E-Plan Implementing Forms envelope GENERAL
REFERENCES:
RA-EP-01500, Emergency Classification HS-EP-02245, Protective Action Guidelines HS-EP-02240, Offsite Dose Assessments RA-EP-01900, General Emergency RA-EP-02110, Emergency Notification
JPM No Admin 4 Page 2 of 7 INITIAL CONDITIONS:
You are the Shift Supervisor.
A Site Area Emergency was declared 15 minutes ago based on EAL 2.A.4.
RA-EP-01800, Site Area Emergency, has been implemented and is complete up through Step 6.6. Step 6.7 is in progress.
INITIATING CUES:
You are to continue with Step 6.8 of RA-EP-1800.
DADS and SPDS are not available.
The following is an update of plant conditions. (Hand examinee cue sheet of plant conditions.)
JPM No Admin 4 Page 3 of 7 INITIAL CONDITIONS:
You are the Shift Supervisor.
A Site Area Emergency was declared 15 minutes ago based on EAL 2.A.4.
RA-EP-01800, Site Area Emergency, has been implemented and is complete up through Step 6.6. Step 6.7 is in progress.
INITIATING CUES:
You are to continue with Step 6.8 of RA-EP-1800.
DADS and SPDS are not available.
The following is an update of plant conditions:
CTMT pressure 20.1 psia CTMT temperature 2140 F CTMT RE 4596A/B 5000 R/hr CTMT RE 4597AA/BA (uCi/cc) Chl=1.7E-02 Ch2=2.2E-02 Ch3=5.OE-08 Ch4=5.3E-03 Ch5=6.lE-04 CTMT RE 4597AB/BB (uCi/cc) Chl=5.OE+01 Ch2=l.OE+00 Ch3=1.lE-06 Ch4=O.OE-OO Ch5=O.OE-OO RCS pressure 1000 psig and stable RCS temperature 350 0 F and stable Pressurizer level O inches RCS SCM 0F Incore thermocouples 800°F and stable HPI flow/line 250 gpm/line and stable LPI flow/line Ogpm/line Main Steam pressure 800 psig in both SGs and stable SG level 124 inches in both SGs and stable AFWPs Both running, each aligned to its own SG Station Vent RE 4598 AB/BB (uCi/c Chl=9.OOE-02 Ch2=9.OOE-02 Ch3=,2.56E-06 Ch4=O.OOE-0 Ch5=O.OE-OO Met Tower Data M006 Wind Speed 61:2' Elevation 2.5 mph MOOS Wind S peed 82'7' Elevation 3.5 mph M003 Wind D irectioia 612' Elevation 3100 M002 Wind D irectioia 827' Elevation 3550 M012 Ambien t Tempeirature 612' Elevation 750 MO11 Temper ature D:Lfferential 827'-612' -0.5° MO10 Temper ature D:Lfferential 917'-612' -0.9°
JPM No Admin 4 Page 4 of 7 PERFORMANCE INFORMATION NOTE: Critical steps denoted with a "C". Failure to meet any one of these standards for this item constitutes failure. Sequence is NOT critical unless denoted in the "Comments".
START TIME:
- 1. PERFORMANCE STEP: Determine offsite dose projection per HS-EP-02240.
STANDARD: Refer to HS-EP-02240, Offsite Dose Assessment, to determine TEDE rate using nomogram.
COMMENT: Hand a copy of the nomogram and HS-EP-02240 to the examinee.
PARs are to be made to offsite agencies along with the initial notification.
CUE: None.
SAT UNSAT
- 2. PERFORMANCE STEP: Plot Station Vent RE reading on Scale B.
STANDARD: Mark 9E-2 (8E-2 to lE-1) uCi/cc.
CUE: None.
SAT UNSAT
- 3. PERFORMANCE STEP: Plot Station Vent flowrate on Scale A.
STANDARD: Mark 146 KCFM.
CUE: None.
SAT UNSAT
- 4. PERFORMANCE STEP: Determine release rate on line between RE and flow reading.
STANDARD: Mark 6 Ci/sec release rate on scale C (5-7).
CUE: None.
SAT UNSAT
- 5. PERFORMANCE STEP: Determine stability class.
STANDARD: Mark Class E on scale 1.
CUE: None.
SAT UNSAT
JPM No Admin 4 Page 5 of 7
- 6. PERFORMANCE STEP: Plot wind speed.
STANDARD: Mark 2.5 mph (4-6) on Scale 2.
CUE: None.
- SAT UNSAT
- 7. PERFORMANCE STEP: Determine X/Q on line between stability class and wind speed.
STANDARD: Mark 2.2E-4 sec/M 3 X/Q on scale 3 (1E-4 to 4E-4).
CUE: None.
SAT UNSAT
- 8. PERFORMANCE STEP: Determine TEDE rate at 0.75 mi on line between
.C. X/Q and release rate.
STANDARD: Mark 2 Rem/hr (1-4) on Scale 4.
CUE: None.
SAT UNSAT
- 9. PERFORMANCE STEP: Determine TEDE rates at 2, 5 and 10 by dividing 0.75 mile valve by 5, 15 and 40.
STANDARD: Record 0.4 Rem/hr (0.2-0.8) for 2 mile, 0.133 Rem/hr (0.07-0.27) for 5 mile and 0.05 Rem/hr (0.025-0.1).
COMMENT: 2 mile value critical if 0.75 mile value is 2.5 Rem/hr or more.
CUE: None.
SAT UNSAT
- 10. PERFORMANCE STEP: Using RA-EP-02245, determine the affected subareas
.C. using Attachment 3, using 2-hour duration.
STANDARD: Determine affected subareas to be 1, 2, 6, 7, 8, 9, and 12.
COMMENT: Hand a copy of RA-EP-02245 to examinee.
CUE: None.
SAT UNSAT
JPM No Admin 4 Page 6 of 7
- 11. PERFORMANCE STEP: Determine evacuation of subareas of 1 Rem or more
.C .per Attachment 2.
STANDARD: Determine evacuation of Subareas 1 and 12 for 3100 wind direction.
COMMENT: For 2 mile TEDE of 1 Rem or more, also determine evacuation of Subareas 2 and 6.
CUE: None.
SAT UNSAT
- 12. PERFORMANCE STEP: Classify event per RA-EP-01500, Emergency
.C .Classification.
STANDARD: Event classified as a General Emergency, per EAL 6.D.6 or 9.5.
CUE: None.
SAT UNSAT TERMINATING CUES: This JPM is complete.
END TIME
JPM No Admin 4 Page 7 of 7 VERIFICATION OF COMPLETION Operator Evaluator SSN Date License []RO []SRO Validated Completion Time: minutes Actual Completion Time: minutes Acceptable Progress Maintained: Yes No N/A Result: [ I SATISFACTORY [ ] UNSATISFACTORY NOTE: An "Unsatisfactory" requires Comment and will require subsequent remedial training.
Comments/Feedback:
Evaluator's Signature Date