Procedure AP/1/A/5500/31, Estimate of Failed Fuel Based on I-131 ConcentrationML20080G515 |
Person / Time |
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Site: |
Catawba |
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Issue date: |
02/07/1984 |
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From: |
DUKE POWER CO. |
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To: |
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Shared Package |
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ML20080G507 |
List: |
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References |
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RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-TM AP-1-A-5500-31, NUDOCS 8402130422 |
Download: ML20080G515 (8) |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
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Restrictive Surveillance Requirements ML20237B6241998-08-14014 August 1998 Proposed Tech Specs 4.6.5.1.b.2 & 4.6.5.1b.3 Relating to Ice Condenser Ice Bed Changing Portion of Surveillances Pertaining to Lower Inlet Plenum Support Structures & Turning Vanes from 9-month Frequency to 18-month Frequency ML20237B5751998-08-12012 August 1998 Proposed Tech Specs 4.6.5.1b.2 Re Ice Condenser Sys Components W/Respect to Accumulation of Frost or Ice ML20237A6571998-08-0606 August 1998 TS Page 3/4 8-9 Re Notice of Enforcement Discretion Request from Enforcing TS Surveillance Requirement 4.8.1.1.2i.2 ML20237A9341998-08-0606 August 1998 Proposed Tech Specs,Deleting SR 4.8.1.1.2i.2 for Pressure Test of DG Fuel Oil Sys ML20237A0361998-08-0505 August 1998 Suppl 8 to Improved TS (Its),Combining Units ITS Pages to Facilitate Ease of Use & Significantly Reduce Vol of Paper That Must Be Processed & Controlled ML20236U1531998-07-22022 July 1998 Proposed Revised Improved Tech Specs,Implementing W Fuel as 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[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20211A9881999-08-18018 August 1999 Rev 5 to DPC Nuclear Security Training & Qualification Plan ML20210N9641999-07-26026 July 1999 Revised Catawba Nuclear Station Selected Licensee Commitments Manual ML20211C3731999-07-26026 July 1999 Revs to Catawba Nuclear Station Selected Licensee Commitments Manual & List of Effective Pages ML20210A5911999-06-10010 June 1999 Revised Catawba Nuclear Station Selected Licensee Commitments Manual ML20216D4061999-06-10010 June 1999 Revised Catawba Nuclear Station Selected Licensee Commitment Manual, List of Effective Pages ML20211C3751999-05-19019 May 1999 5 to Catawba Nuclear Station Units 1 & 2 Pump & Valve Inservice Testing Program. 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ML20045F6771993-06-24024 June 1993 Revs to List of Effective Pages 1 & 5 & Chapter 16.11,pages 16.11-32,33 & 34 of Selected Licensee Commitments Manual ML20045E8251993-06-23023 June 1993 Revised Selected Licensee Commitments Manual ML20127E1961993-01-0707 January 1993 Revs to Selected Licensee Commitments Manual ML20127C4341992-12-29029 December 1992 Revised Selected Licensee Commitments Manual ML20126E8111992-12-21021 December 1992 Revised Selected Licensee Commitments Manual ML20126E0831992-12-16016 December 1992 Revised Selected Licensee Commitments Manual ML20116B3251992-10-21021 October 1992 Revised Selected Licensee Commitments Manual ML20106E2121992-10-19019 October 1992 Revised Selected Licensee Commitments Manual 1999-08-18
[Table view] |
Text
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PAGE NO.
CNS AP/1/A/5500/31 TABLE OF CONTENTS t
Pace No.
\
l A. Purpose 1 B. Symptoms 1 C. Immediate Actions 2 D. Subsequent Actions 2 Endosure 1 5 Enclosure 2 6 l
l L
i
. 8402130422 840207 PDR ADOCK 05000413 A PDR 7.--.-.,..._ ..
f
. 'Fortn 34913 (8 82)
Q, h PAGE NO.
CNS ESTIMATE OF FAILED FUEL AP/1/A/5500/31 BASED ON 1-131 CONCENTRATION 1 1
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED A. PURPOSE The purpose of this procedure is to provide a means of determining the quantity of failed fuel based on 1-131 Concentration in the NC System.
B. SYMPTOMS
- 1. Any of the follow;ag EMF's in alarm:
- a. 1 EMF 48 " Reactor Coolant Monitor"
- b. 1 EMF 18 " Reactor Coolant Filter 1 A"
- c. 1 EMF 19 " Reactor Coolant Filter 1B"
- 2. Any condition in which the operator suspects failed fuel or * '
want an estimate of the amount of failed fuel.
I e i
3
_-.~.~....-._...---Aw
-.--~..n,-- .
-.n. .....e..,__..---,. .
. Form.34013 (8-8h I PAGE NO.
CNS ESTIMATE OF FAILED FUEL AP/1/A/5500/31 BASED ON l-131 CONCENTRATION 2 i
l RESPONSE NOT OBTAINED ACTION / EXPECTED RESPONSE C. IMMEDIATE ACTIONS
- 1. Have Chemistry Obtain A Sample Of The NC System Coolant and determine temperature of sample.
D. SUBSEQUENT ACTIONS
- 1. Have Chemistry Sample For 1-131, Krypton, Xenon, Cesium, Ruthenium And Tellurium.
- 2. Record Concentrations Of Above Radionuclides And Sample Temperature on Enclosure 1.
- 3. If I-131 Concentration is Greater Than 300 uCl/ml, Refer To RP/1/A/5000/01
, (EMERGENCY CLASS DETERMINATION).
- 4. If lodine is Present And The Unit is in A Normal Operational Mode, Go To 8.
- 5. If Krypton Or Xenon Are Present But Only Small Amounts Of Cesium And An Abnormal Transient Or Suspected Mechanical induced Failure (i.e. , Loose Part) Has Occurred, Go To 11.
- 6. If Krypton Or Xenon And Large Concentrations Of Cesium Are Present But Ruthenium And Tellurium Are Not And Incore Thermocouples Have Read High For A Short Period Of Time, Go To -13.
- 7. If All Of The Above Radionuclides Are Present And incore Thermocouples Are High For A Long Period, Go To 15.
- 8. Determine The X And Y Correction Factors From Enclosure 2.
r_
..w.=~ ..-.......w....-.....-- . - . . -....--%,.-..-.~. . _ . . -
' . __ _ _ - - _ _ - _ _ _ - _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ __._m_______. _ _ _ _ _ _ _ _ _ _ _ . _
Form.14913 (8%2) .
h .
/ PAGE No.
CNS ESTIMATE OF FAILED FUEL AP/1/A/5500/31 BASED ON 1-131 CONCENTRATION 3 ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 9. Calculate Tite Amount Cf Failed Fuel Using The Following:
Number of _ Measured 1-131 Failed Pins Concentration uCi/mi ' X
( )* *
+
Percent : Measured 1-131 Failed Pins Concentration uCi/mi
= ( )- . .
+
- 10. Go To 16.
- 11. Determine The X And Y Correction Factors From Enclosure 2.
Calculate the , amount of failed fuel using the following:'
- Number of = Measured 1-131 2
Failed Pins Concentration uCi/mi ' X
= ( )* _ +
Percent : Measured 1-131 Failed Pins Concentration uCi/ml
- ( )* *
+
- 12. Go To 16.
' ~
Form'34913 (8-82) hi) ,
PAGE NO CNS ESTIMATE OF FAILED FUEL AP/1/A/5500/31 BASED ON 1-131 CONCENTRATION 4 ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 13. Determine The X And Y Correction Factors From Enclosure 2.
Calculate the amount of failed fuel using the following:
Number of = Measured 1-131 Failed Pins Concentration uCi/mi
= ( ) __ * +
Percent : Measured 1-131 Failed Pins Concentration uCi/mi
( )* __,
- 14. Go To 16.
- 15. Determine The X And Y Correction Factors From Enclosure 2.
Calculate the amount of failed fuel using the following:
Number of , Measured 1-131 Failed Pins Concentration uCi/mi
- ( )* *
+
Percent : Measured 1-131 Failed Pins Concentration uCl/ml
= ( )* *
- 16. Refer To Tech Spec 3.4.8 a. Refer to appropriate Tech And Ensure 1-131 Activity Spec Action Statement.
Is Within Guidelines.
- 17. Inform The Shift Supervisor And Performance Section Duty Engineer of The Results Of This Procedure.
-END-w --9-mem m we -~ww c-m e w e am _ n ,-,..m,.-, . . . . , . - - . .. . ,..w , . , , , , _ , ,
.s
', Ftrm 34912 (8-82) h ;,
PAGE NO.
CNS AP/1/A/5500/31 ENCLOSUREI 5 l-131 Concentration uCi/mi uCi/ gram Concentration Initial /Date Krypton /
Xenon /
Cesium /
Ruthenium /
Tellurium /
Sample Temperature /
1 e
>"'-Wa*- p 5-***= % 4 .%.. . . . - - %,. _.m. .m., .,,,,,__,m,, , , . . , , , ,
mm--. _. _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ __ _
Form 14912 (6-82) *
@' @O L- 0 v + j PAGE NO.
CNS AP/1/A/5500/31 ENCLOSURE 2 6
- 1. X Determination NC SAMPLE TEMPERATURE F 80 90 100 100 .996 .998 1.00 150 .983 .985 .987 NC 200 .966 .968 .970 250 .945 .947 .949 System 300 .921 .923 .924 350 .894 .895 .897 Temperatu re 400 .862 .864 .865 450 .827 .828 .830
- F 500 .787 .788 .790 550 .739 .740 .741 560 .728 .729 .731 570 .717 .718 .719 580 .706 .708 .708 590 .603 .694 .695 600 .680 .681 .683
- 2. Y Determination if power change is less than 10% within 22 days Y= 100
% F.P. at time of failure Other times Y= 100 OP (e M)+ NP (1 - e-th y Where: .
Y = Correction Factor OP = The % Full Power Before The Power Change NP = The % Full Power After The Power Change At Which Time The Fuel Failurs Has Occured
_.3
o
. Form 349b (8-82) -
- n. -
h ,',
PAGE NO.
CNS .
AP/1/A/5500/31 ENCLOSURE 2 7 I
3 = Decay Constant For I-131 --- 0.0864 day 'I t = One Half The Time To Make The Power Change Plus The Time After The Power Change Until Damage is Suspected. (in Days) i.e. 2 Hours For Power Change And 16 Hours To Damage.
t = 2 + 16 = 17 Hours = .708 Days 2
, 1 .
J
+++w.. a *. e.=.w.o== -, m
-me-m
- w- *-ee - * + = + = -* *= * -= = * * * *--N