ML20137L689
| ML20137L689 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 11/15/1985 |
| From: | MISSISSIPPI POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20137L677 | List: |
| References | |
| TASK-2.B.3, TASK-TM 08-S-03-17, 8-S-3-17, TAC-60187, NUDOCS 8512030511 | |
| Download: ML20137L689 (34) | |
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. . PLANT OPERATIONS MANUAL (L/ Volume 08 08-S-03-17 Section 03 Revision: 6 J
CHEMISTRY PROCEDURE CORE DAMAGE ESTIMATION SAFETY RELATED A A/ A /u jj2) r Prepared: . v/Ar e ' /> %' Reviewed: / v/ / r_ , d. #- Tech'nical R ' 'ew ~ T .
" Director, Quality Assurance Approved: _ /[
stry Rad ti r' Control Superintendent Concurre ce: l b { lb dim Pla*nt Manageri epd'ratb" ' List of Effective Pages: l gage 1-4 Attachments I-XIII dAf tiY EVALUAIl0N APPLICABILITY REVW List of TCN's Incorporated: Yes No l / I (1) Change to Facility as Dese. In FSAR Revision TCN No. (2) Change to Procedure as Dese. In FSAR - (3) Test or Experiment not Desc. In FSAR - 0 None (4) Change 10 Tech. Specs. / (If Yes, perform 10CFR50.59 Safety Eval) 2 N 3 None ENVIRONMEN1 AL EVALUAT10N APPLICABILITY REVIEW (1) Cliange to Environmental Protection Plan ,/ r 5 (2) Will or may effect environment / 6 None es12030811 e51122 (lt Yes, perform Environmental Eval) PDR ADOCK 05000416 I" " -
~
08-S-03-17 CV & CON i <
,', GR$ND GULF NUCLEAR STATION CHEMISTRY PROCEDURE l
Title:
Core Damage Estimation lNo.: 08-S-03-17 l Revision: 6lPage: 1 l l l ! l
,q l V
1.0 PURPOSE-The purpose of this instruction is to estimate the degree of reactor core damage following a major reactor accident. Core damage is estimated using 1) measured fission product concentrations in primary system water and gas samples, 2) isotope ratios and the ptesence of low volatile elements, 3) measured containment atmosphere hydrogen concentration, 4) measured containment atmosphere radiation level, 5) and other plant indicators. 2.0 RESPONSIBILITIES 2.1 The Shift Superintendent or Emergency Director is responsible for requesting the initiation of this procedure and for specifying the time interval between each assessment of the core damage. 2.2 The Chemistry Supervisor will perform the initial calculations and provide the attached data and calculation sheets to the Plant Chemist as soon as available. 2.3 The most Senior Laboratory Chemist on-site will perform the isotopic analyses with another qualified chemist acting as monitor. (O
j 2.4,- The Plant Chemist will provide the Shift Superintendent or Emergency
/ Director with the estimated degree of core damage as soon as the I information is available.
3.0 REFERENCES
3.1 BWROG - 8324, June 17, 1983, BWR Owners' Group, Transmittal of Generic Procedures for Estimation of Core Damage using Post-Accident Sampling *
. System.
3.2 Chetistry Guide to Post-Accident Sampling, Chemistry Instruction l L 08-S-04-950. 3.3 Description of GGNS-1 Core Damage Estimate Procedure, April, 1975 (provides bases of this procedure). - 4.0 A'ITACHMENTS 4.1 Attachment I - Reactor Power History Data 4.2 Attachment II - Measured Fission Product Concentrations 4.3 Attachment III -Normalized I-131 Concentration 4.4 Attachment IV - Normalized Cs-137 Concentration l 4.5 Attachment V - Normalized Xe-133 Concentration 08-S-03-17 TEXT
i' GIU.ND GULF NUCLEAR STATION CHEMISTRY PROCEDURE l
Title:
Core Damage Estimation lNo.: 08-S-03-17 l Revision: 6lPage: 2 l 1 4.6 Attachment VI - Normalized Kr-85 Concentration 4.7 Attachment VII - Core Damage Estimate from Fission Product Concentration 4.8 Attachment VIII - Isotope Ratios 4.9 Attachment IX - Containment Hydrogen Concentration 4.10 Attachment X - Containment Radiation Level 4.11 Attachment XI - Other Plant Indicators Data , 4.12 Attachment XII - Estimate of Core Damage 4.13 Attachment XIII - Representative Samples of Core Conditions during an accident 5.0 DEFINITIONS . 5.1 Core Damage Assessment Categories Categories Degree of Degradation Significant Parameters j1.NoFuelDamage 1% Clad Failure None r
- 2. Initial Clad 1-10%' Clad Failure Clad Rupture with Failure Fuel-Clad Gap Release
- 3. Intermediate 10-50% Clad Failure of Kr, Xe, and I Clad Failure
- 4. Major Clad 50% Clad Failure Failure
- 5. Initial Fuel 10% Pellet Overheating Diffusion of Fission Overheating Products through
- 6. Intermediate 10-50% Pellet Overheating Fuel Pellet and Fuel Overheating
- 7. Major Fuel 50% Pellet Overheating release into the overhearing Coolant. Oxidation of Cladding Releases Hydrogen
- 8. Initial Fuel 10% Fuel Melt Melting of Fuel and Melt Clad, Fuel Fragmentation,
- 9. Intermediate 10-50% Fuel Melt Release of Sr, Ba, Fuel Melt La, and Ru into the
- 10. Major Fuel Melt 50% Fuel Melt Coolant t
08-S-03-17 TEXT
GRAND GULF NUCLEAR STATION CHEMISTRY PROCEDURE l
Title:
Core Damage Estimation lNo.: 08-S-03-17 l Revision: 6lPage: 3 l l l 1 l l
,o U
5.2 Capacity Factor = Energy generated over specified time period (MWth-days) (3833 MWt) (Time period, days) 5.3 Core exposure is defined to occur when the reator vessel water level drops below the top 2/3 of the fuel. 6.0 DETAILS 6.1 Core damage is suupected or has occurred. 6.2 Shift Superintendent or Emergency Director has direci.eu that a core damage assessment be performed. 6.3 Approximately 5 copies of Attachments I through XII of this procedure should be available. 6.4 The Shift Superintendent or Emergency Director should be kept updated of all progress related to this procedure. 6.5 Good ALARA practices will be used during the performance of all aspects of this evolution. O 6.6 The assessment of core damage obtained by using this procedure is only an v ; estimate. Specific conditions must be considered at the time of each [ estimate. It is expected that these estimates will be conservative. 6.7 FISSION PRODUCT CONCENTRATION: 6.7.1 Determine the reactor power history by completing Attachment I. A capacity factor of 0.7 may be used until suff".cient power history data is available. 6.7.2 The measured fission product concentration data are entered on Attachment II as specified in the Chemistry Section Instruction 08-S-04-950. In general, an isotope concentration should be entered for the following sampling locations: drywell atmosphere, containment atmosphere, suppression pool, and either jet jump (preferred) or RHR system (if jet jump sample is unavailable). However, Attachment XIII can bc used to eliminate sampling at some locations, if desired, such that an isotope concentration of zero would be entered on Attachment II for that location. (Note: Measurements of Js-137 and Kr-85 activities are not very likely until the reactor has been shutdown for longer than a few weeks and n.ost of the shorter-lived isotopes have decayed.) O V 08-S-03-17 TEXT
G' RAND GULF NUCLEAR STATION CHEMISTRY PROCEDURE l
Title:
Core Damage Estimation lNo.: 08-S-03-17 l Revision: 6lPage: 4 l l I I I I j, 6.7.3 Determine the normalized measured fission product concentration as follows.
- a. Decermine the normalized fission product concentration of
. I-131 by completing Attachment III.
- b. DeterminethenoNmalizedfissionproductconcentrationof Cs-137 by completing Attachment IV.
- c. Determine the normalized fission product concentration of Xe-133 by completing Attachment V.
- d. Determine the normalized fission product concentration of Kr-85 by completing Attachment VI.
6.7.4 Complete Attachment VII to obtain the estimated degree of core damage based on the measured fission product concentrations. 6.8 FISSION PRODUCT RATIOS 6.8.1 If data was recorded in Attachment II for I-133 or 135, complete Attachment VIII. O 6.9', HYDROGEN CONCENTRATION 5 6.9.1 Complete Attachment IX to estimate the degree of core damage based on the measured containment or drywell hydrogen concentrations. 6.10 CONTAINMENT RADIATION LEVEL 6.10.1 Complete Attachment X to obtain the core damage estimate based on the measured containment radiation level. 6.11 OTHER PLANT INDICATORS 6.11.1 Complete Attachment XI to obtain other indications of core l damage. 6.12 CORE DAMAGE ESTIMATE 6.12.1 Complete Attachment XII and use the results to interpret the degree of core damage that has occurred. Notify plant management. ! 7.0 DOCUMENTATION / CORRECTIVE ACTION Document results of analysis performed under purview of this directive on the
- s,)
{T data sheets provided.
'08-S-03-17 TEXT
i a
-CRAND GULF NUCLEAR STATION . CHEMISTRY PROCEDURE l 08-S-03-17 Revision 6
(~* l Attachment I Page 1 of 2 ( l HXREF/MDOCNO lPage l , I I l l l ATTACHMENT I: REACTOR POWER HISTORY DATA Part A: Date/ Time of Reactor Shutdown Date/ Time = [I.A] Part B: Initial Estimate of Representative Power
- 1. Average capacity factor for last 3 years * = (fraction) = [I.B.1]
)'
- 2. Average capacity factor for last 30 days of operation prior to reactor shutdown = (fraction) = [I.B.2]
Part C: Detailed Power History I When time permits and data is available, complete Table I-1 to yield a more accurate representation of power histroy than that determined in Part B above.
- until adequate power history data is available, a capacity factor of
,g') 0.7 may be used to normalize values.
4 1 1 08-S-03-17 ATT I O
+ ~ ...__-m .-_,_,-._----m... , _ - - m m. _rs. , _ . - . - _ ,,--_.-._-_.,,_._,,y . --....-.- -----,m . - - - - - . .
CHEMISTRY PROCEDURE GRAND GULF NUCLEAR STATION l 08-S-03-17 Revision 6l l Attachment I Page 2 of 2 l l MXREF/MDOCN0 l Page l I I ATTACHMENT I Cont'd TABLE I-1: REACTOR POWER HISTORY DATA Cont'd Pj(1-e -AiTj )e AiT3 . OPERATION AVERAGE POWER, DURATION OF OPERATING T.* I-131 Cs-137 Xe-133 Kr-85 PERIOD, J* Pj, (MWth) ** PERIOD, Tj (days) (da}s)*** (A=0.086) (A6.29E-5) (A=0.132) (A=1.77E-4) Sum: _1095 3651(1-e A)/ Sum: [I.C.1] [I.C.2] [I.C.3] [1.C.4] **** Prepared by: Date/ Time Reviewed by: Date/ Time NOTES:
- Specify the dates (both starting and ending) of each operation period, beginning with the present and moving backwards in time.
** In each period, the variation of steady power should be limited to + 20%.
*** Tj* is the time between the end of operating period j and the current reactor shutdown.
*'*** These fission product correction factors are used in this procedure. They are based on the following formula:
Correction Fac*or = 3651 MWth(1-e-1095A) I Pj (1-e- d)e" l , unitless 08-S-03-17 ATT I
GRAND GULF NUCLEAR STATION CHEMISTRY PROCEDURE l 08-S-03-17 Revision 6l l Attachment II Fage 1 of 1 l l MXREF/MDOCNO Page l l l ATTACHMENT II: MEASURED FISSION PRODUCT CONCENTRATIONS Complete the following table utilizing the methods described in Reference 3.2. Conditons At Conditions Time Permitting, Determine SAMPLING sampling of Sample MEASURED FISSION PRODUCT CONCENTRATIONS the Following Concentrations LOCATION Locations T2 P2 T1 P1 TEMP PRESS TEMP PRESS I-131 Cs-137 Xe-133 Kr-85 I-133 I-135 ( F) (PSIA) ( F) (PSIA) Drywell pCi/ml pCi/ml Atmosphere F psia F psia Date/ Time Date/ Time Containment
~
pCi/ml pCi/ml Atmosphere F psia F psia Date/ Time Date/ Time Jet (Preferred) pCi/ml pCi/ml pCi/ml pCi/ml Pumps Date/ Time Date/ Time Date/ Time Date/ Time RHR Circle Train pCi/ml pCi/ml System That Was Sampled: (Only if jet A or B Date/ Time Date/ Time pump sample unavailable) Suppression pCi/ml pCi/ml Pool Date/ Time Date/ Time Prepared by: Date/ Time:
- Reviewed by: Date/ Time:
08-S-03-17 ATT II O O O
GRAND GULF NUCLEAR STATION' CHEMISTRY PROCEDURE
- a >
l 08-S-03-17 Revision 6 l l Attachment III Page 1 of 2 l MXREF/MDOCN0 l Page
.- ATTACHMENT III: NORMALIZED I-131 CONCENTRATION Part A: Decay Time Date/ time of I-131 samples , .- (from Attachment II)
Date/ time of reactor shutdown = (from Attachment I) Time (days) between reactor shutdown and I-131 sample time = days [III.A] Part B: Mass-Averaged I-131 Measurement
- 1. Measured I-131 concentrations from Attachment II:
I-131 concentration from jet pumps or RHR System = pCi/ml [III.B.1] I-131 concentration from suppression pool = pCi/ml [III.B.2] 2-
- 2. Calculate mass-averaged I-131 measurement:
Mass-averaged I-131 measured concentration = .06*III.B.1+.94*III.B.2
= . 06* + 94*.
= pCi/ml [III.B.3]
Part C: ,/ Decay correction e(.086)(III.A)= [III.C], Unitiess
,(.086)( days)=
[III.C] ,
; Part D: Fission Product Inventory Correction
- 1. Initial estimate (using Part B of Attachment I) 1.03 = [III.D.1]
(I.B.2) , 1.03 = [III.D.1) = ~ ( )
- 2. Detailed calculation (only if Part C of Attachment I is complete) 1.0 = [III.D.2] =
(I.C.1) III.D.1 and III.D.2 should agree within approximately 30%. If not, l recheck the calculations of I.C.1 in Attachment I.
- s i
08-S-03-17 ATT III a
-T F - = 'a--- --- w y v -v - - = * + - " - - - - - - - - - * - - - --+en .
w-s-erc-- *-e- ------w ,.--w------+ - - - - - - - - - - - -c+
GRAND GULF NUCLEAR STATION CHEMISTRY PROCEDURE l 08-S-03-17 Revision 6 l l Attachment III Page 2 of.2 l l MXREF/MDOCN0 l Page l l l ATTACHMENT III: NORMALIZED I-131 CONCENTRATION Cond
. Part E: Normalized I-131 Concentration III.B.3 (pCi/ml) * (III.C) * (III.D.1 ,.1,,05 = [pCi/ml] = [III.E]
or III.D.2 (preferred)
* *
- 1.05 = [III.E]
Prepared by: Date/ Time Reviewed by: Date/ Time O . i O . 08-S-03-17 ATT III
GRAND GULF NUCLEAR STATION CHEMISTRY PROCEDURE l 08-S-03-17 l Revision 6 l l Attachment IV l Page 1 of 2 l f l MXREF/MDOCN0 l Page l I I ATTACHMENT IV: NORMALIZED Cs-137 CONCENTRATION Part A: Decay Time Date/ time of Cs-137 samples , . , , = (from Attachment II) Date/ time of reactor shutdown = (from Attachment I) Time (days) between reactor shutdown and Cs-137 sample time = days [IV.A]
'Part B: Mass-Averaged Cs-137 Measurement
- 1. Measured Cs-137 concentrations from Attachment II:
Cs-137 concentration from jet pumps or RHR System = pCi/ml [IV.B.1] Cs-137 concentration from suppression pool = pCi/ml [IV.B.2]
- 2. Calculate mass-averaged Cs-137 ineasurement:
Mass-averaged Cs-137 measured concentration = .06*[IV.B.11 +.94*[IV.B.2]
= .06* +.94* ']>
N ; = pCi/ml [IV.B.3] Part C: Decay Correction e(6.29x10-5)(W. A)= [IV.C] , e(6.29x10-5)( days)= [IV.C] Part D: Fission Product Inventory Correction
- 1. Initial estimate (using Part B of Attachment I)
.95 = [IV.D.1]
(I.B.1)
.95 = [IV.D.1]
( )
- 2. Detailed calculation (only if Part C of Attachment I is complete) 1.0 = [IV.D.2]
(I.C.2) 1.0 = [IV.D.2] ,o ( ) 5
'/ IV.D.1 and IV.D.2 should agree within approximately 30%. If not, recheck the calculations of I.C.2 in Attachment I.
08-S-03-17 ATT IV
GRAND GULF NUCLEAR STATION CHEMISTRY PROCEDURE , l 08-S-03-17 Revision 6 l l Attachment IV Page 2 of 2 l p l MXREF/MDOCNO l Page l V I - 1 ATTACHMENT IV: NORMALIZED Cs-137 CONCENTRATION Cont'd 4 Part E: Normalized Cs-137 Concentration ' IV.D.1 Measured Mass-Average Cs-137 concentration * (IV.C)
- or
- 1.05 = [IV.E]
1, from IV.B.3 (pCi/ml) IV.D.2 i (preferred) 4 pCi/ml [IV.E]
* *
- 1.05 =
Prepared by: Date/ Time Reviewed by: Date/ Time i O . . i f i ,O i 08-S-03-17 ATT IV
~. . - - . . - .
.' GhAND GULF NUCLEAR STATION CHEMISTRY PROCEDURE l 08-S-03-17 Revision 6 l l Attachment V Page 1 of 2 l
; l MXREF/MDOCN0 l Page l
\ ; l l ATTACHMENT V: NORMALIZED Xe-133 CONCENTRATION Part A: Decay Time Date/ Time of Xe-133 samples = (from Attachment II)
Date/ time of reactor shutdow'n= (from Attachment I) Time (days) between reactor shutdown and Xe-133 sample time = dajs [V.A] Part B: Temperature and Pressure Difference Correction for Drywell Atmosphere P2 * (Tt + 460) = [V.B] Pt * (T2 + 460) ( psia) * ( F + 460) = [V.B] ( psia) * ( *F + 460) (P1 , Tt , P2 , T2 are the drywell conditions from Attachment II; if pressure and temperature data are not available, then V.B = 1.0.) Part C: . Temperature and Pressure Difference Correction for Containment Atmosphere
.P2 * (Tt + 460) = [V.B]
1
/Pt * (T2 + 460)
( psia) * ( *F + 460) = [V.C] ( psia) * ( F + 460)~ (P1 , T 1, P ,2 T2 are 'he containment conditions from Attachment II; if pressure and tempera u re data are not available, then V.C = 1.0.) Part D: Volume-Averaged Xe-133 Concentration with semperature/ Pressure Correction
- 1. Measured Xe-133 in drywell
= pCi/ml (from Attachment II) = [V.D.1]
- 2. Measured Xe-133 in containment
= pCi/ml (from Attachment II) = [V.D.2]
- 3. Volume-Averaged Xe-133 with temperature / pressure correction =
[V.D.1] * [V.B] * [.16] + [V.D.2] * [V.C] * [.84] ( x x .16) + ( x x .84) = pCi/ml [V.D.3] Part E: Decay Correction e(.132)(V.A) = [V.E]
,(.132)( days)
= [V.E] =
iO 08-S-03-17 ATT V
- GRAND GULF NUCLEAR STATION CHEMISTRY PROCEDURE l 08-S-03-17 Revision 6 l l Attachment V. Page 2 of 2 l l MXREF/MDOCN0 l Page O
l i i ATTACHMENT V: NORMALIZED Xe-133 CONCENTRATION Cont'd Part F: Fission Product' Inventory Correction
- 1. Initial estimate (using Par,t B of Attachment I) 0.97 = [V.F.1]
(I.B.2) 0.97 = [V.F,1] ( )
- 2. Detailed calculation (oni.y if Part C of Attachment I is complete) 1.0 = [V.F.2]
(I.C.3) 1.0 = [V.F.2] l ) V.F.1 and V.F.2 should agree within approximately 30%. If not, recheck the calculations of I.C.3 of Attachment I. Part G: [NormalizedXe-133 Concentration [V.D.3,pci/ml] * [V.E.]
- V.F.1 or V.F.2 (preferred)
- 1.18 = [V.G]
pCi/ml [V.G.]
* *
- 1.18 =
Prepared by Date/ Time
. Reviewed by Date/Tima
\.- . V' e 08-S-03-17 AIT V
v
." GRAND GULF NUCLEAR STATION CHEMISTRY PROCEDURE ~ '
l 08-S-03-17 Revision 6 l l Attachment VI Page 1 of 2 l rm l MXREF/MDOCN0 l Page l () i I ATTACHMENT VI: NORMALIZED Kr-85 CONCENTRATION . Part A: Decay Time Date/ Time of Kr-85 samples = (from Att chment II) Date/ time of reactor shutdown = (from Attachment I) Time (days) between reactor shutdown and Kr-85 sample time = days [VI.A] Part B: Temperature and Pressure Difference Correction for Drywell Atmosphere P2 * (Tt + 460) = [VI.B] Pt * (T2 + 460) ( psia) * ( *F + 460) = [VI.B] (_ psia) * ( F + 460) (P , T t, P ,2 T2 are the drywell conditions from Attachment II; if t pressure and temperature data are not available, then VI.B = 1.0.) Part C: Temperature and Pressure Difference Correction for Containment Atmosphere ,rN k) .P2 * (T1 + 460) = [VI.C]
!Pt * (T2 + 460)
( psia) * ( *F + 460) = [VI.C] ( psia) * ( *F + 460) (P , T t, P 2, T2 are the containment conditions from Attachment II; if t pressure and temperature data are not available, then VI.C = 1.0.) Part D: Volume-Averaged Kr-85 Concentration with Temperature / Pressure Correction
- 1. Measured Kr-85 in drywell
= pCi/ml (from Attachment II) = [VI.D.1]
- 2. Measured Kr-85 in containment
= pCi/ml (from Attachment II) = [VI.D.2]
- 3. Volume-Averaged Xe-133 with temperature / pressure correction =
[VI.D.1) * [VI.B] * [.16] + [VI.D.2] * [VI.C] * [.84] ( x x .16) + ( x x .84) = pCi/ml [VI.D.3] Part E: Decay Correction
,(1.77x10-4)(VI.A) = [VI.E]
,(1.77x10-4)( days)
= [VI.E] =
n U 08-S-03-17 ATT VI
+ GRAND GULF NUCLEAR STATION CHEMISTRY PROCEDURE l 08-S-03-17 Revision 6 l l Attachment VI Page 2 of 2 l l Page p) t l MXREF/MDOCN0 l
l I ATTACHMENT VI: NORMALIZED Kr-85 CONCENTRATION Cont'd Part F: -Fission Product Inventory Correction
- 1. Initial estimate (using Par,t B of Attachment I)
.95 = [VI.F.1]
(I.B.1)
.95 = [V.F.1]
( )
- 2. Detailed calculation (only if Part C of Attachment I is complete) 1.0 = [VI.F.2]
(I.C.4) 1.0 = [VI.F.2] ( ) VI.F.1 and VI.F.2 should agree within approximately 30%. If not, recheck the calculations of I.C.4 of Attachment I. Part G: / Normalized Kr-85 Concentration I [VI.D.3, pCi/ml] * [VI.E.] * [VI.F.1] or [VI.F.2] (preferred)
- 1.18 = [VI.G]
* *
- 1.18 = pCi/ml [VI.G)
Prepared by Date/ Time Reviewed by Date/ Time O 08-S-03-17 ATT VI
- GRAND GULF NUCLEAR STATION CHEMISTRY PROCEDURE l 08-S-03-17 Revision 6 l l Attachment VII Page 1 of 5 l ,G l MXREF/MDOCN0 l Page l V I I ATTACHMENT VII: CORE DAMAGE ESTIMATE FROM FISSION PRODUCT CONCENTRATION Part A: Record Data Record the normalized measured fission product concentratton below:
I-131 = pCi/ml (via III.E) Cs-137 = pCi/ml (via VI.E) Xe-133 = pCi/ml (via V.G) Kr-85 = pCi/ml (via VI.G)
~Part B: Evaluate Data Using the above data and Figures VII-1 through VII-4, record the predicted core damage category below:
I-131: Damage Category (1-10) = (via Figure VII-1),(VII.B.1) Cs-137: Damage Category (1-10) = (via Figure VII-2),(VII.B.2) Xe-133: Damage Category (1-10) = (via Figure VII-3),(VII.B.3) Kr-85: Damage Category (1-10) = (via Figure VII-4),(VII.B.4) A U Part C: 3 Draw Conclusion l
' Utilizing the results of Part B, draw conclusion of core damage based on fission product concentrations:
~ Damage Category (1-10) = , (VII.C.1)
Part D: Presence of Low Volatility Isotopes If the damage category is 7, attempt to sample for Sr-92 and La-140, Ba-140, and Ru-103. The presence of these isotopes are an indication of fuel melt (Damage Category 8-10]. Presence of low Vol. Isotopes = (Yes or No) Damage Category (1-10) = (VII.D.1) Prepared by Date/ Time Reviewed by Date/ Time
/^\
U 08-S-03-17 ATT VII
i .
. GRAND GULF NUCLEAR STATION CHEMISTRY PROCEDURE l 08-S-03-17 Revision 6 l l Attachment VII Page 2 or 5 l l MXREF/MDOCN0 l Page l O i i FIGURE VII-1 dl
- 1 I 2 1 3 I 4 h Is171pl s slo I '
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~ , Relationship Between 1-131 Concentraties in the Primary Coolant Oteacter Water + Pool Water) and the Estent of Core Damage la Reference Plant
G'AND R GULF NUCLEAR STATION CHEMISTRY PROCEDURE l 08-S-03-17 Fevision 6 l l Attachment VII Page '* of 5 l l MXREF/MDOCN0 l Page l
. FIGURE VII-2 '
it'i ' 1 1 2 1 31 415 I sI71 si s I 1o 3 ruel Damage categories (1-1o)
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, & PUEL aseLTDeWM Relationship Between Ca-137 Concentration la the Primary Coolant (Reactor Ustar + Pool Water) and the Estemt of Core Damage in s Reference Plass
GRAND GULF NUCLEAR STATION CHEMISTRY PROCEDURE l 08-S-03-17 Revision 6 l l Attachment VII Page 4 of 5 l l MXREF/MDOCN0 l Page l FIGURE VII-3 _ [ 1 2 I 3 I.4151617133 ,9 'E 10 3 Fuel Damage Categories (1-10) ,e
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- Relationship Between Ie-133 Comcastration in the Containment Gas prywell + Torus
- Gas) and the Estant of Cere Damage in Referessa
. Flams
*or Containment
GRAND GULF NUCLEAR STATION CHEMISTRY PROCEDURE
'~
l 08-S-03-17 Revision 6 l l Attachment VII Page 5 of 5 l MXREF/MDOCNO l Page l FIGURE VII-4 teF j 1 l 2 1 3 I .415 I657183 ~ 9 3 10 3 puel Damage categories (1-10) m
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Relationship Between Kr-45' Concentration in the contairnest cas (Drywell + Torus
- Gas) and the Extent of Core Damage in Referenes Plant I *or Containment
GRAND GULF NUCLEAR STATION CHEMISTRY PROCEDURE
'l 08-S-03-17 Revision 6 l l Attachment VIII Page 1 of 2 l p l MXREF/MDOCNO l Page l V l l
' ATTACHMENT VIII: ISOTOPE RATIOS Part A: Decay Time Date/ time of Iodine samples , =. (from Attachment II)
Date/ time of reactor shutdown = (from Attachment I) Time (hours) between reactor Shutdown and Iodine sample = hours [VIII.A] Part B: Iodine Concentrations from Attachment II I-131. concentration (jet pump or RHR system) = pCi/ml [VIII.B.1] I-133 concentration (jet pump cc RHR system) = pCi/ml [VIII.B.2] I-135 concentration (jet pump or RHR system) = pCi/ml [VIII.B.3] Part C: Iodine Isotope Ratios I-133 = 'VIII.B.2] = ( pCi/ml) = [VIII.C.1] I-131 ;VIII.B.1] = ( pCi/ml) I-135 = [VIII.B.3] = ( Ci/ml) = [VIII.C.2] 1-131 [VIII.B.1] = ( Ci/ml) PartD.[DecayCorrectionFactor e(0.0333) * [VIII.A] = [VIII.D.1] e(0.00359)* [VIII.A] e(0.10486) * [VIII.A] = [VIII.D.2] . e(0.00359)* [VIII.A] Part E: Corrected Iodine Isotope Ratios I-133 = [VIII.C.1] * [VIII.D.1] = * = [VIII.E.1] I-131 I-135 = [VIII.C.2] * [VIII.D.2] = * = [VIII.E.2] I-131 O 08-S-03-17 ATT VIII
. GRAND GULF NUCLEAR STATION CHEMISTRY PROCEDURE l-08 S-03-17 Revision 6 l l Attachment VIII Page 2 of 2 l m l MXREF/MDOCN0 l Page l
, -' () - .l l ATTACHMENT VIII: ISOTOPE RATIOS (Cont'd) Part F: Fraction of Isotope from Pellet
- 1. I-133 released fraction fro,m pellet = [VIII.E.1] .685 2.09
=( ) .685 2.09
= [VIII.F.1]
- 2. 1-135 released fraction from pellet = [VIII.E.2] .364 1.97
=( ) .364 1.97
= [VIII.F.2]
Part G: Estimated Damage Category - b9 . Estimate the core damage category by utilizing Part F and the table r' below: f I-133 Damage Category (4-9) = [VIII.G.1] I-135 Damage Category (4-9) = [VIII.G.2] Fraction Released Damage From Pellet Category
.05 4
.05 .10 5
.10 .40 6
.40 .70 7
.70 .90 8
.90 9 Prepared by Date/ Time Reviewed by Date/ Time O
08-S-03-17 ATT VIII
GRAND GULF NUCLEAR STATION CHEMISTRY PROCEDURE-l 08-S-03-17 Revision 6 l l Attachment IX Page 1 of 2 l
/~') l MXREF/MDOCN0 l Page l Is- /' ,
l l ATTACHMENT IX: CONTAINMENT HYDR 0 GEN CONCENTRATI0'~ Part A: Hydrogen /0xygen Data
- 1. H2 concentration from drywell monitor = %H2 [IX.A.1]
- 2. H2 concentration from containment monitor = %H2 [IX.A.2]
- 3. 02 concentration from drywell monitor = %02 [IX.A.3]
- 4. 02 concentration from containment monitor = %02 [IX.A.4]
Part B: Volume-Averaged Hydrogen /0xygen Concentration
- 1. Average Hydrogen concentration = .16 * [IX.A.1] + .84 * [IX.A.2]
= .16 * + .84 *
= %H2 = [IX.B.1]
- 2. Average Oxygen concentration = .16 * [IX.A.3] + .84 * (IX.A.4]
= .16 * + .84 *
! =
%02 = [IX.B.2]
Part C: Hydrogen Concentration
- 1. If hydrogen igniters are not energized and there is no indication
( ]f of a hydrogen burn, then: [ H2 concentration = (IX.B.1) = %H2
- 2. If hydrogen igniters are energized or there is indication of a hydrogen burn, then:
H2 concentration = (IX.B.1) + (20.8% - IX.B.2)
- 2 H2 concentration = + (20.8% - %)
- 2 j H2 concentration = + (20.8% - %)
- 2 H2 concentration = %H2 Part D: Estimate Core Damage Using the results of Part C and Figure IX-1, estimate the core damage.
l Damage Category (1-8) = [IX.D] ) Prepared by: Date/ Time Reviewed by: Date/ Time O t 08-S-03-17 ATT IX
i i GRAND GULF NUCLEAR STATION CHEMISTRY PROCEDURE l 08-S-03-17 Revision 6 l l Attachment IX Page 2 of 2 l l MXREF/MDOCN0 l Page l O i i FIGURE IX-1 Deange Category M ~T" 4 ' 5 ' 6 y e a. M n : . m E 4 a 3 r . ,= n E . 3 M - m m -
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. m_ - - !1 iO 08-S-03-17 ATT IX
. GRAND GULF NUCLEAR STATION CHEMISTRY PROCEDURE l 08-S-03-17 Revision 6 l l Attachment X Page 1 of 2 l l MXREF/MDOCN0 l Page l te 1 I-
. ATTACHMENT X: CONTAINMENT RADIATION LEVEL Part A: Containment Radiation Monitoring Reading
- 1. Drywell radiation monitor re,ading Rem /hr. [X.A.1]
- 2. Date/ time of reading Part B: Decay Time
- 1. Date/ time of reactor shutdown = (from Attachment I)
- 2. Time (days) between shutdown and radiation reading = [X.B]
Part C: Normalized Radiation Level at 100% FP
- 1. Average Capacity Factor for last 30 days of operation prior to reactor shutdown (via I.B) = (fraction) [X.C.1]
- 2. Normalized Radiation Level
= [X.A.1 = Rem /hr. [X.C.2] !
[X.C.1 Part D: ,tstimate Core Damage
~Using the normalized radiation level of [X.C.2], the shutdown time of
[X.B], and Figure X-1, estimate the core damage. Damage Category (1-7) = [X.D] Prepared by: Date/ Time Reviewed by: Date/ Time O 08-S-03-17 ATT X
. GRAND GULF NUCLEAR STATION CHEMISTRY PROCEDURE l 08-S-03-17 Revision 6 l l Attachment X Page 2 of 2 l l MXREF/MDOCNO l Page l O I I FIGURE X-1 CONTAINMENT RADIATION LEVEL 4 64 l ,
E = Core Damage Categy 3 as8 M I E x=6 i
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x=5 O f w: 4, ,
=4 b-x.s .
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- O 08-S-03-17 ATT X
GRAND GULF NUCLEAR STATION CHEMISTRY PROCEDURE l 08-S-03-17 Revision 6 l l Attachment XI Page 1 of 3 l l_MXREF/MDOCN0 l Page l V(~'s l l ATTACHMENT XI: OTHER PLANT INDICATORS DATA Part A: Reactor Vessel Level Determine from the control roog,1f the core was uncovered during the transient.
-1. If exposure did not occur, core damage is unlikely; damage category = 1. . 2. If exposure did occur, request from the control toom the time after shutdown at which exposure occurred and the time interval of exposure. Determine the damage category from Figure XI-1.
Time of Exposure = Length of Exposure = Damage Category (1-10) = Part B: ECCS Operation k- ; Determine from the control room if at least one ECCS train was fully [ operating throughout the transient.
- 1. If at least one train was operating, core damage is unlikely; damage category = 1.
- 2. Otherwise, core damage (category 2-10) may have occurred.
Damage Category (1-10) = Part C: Primary Temperature Determine from the control if the safety / relief valve tailpipe thermocouples (if available) indicate that non-superheated conditions existed within the primary system throughout the transient. If non-superheated conditions existed, core damage is unlikely; damage category = 1. Otherwise, core damage (category 2-10) may exist. Tailpipe Temperature = . Steam or Syst. Pressure = . Damage Category (1-10) = . O 08-S-03-17 ATT XI i
GRAND GUIE NUCLEAR STATION CHEMISTRY PROCEDURE l 08-S-03-17 Revision 6 l l Attachment XI Page 2 of 3 l
. MXREF/MDOCN0 l Page ATTACHMENT XI: OTHER PLANT INDICATORS DATA Cont'd l Part D: Gross Core Damage If it appears that severe damagg (category 7-10) has occurred, and if the TIP machine is operable, insert the TIP in various guide / tubes and monitor the length of travel. If the TIP cannot move the full travel, this is an indicator that the guide tubes are grossly deformed or broken and that severe core damage may exist.
- Note Results
! Damage Category (1-10) = .
- Part E
- Conclusions j Based on Parts A, B, C and D, draw conclusion on core damage.
l A. Reactor Vessel Level Damage Category (1-10) = I B. ECCS Operation Damage Category (1-10) = , 1 1 O 9
. C. Primary Temperature Damage Category (1-10) =
D. Gross Core Damage Damage Category (1-10) =
- Damage Category (1-10) = [XI].
Prepared by: Dite/ Time Reviewed by: Date/ Time 1 4 1 4 , 4 1 i O [ V l 4 08-S-03-17 ATT XI I
GRAND GULF NUCLEAR STATION CHEMISTRY PROCEDURE
~
l 08-S-03-17 Revision 6 l l Attachment XI Page 3 of 3 l l MXREF/MDOCN0 l Page l I l FIGURE XI-1 90
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- GRAND GULF NUCLEAR STATION CHEMISTRY PROCEDURE l 08-S-03-17 Revision 6 l l Attachment XII Page 1 of 2 l (N l MXREF/MDOCN0 lAe l I
(s-) l ATTACHMENT XII: ESTIMATE OF CORE DAMAGE Part A: Record Available Data Variable Damage Category (1-10) I-131 Concentration [from VII.B.1] Cs-137 Concentration [from VII.B.2] Xe-133 Concentration [from VII.B.3] Kr-85 Concentration [from VII.B.4] Presence of Sr-92 or La-140 [from VII.D] I-133 Released from Pellet (from VIII.G.1] 1-135 Released from Pellet [from VIII.G.2] Hydrogen Concentration [from IX.D] Radiation Level (from X.D] Other Indicators [from XI] Part B: Draw Conclusion It may be useful to plot the data from Part A on Figure XII-I prior to () (_/ . drawing conclusion. jConclusion [ Damage Category, 1-10] Report the above to Emergency Director Part C: Comments Prepared by: Date/ Time Reviewed by: Date/ Time CN U 08-S-03-17 ATT XII
r-------------------------
- x.
- GRAND GULF NUCLEAR STATION CHEMISTRY PROCEDURE I 08-S-03-17 i Revision 6I . -
1 Attactument XII l Page 2 of 2.I l MXREF/MDOCNO I Page l I I
~,..
l ATTACHMENT XII: ESTIMATE OF CORE DAMAGE (Cont'd) FIGURE XII-1, ESTIMATE OF CORE DAMAGE I I I I I I I I I I I i 10 1 I l I I I I l- I - I I I I I I I I I i 9 I I I I I I I I 1_ I I I I I I I I I 8 I I I I I I I I I I I I I I I I I l i I 7 I I I I I I I I I I I I I I I I I I I I I I 6 I I I I I I I -1 1 I I i l 1 1 I I I I I I I 5 I I I I I I I I I I I I I I I I I I I I I I I 4 I I I I I I I I I I I I I I I I I 3 I I I I I I I I I I I i i l i I I I I 2 I I i I I i l I I I I I I I I I i l I I i 1 I I I I I I I I I I-131 l Cs-137 I Xe-133 i Kr-85 ISr-92, I I-133 I I-135 I HYDROGEN l RADIATION! OTHER I l CONCENTRATION ICONCENTRATIONICONCENTRATIONlCONCENTRATIONiLa-140,1 FROM i FROM ICONCENTRATIONILEVEL I I I I I I IBa-140,1 PELLETI PELLETl i I I I I I i 1Ru-103 I I l l l l PARAMETERS OF INTEREST I l Attempt to identify any trends or discrepancies. 08-S-03-17 ATT XII
fm *. (- [--
- [,)\
q . . GRAND GULF NUCLEAR STATION CHEMISTRY PROCEDURE l 08-S-03-17 l Revision 6l
- l Attachment XIlli Page 1 of 2 l l MXREF/MDOCNO l Page l l l y ~~...
REPRESENTATIVE SAMPLES OF CORE CONDITIONS DURING AN ACCIDENT Event Type / Power Conditions Sample Location Other Instructions - Supp. Supp. Jet Pool Pool l Pump Liquid RHR Atmos. Drywell Non-Break (eg. MSIV Closure)/ Reactor Yes - - Yest Yes2 i Power > 1% Non-Break (e.g. MSIV Closure)/ Reactor - - Yes Yes! Yes2 1. RHR must be in shutdown cooling mode. i Power < 1%
- 2. Reactor water level should be raised to the level of moisture Small liquid line Break / Reactor Yes - -
Yes! Yes2 Power > 1% 1. Same as above Small Tiquid line Break / Reactor - - Yes Yes! Yes2 2. Same as above Power < 11 Small steam line Break / Reactor Yes - - Yest Yes2 Power > 11 1. Same as above Small steam line Break / Reactor - - Yes Yes! Yes2 2. Same as above Power < 1% .
> 08-S-03-17 ATT XIII -
i l GRAND GULF NUCLEAR STATION CHEMISTRY PROCEDURE l 08-S-03-17 l Revision 6l ** l Attachment XIIIl Page 2 of 2 l l MXREF/MDOCNO l Page l I I l REPRESENTATIVE SAMPLES OF CORE CONDITIONS DURING AN ACCIDENT I Event Type / Power Conditions Sample Location Other Instructions Supp. Supp. Jet Pool Pool IPump -Liquid RHR Atmos. Drywell Large liquid line Break / Reactor Yes3 Yes4 - Yes! Yes2 Power > 1% Large liquid line Break / Reactor - Yes* Yes 3 Yes! Yes2 1. RHR must be in shutdown Power < 1% cooling mode
- 2. Suppression pool must be in suppression cooling mode.
- 3. Reactor Water level should be raised to the level of moisture separators.
Large steam line Break / Reactor Yes3 Yes4 - - Yes - Power > 11 Large steam line Break / Reactor - - Yes Yes! Yes 2 1. RHR must be in shutdown Power < 1% cooling mode.
- 2. Reactor water level should be raised to the level of moisture separators.
- 1. Use if SRV's are vented to the suppression pool.
- 2. Use if SRV's are not vented to the suppression pool.
- 3. Use if makeup water flow is < 50% of core flow present.
- 4. Use if makeup water flow is > 50% of core flow present.
08-S-03-17 ATT XIII}}