AEP-NRC-2017-02, EP-CALC-CNP-1602, Rev. 0, Containment Radiation EAL Threshold Values.

EP-CALC-CNP-1602, Rev. 0, Containment Radiation EAL Threshold Values.

ML17146A078
Person / Time
Site:	Cook
Issue date:	10/07/2016
From:	Mccain S American Electric Power
To:	Office of Nuclear Reactor Regulation
References
AEP-NRC-2017-02 EP-CALC-CNP-1602, Rev. 0
Download: ML17146A078 (18)

Text

• • Cook Nuclear

• Pla.!nt (C:NP)

.*contain.m*ent Radiation EA'L

.T:hre.sih:*old Val uce-s 1 EP~CALC~c*N p ..1602 Revision 0 Document Author: Scott McCain Consultant, CMCG Technical Reviewer: Kevin'Simpson EP SUpervisor, D.C. Cook EPM Approval: Ron *Sieber EP Manager, O.c. Cook

• DocuineritAuthor: ~f!!!Tt>te411.J 'fitt fflFt"b"'I.

Technical Reviewer:  :&if~*~.t>*BA!>6E~b ERM Approval: ~~ #,.~Sld~ /6,67/i~

CNP EAL Technical Bases Calculations - CHRRM FPB Series Table of Contents

1. Purpose/Objective .............................................................................. .' .................................. 2

2. Development Methodology and Bases .................................................................................. 3 2.1. Fuel Clad Loss ............................................................................................................. 3 2.2. Reactor Coolant System Loss ......................................................................................4 2.3. Containment Potential Loss .......................................................................................... 4 2.4. Decay Considerations .................................................................................................. 5

3. Design Inputs ........................................................................................................................6

4. Calculations ..........................................................................................................................8 4.1. Fuel Clad Damage Estimate Based on 300 µCi/cc DEl-131 ......................................... 8 4.2. CHRRM Readings for the FPB Thresholds ................................................................... 9

5. Conclusions ........................................................................................................................ 1O

6. Rererences ......................................................................................................................... 11 Attachments , 300 µCi/gm DEl-131 Equivalent Clad Damage................................................... 12 , FPB CHRRM Readings ...................................................................................... 13 , EVAL-RD-99-11 Bases lnformation .................................................................... 14 EP-CALC-CNP-1602 Page 2of18 Revision 0

CNP EAL Technical Bases Calculations - CHRRM FPB Series

1. PURPOSE/OBJECTIVE The Cook Nuclear Plant (CNP) Emergency Action Level (EAL) Technical Bases Manual contains background information, event declaration thresholds, bases and references for the EAL and Fission Product Barrier (FPB) values used to implement the Nuclear Energy Institute (NEI) 99-01 Rev. 6 EAL guidance methodology. This calculation document provides additional technical detail specific to the derivation of the FPB containment high range radiation monitor (CHRRM) readings developed in accordance with the guidance in NEI 99-01 Rev. 6.

Documentation of the assumptions, calculations and results are provided for the values associated the NEI 99-01 Rev 6 Table 9-F-3, PWR EAL Fission Product Barrier Table, thresholds listed below.

• NEI Fuel Clad Loss 3.A

• NEI Reactor Coolant Loss 3.A

• NEI Containment Potential Loss 3.A

2. DEVELOPMENT METHODOLOGY AND BASES 2 .1 . Fuel Clad Loss Guidance Criteria Per NEI 99-01 Rev 6, this radiation monitor reading corresponds to an instantaneous release of all reactor coolant mass. into the primary containment, assuming that reactor coolant activity equals 300 µCi/gm dose equivalent 1-131. Reactor coolant activity above this level is greater than that expected for iodine spikes and corresponds to an approximate range of 2% to 5% fuel clad damage. Since this condition indicates that a significant amount of fuel clad damage has occurred, it represents a loss of the Fuel Clad Barrier.

The radiation monitor reading in this threshold is higher than that specified for RCS Barrier Loss threshold since it indicates a loss of both the Fuel Clad Barrier and the RCS Barrier.

The reading should be determined assuming the instantaneous release and dispersal of the reactor coolant noble gas and iodine inventory, with RCS radioactivity concentration equal to 300 µCi/gm dose equivalent 1-131, into the primary containment atmosphere.

CNP Bases The Fuel Clad FPS threshold value is based on an instantaneous release of all reactor coolant into the containment at an activity equivalent to 300 µCi/cc DEl-131. NUREG-1940 Table 1-1 equilibrium core activity was used to develop the site specific source term that correlates 300 µCi/cc DEl-131 to a% fuel clad damage value. That% fuel clad damage value is ratioed to a CHRRM reading for 100% clad damage to establish the Fuel Clad FBP threshold value in R/hr.

EP-CALC-CNP-1602 Page 3of18 Revision 0

CNP EAL Technical Bases Calculations - CHRRM FPB Series 2.2. Reactor Coolant System Loss Guidance Criteria Per NEI 99-01 Rev 6, this radiation monitor reading corresponds to an instantaneous release of all reactor coolant mass into the primary containment, assuming that reactor coolant activity equals Technical Specification allowable limits. This value is lower than that specified for Fuel Clad Barrier Loss threshold since it indicates a loss of the RCS Barrier only.

The reading should be determined assuming the instantaneous release and dispersal of the reactor coolant noble gas and iodine inventory, with RCS activity at Technical Specification allowable limits, into the primary containment atmosphere. RCS activity at this level will typically result in primary containment radiation levels that can be more readily detected by primary containment radiation monitors, and more readily differentiated from those caused by piping or component "shine" sources. If desired, a plant may use a lesser value of RCS activity for determining this value.

In some cases, the site-specific location and sensitivity of the containment radiation monitor(s) may be such that radiation from a cloud of released RCS gases cannot be distinguished from radiation emanating from piping and components containing elevated reactor coolant activity. If so, determine if an alternate indication is available.

CNP Bases The RCS iodine activity for a pre-existing iodine spike is based on the Technical Specification 3.4.16 limit of 60 µCi/gm of dose equivalent 1-131 during normal operations. The% clad damage equivalent to 60 µCi/gm DEl-131 is determined by ratio to the% clad damage equivalent to 300 µCi/gm DEl-131. That% fuel clad damage value is ratioed to a CHRRM reading for 100% clad damage to establish the Fuel Clad FBP threshold value in R/hr.

2.3. Containment Potential Loss Guidance Criteria Per NEI 99-01 Rev 6, this radiation .monitor reading corresponds to an instantaneous release of all reactor coolant mass into the primary containment, assuming that 20% of the fuel cladding has failed. This level of fuel clad failure is well above that used to determine the analogous Fuel Clad Barrier Loss and RCS Barrier Loss thresholds.

NUREG-1228 indicates the fuel clad failure must be greaterthan approximately 20% for there to be a major release of radioactivity requiring offsite protective actions. For this condition to exist, there must already have been a loss of the RCS Barrier and the Fuel Clad Barrier. It is therefore prudent to treat this condition as a potential loss of containment which would then escalate the emergency classification level to a General Emergency.

NUREG-1228 provides the basis for using the 20% fuel cladding failure value. Unless there is a site-specific analysis justifying a different value, the reading should be determined assuming the instantaneous release and dispersal of the reactor coolant noble gas and iodine inventory associated with 20% fuel clad failure into the primary containment atmosphere.

• EP-CALC-CNP-1602 Page 4 of 18 Revision 0

CNP EAL Technical Bases Calculations - CHRRM FPB Series CNP Bases The Containment FPB threshold value is based on an instantaneous release of all reactor coolant into the containment at an equivalent of 20% clad damage. That % fuel clad damage value is ratioed to the CHRRM reading for 100% clad damage to establish the Containment FBP threshold value in R/hr.

2.4. Decay Considerations Guidance Criteria Fission product barrier thresholds and their associated EALs are only applicable when the plant is in Hot Shutdown, Startup, or Power Operation mode (known as the hot operating modes).

Per NEI 99-01, the events for these thresholds correspond to an instantaneous release of all reactor coolant mass into the primary containment.

CNP Bases There is no decay correction applied to the source term used to determine the %

damage. This is based on the assumption that the LOCA and dispersion of activity within containment occur instantaneously from a critical reactor.

EP-CALC-CNP-1602 Page 5 of 18 Revision O

CNP EAL Technical Bases Calculations:-- CHRRM FPB Series

3. DESIGN INPUTS 3~ 1. General Constants and Conversion Factors 3.1.1. 453.597 cc per lbin water conversion factor 3.1.2. Rated Power

• Standard Plant (NUREG-1940 Section 1.2.4) ............................................. 3,000 MWt

• Unit 1 (UFSAR 3.1.1) ......................... ,.... ,., ................................................. ,3304 MWt

• Unit 2 (UFSAR *3.3.1.3.1) .............................................................................. 3468: MWt 3.1.3. RCS Liquid Volume (UFSAR Table 4.1-1)

• .

Unif1 . ............................................................................................................. 1*1,990.ft . ***.* 3

• .* Onit 2 ........................................................ ;*.................................................... 12,0.1'9 ft3 3.1.4, NOT (12,.THP"6020~CHM"'to1 Data Sheet6)

• Unit *1 ............................."............... ;...................................................................................................;571°

• Unit 2 ..........................................................................................................................514° 3.. 1.5. Density Correction C1-tHP-6020"CHM-122Figure1)

• 571° (interpolated from 568° ahd 5726° table values) .................. ,....... 44.5338 lbm/ft3

• 574° (average of572° arid 576° table values) ................................... ;........ 44~3169 Jbm/ft3 3.2. Source Term 3.2, 1. Core Release Fraction - CRF (NUREG-1228 Table4.1l ORF represents the fraction of radioactive material released.from the fuel pin cladding and/orfLlel pellet by fission product type or chemical grouping, The CRF fdr i::duel clad failure (gap release) scenario for Halogens (I, Br) is 0.02 (2%).

3,2.2. Iodine EqUilibrium *Core Activity (NUREG-194d Table 14)

.d'~:.{~~11/ll.  ::;i

1

::131 2.67E+04

,

1Jf't3~: 3~88E+04

,, 1..:133:: 5A2E:+04

'1n;134 5..98E+04

1~.1

3.5 5.18E+04 EP~CALC-CNP-1602 Page*6of18 RevlSion o

CNP EAL Techni~al Bases Calculations - CHRRM FPB Series 3.3. Iodine Conversion Factors ,- ICF(Tf D.,14844 Table Ill)

• 1~1~2 5.35E+04 1,,1:.135 L24E:+05 I

Page? of1B Revision 0 r I

CNP EAL Technical Bases Calculations - CHRRM FPB Series

4. CALCULATIONS 4.1. Fuel Clad Damage Estimate Based on 300 µCi/ccDEt-131 4.1.1. 100% Core Activity EqoivaleritReactorCoolanUodine Concentrations

. . (µ . ) _ActivitYcore-i(Ci/MWt) X Unit(MWt).x 10 6 AetivitJrRCS100%core-i Ci1cc - v* l ( )

0 RCS CC 3:6,7E+05. 3.83E+05 5.33E+05 5.57E+05 7.45E+05 7.78E+05 822E+05 8.58E+.05 7;12E+05 7.44E+:05 4.1.2. 1on% Fuel Clad Activity Equivalent Reactor Coolant Iodine Concentrations ActivitYncs1 oo%Clad-i(µCi/cc) = ActivitYncs1 oo%core-i(µCi/ cc) X CRF

. ff~ftA~~~j~i~ <~g,~ft~l~~t:'r .

• *i.;1.:.135 1.42E+04 1.49E+d4.

4.1.3. 100% Fuel Clad Activity Equivalent Reactor Coolant DEH 31 *Concentrations ActivityRcs1 oo%DEI(µCi/ci:) =I ActivitYRcs1 oo%cladi(µCi/cc) x DE! lCFi The DEl-131 value for each iodine isotope isdetermined as follows:

. . TID 14844 Table III Iodin,e Conversion Factori(Rad/Ci)

DE/ ICFi = TID 14844 Table mI~diile Conversion Factdr1-13t(Rad/Ci)

• • 1-131 7;34E+03 7.67E+03.

< <:1~1.32 3.86,E+02 4;03E:!:02

'\:t;;.133 4.03E+03 4.21E+03

. ;;1;134 2.78E+02 I 2;90E+02 d'. >1:::135 1.19E+03. 1.25E+03

. T6.tal 1.32E+04 1.38E+04 EP:.cALC.:CNP.::1602 Page 8of1a* Revision a

CNP EAL Technical Base$ Calculation.s -Cl-IRRM FPl3 Series 4.1.4. % Fuel Clad Activity Equivalent Reactor Coolant at 300 µCi/g DEl-131 300µCi/cc

%Clad Damage =*. . .. .. . .

RCS ActnntYioo%DEl(µCi/cc)

See Attachment 1 for the spreadsheet calculations that develop the fuel clad source term activity and the % clad damage.

4.2. CHRRM Readings for the FPB Thresholds EVAL-RD-'99..:11 is utilized as the basis for associating tHe contaimneht high range radiation monitors to a particular amount of clad damage.

See Attachment 2 for the derived CHRRM threshold values.

See Attachment 3 for the applicable portions of EVAL-RD-'99-11 that support the E:AL threshold value dedvations.

4.2.1. Containment Potential Loss {.20% Fuel Clad Aetivity CHRRM Reading)

CHRRM20%(R/hr) = CHRRM100% (R/hr) x 0.2 I*VP.A 1410/2410.(650~) 6,261::+/-03 6.26E+03 l'.:VRA1310/231ff'(612'l R11E+03 9.11E+03 4.2.2. FLielCla:d*Loss (300 UCi/cc DE1"131 ActivitY CHRRM Reading)

CHRRM300 µci/ccDEI-1:31.CR/hr) = CHRRM100% (R/ht) x % Darnage3ooµci/ttDE1-131 Ur:litt . * .>Unit 2

..V'RA14tOl2:410' 650'. 7.10E+02 6,80E+02 .

VRA.13.10/2310 612' : 1.03E+03 9.90E+02 4.2.3, Re*actorCdolanHRCSTS Activity CHRRM Reading)

.* . .. . . . .* .. . 60µCi/cc

%Clad Damg.ge = CHRRMsoo µcifcc nl!:i-131 (R/hr) X /l.Ci/cc 300

.*VRA1410/24~o: 650' .1,361::+02 VRA1310/2310: 612' 1;98E+02 EP.:.CALC:-CNP;.1602 Page 9of18 Revision 0

CNP EAL Technical Bases' Calculations""" CHRRM<FPB Series

5. CONCLUSIONS 5.1. 300 µCi/gm DEl-431 is equivalent to:

• Uriit 1 ............................................................................ 2.27% fuel Clad (gap) damage

• Unit 2 ............................................................................2.17% fuel. clad (gap) damage 5.2. EAL Fission Product Barrier thresholdvalues are as follows:

. Rue1c1ad . RCS, : *.*. Con~ainment

, ; .i'.o$~Y- * < . . L6~5\ . << i:>~t~ntia1 Lost.

-,Vft~.t,J .:<:: , VRA14t()\(650') .. 7.1 OE+02. 1.42E+02 6,26E+03

(R/hr)

'.:'.'iVRA13tQ (~12~.) 1.03E+03 2.07E+02 9.11E+03

- Qni(?!' *:1.1',~r:~R.t\:24'1();:(6~0~) 6.BOE+o2 1.36E+02 6.26E+03

(R/hr)/_ *'*:VRA2310 (612~) 9.90E+02 1.98E+02 9.11E+03

-*-.----

Based on monitor accuracy/readability, hurnan factors and.the similarity Of results for each unit; the EAL Fission Product Barrier thresholds are established as follows:

VRA1410/2410:"."" Rlhr; 650' : 700 HO .. 6300 VRA1310/2310,.:.Rfhr 6:12'. 1000 200 9100 EP'-CALC-CNP-'1662 Page 10of18 Revisiono

CNP EAL Technical Bases Calculations - CHRRM FPB Series

6. RERERENCES 6.1. NEI 99-01 R6, Methodology for Development of Emergency Action Levels, November 2012 6.2. NUREG-1940, RASCAL 4, Description of Models and Methods, December 2012 6.3. NUREG-1228, Source Term Estimation During Incident Response to Severe Nuclear Power Plant Accidents, October 1988 6.4. NUREG-1465, Accident Source Terms for Light-Water Nuclear Power Plants, February 1995 6.5. TID-14844, Calculation of Distance Factors for Power and Test Reactor Sites, 03/23/62 6.6. Cook Updated Final Safety Analysis Report, Revision 26

• Unit 1 UFSAR Section 3.1.1

• Unit 2 UFSAR Section 3.3.1.3.1

• UFSARTable4.1-1

6. 7. 12-THP-6020-CHM-101, Reactor Coolant System, Revision 41 6.8. 1-THP-6020-CHM-122, Unit 1 Reactor Coolant System Chemical Addition, Revision 5 6.9. EVAL-RD-99-11, Evaluation of Radiation Monitoring System Setpoints, Rev 0 6.10. Radiological Consequences of Accidents for the Donald. C. Cook Nuclear Plant Units 1 and 2 Using Source Term Methodology from NUREG-1465, Engineering Report, Westinghouse Electric Company, October 14, 1999 EP-CALC-CNP-1602 Page 11of18 Revision 0 300 µCi/gm DEl-131 Equivalent Clad Damage Unit 1

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1-131 2.67E+04 9.26E+07 3.83E+05 7.67E+03 1.48E+06 1.00E+OO 7.67E+03 1-132 3.88E+04 1.35E+08 5.57E+05 1.11E+04 5.35E+04 3.61 E-02 4.03E+02 1-133 5.42E+04 1.88E+08 7.78E+05 1.56E+04 4.00E+OS 2.70E-01 4.21E+03 1-134 5.98E+04 2.07E+08 8.58E+05 1.72E+04 2.50E+04 1.69E-02 2.90E+02 1-135 5.18E+04 1.80E+08 7.44E+05 1.49E+04 1.24E+05 8.38E-02 1.25E+03 Total 2.31E+05 8.02E+08 3.32E+06 6.64E+04 1.38E+04 Volume Conversion (cc/lbm): 453.597 Rated Power (MWt): 3468 Halogen Release Fraction: 2.0% RCS Liquid Vol @ NOT (ft3): 1.20E+04 Target DEi: 3.00E+02 Density@ NOT (lhm/ft3): 44.3169 RCS Liquid Vol @ NOT (Ihm): 5.33E+OS RCS Liquid Vol @ NOT (cc): 2.42E+08

% Clad Damage: f. ?'-%

EP-CALC-CNP-1602 Page 12of18 Revision 0 FPB CHRRM Readings Unit 1 Unit2 100% Clad Damage (Rlhr) (Rlhr)

VRA1410/2410 (650'): 3.13E+04 3.13E+04 VRA1310/2310 (612'): 4.56E+04 4.56E+04 Containment Potential Loss Threshold VRA 1410/2410 (650'):

VRA1310/2310 (612'):

Fuel Clad Loss Threshold VRA1410/2410 (650'):

VRA1310/2310 (612'):

RCS Loss Threshold VRA1410/2410 (650'):

VRA1310/2310 (612'):

Containment Potential Loss : 20% 20%

Fuel Clad Loss (300 µCi/cc) : 2.3% 2.2%

RCS Loss (60 µCi/cc) : 0.5% 0.4% .

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EP-CALC-CNP-1602 Page 14of18 Revision 0

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Attachment 3 EVAL-RD-99-11 Bases Information Rofdoli: 0 AUACHMIHTA

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V:ah.te 612

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Rt'f M .e Upper, fl" 1.1E& T.ti912 CIRel M 2 romi ff ures Tllblle 17 cf Rtl M 2 Ttbte 13 i:I Rtf M 2 TM po~ LOCA ciqt.lltrium M~ gn o:n h'l*rt*t'lloly ll Dsted In Te.ble A1 f.t TM nob'9 p fiMI rod p:ip

.ch-Ilea ;n c:alt~~ tr/ mr.t1Splf~ ttte 031 LOO\ r.>tlle ;as dvd.esin Tal:*>At.t.t bf~* bil rod gap tr.-.. ***d In Tac~ AS.1-t. The nctie OH"'~ red Q::IP ~l!iet en kited in ~lo /4 1--2 EP-CALC-CN P-1602 Page 15of18 Revision 0 EVA L-RD-99-11 Bases Information ATT4CHM!JNTA Ttbltt.31=( NQb!!Ck!!<WN!t&

!WU Cl lnc nol'llW cpcnlcn rw=r ..... no* G* ectYillM fTll* e cl Ref M.2] n rated In Tab c A3. 1 3 11'1Ma 11eh1tt.s aro ~on 1" r1.1e1 onc1t.

!60f0~ ld'llty.14CL"arr l(f-8Stn 192&

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1. 1

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~tlid ~ ... e billWhl d 106.9 ftot.

2 "ea aatua'ted flat 1w: 1tefurre betw9en e>e er:inc ~ :i'!O 1tio ~wail ooo bo mode*' &t ann.hr ISJllllCIC: with 1n inner nd&a of<< 5 ft. and an ou'1t' raillut c' 57.S leoet Md a ~11$d efteti\-e hc1gli of 15' .2 lltt.

3. It la 8-.mod f\Ot the~ neh ranot ARI.ta 1,. loultd on-...~ ot ht OOl'Mirmtm wal.

Tno sot.1t1e ~ foOI' !ho rooctM-*r 4IO eo~ by rruti;:iyr.; the ~ 9111t ll01l:lplll tll4to In Tlb'!I A3.1-3b'/ h "*8 of or rnal'f eoob'lt ('2.*,e.a gmrr~)illtld t~tiCi IO() Tht ncitil*oauouroe !!fr.$

are 1s ltdlnT~AU*1 .

EP-CALC-C NP-1602 Page 16of 18 Revision 0 EVAL-RD-99-11 Bases Information Slllf!drn flodfi foe liiQh B1rot MM MA 131!lt'23i.Q)

CQC'C41 Wl!nl'll I"~ Rlt"~AFU.*a VRA 131G'23i Oare loeslodM ltw:660fl devlllM (Rir.. M ..c} Ortt,'flc I~ OOIO '1:tYI U!t llP* ~~\'Olnlt (l*. lllbc:wo tflO ~ OOCk) wh be~ k\ ttn CO'CualOi'\. Th& itl't'n:ftbn ~from bcb.-*h:opoia!ing O.C:l: Wbt ~Cid 'flt ln. C>PO'~ ~ tirQI I I* llll'Otll ttiree feel !IQ Pet AJt11~ t, h llf>PIW ~lnmcrn It rncdOl!rl M

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tr)9 et#I& Wll Yt ?I ~ tt1olded t:f ltlo cnne 'fo*a11noe It

• VOlu~ '* lnnor 8n:I ~ ntd!l ct 44.G~ ano 51.6 t: ~v~.

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!!7 6 ft wic:1

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• llnlllH tpOClt ~ en tu~ rd.io tf he wlun-. of ht .n11'1t spia ID ti.It d ~Mllltlt, "'ce 3E.OS' 1.~

0.401).

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%Qf ~Iii t ltf*

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• 15U ft

• 0 Oe14

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• loe.atbd en 11e 11'1116d6 of~ eone,, m~ ...... w!littl ;i'fe* u ~ ot 61.6 It. h l'IO ISOSKl.C*PC ~ .

AJA. R,_b 111d Colldv.,.,.

n. ruula eite limna'!MO In Tab!i: A3.4*t imM.

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