ML032250034

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Submittal of Emergency Plan Implementing Instructions EPI-B13, Revision 3
ML032250034
Person / Time
Site: Perry FirstEnergy icon.png
Issue date: 08/05/2003
From: Bauguess D
FirstEnergy Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
PY-CEI/NRR-2728L EPI-B13, Rev 3
Download: ML032250034 (26)
v • d • e


Text

FENOC RmSnew Nucear Operatkig Coany Perry Nuclear Power Plant 10 Center Road PO. Box 97 Perty Ohio 44081 August 5, 2003 PY-CEI/NRR-2728L United States Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555 Perry Nuclear Power Plant Docket No. 50-440 Submittal of Emergency Plan Implementing Instructions Gentlemen:

Pursuant to 10 CFR 50 Appendix E, enclosed are changes to the Emergency Plan Implementing Instructions (EPIs) for the Perry Nuclear Power Plant. These changes constitute revisions, temporary changes, or reissued pages. Please follow the updating instructions per the attached Controlled Document Instruction Sheet and return the signed Acknowledgment of Receipt form.

If you have questions or require additional information, please contact me at (440) 280-5589.

Very truly yours, David 1. Bauguess, Supervisor Emergency Planning Unit DLB:byr Enclosure cc:

NRR Project Manager NRC Resident Inspector NRC Region Ill, Incident Response Center w/attachments 5A

FIRSTENERGY CORPORATION PERRY NUCLEAR POWER PLANT UNIT I &2 ACKNOWLEDGMENT OF RECEIPT Title Emeraency Plan ImRlementing Instructions EPI-B13/ Rev.3 Control No. 60 Letter No./Date PY-CEI/NRR-2728L / Auaust 5. 2003 Signature Title Date Return to:

Perry Nuclear Power Plant Attn: B.Y. Richardson, A240 P. O. Box 97 Perry, Ohio 44081

FIRSTENERGY CORPORATION Perry Nuclear Power Plant Controlled Document Instruction Sheet Manual: Emergencv Plan Implementina Instructions EPI-B13/ Rev.3 Control Number 60 Revision Number 3

Insert EPI-B13/ Rev 3 Remove and Rerplace Reissue Entire Document

PERRY NUCLEAR POWER PLANT Pe EPumBe 3

Title:

Use Category.

Determination of Core Damage In-Field Reference Under Accident Conditions

Revo:

Page

.~~~~~~~~~~3 f2 PNPP 0 :

-: -0 :

CONTRE ED COPY No.

INFORMATION

- -:0 X -: -f5 iONLY DETERMINATION OF CORE-DAMAGE UNDER ACCIDENT CONDITIONS Effective Date:*-

r731-3 Preparer:

Joe Lvnch

-I 3 Date

PERRY NUCLEAR POWER PLANT i Procedure Number.

EPI-B13 I

Determination of Core Damage Under Accident Conditions Use Categoy.

t In-Field Reference Revision:3*

Page I

2 of 23 I-TABLE OF CONTENTS

  • for A.

"'I V. WM 1.0

- PURPOSE Page 2.Q, i SCOPEl 3.0 DEFINITIONS 4.0 PROCEDURE DETAILS 4.1 Responsibilities 4.1.1 Core Thermal Hydraulics Engineer 4.1.2 Post Accident Sampling Teams 4.2 Actions 4.2.1 Assessment of Core Damage Based on Containment Dose Rate' 4.2.2 Assessment of Core Damage Based on Sample Results 5.0 6.0 7.0 RECORDS REFERENCES SCOPE OF REVISION 3

4 5

6 6

6 6

6

.6 8

11 11 12 14 15 16 17 18 19 20 21 23 ATTACHMENTS - Dose Rate at Containment Monitor

- Zirconium - Water Reaction Calculation Power Correction Factor Calculation odine-131 Activity vs. Core Degradation

- Xenon-133 Activity vs. Core Degradation

- Cesium-137 ACTIVITY vs. CORE DEGRADATION

- Krypton-85 Activity vs. Core, Degradation

- Estimate of Core Damage Data Sheet for Attachments 4, 5, 6, 7

- Ratios of Isotopes in Core Inventory and Fuel Gap

11 PERRY NUCL LAA POWER PLANTANT O e PrsNmbe

Title:

~

~~

Use Categorfr.

Determination of Core Damage In-Field Reference Under Accident Conditions,

.~~~~~~~~~~~~~~~~~~~~

3 of

.2.

1.0 PURPOSE This instruction provides two methods to estimate reactor core damage.

Method #1 provides methods or-indications of reactor core damage which may be utilized during the event. This method primarily utilizes i ncreased radiation levels from the Containment (X) and/or Drywell (DW) detected by the Post Accident Radiation Monltorsm (D19).

Method #2 provides a manual method to estimate the extent of core damage. This method is based upon odine-131 and Cesium 137 concentration in the reactor coolant, and Xenon-I 33, Krypton-85 and Hydrogen in the Containment atmosphere. Core damage is determined/verified via calculated activity ratios of several isotopes and the presence or absence of hydrogen. This method relies on samples of reactor coolant and/or other designated samples. Method # is best utilized at the conclusion of the event to more accurately estimate reactor core damage.

1.1 Method #1 Radiation levels as indicated on Drywell and/or Containment DI 9 radiation-monitors are compared against Attachment 1. illustrates dose projections for various reactor core states.

Curve #1 is a projection for 100% Inventory Release, 100% Fuel Damage and potential core melt. Curve #4 is based upon No Clad failure, 100%

Coolant Inventory Release. Attachment 1. is used as a. referenice to estimate the percentage or type of core damage.

NOTE 0 ; 0., i' -, 7Fa-Ier (O In conjunction with the Instruction Gross Cladding NFallure ONl-J41-i)l, Process Radiation Monitors (DI7s) on Main Steam Lines, arid Atrea Radiation Monitors (D21) in Containment and Drywell-can also be utilized -s indicators of core damage.

I I PERRY NUCLEAR POWER PLANT ii PuNumbt Tle:

Use Category Determination of Core Damage In-Field Reference Under Accident Conditions 1.2 Method #2 This method is based upon odine-131 and Cesium 137 concentration in the reactor coolant, and Xenon-133, Krypton-85 and Hydrogen in the Containment atmosphere. Core damage is deterninedverified via calculated activity ratios of several isotopes and the presence or absence of hydrogen.

NOTE Method #2 is best suited for estimating the extent of the core damage at the conclusion of the event. A sample of reactor coolant taken early in an event may generate results not representative of core conditions. Additionally reactor coolant samples may have to be shipped off site for accurate analysis.

Analyses in this procedure are based upon fission product inventories in the core of a Reference Plant. A BWR 6 with Mark IlIl containment was used as the reference plant, operating at 102% of rated thermal power for 1095 days (3 years). Specifications of the Reference Plant vs. Perry Nuclear Power Plant (PNPP) are considered to be equivalent for the purposes of this procedure and any slight deviations in comparison to the uncertainties of fission products release fraction and other assumptions is insignificant. Either of these methods are qualitative in nature and are to be used as an estimate of fuel clad failure, fuel overheat, or fuel melt 2.0 SCOPE The use of Process Radiation Monitors (D17) on Main Steam Lines, D19 or Area Radiation Monitors (21) in Containment and Drywell can be utilized as indicators of core damage.

NOTE D17s on the Main Steam Lines should only be utilized for a core damage indicator if the Main Steam Isolation Valves MSIVs) are not shut.

PERRY NUCLEAR POWER PLANT ProcedureNumber:

_E PI-B133 Wte:

Use category Determination of Core Damage In-Field Reference Under Accident Conditions EPI-B13 and ONI-J1I 1-1 can be utilized to project the extent of core damage during the early phase of an accident. EPI-B13 also provides methods to estimate the extent of core damage in an accident.

- 0
DEFINITIONS:-

30 DEFINITIONS 0000 0

;0 tS00 3.1 Core Damaae Cateaories 3.1.1 No damage refers to a condition i which no positive-indication of core damage has been detected. Fuel cladding temperatures are below 1 500 0F and fission product releases are limited to radionuclides normally present in the reactor coolant. This includes small pinhole defects previously identified.-

3.1.2 Cladoing damage Is a degradation of the fuel cladding resulting in the release of fission products normally present in the fuel rod gap. Significant cladding damage is expected to beginat temperatures of approximately 15000F.

3.1.3 Fuel Melt (Overheating damage) occurs when fuel temperatures rise to approximately 2200 0F and fission products are released from the fuel pellets themselves.

3.2 Reference Plant Specifications BWR 6/Mark IlIl Rated Thermal Power (100% /102%)

Number of Fuel Bundles Reactor Coolant Volume Suppression Pool Volume E

Total Primary Coolant Volume Drywell Atmosphere Volume Containment Atmosphere Volume Total Atmospheric Volume 3579 1 3650 MWt 748 Bundles 2.46 x 108-ml,-t f0:;i 3.07 x 109 m1 3.92 x 109 ml 7.77 x 109 cc 3.25 x 1010 cc 4.0 x 10 cc

PERRY NUCLEAR POWER PLANT I.Piocedue NumberEPI-13 Tifs:

Use Category Determination of Core Damage In-Field Reference Under Accident Conditions

-lf 2 3

4.0 PROCEDURE DETAILS 4.1 Responsibilities 4.1.1 Core Thermal Hydraulics Engineer Utilize Method I or Method 2 and provide the results to the Radiation Protection Coordinator or Emergency Coordinator as soon as available.

l 4.1.2 Post Accident Sampling Teams Collect and analyze reactor coolant and/or containment atmosphere samples in accordance with SOI-P87, "Post Accident Sampling Systems and CHI-0053, Operation of the Gamma Spectroscopy System".

4.2 Actions 4.2.1 Assessment of Core Damage Based on Containment Dose Rate NOTE This is a quick and rough estimate of core damage.

Dose rate at the D19 Containment Radiation Monitor (Attachment 1) provides theoretical curves of gross gamma dose rate versus time for a range of potential source terms. To determine the meaning of the measured dose rates: -

1.

Obtain the time after reactor shutdown and Containment dose rate reading.

2.

Locate the intersection point of the dose rate and time after shutdown on the graph.

0PERRY NUCLEAR POWER PLANTPreu Nubyer:EPI-13

Title:

Use Cateor.

Determination of Core Damage In-Field Reference Under Accident Conditions loage

3.

Determine the percent fuel inventory released to the Containment (X) air corresponding to the measured dose rate. Interpolate between curves for-a closer estimate. Relate the percent fuel inventory released to the approximate source and damage estimate as indicated below.

Curve No.

.I

%Fuel

- Inventory Released Estimate 100 10 1

1 2

Aproximate Source and Damage 100% Fuel Damage, potential core melt Total clad failure, core partially uncovered Approximately 10% clad-failure 100% coolant release 3

.4 NOTE The curves represent direct readings from the Containment Post Accident Radiation Monitors (1D19-N200A&B), at elevation 689 feet, inside containment.

The curves account for the finite Containment volume seen by the detector but -

do not account for any physical or shielding characteristics of the.n motor or calibration uncertainties.

p

~~~~~~~~~. &-

NOTE 2 The curves assume-that only airborne noble gases and odiris aresidnificant.

Sprays (if used) would make the.iodine and any particulate contribution -

insignificant. However, particulate plateout on surfaces and direct shine doses from components may make the readings unreliable. The calculation of monitor response does not include any particulates, since the noble gases and iodine are the most significant contributors to dose rate In the Containment.

i I' -

PERRY NUCLEAR POWER PLANT P

Procedure Number

Title:

s Use Categrr.

Determination of Core Damage

)

In-Field Reference Under Accident Conditions NOTE 3 100% Fuel Inventory = 100% Noble Gas, 25% Iodine.

NOTE 4 If the radiation levels from the Containment Post Accident Radiation Monitors, (1Dl9-N200A&B) are below the maximum radiation levels predicted for release of 100% of the normal operating coolant activity, including the maximum allowable iodine spike, it is assumed that no core damage exists.

NOTE 5 See ONII 1-1, Gross Cladding Failure for additional cladding failure indicators.

NOTE 6 (Zirconium-Water Reaction Calculation) may be completed if the Hydrogen Monitoring System is operable, and registering hydrogen concentrations. This calculation generates the % of-cladding reacted.

/

NOTE 7 Per RTM 96 (NRC Response Technical Manual), if the Hydrogen concentration is 2%, cladding failure may be indicated.

4.2.2 Assessment of Core Damage Based on Sample Results

1.

Collect and analyze the post accident samples utilizing SOI-P87, "Post Accident Sampling System" and CHI-0053, "Operation of the Gamma Spectroscopy System". Use the time of reactor shutdown for sample time to achieve the correct decay time.

I.

Procedure Number PERRY NUCLEAR POWER PLANT eb-B-ne:

Use Categor-Determination of Core Damage

-In-Field:Reference Under Accident Conditions.

e

Pag of 2
2.

Using the Power Correction Factor Calculation equation (Attachment 3), perform the following Power Correction Factor Calculation for each isotope to be'-itilized In core damage assessment on the data obtained in Step 1 (1-131, Xe-133, Cs-137, Kr-85). Multiply these correction factors bythe decay corrected uCi/unit volume -to normalize the activities to the Reference Plant Data Base.

Correction Factor for sotope:-

f 0~~-

-1095AIfL = -

3651(1-e X, ;{ (

.41TIjj ei~ }X f 0

_16~

-O Where:

- j

= A given operating -period where the steady state of power level variation is less than +/-20%. A minimum of 60 days of power correction must be performed.

Ai

= Decay Constant for isotope I (day -1) (listed on )

P

= Steady Reactor Power of operating periidi(MWt)

T.

= Duration of operating period j (ay)a) 0~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

= Time between the end of operating period j and the time

_j of last reactor shutdown (day) This' equals zero for operating period immediately prior to accident.

3651 = Average operating power (MWt) for Reference Plant 1095 = Continuous operation time (day) for Reference Plant

PERRY NUCLEAR POWER PLANT iv Procedure Number

~EPI-13 TiVe:

Use categoi.

Determination of Core Damage In-Field Reference Under Accident Conditions R..*lof NOTE A spreadsheet may be used to perform the above calculation.

3.

Utilize Activity vs. Core Degradation (Attachments 4 through 7) and the normalized activities calculated in Step 2 to obtain the Upper Release, Best Estimate and Lower Release values pertaining to core damage. Record these results on the Estimate of Core Damage Data Sheet (Attachment 8).

4.

Perform uActivity Ratio for Noble Gases calculations and Activity Ratio for lodines calculations (Attachment 9), using non-normalized reactor water activities for each isotope listed in.

5.

Determine the Best Estimate of core damage type by comparing the ratios calculated in Step 4 to the Core Inventory and Fuel Gap Ratios. A ratio equal to or greater than the listed Fuel Gap ratio indicates cladding failure and a ratio equal to or greater than the Core Inventory indicates fuel melt. Record results on Attachment 9.

6.

Complete the Zirconium-Water Reaction Calculation (Attachment 2).

NOTE gen concentrations are obtained'from Containment Hydrogen Monitoring m or performed by grab sample analysis.

7.

Utilizing all of the above information and/or calculations and the following discussion, complete the Estimate of Core'Damage Data Sheet (Attachment 8), formulating the Best Estimation of Core Damage".

Plant parameters/indications that should be considered along with the analysis data include:

The loss of reactor coolant volume below the TAF region (Top of Active Fuel) can result in core overheat and subsequent clad and fuel damage.

i E PERRY NUCLEAR POWER PLANT Procedure Number

_______EPI-B I13 te:

use C-teg.-

Determination of Core Damage In-Field Reference Under Accident Conditions Pa

_~~~~~~~~~~~~~~~~~~3 1

of 23 The presence of hydrogen, the result of a Zirconium - Water reaction, without significant amounts of less volatile elements, is ndicative of a clad overheat condition without fuel melt.

- @ - The presence of unusually high concentrations of Strontium-92 and Lanthanum-140 orother low volatile elements, such as Barium, Ruthenium and Tellurium, implies some degree of core melt.

5.0 RECORDS 5.1 Records HandlingA Non,-

5.2 Records Capture The following records are completed/generated by this document:

Qualit Records Power Correction Factor Calculation (Attachment 1)

Zirconium - Water Reaction Calculation (Attachment 2)

Estimate of Core Damage Data Sheet (Attachment 8)

Non-Quality Records None

6.0 REFERENCES

6.1 Developmental NEDC-33045P, Revision 0, aMethods of Estimating Core Damage in BWRs"

PERRY NUCLEAR POWER PLANT 1

durNumbet

_EPI-B 13 Tite:

Use Catego.

Determination of Core Damage In-Field Reference Under Accident Conditions Ronv:P g

o2 NEDO-22215, Procedures for the Determination of the Extent of Core Damage Under Accident Conditions" TNUS Drywell Radiation Plots and Technical'Basis Dose Rate Plots Memo# PY-NUS/CEI-705 PY-NUS/CEI-705 letter dated 5/10/83 Radioactive Decay Data Tables, David C. Kocher, 1981 USAR Table 6.2-5 6.2 Imglementation CHI-0053, "Operation of the Gamma Spectroscopy System" ONIJ1 1-1, "Gross Cladding Failure" RTM-96, USNRC Response Technical Manual 6.3 Commitments L00053 All Sections l L02480 All Sections l L02481 All Sections l L02482 All Sections 7.0 SCOPE OF REVISION Rev. 3

1.

Updated to new Writers Guide format

2.

Replaced reference to cancelled RPI-1313 to replacement instruction CHI-0053.

3.

Updated reference to NEDC-3304P, Methods of Estimating Core Damage in BWRs".

4.

Added reference to NUS Drywell Radiation Plots and Technical Basis" memo # PY-NUS/CEI-705, the basis of the origination of Attachment 1.

5.

Added Note 4, page 8,indicating no cladding challenge when XIDW D19 indicate radiation levels are below projected levels for 100% coolant release.

6.

Added Note 5, page 8 indicating ONI-J1 1-1 Gross Cladding Failure for additional cladding failure indicators.

r PERRY NUCLEAR POWER PLANT-EPIB3 Tie:

Use Categwy:

Determination of Core Damage In-Field Reference Under Accident Conditions

.~~~~3 13of2

7.

Referenced use of Hydrogen -,monitors and Attachment 2 as method to determine cladding activity %&-

8.

Added definitions in Section 3.1, clarifying core status.

9.

Added a Note in-Section 1.0 clarifying that reactor core coolant sampling should be performed at the conclusion of an event and may have to be shipped off site for analysis.

10.

Added notes to Attachment 1, explaining what each curve represents. Notes are based upon procedure text explanations.'

11.

Added a Note in Section 2.0 stating D17s on the Main Steam Lines should only be utilized for a core damage Indicator if the Main Steam Isolation Valves (MSIVs) are not shut.

12.

Loose Parts monitoring has been eliminated. Reference to this system has been removed.

13.

Note number 7 in Section 4.2.1 added to reference RTM 96, Response Technical Manual (NRC) indicating possible cladding damage if 2% hydrogen concentration is present

14.

Added Note 6, page 8, referencing Attachment 2.

15.

Updated commitments to reflect PASS updates.

I

PERRY NUCLEAR POWER PLANT ProcpdueNwnber Titw:

Use Categoiy:

Determination of Core Damage General Skill Reference Under Accident Conditions 3i 14 ATTACHMENT 1: DOSE RATE AT CONTAINMENT MONITOR Page of I

t.

Curve I 100% Inventory release, 100% Fuel Damage, potential core nelL Curve 2 10% Inventory release, Total clad failure 100%), core partially uncovered.

Curve 3 1% Inventory released, Approximately 0% dad failure.

Curve 4 No clad failure, 100% coolant inventory release.

i 111.1;I1, i

4' j,,

2 3

4 5 7

1 0 2

3 4 5 6 79 2

3 4 5 79 TIME REACTOR POWER 15 LESS MMAN 4%

M(,S)

PERRY NUCLEAR POWER PLANT e-c I

Ner:

E PI B I13.

Tlte:

Determination of Core Damage Under Accideht Conditions-Use Category:

In-Field Reference

- : f:-

Revision:

I 3*

IPage 1 2

ATTACHMENT 2: ZIRCONIUM - WATER REACTION CALCULATION Hydrogen concentration:

- Page 1 of I I Date/Time:, _

/_

Calculation:

%H:- (Fzr)x(Mzr)x(C) xl=O

[(Fzr)X(M ;TX(C)1+V where:-

'FZr Fraction of Zirconium Reacted Mzr Total Mass of Zirconium 1.60E5 Ibm C

= SCF H2 per bm of Zirconium = 8 SCF H2Ilbm V

= Dilution Volume

.42E6 ft3 Fz (I.28E8) - (I.28E6 x' %H )

F =

(1.42E6)(

)j' (1.28EB) -(1.28ESx 4.I1~

I, 'i 4 Fir =

% Cladding Reacted -

Fzr x 100 =

I PERRY NUCLEAR POWER PLANT PdureNumbefEPI-133 Titoe:

Use Category:

Determination of Core Damage In-Field Reference Under Accident Conditions RevIs*on:

P;ge 3pag16 of 23 ATTACHMENT 3: POWER CORRECTION FACTOR CALCULATION Page 1 of 1 Correction Factor for Isotope 361 -1095 A1 3651 i=

{ P DECAY DECAY ISOTOPE CONSTANT CORRECTED CORRECTION NORMALIZED (Ai)

ACTIVITY FACTOR ()

ACTIVITY 1-131 Primary 8.62E-2 Coolant Xe-133 Containment 1.32E-1 Gas X

Cs-137 Primary 6.29E-5 Coolant Kr-85 Containment 1.77E-4 G a s NOTE:

Some isotopes will be difficult to analyze immediately following an accident, specifically Cs-1 37 and Kr-85, which would be best utilized for core damage estimates several weeks after shutdown, allowing for sufficient decay of the shorter lived interfering isotopes.

r

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4

-1

=w PERRY NUCLEAR POWER PLANT o

Number:EPI-133 Tlte:

U

-se Category:

Determination of Core Damage In-Field Reference Under Accident Conditions Revon

-t;0

  • ~~~~~~~~~~~~~~~~~1 of

.2=3 ATTACHMENT4: IODINE-131 ACTIVITY vS. CORE DEGRADATION Page of I c;-

-FUEL MELTDOWN IPER RELEASE LMTS

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i F, Ea= Procedure Number PERRY NUCLEAR POWER PLANT UeCtgr P-1

Title:

Use Categy Determination of Core Damage In-Field Reference Under Accident Conditions -

PSa0 Page ATTACHMENT 5: XENON-133 ACTIVITY vs. CORE DEGRADATION Page 1 of I A

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Procedure Number EPI-Bi3

Title:

X

Use Category.

Determination of Core Damage In-!ield Reference Under Accident Conditions :

-R 8

ATTACHMENT 6: CESIUM-137 ACTIVITY vs. CORE DEGRADATION Page lofI1 ---

FUEL MELTDOWN WU!ER RELEASE LIUIT BEST ESTIMATE

'F LOWER RELEASE UtJIT

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PERRY NUCLEAR POWER PLANT i; rocedure Number This:

Determina~~n of Core Damage Use Categor I.

Determnination of Core Damage

\\

In-Field Reference Under Accident Conditions r

lPage ATTACHMENT 7: KRYPTON-85 ACTIVITY vs. CORE DEGRADATION Page 1 of I S

II I-I I.

a i

V l

SCLADDING FAILURE l

to to IO S PFUEL MELTDOwN

PERRY NUCLEAR POWER PLANT PdumNumber

Title:

Use Category-

.Determination of Core Damage In-Field Reference Under Accident Conditions 3
Page ATTACHMENT 8:- ESTIMATE OF CORE DAMAGE DATA SHEET FOR ATTACHMENTS 4.5. 6.7 Page of 2

-Upper Release Best Estimate Lower Release Iodine 131 Cladding (liquid)

Failure Fuel Meltdown Xenon 133 Cladding (atmosphere)

Failure Fuel

_ _ Meltdown XX__:

Optional Cladding Cesium 137',

Failure

_._X_:____

(liquid)

Fuel M eltdow n__

Krypton 85 Cladding 0

(atm osphere)

Failure

_i;___:_____._

Fuel

_ M eltdown Cladding Failure:

Fuel Meltdown:

EIYes / ONO MYes /-ENo :

Cladding reacted:

Additional Plant Parameters/Indications:

It-I Did Reactor Coolant drop below the Top of Active Fuel?

E OYes / nNo

- f S:

Lowest known level:

Presence of low volatile elements?

DYes /

No Isotopes:

PERRY NUCLEAR POWER PLANT ePNuber

~EPI-133 Ttle:

Use Category.

Determination of Core Damage In-Field Reference Under Accident Conditions Revisiof:

ATTACHMENT 8: ESTIMATE OF CORE DAMAGE DATA SHEET FOR ATTACHMENTS 4. 5.6.7 Page 2 of 2 Best Estimation of Core Damage:

Fuel Overheat Indications JYes / [No

/6 Cladding Failure __

% Fuel Meltdown Completed By:

Date Time I

I A

I~'-I Procedure Number PERRY NUCLEAR POWER PLAN-

-PI-B

Title:

Use Ctegory Determination of Core Damage In-Field Reference Under Accident Conditions Revison

.~~~~~~~~~~~~~~~~~~3 f2 ATTACHMENT 9: RATIOS OF ISOTOPES IN CORE INVENTORY AND FUEL-GAP Page of 1-

- ActiVty Ratio-Fuel Gap 2 Core Inventory-Calculated.

Isotope Half life Noble Gas:

Kr-87 Kr-88 Kr-85m Xe-133 76.3 min.

2.84 hr.

-4.48 hr.

5.25 day 0.0234 0.0495 0.023 1;0 0.233 0.33 0.122 1.0

-I Iodine:

1-134 1-132 J/

1-135 1-133 1-131 52.6 min.

2.3 hr.

6.61 hr.

20.8 hr.

8.04 day 0.155 0.127 0.364 0.685 1.0

. I 1.46

-1.97-2.09

1.0 Activity Ratio =

for Noble gases Noble as Isotope concentration Xe-133 concentration Activity Ratio-I odine iSotoDe concentration for lodines 1-131 concentration Type of core damage best estimate:

Fuel Gap (Cladding Failure)

Core Inventory (Fuel Meltdown)

Yes I No Yes I No

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