Text

Rev 1 to Plant Emergency Procedure PEP-362, Interpretation of Liquid & Gas Samples for Core Damage Assessment
	ML18018B953
Person / Time
Site:	Harris
Issue date:	03/04/1985
From:	John Miller; CAROLINA POWER & LIGHT CO.
To:	;
Shared Package
ML18018B952	List: ML18018B951; ML18018B953;
References
	PEP-362, NUDOCS 8505230407
	Download: ML18018B953 (118)
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CAROLINA POWER 6 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT PLANT OPERATING MANUAL VOLUME 2 PART 5 PROCEDURE TYPE:

PLAHT EMERGEHCY PROCEDURE NUMBER:

PEP-362 TITLE:

IHTERPRETATION OF LIQUID AHD, GAS SAMPLES FOR CORE DAMAGE'SSESSMENT REVISION I APPROVED:

Signature Date TITLE:

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TABLE OP CONTENTS Table of Contents List of Effective Pages 1

0 PURPOSE 2 0 REFERENCES 3.0 5

0 6.0 7.0 8 0 9

0 10.0 Mass Vs.

2.1.

Emergency Plan References 2.2 Referenced Plant Emergency Procedures 2,3 Other References RESPONSXBILITIES DEPXNXTIONS/ABBREVIATIONS GENERAL INITIATING CONDITIONS PRECAUTIONS AND LIMITATIONS SPECIAL TOOLS AND EQUIPMENT PROCEDURE STEPS DIAGRAMS/ATTACHMENTS l.

Xsotope Release Worksheet 2

Sample Data 3 ~

Sample Space Mass Calculations 4.

Equivalent Power Level Calculations 5.

Equivalent Power Level Worksheet for Kr-85m 6 ~

Equiva1.ent Power Level Wozksheet for Kr 87 7..

Equivalent Power Level Wozksheet'or Kr 88 8 ~

Equivalent Power Level Wozksheet. for Xe-135 9 ~

Equivalent Power Level Worksheet for I-132 10'quivalent Power Level Worksheet for I-133 11.

Equivalent Power Level Worksheet. for I-135 12'quivalent Power Level Worksheet for Te-129 13..

Equivalent Power Level Worksheet for La-142 14'quivalent Power Level Worksheet for Pr-144 15.

Equivalent Power Leve1. Worksheet for Xe-131m 16.

Equival.ent Power Level Worksheet for Xe-133 17.

Equivalent Power Level Worksheet foz Xe-133m 18.

Equivaler t Power Level Wozksheet for I-131 19.

Equivalent Power Level Worksheet foz Te-132 20.

Equivalent Powez Level Worksheet for Ba-140 21.

Equivalent Power Level Wozksheet for La-140 22'eport to SEC on Core Damage Status 23'ater Density Ratio (Temperature vs. Standard Temperature and Pressure) 24 Standard Temperatuze and Pressure H20 Containment Level 25.

Equivalent Power Level for Cs-134 Based on Average Power During Operation 26 'elationship of X Clad Damage with X Core Inventory Released of Kr 87 27.

Relationship of Z Clad Damage with X Coze Inventory Released of Xe-131m

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Relationship of X Clad Damage with g Core Inventory Released of Xe-133 f ~pae 2

5 5

6 7

7 16 18 19 20 22 23 24 25 26 27 28 29 30 31 32 33 34 35.

36 37 38 39 40 42 43 44 45 46 PEP-362 Rev.

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TABLE OF CONTENTS (continued)

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Relationship of X Clad Damage with X Core Inventory Released of I-131 30.

Relationship of X Clad Damage with X Core Inventory Released of I-131 with Spiking 31.

Relationship of X Clad Damage with X Core Inventory Released of I-132 32.

Relationship of X Clad Damage with Z Core Inventozy Released of I-133 33.

Relationship of X Clad Damage with X Coze Inventory Released of I-135 34.

Relationship of X Fuel Overtemperature with X Core Inventory Released of Xe, Kr, I, Cs oz Te 35.

Relationship of X Fuel Overtemperatuze with X Core Enventory Released of Ba, Sr or La 36.

Relationship of Z Fuel Melt with X Core Inventory Released of Xe, Kr, I, Cs oz Te 37.

Relationship of X Fuel Melt with X Core Inventory Released of Ba, Sr, or La 38.

Relationship of X Fuel Melt ~ith X Core Inventory Released of Pz 39.

Isotopic Activity Ratios of Fuel Pellet and Gap 40.

Containment Hydrogen Concentration Based on Zirconium - Water Reaction 41.

Percent Noble Gases in Con)ailment for Containment Volume of 2x10 ft 47 49 50 53 56 57 59 PEP-362 Rev.

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LIST OF EFFECTIVE PAGES

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1.0 PURPOSE I

The purpose of this procedure is to partially implement Section 4.4, "Assessment Actions," of the SHNPP Emergency Plan, which is a regulatory commitment.

This procedure provides the means to relate coze damage with measurements of zadionuclide concentrations and with auxiliary indications (reactor vessel level, core exit thermocouples, con-tainment hydrogen and radiation levels) such that it is possible to distinguish the fouz major fuel conditions:

no damage, clad failure, fuel overheat, and core melt.

The approach used is the measurement of fission product concentra-tions via the post-accident sampling system and isotopic analysis..

These results aze corrected to account foz sample pzessures and temperatures, precursor effects, and zadioactive decay to obtain the total activity release for the various iso-topes.

These are compared to the initial. activity available for release from the core; the quantity and type of isotopes released are used to estimate the type and extent of core damage.

2o0 REFERENCES 2il EMERGENCY PLAN REFERENCES 1

Section 4.4>. "Assessment Actions" 2.2 REFERENCED PLANT EMERGENC7 PROCEDURES 1.

PEP-218, "Accident Assessment Team Leader" 2.3 OTHER REFERENCES 1.

CRC"828, "Isotopic Analysis for Coze Damage Evat.uation"'.

Westinghouse Owners Group document, "Coze Damage Assess-ment Methodol'ogy," November, 1984, Revision 2.

3' RESPONSIB'ILITIES 1 ~

The Accident Assessment Team is responsible for performing this,procedure.

4.0 DEFINITIONS/ABBREVIATIONS Hone Appl.icable 5.0 GENERAL It is not necessary to have a complete isotopic analysis or to perform calculations for all isotopes listed on Attachment 1 to estimate core damage.

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5.0 GENERAL (continued)

A single isotope, either Xe-133 or I-131, could be us'ed as an indication for all three levels of core damage, however, fuel melt is best comfirmed by measuring Promethium, Lauthanum,

Bazium, oz Stzontium isotopes, and fuel overtemperature is best comfirmed by measuzing Cesium-oz Tellerium isotopes.

Stzontium isotopes are included on Attachment 1 for long term damage evaluation, since quantitative analysis of these isotopes may take sevezal days.

In order to determinefuel overheat or melt using noble gas or Iodine isotopes, it is best to have values foz Xe-133 or I-131 activity,. respectively.

It should be realized 'that it is unlikely. that all isotopes listed on Attachment 1 can be resolved with available detectors.

6.0 INITIATING CONDITIONS

'1.

The. Site Emergency Coordinator has decided that this procedure should be implemented.

7.0 PRECAUTIONS AND LIMITATIONS

'.1

7.2 ACCVKLCY

yha categories of core damage are considered to overlap considerchiy; this is, however, consistent with the intent of the procedure to provide a generalized estimate of the extent of core damage.

SPQZNG PHENOMENA: If major transients in-core power, pres-

suze, or temperature Pave. occurred prior to shutdown,'odine concentrations may indicate a significantly more severe damage state, and should therefore be considered see Attachment 30.

7' OXYGEN CONCENTRATION: If a significant decrease in containmeat oxygen concentratioa has occurred since

shutdown, this may indicate a hydrogen burn has occurred, aad should be considered in evaluating containment hydrogen Wevels-m an indicator of core damage.

7 '

STEAM GENERATOR TUBE RUPTURE OR OUTSIDE CONTAINMENT LOSS OF COOLANT ACCIDENT Zf core activity has been released to systems not covered by the Post Accident Sampling System, (e.g.,

secondary

system, Component Cooling Meter), this procedure will give a non-consezvative estimate of core damage.

This vill be noted as auxiliary indicators esti" mating more severe damage than the isotopic analysis.

If accurate samples of these systems aze available as well as reasonable estimates of the sample space volume or mass, the methodology of this procedure may be applied to improve the accuracy of the isotopic zelease estimate of the core damage.

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7.5 INADE UATE CORE COOLINQ CONDITIONS:

Th~is procedure will estimate coze damage status at time of> sampling. If inadequate core cooling occurs after qr during sampling, the I

actual core damage status would be mope severe.

8.0 SPECIAL TOOLS AND E UIPMENT Scientific Calculatoz 9'

PROCEDURE STEPS NOTE:

Section 9.8 may be implemented independent of sections 9.1 to 9.7 to estimate core damage-status by auxiliary indications'Additionally, samples are only requized from locations consistent with accident conditions.

For example, if no coolant has been released to containment, then containment sump and air sample analysis is not required.

9.1 As per Procedure CRC"828, "Isotopic Analysis foz Core Damage Evaluation," request the Plant Monitoring Team Leader to sample the Reactor Coolant System, ECCS Recirculation

Sumps, and Containment Atmosphere, and, perform isotopic analysis.

Accident Assessment Team shall be contacted at the time samples are being drawn so that plant status can be recorded on Attachment 2.

Section 9.6 of. this procedure should be implemented as samples are being processed..

When sample analysis results are transmitted to the Accident Assessment Team,. they will complete all remaining items on Attachment 2

and continue in this procedure.

9.2 On Attachment 1,

CoLumn 11, enter the sample specific activity (pCi/g or pCi/cc) for each isotope, as determined fzom the analysis of Step 9.1.

9.3 On Attachment 1, Column 1, enter the time after shutdown until the sample was analyzed (hrs.) from Attachment 2, lines 6,

12 and 19, for R!actor Coolant System (R),

ECCS Recirculation Sumps (S) and Containment Atmosphere (A) for each analyzed isotope.

9.4 Calculate the sample density ratios by completing Attachment 3 (Part A) per the foLlo~ing instructions:

NOTE:

If a sample is repozted per unit mass (pCi/g), use a

density ratio = 1.0 on Attachment 1, Column 13.

Lines 1 and 2:

Containment Atmosphere temperature and pressure at time of sampling from Attachment 2, lines 14 and 15.

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9.0 PROCEDURE STEPS (continued)

Lines 3 and 4:

Containment Atmosphere Sample temperature and pzessure fzom Attachmeat 2, lines 7 and 8 ~

Line 2 x Line 3 line 5

Density Ratio Line 1 x Line 4 Enter calculated value on Attachment 1,

Column 13, for each analyzed isotope's atmosphere sample.

9.4.2 Line 6 Use Reactor Coolant System Sample temperature from "Attachment'2, Line 3 and Attachment 23: Mater Density Batio (Temperature Vs. Standard Temperature and Pressure)

Line 7

Use Reactor Coolant. Sys ter temperature at time of sampling from Attachment 2, Line' and Attachment 23:.

Mater Density Ratios (Temperature Vs. Standard Temperature and Pressure).

Line 7

Line 8:

Density Ratio L n 6

Enter calculated value on AtkacCment 1, Column 13,. for each analyzed isotope's Reactor Coo'lant System sample.

9.4 '

Line 9:

Use ECCS Recirculation Sump Sample temperature from Attachment. 2, Line 9 and Attachment 23: Mater Density Ratio (Temperatuze Vs Standazd Temperature and Pressure).

Line l0:

Use ECCS Recirculation Sump temperature at time of sampliag from Attachment 2, l.ine 8 and 3:

Water Density Ratio (Temperature Vs.

Standard Temperature and Pressure).

Line 11:

Density Ratio

"- L.

Line 10 Line 9 Eater calculated value on Attachment 1,

Column 13 foz each analyzed isotope's sump sample.

9 ~ 5 Calculate the mass oz volume of the three sample spaces by completing Attachment 3, Parts Bp C,

and D per the following iastzuc'tions'.5

~ 1 Line 12:

Containment water level, at time of sampling from Attachmeat 2, Line 10.

Line 13:

Use Attachment 24, Standard Temperature and Pressuze FI>0 Mass Vs. Containment Level to find mass of sump liquid at standard temperature and pressure.

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'.0 PROCEDURE STEPS (continued)

Line 14:

Multiply Standard Temperature and Pressure sump mass by sump Density Ratio.'ine 13 x Line 10.

Enter calculated value on Attachment 1,

Column 15, for each isotope's sump sample.

9.5.2 Line 15: If the pressurizer is empty, assume an otherwise filled Reactor Coolant System and multiply the Reactor Coolant System Density Ratio at time of Reactor Coolant System sampling by Standard Temperature and Pzlssure Reactor Coolant System mass:

Line 7x(2.14 x 10 g).

Line 16: If the pressuriser has a liquid level at time of Reactor Coolant System sampling, sm'ltiply the Reactor Coolant System Density Ratio by Standard Temperature and Pressure Reactor Coojant'ystem and Fressuriser mass:

Line 7 x f(2e14 x 10 g) + (Attachment 2, Line 4)J x (.01) x (3.96 x 10 g).

v Enter calculated value on Attachment 1,

Column 159 for each analyzed isotope's Reactor Coolant System sample.

9;6 Calculate the correction factors for thermal power variation by completing Attachment 4 per the following instructions'.

9.6.1 PART A:

Equivalent Power Level for Lang-Lived Isotopes

[Cs-137, Sr-89,. Sr 90]

Line 1:

Enter number of effective fu11 power days during current core cycle (i.e., previous three years for a three region core) 9 obtained from operating Logs ~

Line 2:

Enter number of effective full power days enpected for current core cycle operation.

'Line 1

Line 3:

Equivalent Power Level = Line 2 Enter calculated value on Attachment 1,

Column 18, for these three isotopes.

9.6.2 VARI 8:

Equivalent Power Level for Short-Lived Isotopes jgr 85m, K-r 87, Kr-88, X-e-135, I-132, I-133, 1-135, Te-129, La-142, Pr-144j PEP-362 Rav.

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9.0 PROCEDURE STEPS (continued)

Line 4: If the reactor thermal Power has been constant over the four (4) days p'rior to shutdown

(<1BX Rated Thermal Power variation from 4-day avezage power level),

then these isotopes have reached equilibrium concen-

trations, and the Equivalent Power Level is that fractional power level.

(For example, 70Z power level is an Equivalent Power Level of 0.70.)

Enter the value on Attachment 1,

CoLumn 18, for these ten isotopes and continue with 9.6.3.

Otherwise, an Equivalent Power Level Wozksheet must be completed for each isotope being analyzed to account for the effects of power changes over the 4-day period.

Using plant operating records, determine the powez history for previous 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months .

Whenever core power Level has changed by more than 10Z of rated thermal

powez, a separate Line on each isotope's Equivalent Power Level wozksheet must be completed.

r.

Instructions for Equivalent Power Level Wozksheets, Attachments 5 through 14:

NOTE:

Column Column Column All tzansient time should be included at the lower power level for conservatism in the calculations.

1: P. - thermal po~er Level for interval (MMt) 3 2: t

~ - duzation of core operation at P

~,

(hrs.)

3 3

3 t + - duration from end of interval until shutdown (hrs.)

C 1

4

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( Xi x Column 2)]

Column Column

(-X x Column 3) 6.:

Cot.umn 1 x Column 4 x Cot.umn 5

After completing the necessazy lines on each isotope's worksheet to cover the previous 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months , add the values recorded in Column 2 for each isotope and verify the sum is 96 houzs

~

Add the values in Column 6 and divide the sum by 2775MW.

This is the Equivalent Power Level - entez this value on Attachment 1, Column 18 foz these ten isotopes.

9.6.3 PBRT C:

Equivalent Power Level for Intermediate-Lived Isotoces

[Xa-131m, Xe-133, Xa-133m, I-131, Te-132P, Ba-140, La-140]

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9.0 PROCEDURE STEPS (continued)

Line 5:

ZR tha reenter thermal poeer has been oonstant aver the thirty (30) days prior to shutdown

(<'.OX Rated Thermal Power variation fzom the 30"day averag power level), then these isotopes have reached equil'brium concentzations, and the Equivalent Power Level is that fractional power level.

(For example, 70Z power level is an Equivalent Power Level of 0.70).

Enter "he value on Attachment 1, Column 18, foz these seven isotopes and continue with 9.6.4.

Otherwise, an Equivalent Power Level wozksheet must be completed for each isotope being analyzed to a count of

'he effects of power changes over the 30-day p riod.

Using plant operating records, determine the p>wer

'istory for the previous 30 days.

Whenever co-.e power level has changed by more than 10Z of rated th rmal po~er, a separate line on each isotope's Equivalent Power Level, worksheet must be completed.

Instructions foz -Equivalent Power Level Workshsets, Attachments 15 through 21:

NOTE ALL transient time should be incLuded at the lower power level for conservatism in, the calculations.

Column':

. Column 2':

Column 3:

P

" the'rmal po~er level for intervaL (MWt) 3 t ~ - duration of core operation at PE (days)

J l

t+- duration from end of intex~aL until shutcvwn days)

4. lt -(X x Column 2)]

e-(Xi x Column 3)

Column 6: Column 1 x Column 4 x Column 5

After completing the necessary lines on each isotope's worksheet to cover the previous 30 days, add the values recorded in CoLumn 2 for each isotope and verify the sum is 30 days.

Add the values in Column 6 and divide the sum by 2775 NW.

This is the Equivalent Power Level - enter this value on Attachment 1,

CoLumn 18 for these seven

~ isotopes.,

PEP-362 Rev.

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9' PROCEDURE, STEPS (continued) l 9.6.4 PART 9:

Equivalent Pauet Level fat Ce-134 Using the Equivalent Power Level foz lang-lived isotopes (Line 3) and Attachment 25:

E uivalent Power Level foz Cs-134 Based on Avera e Power Durin 0 eration, find the Cs-134 Equival.ent Power Level.

( Cycle Operation'efers to age of most burned fuel in core.)

Enter value on Attachment 1, Column 18 for Cs-134.

9.7 Complete Attachment 1 per the following instructions.

I 9 ~ 7 ]

Column 4 e e-(Co lumn 2 x CoLumn 1 )

9.7.2

.Col~ 5.

-(Column 3 x Column 1)

{ifapplicable for isotope) 9.7.3 Column Column 9: (if applicable for isotope) 6 x Column 7 x Column 2 x (Column 4 Column 5)

(Column 3 - Column 2)

(Column 4 - Column 5)

+

(Column 8 x Column 4 )

(if applicable foz isotope) r (This is the isotope activity at time of samplee) 9.7.4 Column 10:

(Column 8) x (Column 4)

Column 9)

(if applicable for isotopes)

NOTE 9.7.5 (This is the fraction of the isotope activity due to initial inventory at shutdown.)

For isotopes with two precursozs (Xe-133, Xe-135 and Te-129) add the two precursor values in Column 10 foz each sample and subtract 1.0; then apply formula fox Column 12 per step 9.7.5.

(Column 10) x (Column 11)

Column 4)

(This accounts for the calculated precursor contribution and for radioactivity decay since shutdown.)

9.7.6 Column 14:

(Column 1.2) x (CoLumn 13)

(This accounts for density variation of sample with the actual medium).

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9.0 PROCEDURE STEPS {continued) 9.7.7 Column 16:

{Column 14) x (Column 15) x 10 (This value is the total activity actually released in the Reactor Coolant System, sump, or containment atmospheze.)

9.7.8 9.7.9 Column 19:

(Column 17) x (Column 18)

(This value is the source term corrected for powez history and power level at shutdown.)

Column 16 x 100Z Column 19 Sum the three values and enter as TOTAL.

{This value is the fraction of. the total inventory available which was actually released to the Reactor Coolant System,

sump, and containment atmosphere.)

9.7.10 Column 21:

AppLicable to noble gases and iodine:

Noble Gases - Divide isotope's Column 20 Total by the Xe-133 Column 20 Total,, if available.

Iodines - Divide isotope's Column 20 Total by the 1'-131

'Column 20 Total, if available.

9.7.LL.

Column 22:

Use Attachments 26-33 oith applicable isotope s Column 20 Total to detetmine.

each isotope's estimate of percentage cladding damage,.

9.7.12 9.7.13 Column 23:

Use Attachments 34 and 33 with applicable isotope s Column 20 Total to datesmine each isotope's estimate of percentage fuel overheat damage.,

Column 24:

Use Attachments 36-38 uith applicabla isotope s Caiman 20 Total to detetmine each isotope's estimate of percentage fuel melt damage.

9.8 Obtain the following general information fzom the data provided from the samples,.plant operating records, control room pezsonnel, Emergency Response Facility Information System and radiation monitors:

9.8.1 Containment Hydzogen 9.8.2 Containment Radiation Monitors Z by volume R/hz 9.8.3 Divide (9.8.2) by 2775 MW and multiply by 1 ~ 125:

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9.0 PROCEDURE STEPS (continued)

(This adjusts the zadioactive levels to core power level and containment volume-)

NOTE'btain ERPIS traces of the following, if possible.

9.8.4 Reactor Coolant Pump status:

9.8.5 RVLIS Duration and depth of uncovery:

9.8'6 Thezmocouples - Superheated Steam?

Y/N Highest tempezatures and duration.'

' eactor Coolant System Pressure:

9.9 Coze Dama e Assessment

'I Isotoaic Anal sis'Prom Attachment 1,

Column 22 through Column 24, each isotope analyzed has yielded a percentage of cladding

damage, fuel overheat, and/or fuel melt.

i'his information should be analyzed to determine how the majority of isotopes are estimating coze damage status'he activity ratios recorded in Cot.umn 21 are used with Attachment 39 to distinguish fuel overheat and clad failure, if required9 if Xe-133 and/or I-131 activity values were available.

Every isotope should predict the same general damage status; thus if any isotope pze.diction is significantly different from the average, its calculations should be reverified, and if necessary, disregarded.

The core damage status should be estimated as follows.'O DAMAGE 0-50X 50-100X 0.-50X 50-100X 0-50X 50-100X (insignificant isotope release)

Clad Failuze Clad Failure Pue1. Overheat Fuel Overheat Fuel Melt Fuel Melt PEP-362 Rev.

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Since it is proba occurred in the l.

estimated core da cate major cl.addi:

degree of fuel ov melting (<1X).

This would be a 1

is emphasized tha value of any one of values.

l.e that more than one type of damage may have zge coze, it is best to predict a range of age.

For'xample, the isotope data might indi-g failuze (50-100X) with indications of some rheat

(<10X) and the possibility of minor fuel gitimate prediction of coze damage status.

It it is not reasonable to predict a specific ategory of damage, but rather to predict ranges Auxilia Indi cat other indication Containment recorded in Zirconium-Ma spond to the Containment value zecorc noble gas iz failure, up cates fuel c

rs'.

Following (ar prior to) isotopic analysis,

,houl.d be evaluated to determine a correlation.

~Idee en - Uae Attachment 40 with the value step 9.8.1 to determine the extent of the

er zeaction.

This should approximately corze-estimate of cladding failure.

radiation Monitors - Use Attachment 41 with the

.'d in step 9'8.3 to determine the 'percentage

.of

~entory released.

Below 0.3Z indicates clad

o 52X indicates fuel overheat, up to 100X indi-1.t..

The fol.lowing in=

core exit thermos Highest cia readings than 1300'F lower limit

~zmation applies to the analysis of RVLIS and

couples, Steps 9.8.4 - 9.8.7.-

temperatures vill be greater than thermocouple thus if the thermocouple readings are greater clad failure may have occurred.

(1300'F is the for clad failure

)

. If any Reac vill be goo should occu or Coolant Pump's aze operating, thermocouples indicators of clad temperatuze no core damage due to cooling by steam - vater forced flow.

If Reactor Coola t Pump's vere stopped, the following apply:

Mo generali uncovered; indicate no occurred.

.ed core damage can occur if the core has not o if RVLIS indicates full range and thermocouples superheated

steam, no generalized damage has If RVLIS ir core OR the core has ur depending c

uncovery.

iicates a liquid level oE less than 3.5 ft. in"the mocoupl.es indicate superheated

steam, then the

overed and core damage may have occurred a the time after shutdown, duration and depth of PEP-362 Rev.

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9.9 Core Dama e Assessment (continued)

If RVLIS indicates a liquid level between 3.5 ft. and the top of the core, then thezmocouple readings should be monitored for supezheated steam temperatures to determine if core uncovery has occurred.

9.10 Complete Attachment 22:

Report to SEC on Core Dama e Status, and deliver it to the SEC.

10.0 DIAGRAMS/ATTACHMENTS 1.

20 3 ~

4 ~

5.

6.

7.

8.

9'0.

11.

12.

13.

14.

15.'6'7.

18.

19 20.

21.

22.

23.

Pres 24.

Leve 25

'6

~

27.

28.

29.

30

'1.

Isotope Release Worksheet Sample Data Sample Space Mass Calculations Equivalent Power Level Calculations Equivalent Power Level Wozksheet for Equivalent Power Level Worksheet for Equivalent Power Level Wozksheet foz Equivalent Power Level Worksheet for Equivalent Power Level. Wozksheet foz Equiva1.ent Power Leve1. Worksheet for EquivaIent Power Level Worksheet for Equivalent Po~er Level Worksheet foz Equivalent Power Level Wozksheet for Equivalent Power Level Worksheet for Equivalent Power Level Worksheet for Equivalent'ower Level Wozksheet 'for Equivalent Power Leve1. Worksheet for.

Equivalent Powez Level Wozksheet foz Equivalent Power Level Vorksheet for Equivalent Power Level Worksheet for Equivalent Powez Level Worksheet for Report to SEC on Coze Damage Status Water Density Ratio (Temperature vs.

sure)

Standard'emperature and Pzessure H20 1

Equivalent Power Leve1. i'or Cs-1.34 Bas During Operation Relationship of X Clad Damage with Z of Kz-87 Relationship of X Clad Damage with X of Xe-131m Relationship of X Clad Danmge with X of Xe-133 Relationship of X Clad Dam-.ge with Z of I-131 Relationship of X Clad Damage with X of I-131 with Spiking Re1.ationship of X Clad Damage with of I-132 Kr-85m Kr-87 Kr-88 Xe-135 I-132 I-1,33 1-135 Te-129 La-14'2 Pr-144 Xe-131m Xe-133 Xe-133m I-131 Te-132 Ba-140 La-140 Standazd Temperature and ss Vs. Containment ed on Average Power Core Inventory Released Coze Inventory Released Coze Inventory Released Coze Inventory Released Core Inventory Released Core Inventory Released PEP-362 Rev.

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10.0 DIAGRAMS/ATTACHMENTS (continued) 32.

33 ~

34 ~

35 ~

36 ~

37 ~

38.

39 ~

40.

41.

Relationship of Z Clad Damage with Z Co'ze Inventory Released of I-133 Relationship of Z Clad Damage with Z Coze Inventory Released of I-135 Relationship of Z Fuel Overtempezature with Z Core Inventozy Released of Xe, Kr, I, Cs oz Te Relationship of Z Fuel Overtemperature with Z Coze Inventory Released of Ba, Sr oz La Relationship of Z-Fuel Melt with Z Core Inventory Released of Xe, Kr, I, Cs or Te Relationship of Z Fuel Melt with Z Coze Inventory Released of

~Ba, Sr, or La Relationship of Z Fuel Melt with Z Core Inventory Released bf Pr Isotopic Activity Ratios of Fuel Pellet and Gap Containment Hydrogen Concentration Based on Zirconium - Mater React'ion Percpt Nobi.e Gases in Containment for Containment Volume of 2x10 ft PEP-362 Rev.

Page 17 of 59

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ATTACHMENT 2:

Sample Data Reactor Coolant S stem SAMPLE {R) 3 ~

4.

5 ~

6.

Sample Temperature.

When Analyzed:

Pressurizer Level at Time of Sampling:

Data and Time Sample AnaLyred:

/

Time After Shutdown When Smsole Analyzed:

1.

Date and Time Sample Drawn:

/

2s Scooter Coolant System Temperature at Time of SampLing!

'F

'F 2

hrs.*

CONTAINMENT RECIRCULATION SUMP SAMPLE (S) 7 Data and Time Smsple

.Drawn:

/

S.

Sump Temperature at Time of SampLing:

9.

Sample Temperature When Analyzed:

LC.

Containment Flooded Level at Time of Sampling:

v 11.

Date and Time Sample Analyzed:

/

12.

Time After Shutdown When Sample Analyred'=

4F

'F ft elevation or X LI"7160 or in LI-7162 hrs.w CONTAINMENT ATMOSPHERE SAMPLE (A) 13.

Date and Time Sample Drawn:

/

LA.

Containment Temperature at Time of Cmspling:

15'.

Containment Pressure at Time of Sampling'.

16.

Sample Temperature When Analyzed:

17.

Sample" Pressure When Analyzed:

18.

Date and Time Sample Analyzed:

/

19..

Time After Shutdown When SampLe Analyzed:,

4F PSIA

'F PSIA hrs.e

Normal y computer-corrected to time of sampling.
PEP-362 Rev.
1
~
Page 19 of 59
II
ATTACHMENT 3 Sam le S ace Hass Calculations Page 1 of 2 Containment Atmosphere 1.
Containment Atmosphere Temperature'.
'F + 460
=
R 2.
Containment Atmosphere Pressure:
3.
Sample Temperature:
4.
- Sample Pressure:
5.
)Density Ratio Line 2 x Line 3 Line 1 x Line 4
'F + 460
=
ps@a psxa Reactor Coolant S stem unit mass, use Density 6.
Density Ratio for (Mote.
Xf sample activity is reported per Ratio = 1.0 on Attachment 1.)
Sample (Attachment 23):
7.
Density Ratio for Reactor Coolant System (Attachment 23):
8.
Reactor Coolant System Sample Density Ratio
~
Line 7
ECCS Recirculation Sumo (Note:
Xf sample activity is reported per unit mass, use Density Ratio = 1.0 on Attachment 1.)
9.
Density Ratio for Sample (Attachment 23):
10.
Density Ratio for Sump (Attachment 23):
Line 10 ll.
Sump Sample Density Ratio Line 9
PEP-362 Rev.
1 Page 20 of 59
>pi 8
E 1
4
'P al
ATTACHMENT 3 Sample S ace Mas Calculations (Cont'd)
.Page 2 of 2 ECCS Recirculation Sumo Mass 12.
13.
Containment Level:
or or Sump Mass (Stan'dard Temperature and g
MSL X (LI-7160) inches (DI-7162)
I Pressure)
(Attachment 24) 14.
Sump Mass (Temp. corrected: ):
~
C Reactor Coolant S stem 15.
No Level Indicated on Pressurizer; Reactor Coolant System Mass
= (2.14 g
x 10
) x Line 7
OR r
Level Indicated On Pressurizer'.
Reactor Coolant System Mass
~ f(2.14 r 10
) + (X. PZR 8
Level)(0.01)(3.96 x 10 ))
x. Line 7 uP'P-~62 Rev.
1 Page 21 of 59
ATTACHMENT 4:
E uivalent Power Level Calculations A
E uivalent Power Level for Lon -Lived Isotopes Effective Full Power Days in Core Cycle Effective Full Power Days 2:
3 ~
Expected Effective Pull Power Days for this core
~
cycle Line 1
Equivalent Power Level Line 2
B.
E uivalent Power Level. for Short-Lived Isotopes 4
~
Thermal Power Equivalent Power Level =
C.
E uivalent Power Level for Intermediate-Lived Isotopes Thermal Power Equivalent Power Level "-277/
D.
E uivalent Power Level. for Cs-134 from,Attachment 25:
PEP-362 Rev.
1 Page 22 of 59
~ i(
P
~ r,
~
~
ATTACHMEHT 5:
Equivalent Power Level Wovksheet foz Kr-85m ISOTOPE:
Er 85m Zi(h=
):
0.155 (cl)
P
~
(c2)
(c3)
(c4)
(c5)
(ce) t
~
1-e i j e i j (Cl)*(C4)*(C5) 3 z(C2) z(ce)
Equivalent Powez Level ~ Z(ce)/2775
~
PEP-362 Rev.
1 Page 23 of 59
ATTACHMENT 6:
Equivalent Power Level Worksheet for Kr-87 ISOTOPE:
Kr-87 Xi(hr ):
O.545 (ca)
(c2)
P
~
(cs)
t e
J (c4)
(cs)
(c6) l"e i j e i j (Cl)*(C4)*(C5) z(c2)
(should be 96 Hours) z(cs)
Equivalent power Level ~ E(C6)/2775
=
neo-ar e Rav';
1 page 24 of 59
'h S
ATTACHHENT 7:
Equivalent Power Level Morksheet for Kr-88 f
ISOTOPE:
Kr-88 Xi(hr ):
0.244 (Cl)
(C2)
P
~
(c3)
(c4)
(c5)
(ce) 1-e "i j e i j
{Cl)*(C4)*(C5) 3 z(c2) z(cs)
Equivalent Po~er Level = Z{ce)/2775 =
PEP-362 Rev.
1 Page 25 oC 59
h, (I
ATTACHMENT 8:
Equivalent Power Level Morksheet~
Xe-135 ISOTOPE:
Xe-135 Xi(hr ):
0.0762 (Cl)
P
~
(C2)
(C3)
(C4)
{C5)
(C6) e i j (Cl)*(C4)*(C5)
J E(C6)
Z(C2) t Equivalent Power Level = E(C6)/2775
=
PEP-362 Rev.
1 Page 26 of.'9.
<I' t
)gv I
v.
I tl tI
ATTACHMENT 9:
Equivalent Power Level Morksheet for I-132 ISOTOPE:
I"132 X ~ (hr
):
0,301 (Cl)
(C2)
P
~
(C3)
(Ca)
(C5)
(C6) t
~
1 e i j e i j (C1)*(C4)*(C5)
J z(c2) z(c6)
Equivalent Po~er Level = Z(C6)/2775
=
PEP-362 Rev.
1 Page 27 of 59
Q S'
I I
i1
ATTACHMENT 10:
Equivalent Power Level Worksheet for I-133 ISOTOPE:
I-I33 ii(hr '):
0.0333 (Cl)
(C2)
P
~
(C3)
(C4)
(C5)
(C6) t -
1-e i j e
i. j (Cl)*(C4)*(C5)
J z(C2)
.(should be 96 Hours) z(c6)
Equivalent Power Level = Z(C6)/2775
~
PEP-362 Rev.
1 Page 28 of 59
Y i(g V,
ATTACHMENT 11:
Equivalent Power Level Morksheet for I-135 ISOTOPE'-135
~i(hr
):
0.105 (Cl)
(CZ)
P
~
(C3 }
(C4)
(C5)
(C6) t I-e i j e
i-j (Cl)~(C4)*(C5) 3 Z(Ci) z(C6)
Equivalent Power Level ~ E(C6)/2775
=
PEP-362 Rev.
1 Page 29 of 59
y ~
kx:
ATTACHHEHT 12:
Equivalent Power Level Morksheet for Te-129 iSOTOPE:
Te-129 (hr
):
0.598 (Cl)
(C2)
Pj (C3)
(C4)
(C5)
(C6) t.
1-e i j e i j
('Cl)*(C4)*(C5)
Z(C2)
(
z(C6)
Equivalent Power Level = Z(C6)/2775
=
"'EP"362 Rev.
1 Page 30 oE 59
V I
ATTACHMENT 13 Equivalent Power Lev~ Morksheet for La-142 ISOTOPE:
La-142 Xi(hr '):
0.450 (cl)
(c2)
P
~
(c3)
(c4)
.t
~
1e i j 3
(c5)
(cs)
{c1)*(c4)+(C5) z(c2) f z(cs)
Equivalent Power Level = E(CS)/2775
=
PEP-362 Rev.
1 Page 31 of 59
ATTACHMENT 14:
Equivalent Power Level Worksheet for Pr-144 ISOTOPE:
Pr-144 (hr
):
2.41 (c1)
(c2)
P
~
(c3)
(c4)
(c5)
(c6) 1-j ~ t
~
-X-t ~
(Gl)*(G4)*(G5) z(c2)
(sbou14 be 96 ~ours'(cs)
Equivalent Power Level = Z(CS)/2775
=
PEP-362 Rev.
1 Page 32 of 59
ATTP.
HMENT 15 Equivalent Power Level Morksheet for Xe-131m ISOTOPE Xe-131m i day
):
0.0582
{cl)
P
~
(c2)
{C3)
(c4)
(c5)
(c6) t.
1-e i j e i j (Cl)*(C4)*(C5)
J z( 2) t z(C6)
"quivalent Power Level = Z(C6)/2775
~
PEP-36:
Rev.
1 Page 33 of 59
\\ ~
P1
ATTACHMENT 16 Equivalent Pover, Level Morksheet for Xe-133 ISOTOPE:
Xe-133 (aalu
)-'. 132 o
(c1)
(c2)
P
~
(c3)
(c4)
{C5)
(c6) t -
1"e i j e i j (Cl.)*(C4)*{C5) z(C2) z(c6).
Equivalent Po~er Level ~ Z(C6)/2775
=
PEP-362 Rev.
1 Page 34 of 59
q1 II I.T 'L h
4
ATTACHMENT 17 Equivalent Power Level Morksheet for Xe-133m TSOTOPE:
Xe-)33m ii(cay '):
0.316 (cl)
(c2)
(c3)
(cc )
(c5)
(c6) 1-e i j e
w j.
(Cl)*(CA)+(C5) 3 z(c2) z(c6)
Equivalent'ower L'evel = Z(C6)/2775
=
PEP-362 Rev.
1 Page 35 of 59
t
~ ATTACHMENT 18 Equi'nt Power LeveL Morksheet for I-131 ISOTOPE:
I-131 ii(say
):
0.0862 I
(c2)
P
~
(c3)
(ca)
(cS)
(c6) t.
1-e i j e
j
{Cl)*{C4)*(C5)
E(cz)
(
E(c6)
Equivalent.Po~er Level = E(C6)/2775
=
PEP-362 Rev.
1 Page 36 of. 59
1 P
,I I-
ATTACHMENT 19 Equivalent Power Level Worksheet for Te-132 ISOTOPE:
Te-. 132 Xi(day
):
0.213
{Cl)
{C2)
P
~
(C3)
(ca)
(C5)
(C6) t 1-e i j e i j (Cl)*(C4)*(C5) 3 Z(C2)
(
Z(C6)
Equivalent Power Level ~ Z(C6)/2775
=
PEP"362 Rev; 1
Page 37 of 59
j,C
'a
ATTACHMENT 20 Equivalent Power Level,Worksheet for Ba-140 ISOTOPE:
Ba-140 day
):
0.0544 (cl)
(c2)
P
~
(C3)
(c4)
(c5)
(c6) t.
1-e i j e i j (Cl)*(C4)*(C5)
J z(c2) t l~
z(c6)
Equivalent Po~er Level = Z(C6)/2775 =
PEP-362 Rev.
1 Page 38 of 59
l-FI
ATTACHMENT 21 Equivalent Power Level Worksheet for La-140 ISOTOPE:
La-140 Xi(day
) :
0. 4 13 (cl)
P
~
(c2)
( c3 )
(c4 )
( c5 )
( c6 )
1-e i j e
i. j
( C 1 )*(C4 )*( C5 ) '
x(cz)
'(C6)
Equivalent Power Level = E(C6)/2775
=
PEP-362 Rev.
1 Page 39 of 59
1 I!
'C
'y C'
ATTACHMENT 22:
Re ort to SEC on Core Dama e Status PEP-362 has been completed and based on sample analysis and auxiliary indications (radiation levels, core temperatures,
RVLIS, and containment hydrogen levels) the core damage status is as follows:
CLAD DAMAGE:
Estimated Z:
Basis'.
NOTE:
Loss of Fission Product Barrier " Refer to EAL Neurork for possible upgrading of emergency classification.
YES/NO FUEL OVERHEAT:
Estimated Z:
Basis:
FUEL MELT:
Estimated. Z:
Basis:
Qualitative Indications agree with Sample Analysis".
YES/NO Comments.'nitiated:
Revieved:
Approval:
Team Leader
Optional at discretion of Team Leader PEP-362 Rev.
1 Page 40 of 59
a lit A
I
~
~
~
8
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1g 2 k.
Pl gg li
ATI'ACHMENT 241 STP H>o ASS VS.,
Q 7 222 220 EI
[FT.)
210 200 190 Iso LI-7160 {Q 170 160 150 140 80 226 60 225 40 130
~
120 1IO 22I 10r'5 SWOR MASS AT STP tx )0 GRAS) 20 PEP-362 Rev.
1 Page 42 of 59
I n,
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ATTACHMENT 29:
RELATIONSHIP OF X CLAD DAMAGE MITH X CORE INVENTORY RELIED PF I )3]
1
~
0.7 0-5 0.0 0.2 0 '
.QT
.05
-05
~ 02
~ 0]
~ GOT
.005
.003
'CC
.002 0
~
.001 g
r.o-o'.5-04 j
5o 0~4 o
R.Q
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~
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I
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I
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liQ 4 7 0-$
5.0-5 5.0 5 2.0-5 I
I
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Ol Ch 0a
~
~
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4
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~
~
~
~
~
~
~
cv n
e.i o '.o o
o o
o o
o o
o eo
.n e
~
o Clad Damage (X)
PEP-362
Rev, 1
Page 47 of 59
e tj',
ATTACHMENT 301 REIATIONSHIP OF
'S CLAD~GE HITH S CORE INYENTORY RELEASED OF I-131 HITH SPIKING j
le 0-7 0 5) o.v!
0.2 I
I i
O.
1
~ 07 05 05
-. 01 g.,oor
-005 EIS..003
002, g
.001 w'.0-4 5.0~4 C
~ 0-4 o 2'io-4 leo 4
5 ~ 0-5 5-0-5
2. 0-5 1 0"5 tYG t7 0 I
~
~
~
~
~
~
~
0
~
~
~
CW e
a N
O o
o o o:.
Clad Damage (g)
~
~
o o
~I ~
p PEP-362 Rev.
1 Page 48 of 59
<a' C
P gh
ATTACHMENT 31:
RELATIONSHiP PF g CLAD DAMAGE g57H X CORE INVENTORY RELEASED OF I-132 F 45
~ 42
.407 I
(
(
(
I
~
(
I i I
0
~
I 40l
e. 7-4-4
~~-
5-4-4-4-<
(L)
QaQ l-D"4
'7 0-5 5.0-5 I
I I
I I
I i
~
I J
I
)
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I
(
3- 0-5 2.4-5
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o
~
0
~
~
0
~
0
~
~
~
CV tS H
A 0
0 o
o 0'0 Ill clod ~go (x)'
0 0
0 N ~
0.
PEP-362 Rev.
1 Page 49 of 59
J 'I pl
ATTACHHENT 32'ELATiQNSHIP OF I CLAD DAStGE MITH I CORE iNVDtTORY RELEASED OF I-133 1
~
0.7 0 '
0.3 0-2 0.1
.07 05
~ 02
-01 007
"-005 I
I
~
I
(
I
~
.002 001 7-0-4 5-0-a 5-0-4 2.04 1.0 4
7-0"5 5.0-5 5 0-5 2-0-5 I
I
(
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j 1
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~
~
~
~
~
~
Ol h
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O o
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ee
~
~
~
0 0
00 PEP-362 Rev.
1 Page 50 of 59
't 1
t, ll 4
W p+v
'I
',l j1 R
,F
ATTACHMENT 33:
RELATIONSHIP OF X.CLAD GARBAGE MITH X CORE INVENTORY RELEASED OF I-135
)
o 0.7 0
5 0 0 0 '
~
(
~
~
0-1
.07
.0$
.02 OP 07 CL C
CP 0
,.01
.007
.005
-002
~ 401 '.
7. 0-4 5.0 4 5.0 4
2 ~ 0-4
(
~
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$ -0 5 5-0-S
2. 0-5 1 5
'N 1a
~
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~
\\
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~
0
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0 nod o
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~
0 PEP-362 Rev.
1 Page 51 of 59
'J ~i
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ATTACHMENT 39:
FF p
T NQ P
~c~~id e el P ll Act1v(
N tio Act 1 v1 t 1 o Kr-85m Lr-87 Lr-88 Xe-1 31m Xc-133 Xe-133m Xc-135 0.11 D.22 0.29 0.004 1.0 0.14 D.19 0.022 0.022 0.045 D.DN 1.0 0.09e
0. 051 I-1 31 I-132.-
I-133
!-1 35 1.0 1.5 2.1 1.9 I
1.0 D.17 0.71 0.39 Noble Gas soto c Invento Xe-133 Inventory.
Noble Gas Ratio I-131 Inventory The aeasured ratios of various nuclidcs found in reactor coolant during normal operation is a function of the ~unt of 'tramp'ran1um on fuel ro cladding. the. number and size of 'defects'1.e.
'pin holes',
and the location of the fuel rods conta1ning the defects in the core.
The ratios der1ved 1n 'this report are based on 'calculateo values of relative concentrations 1n the fuel or 1n the gap.
The use of these present ratios for post accident damage assessment is restr1cted to an attempt to d1fferent1ate betaken fuel overtemperature cond1tions and fuel cladding fa1lure conditions.
Thus the ratios derived here are not related to feei derect qeveis incurred durino nomai operation.
PEP-362 Rev.
pege 57 of 59
gr' 4
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4
ATTACHMENT 41:
O FT PERCENT NOBLE aAEE3 IN CONTAINMENT FOR CONTAINMENT YOLVME OF R x IO FT 1000.0 100. 0
10. 0 52K Noble Gas Release 0.3X Noble Gas R
1 1.0-3 5 18. l Normal Operating Noble Gas Relet e
'.0-4 1.0-5 1.0 10.0 100.0 1000. 0 TIN AFTER ACCIDENT {HOURS)
PEP-362 Rev. l Page 59 of S9
i
CAROLINA POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT PLANT OPERATING MANUAL VOLUME 2 PART 5 PROCEDURE TYPE:
PLANT EMERGENCY PROCEDURE (PEP)
NUMBER:
PEP"371 TITLE:
EMERGENCY RESPONSE IN RADIOLOGICAL AREAS REVISION 0 APPROVED:
Signature Date pc/
TITLE:
PEP-371 Rev.
0 Page 1 of 15
APR010 TABLE OF CONTENTS Table of Contents List of Effective Pages 1.0 PURPOSE
2.0 REFERENCES
2.1 Emergency Plan References 2.2 Referenced Plant Emergency Procedures 2.3 Corporate Emergency Plan and Implementation Procedures Reference 2.4 Other References 3.0 RESPONSIBILITIES 3.1 Plant General Manager 3.2 Environmental and Radiation Control Manager 3.3 Site Emergency Coordinator 3.4 Radiological Control Director 3.5 Personnel Protection and Decontamination Team Leader 3.6 Personnel Protection and Decontamination Team 3.7 Emergency Security Team Leader 3 '
On-Site Personnel 4.0 DEFINITIONS 5.0 GENERAL 6.0 INITIATINGCONDITIONS 7.0 PRECAUTIONS AND LIMITATIONS 8.0 SPECIAL TOOLS AND EQUIPMENT 9.0 PROCEDURE STEPS 10.0 DIAGRAMS/ATTACHMENTS 10.1 Emergency Worker Exposu're Criteria 10.2 Emergency Radiation Work Permit
~Pa e
2 3
4 4
4 4
4 4
5 5
5 5
5 6
6 6
6 8
8 9
9 13 14 15 PEP-371 Rev.
0 Page 2 of 15

ML18018B953

Text

7.2 ACCVKLCY

2.0 REFERENCES

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