NRC 2003-0012, Emergency Plan Implementing Procedure Revisions, Point Beach Nuclear Plant, Units 1 & 2

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Emergency Plan Implementing Procedure Revisions, Point Beach Nuclear Plant, Units 1 & 2
ML030520173
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 02/07/2003
From: Cayia A
Nuclear Management Co
To:
Document Control Desk, Office of Nuclear Security and Incident Response
References
NRC 2003-0012
Download: ML030520173 (22)
v • d • e


Text

Committed to NuclearExcellenMc Point Beach Nuclear Plant Operated by Nuclear Management Company, LLC NRC 2003-0012 February 7, 2003 Document Control Desk U.S. Nuclear Regulatory Commission Mail Station P1-137 Washington DC 20555 Ladies/Gentlemen:

DOCKETS 50-266 AND 50-301 EMERGENCY PLAN IMPLEMENTING PROCEDURE REVISIONS POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 Enclosed are copies of revised procedures to the Point Beach Nuclear Plant Emergency Plan Implementing Procedures. The revised procedures dated February 3, 2003, should be filed in your copy of the manual.

Sincerely, S1Vc dent FA d Enclosures cc: NRC Resident Inspector (w/o/e)

Incident Response Center, Region III 6590 Nuclear Road 0 Two Rivers, Wisconsin 54241 Telephone: 920 755 2321

EPIP 10.2 CORE DAMAGE ESTIMATION DOCUMENT TYPE: Technical CLASSIFICATION: NNSR REVISION: 20 EFFECTIVE DATE: February 3, 2003 REVIEWER: N/A APPROVAL AUTHORITY: Department Manager PROCEDURE OWNER (title): Group Head OWNER GROUP: Emergency Preparedness Verified Current Copy:

Signature Date Time List pages used for Partial Performance Controlling Work Document Numbers

POINT BEACH NUCLEAR PLANT EPIP 10.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 20 February 3, 2003 CORE DAMAGE ESTIMATION TABLE OF CONTENTS SECTION TITLE PAGE 1.0 PURPO SE ...................................................................................................................... 4 2.0 PREREQU ISITES ..................................................................................................... 4 3.0 PRECAU TION S AN D LIM ITATION S ................................................................... 4 4.0 IN ITIA L CON DITION S ............................................................................................ 5 5.0 PROCEDURE ........................................................................................................ 5 6.0 REFEREN CES .............................................................................................................. 21 7.0 BA SES .......................................................................................................................... 21 TABLES TABLE A SAM PLE RESULTS ..................................................................................................... 6 TABLE B DECAY CORRECTION OF (RCS/ATMOSPHERIC/SUMP)

SA M PLE RESU LTS ..................................................................................................... 7 TABLE C DECAY CORRECTION OF SAMPLE RESULTS WITH PARENT/DAUGHTER RELATIONSHIPS ................................................................ 9 TABLE D DETERMINATION OF THE DECAY OF THE HYPOTHETICAL DAUGHTER ACTIVITY FOR SAMPLE RESULTS WITH PARENT/DAUGHTER RELATIONSHIPS .............................................................. 10 TABLE E DETERMINATION OF THE MEASURED SAMPLE SPECIFIC ACTIVITY FOR SAMPLE RESULTS WITH PARENT/DAUGHTER RELATIONSHIPS ................. 11 TABLE F DETERMINATION OF THE DECAY CORRECTED SPECIFIC ACTIVITY FOR SAMPLE RESULTS WITH PARENT/DAUGHTER RELATIONSHIPS ................. 12 TABLE G TEMPERATURE / PRESSURE CORRECTION ....................................................... 13 Page 2 of 21 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 10.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 20 February 3, 2003 CORE DAMAGE ESTIMATION SECTION TITLE PAGE TABLE H-1 TOTAL ACTIVITY OF EACH MEDIUM - ATMOSPHERE ................................ 15 TABLE H-2 TOTAL ACTIVITY OF EACH MEDIUM - RCS ................................................... 16 TABLE H-3 TOTAL ACTIVITY OF EACH MEDIUM - SUMP ................................................. 17 TABLE I TOTAL ACTIVITY RELEASED (ATMOSPHERIC, RCS, AND SUMP) ............ 18 TABLE J FRACTION OF CORE RELEASED (ATMOSPHERE, RCS, AND SUMP) ...... 19 Page 3 of 21 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 10.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 20 February 3, 2003 CORE DAMAGE ESTIMATION 1.0 PURPOSE This procedure is used to implement the Westinghouse Owner's Group (WOG) Core Damage Assessment Methodology. The WOG methodology is the primary method for estimating core damage through the measurement of fission product concentrations in the coolant system, containment atmosphere and containment sump. Auxiliary indicators: core exit thermocouple temperature, reactor vessel water level, containment radiation monitors, and containment hydrogen concentrations are also used to verify the extent of core damage.

2.0 PREREOUISITES 2.1 Responsibilities 2.1.1 The Rad/Chem Coordinator is responsible for the completion of this procedure.

2.1.2 The Reactor/Core Physics Engineer will assist by obtaining data such as:

a. Plant power history
b. Reactor shutdown time
c. Dilution quantities.

2.2 Equipment Plant Process Computer System 3.0 PRECAUTIONS AND LIMITATIONS 3.1 The completion of this procedure does NOT have a specific time frame but will be performed whenever needed and appropriate. Implementation of this procedure shall NOT interfere with the overall response to the emergency.

3.2 The procedure user(s) should use as many indications as possible to differentiate between the various core damage states. Because of overlapping values of release and potential simultaneous conditions of core damage, overtemperature, and/or core melt, considerable judgment needs to be applied.

3.3 The Westinghouse Owner's Group (WOG) Post-Accident Core Damage Assessment Methodology is available for reference.

3.4 Plant data required for performance of this procedure is available from the Plant Process Computer System (PPCS) or documented on EPIP 2.1, Attachment E, Status Report on Plant Systems and Controls for Affected Units.

Page 4 of 21 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 10.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 20 February 3, 2003 CORE DAMAGE ESTIMATION 4.0 INITIAL CONDITIONS 4.1 Some or all of the following may be present if fuel damage or loss of reactor coolant system integrity has occurred:

4.1.1 The failed fuel monitor, l(2)RE109, may be unusually high or offscale.

4.1.2 The containment airborne radiation monitors, 1(2)RE211 or 1(2)RE212, may be unusually high or offscale.

4.1.3 The containment area radiation monitors, 1(2)RE102 or the seal table monitors, 1(2)RE107 may be unusually high or offscale.

NOTE: Typical full power high range values are 1.2 - 1.5 R/hr.

4.1.4 The containment high range radiation monitors, 1(2)RM1 26, 127 or 128 may be elevated.

4.2 Reactor coolant, containment atmosphere and/or containment sump samples have been taken and analyzed in accordance with:

4.2.1 EPIP 8.4.1, Post-Accident Sampling and Analysis of Potentially High Activity Reactor Coolant.

4.2.2 EPIP 8.4.2, Post-Accident Sampling of Containment Atmosphere.

4.2.3 EPIP 8.4.3, Emergency Containment Sump "A" Sampling.

5.0 PROCEDURE 5.1 Obtain the following information:

5.1.1 Started Reactor Shutdown Time 5.1.2 Reactor Shutdown Time 5.1.3 Power level at time of Shutdown  %

5.1.4 Sample Time 5.1.5 Delta Time - hours 5.1.6 Sample Temperature OF 5.1.7 Temperature of Where Sample was Taken Page 5 of 21 REFERENCE USE

POINT BEACH NUCLEAR PLANT POINT BEACH NUCLEAR PLANT EPIP 10.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 20 February 3, 2003 CORE DAMAGE ESTIMATION 5.2 Enter the sample results, in jtCi/cc, for the appropriate sample location in Table A.

TABLE A SAMPLE RESULTS SAMPLE REACTOR CONTAINMENT CONTAINMENT LOCATION COOLANT ATMOSPHERE SUMP

__________. SYSTEM POSSIBLE ISOTOPE SPECIFIC SAMPLE ACTIVITY IN tCi/cc (A)

CORE DAMAGE STATE CLAD FAILURE Kr-87

  • Xe-131m
  • Xe-133m
  • Xe-133
  • Xe-135 1-131

"*-132 1-133 1-135 Rb-88 FUEL OVERHEAT Cs-134 Cs-137 Te- 129 Te-132 FUEL MELT Ba-140

  • La- 140 La-142 Pr- 144
  • Isotopes with parent/daughter relationships 5.3 Compare the isotopes identified in the samples with the core damage state listed to the left of Table A to determine the most likely type of fuel damage that may have occurred.

Most likely fuel damage (circle one):

CLAD FAILURE / FUEL OVERHEAT / FUEL MELT Page 6 of 21 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 10.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 20 February 3, 2003 CORE DAMAGE ESTIMATION 5.4 Decay correct sample results, for isotopes without parent/daughter relationships to the time of reactor shutdown using the formula:

A Ao-I-At Where:

A0 = Sample Specific Activity at Time of Reactor Shutdown A = Sample Activity X = Decay constant (hours")

At = Time of Sample - Time of Reactor Shutdown NOTE: If more than one location was sampled for this evaluation, use a separate copy of Table B for each sample location.

TABLE B DECAY CORRECTION OF (RCS/ATMOSPHERIC/SUMP) SAMPLE RESULTS (circle one)

ISOTOPE SPECIFIC SAMPLE DECAY CONSTANT SAMPLE CORRECTED ACTIVITY (A) (k) hours' ACTIVITY (A0) pCi/cc Kr-87 5.46E-1 1-131 3.58E-3 1-133 3.4 1E-2 1-135 1.04E-1 Rb-88 2.34E0 Cs-134 3.95E-5 Cs-137 2.60E-6 Te-129 6 05E-1 Te-132 8.92E-3 Ba-140 2.26E-3 La-142 4.50E-1 Pr-144 2.41E0 Page 7 of 21 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 10.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 20 February 3, 2003 CORE DAMAGE ESTIMATION 5.5 If time allows, or if there is a large number of isotopes with parent daughter relationships (those identified with an asterisk on Table A, decay correct the sample results by completing Steps 5.5.1 through 5.5.4. If time is limited or the activity of isotopes with parent daughter relationships is low, go directly to Step 5.6.

5.5.1 Calculate the hypothetical daughter concentration (QB) at the time of the sample analysis assuming 100 percent release of the parent and daughter source inventory. Use the following equation:

QB(A) K= 2BK- .Q 0 .(e 2AAt - e2 At )+Q 'e 2 At Where:

QB = Concentration of daughter at time of sample analysis Q0 = 100% Source Inventory of Parent QO = 100% Source Inventory of Daughter K = Decay Branching Factor A = Parent Decay Constant AB = Daughter Decay Constant At = Time of Sample - Time of Shutdown 2 45 Xe"3 'M QB(At 358 4

) = .011 (-2.168)(4.2E+07) -[e 4 E-3x At hrs) _ e-( E-3)( At hrs)] + 2.7E+05 - e (2 5E-3X At hrs)

) = .029 (-0.601)(8 5E7) . [e" 2

41E- )( At hrs) _ e-] 28E-2xAt hrs)I + 1.2E7 e°I 28E-2x At hrs)

Xe133 m QB(At Xe133 QB(At) = .971 (-.1915(8.5E7) . [e-(34 1E-2 )(At hrs). e -(5 48E.3 x At hrs)] + 8.5E7 e"4548E-3x At hrs 7 2 Xe135 QB(At ) = .835 (-2.650)(7.4E+07) - [e,' 04E-1X At hrs) - e-(7 58E-2)( At hrs)] + 1.6E+07 *e"( "58E-X At hrs) 8 92 3 3 07 + 6.4E+07 *e0 07E-1X At hs) 1132 QB(At ) = 1.00 (1.03)(6.4E+07). [e"( E- )(At hrs) - e ( E-lx At hrs)

La140 QB(At ) = 1.00 (2.26E-3)(7.4E+07) * [e( 2 26E-3x At hrs) - e-( 72E-2x At hrs)] + 7.4E+07 e"1 72E-2) At hrs)

For each isotope enter the decay time to be considered. Perform the calculation for each of the isotopes and list the results in Table C on the following page.

Page 8 of 21 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 10.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 20 February 3, 2003 CORE DAMAGE ESTIMATION TABLE C DECAY CORRECTION OF SAMPLE RESULTS WITH PARENT/DAUGHTER RELATIONSHIPS DAUGHTER VARIABLES FOR PARENT/DAUGHTER DECAY CORRECTIONS IN STEP 5.5 HYPOTHETICAL ISOTOPE DAUGHTER ACTIVITY AT SAMPLE TIME (Q3 At) CURIES BRANCHING SOURCE SOURCE DECAY CONSTANT DECAY CONSTANT FACTOR INVENTORY - INVENTORY (%) hours" (N)hours' (K) PARENT - DAUGHTER PARENT DAUGHTER Curies Curies Xe-131m .011 4.2E+07 2.7E+05 3.58E-3 2.45E-3 (1-131) (Xe-131m)

Xe-133m .029 8.5E+07 1.2E+07 3.41E-2 1.28E-2 (1-133) (Xe-133m)

Xe-133 .971 8.5E+07 8.5E+07 3.41E-2 5.48E-3 (1-133) (Xe-133)

Xe- 135 .835 7.4E+07 1.6E+07 1.04E-1 7.58E-2 (1-135) (Xe-135) 1-132 1.00 6.4+07 6.4E+07 8.92E-3 3.07E-1 (Te-132) (1-132)

La-140 1.00 7.4E+07 7.4E+07 2.26E-3 1.72E-2 (Ba-140) (La-140)

NOTE: Branching factors are taken from Kocher, David. C., "Radioactive Decay Data Tables," Technical Information Center, USDOE, 1981. DOE/TIC - 11026.

Page 9 of 21 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 10.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 20 February 3, 2003 CORE DAMAGE ESTIMATION 5.5.2 Using Table D and the formula below, calculate the fraction of contribution of the decay of the initial inventory of the daughter to the hypothetical daughter activity at sample time:

FrQ e-2 B At QBAt Where:

Fr = Fraction of Contribution of Decay of Initial Inventory of Daughter QB = 100% of Source Inventory of Daughter QBAt = Hypothetical Daughter Activity at Sample Time XB = Daughter Decay Constant (hours -1)

At = Time of Sample - Shutdown Time (hours)

TABLE D DETERMINATION OF THE DECAY OF THE HYPOTHETICAL DAUGHTER ACTIVITY FOR SAMPLE RESULTS WITH PARENT/DAUGHTER RELATIONSHIPS DAUGHTER 100 % SOURCE HYPOTHETICAL DECAY CONSTANT FRACTION ISOTOPE INVENTORY OF DAUGHTER (k) hours" DAUGHTER ACTIVITY DAUGHTER (Fr)

(Q°B) CURIES (QBAt)

Xe-131m 2.7E5 2.45E-3 I Xe-133m 1.2E7 1.28E-2 I Xe-133 8.5E7 5.48E-3 I Xe-135 1.6E7 7.58E-2 I 1-132 6.1E7 3.07E-1 La-140 7.4E7 1.72E-2 5.5.3 Using Table E and the formula below, calculate the amount of the measured sample activity associated with the decay of the daughter released:

MB = Fr x measured specific activity (pCilcc)

Where:

MB = Measured Sample Activity of Daughter Fr = Fraction of Contribution of Decay of Initial Inventory of Daughter Page 10 of 21 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 10.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 20 February 3, 2003 CORE DAMAGE ESTIMATION TABLEE DETERMINATION OF THE MEASURED SAMPLE SPECIFIC ACTIVITY FOR SAMPLE RESULTS WITH PARENT/DAUGHTER RELATIONSHIPS DAUGHTER FRACTION MEASURED SAMPLE ACTIVITY SAMPLE SPECIFIC ISOTOPE (Fr) OF ISOTOPE (gCi/cc) ACTIVITY FROM TABLE A (MB)

Xe-131m Xe-133m Xe-133 Xe-135 Xe-135m 1-132 La-140 5.5.4 Decay correct the measured sample activity (MB) to the time of reactor shutdown using the following formula:

M_ My e-2B At MOB = Corrected Activity of Daughter at Time of Reactor Shutdown MB = Measured Sample Activity of Daughter XB = Daughter Decay Constant At = Time of Sample - Time of Reactor Shutdown (hrs)

Enter the results on Table F located on the following page.

Page I I of 21 REFERENCE USE

PONT BEACH NUCLEAR PLANT POINT BEACH NUCLEAR PLANT EPIP 10.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 20 February 3, 2003 CORE DAMAGE ESTIMATION TABLE F DETERMINATION OF THE DECAY CORRECTED SPECIFIC ACTIVITY FOR SAMPLE RESULTS WITH PARENT/DAUGHTER RELATIONSHIPS DAUGHTER SPECIFIC SAMPLE DAUGHTER DECAY SAMPLE SPECIFIC ISOTOPE ACTIVITY CONSTANT ACTIVITY AT TIME OF (MB) giCi/cc XB REACTOR SHUTDOWN FROM TABLE E (MB0 )

Xe-131m 2.45E-3 I Xe-133m 1.28E-2 Xe-133 5.48E-3 Xe-135 7.58E-2 1-132 3.07E-1 La- 140 1.72E-2 5.6 If the samples were taken from the reactor coolant system or containment sump and the temperature of the reactor coolant system or sump exceeded 200'F, then the specific sample activities need to be adjusted for temperature and volume. Correct the sample activities in Table B and Table F for temperature and pressure using Table G on the next page. If only containment atmosphere sampling was performed, then proceed to Step 5.7, since containment atmosphere samples are corrected for temperature and pressure during analysis. If the coolant or sump samples are < 200'F then use 1.0 as the water density ratio and proceed to Step 5.7.

Reference Figure 1, "Water Density Ratio," for the temperature of the sample. Enter the water density ratio on Table G and multiply the Specific Sample Activity by the water density ratio to obtain the adjusted specific activity.

Figure 1.

0 p/p @STP 02 0.4 Water density ratio /10 0.$

(temperature vs. STP) 0.8 1.9 lag 100 206 30 4W 500 600 700 g0o Temperature*, F Page 12 of 21 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 10.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 20 February 3, 2003 CORE DAMAGE ESTIMATION TABLE G TEMPERATURE / PRESSURE CORRECTION ISOTOPE SPECIFIC SAMPLE WATER DENSITY ADJUSTED SPECIFIC ACTIVITY (pCi/cc) RATIO ACTIVITY (gCi/gm)

Kr-87

  • Xe-131m
  • Xe-133m
  • Xe-133
  • Xe- 135 1-131

"*1-132 1-133 1-135 Rb-88 Cs-134 Cs-137 Te-129 Te-132 Ba-140

  • La-140 La-142 Pr-144 Page 13 of 21 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 10.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 20 February 3, 2003 CORE DAMAGE ESTIMATION 5.7 Calculate the total activity for each sample location, in Curies (Ci), at the time of reactor shutdown by adjusting for sample dilution and volumes for each isotope in Table H-I through Table H-3 for each sample location of Atmosphere, RCS, or Sump.

Estimated volumes:

Containment volume = I x 106 ft3 = 2.83x10°cc Ul Reactor Coolant System Liquid Volume including Pressurizer Volume at Full Power (60% Full) = 6000 ft3 = 1.71 x 108gm @ STP U2 Reactor Coolant System Liquid Volume including Pressurizer Volume at Full Power (60% Full) = 6148 ft3 = 1.74 x 108gm @ STP Available dilution sources for sump or coolant:

Accumulators: 2 at 8,000 gallons each = gallons RWST 275,000 gallons x _% = gallons 100 BAST (1 of 3) 5,000 gallons x -%= gallons 100 Spray Additive Tank 2,574 gallons x -% = gallons 100 Total Estimated Injection Volume (EIV) gallons

  • 28,317 = cc Convert EIV gallons to mass at STP.

Total EIV (gm) = EIV (gallons) x. 1337 ft3/gal x 2.832E4gm/ft 3.

Add EIV to sump or RCS volume to obtain total mass from which sample was drawn.

Page 14 of 21 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 10.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 20 February 3, 2003 CORE DAMAGE ESTIMATION TABLE H-1 TOTAL ACTIVITY OF EACH MEDIUM - ATMOSPHERE ISOTOPE ADJUSTED SAMPLE VOLUME/MASS OF RCS (gm), TOTAL ACTIVITY ACTIVITY (p.Ci/gm) SUMP (gm) OR CONTAINMENT (Ci)

ATMOSPHERE (cc)

Kr-87 xICI/, 0 6 p.Ci

  • Xe- 131m xICI/io66pCi
  • Xe-133m xlCi/0 o6 paCi
  • Xe-.133 xC/t10o6 P.Ci
  • Xe- 135 xlCl/io 6 iCi 1-131 xIC/io06 PaCi

"*1-132 xlCI/, 0 6htCi 1-133 xlC/10 o6 [tCi 1-135 xlC0/ 10 6 JiCi Rb-88 x1Ci/ 1 06 11Ci Cs- 134 x C10/06 pCi Cs-137 xIco M1tC_

6 Te-129 xICh/ 1, 6 jtCi Te-132 x 1C/ 1 0 6 6tCi Ba-140 x CI/ 1 06 p.Ci

  • La-140 xICI/ 1o6 PC, La-142 xICi/1 o6 gC_

Pr-144 xlCi/2 o66.tCl 5.8 Determine total activity release for each isotope by adding the total Curies released.

Enter the results in Table I.

Page 15 of 21 REFERENCE USE

POINT BEACH NUCLEAR PLANT POINT BEACH NUCLEAR PLANT EPIP 10.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 20 February 3, 2003 CORE DAMAGE ESTIMATION TABLE H-2 TOTAL ACTIVITY OF EACH MEDIUM - RCS ISOTOPE ADJUSTED SAMPLE VOLUME/MASS OF RCS (gm), TOTAL ACTIVITY ACTIVITY (gCi/gm) SUMP (gm) OR CONTAINMENT (Ci)

ATMOSPHERE (cc)

Kr-87 xlCi/ 1 0 6 gCi

  • Xe-131m xIcM/,o 6 gaCi
  • Xe-133m xC / 10o6 gCi
  • Xe-133 xIC1/, 0 6 jiCi
  • Xe-135 xC10/,06 jiCi 1-131 xICi/ 10 6 gCi
  • 1-132 xIC/,06 ttCi 1-133 xlC/10 16 gCi 1-135 x CIQ 106 gCi Rb-88 xlC10/06 tC, Cs- 134 xlCi/1 o6 gCi Cs-137 xICI/o6 gaCi Te-129 xICI/1 O6 jiCi Te-132 xlCl/ 106 itCi Ba-140 xlC/io 6 pCi
  • La-140 xlCi/to6 11Ci La-142 xlC1/,o 6 tCi Pr- 144 xICI/ 106 11a 5.9 Determine total activity release for each isotope by adding the total Curies released.

Enter the results in Table I.

Page 16 of 21 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 10.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 20 February 3, 2003 CORE DAMAGE ESTIMATION TABLE H-3 TOTAL ACTIVITY OF EACH MEDIUM - SUMP ISOTOPE ADJUSTED SAMPLE VOLUME/MASS OF RCS (gin), TOTAL ACTIVITY ACTIVITY (p.Ci/gm) SUMP (gm) OR CONTAINMENT (Ci)

ATMOSPHERE (cc)

Kr-87 xICi/1 o 6 tCi

  • Xe- 131 m x10c/, 0o6 giC
  • Xe-133m xlC/io6 gICi
  • Xe-133 x C101i6 gaCi
  • Xe-135 xC0/10o6 jiC_

1-131 x 6 Ci/ 1o gCi

  • 1-132 xlCil/o6 giCi 1-133 xC10/,o6 aCi 1-135 xICI/ 10 6 gaCi Rb-88 xC1/10o6 pCl Cs-134 xICI/10o6 jtCi Cs-137 xI Ci/ 10 6 gCi Te-129 x C1/10 6 g.tCi Te-132 xCj/10 6 gCi 6

Ba-140 xCM/,o PCi

  • La-140 x C10106 gCi La-142 xICI/, 0 6 paCi Pr-144 xlCI/lo 6 gaCi 5.10 Determine total activity release for each isotope by adding the total Curies released.

Enter the results in Table I.

Page 17 of 21 REFERENCE USE

POINT BEACH NUCLEAR PLANT POINT BEACH NUCLEAR PLANT EPIP 10.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 20 February 3, 2003 CORE DAMAGE ESTIMATION I TABLE I TOTAL ACTIVITY RELEASED (ATMOSPHERIC, RCS, AND SUMP) 1 2 3 4 5 ISOTOPE TOTAL TOTAL REACTOR TOTAL SUMP TOTAL ACTIVITY ATMOSPHERIC COOLANT SYSTEM ACTIVITY (Ci) RELEASED FROM ACTIVITY (CQ) ACTIVITY (Ci) (From TABLE H-3) CORE (Ci)

(From TABLE H-i) (From TABLE H-2) (Sum columns 2,3, &4)

Kr-87

  • Xe-131m
  • Xe-133m
  • Xe-133
  • Xe-135 1-131

"*1-132 1-133 1-135 Rb-88 Cs-134 Cs-137 Te-129 Te-132 Ba-140

  • La-140 La-142 Pr-144 Page 18 of 21 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 10.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 20 February 3, 2003 CORE DAMAGE ESTIMATION 5.11 Determine the fraction of total available core activity released. Enter the results in Table J.

NOTE: The total inventory values available for release, Curies, have been corrected for thermal output differences in the WOG Core Damage Methodology tables. The values in Table J below are based upon PBNP's I 1540 MWT output versus the 1961 MWT core inventory referenced in the WOG tables.

5.11.1 Calculate the fraction released by dividing the total activity released from the core (Table I) by the total activity (inventory) available for release.

5.11.2 Multiply the results by 100 to obtain percentage of release.

TABLEJ FRACTION OF CORE RELEASED (ATMOSPHERE, RCS, AND SUMP) 1 2 3 4 5 ISOTOPE TOTAL ACTIVITY TOTAL ACTIVITY FRACTION  %

INVENTORY RELEASED FROM RELEASED CORE AVAILABLE FOR CORE (Ci) (PERCENTAGE) DAMAGE RELEASE (Ci) (From TABLE I) (CLAD, OVERTEMP, OR MELT)

Kr-87 1.73E+07

  • Xe-.131 m 2.75E+05
  • Xe- 133m 1.26E+07
  • Xe- 133 8.64E+07
  • Xe- 135 1.65E+07 1-131 4.24E+07
  • 1-132 6.20E+07 1-133 8.64E+07 1-135 7.77E+07 Rb-88 2.5 1E+07 Cs-134 1.02E+07 Cs-137 4.63E+06 Te- 129 1.41E+07 Te-132 6.20E+07 Ba-140 7.38E+07
  • La-140 7.77E+07 La-142 6.60E+07 Pr-144 5.42E+07 Page 19 of 21 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 10.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 20 February 3, 2003 CORE DAMAGE ESTIMATION 5.12 For each isotope, on the appropriate figure (Figure 2-2 through 2-9 located on pages 15 - 22, Figure 2-11 and 2-12 located on pages 40-42 and Figure 2-13 through Figure 2-15 located on pages 45-47 of the WOG Methodology Manual), find the Fraction Released (Percentage) value from Table J on the "Y" axis and read the percentage of core damage on the "X" axis where the value of core inventory released crosses the average burn-up line on the graph.

5.13 If power history was NOT steady state prior to the accident, power correction may be necessary for core inventories. Reference page 4 of the WOG Methodology Section 2.3.

5.14 If iodine spiking is suspected, the amount of clad damage may be overestimated.

Reference page 25 of the WOG Methodology Section 2.4.3.2.

5.15 Evaluate the results for each isotope to determine which of the following seven categories best represents the condition of the core:

  • No Clad Damage 0 0-50% Clad Damage 0 0-50% Fuel Pellet Overtemperature S0-50%Fuel Melt
  • 50-100% Clad Damage
  • 50-100% Fuel Pellet Overtemperature
  • 50-100% Fuel Melt Best estimation of Core Damage 5.16 Relay the results to the TSC Manager and Dose/PAR Coordinator.

Performed By:

Performer (Print and Sign) Date / Time Reviewed By:

Reviewer (Print and Sign) Date / Time Page 20 of 21 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 10.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 20 February 3, 2003 CORE DAMAGE ESTIMATION

6.0 REFERENCES

6.1 EPIP 8.4.1, Post-Accident Sampling And Analysis Of Potentially High Activity Reactor Coolant 6.2 EPIP 8.4.2, Post-Accident Sampling Of Containment Atmosphere 6.3 EPIP 8.4.3, Emergency Containment Sump "A" Sampling 6.4 Radioactive Decay Data Tables, Technical Information Center, Kocher, David. C.,

USDOE, 1981. DOE/TIC - 11026.

7.0 BASES B-1 Westinghouse Owner's Group Post-Accident Core Damage Assessment Methodology Page 21 of 21 REFERENCE USE

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