ML20056G910

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Radioactive Effluent Release Rept North Anna Power Station Jan-June 1993
ML20056G910
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 06/30/1993
From: Bowling M
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
93-571, NUDOCS 9309070308
Download: ML20056G910 (27)
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VluGINIA Eu:cruic ann Pownu COSIPANY Hicnnoxn,Vinoisir unen September 1, 1993 United States Nuclear Regulatory Commission Serial No.93-571 Attention: Document Control Desk NAPS /JHL RMN Washington, D. C. 20555 Docket Nos. 50-338 50-339 License Nos. NPF-4 NPF-7 i

Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT NOS.1 AND 2 RADIOACTIVE EFFLUENT RELEASE REPORT Pursuant to Technical Specification 6.9.1.9, enclosed is the Radioactive Effluent Release Report for North Anna Power Station Unit Nos.1 and 2 for the reporting period of January 1,1993 to June 30,1993.

If you have any questions or require additionalinformation, please contact us.

Very truly yours,

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M. L. Bowling Manager - Nuclear Licensing and Programs Attachment  !

cc: U. S. Nuclear Regulatory Commission Region 11 101 Marietta Street, N. W.

Suite 2900 Atlanta, Georgia 30323 NRC Senior Resident inspector North Anna Power Station 070f'UI.

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9309070308 930630 'T PDR ADOCK 05000338 M R ppg g

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a RADIOACTIVE EFFLUENT RELEASE REPORT NORTH ANNA POWER STATION (JANUARY 01, 1993 TO JUNE 30, 1993)

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PREPARED B'it- -[

/upervisor S

Radiological Analysis REVIEWED BY:

I supervisor Technical Services

.i APPROVED BY: . /.

7/ i Superintendent Radiological Protection F

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FORWARD i

This report is submitted as required by Appendix A to Operating License Nos. NPF-4 and NPF-7, Technical Specifications for North Anna Power Station, Units 1 and 2, Virginia Electric and Power Company, Docket Ncs. 50-338, 50-339, Section 6.9.1.9.

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RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE t NORTH ANNA POWER STATION I i

JANUARY 01, 1993 TO JUNE 30, 1993 INDEX Section No. Subject Page 1 PURPOSE AND SCOPE..................... 1 -

2 2 DISCUSSION............................ 2 -

4 3 SUPPLEMENTAL INFORMATION.............. 5 Attachment 1 -

Effluent Release Data................. 6 Attachment 2 -

Annual and Quarterly Doses............ 7 ,

Attachment 3 -

Revisions to Offsite Dose Calculation Manual (ODCM)......................... 8 Attachment 4 -

Major Changes to Radioactive Liquid, t Gaseous, and Solid Waste Treatment Systems............................... 9 ,

Attachment 5 -

Inoperability of Radioactive Liquid ~

and Gaseous Effluent Monitoring Instrumentation....................... 10 l Attachment 6 -

Unplanned Releases.................... 11 l

Attachment 7 -

Lower Limits of Detection (LLD) for I Effluent Sample Analysis.............. 12 l a

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t 1.0 PURPOSE AND SCOPE .

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The Radioactive Effluent Release Report includes, in Attachment 1, a  !

summary of the quantities of radioactive liquid and gaseous effluents i

and solid waste as outlined in Regulatory Guide 1.21, " Measuring, l I

Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants", Revision 1, June 1974, with data ,.

!I summarized on a quarterly basis following the format of Tables 1, 2 and i 3 of Appendix B thereof. The report submitted within 60 days after

, January 1 of each year includes an assessment of radiation doses to the l maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site during the previous calendar year. The report submitted within 60 days af ter July 1 of each year has ,

the same sections except for the assessment of radiation doses. .The report also includes a list of unplanned releases during the reporting l

! period, in Attachment 6. ,

i As required by Technical Specification 6.15, changes to the Offsite Dose Calculation Manual (ODCM) for the time period covered by this report are i

included in Attachment 3.

Major changes to radioactive liquid, gaseous and solid waste treatment systems are reported in Attachment 4, as required by the ODCM, section 6.5.2. Information to support the reason (s) for the change (s) and a summary of the 10 CFR 50.59 evaluation are included. In lieu of reporting major changes in this report, major changes to the radioactive waste treatment systems may be submitted as part of the annual FSAR-  !

update.

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1.0 PURPOSE AND SCOPE (cont).

l As required by the ODCM, sections 6.2.2.b.2 and 6.3.2.b.3, a list and explanation for the inoperability of radioactive liquid and/or gaseous effluent monitoring instrumentation is provided in Attachment 5 of this  ;

report.

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2.0 DISCUSSION i

The basis for the calculation of the percent of technical specification for the critical organ in Table 1A of Attachment 1 is the ODCM, section i 6.3.1, which requires that the dose rate for iodine-131, for tritium, i and for all radionuclides in particulate form with half-lives greater than 8 days shall be less than or equal to 1500 mrem /yr to the critical organ at or beyond the site boundary. The critical organ is the child's thyroid via the inhalation pathway.

The basis for the calculation of percent of technical specification for  ;

the total body and skin in Table 1A of Attachment 1 is the ODCM, section 6.3.1, which requires that the dose rate for noble gases to areas at or beyond site boundary shall be less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the skin. l r

The basis for the calculation of the percent of technical specification ,

t in Table 2A in Attachment 1 is the ODCM, section 6.2.1, which states ,

that the concentrations of radioactive material released in .

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i 2.0 DISCUSSION (cont). ,

liquid effluents to unrestricted areas shall be limited to the concentrations specified in 10 CFR 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For j dissolved or entrained noble gases, the concentration shall be limited l to 2.0E-4 microcuries/ml.  ;

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l Percent of technical specification calculations are based on the total gaseous or liquid effluents released for that respective quarter.

The annual and quarterly doses, as reported in Attachment 2, were  ;

calculated according to the methodology presented in the ODCM. The beta ,

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and gamma air doses due to noble gases released from the site were ,

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calculated at site boundary. The maximum exposed member of the public j from the releases of airborne iodine-131, tritium and all radionuclides ,

in particulate form with half-lives greater than 8 days, is defined as an infant, exposed through the grass-cow-milk pathway, with the critical organ being the thyroid gland. The maximum exposed member of the public i 4

from radioactive materials in liquid effluents in unrestricted areas is  ;

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! defined as an adult, exposed by either the invertebrate or fish pathway, ,

4 with the critical organ being the liver. The total body dose was also i determined for this individual.

Presented in Attachment 6 is a list of unplanned gaseous and liquid .

releases exceeding the ODCM limits of sections 6.3.1 and. 6.2.1 respectively.

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i 2.0 DISCUSSION (cont). [

The typical Lower Limit of Detection (LLD) capabilities of the  !

l radioactive effluent analysis instrumentation are presented in l Attachment 7. These LLD values are based upon conservative conditions l l

(i.e., minimum sample volume and maximum delay time prior to analysis).

Actual LLD values may be lower. If a radioisotope was not detected when effluent samples were analyzed, then the activity of that radioisotope was reported as Not Detectable (N/D) on Attachment 1 of this report.

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3.0 SUPPLEMENTAL INFORMATION As required by the ODCM, section 6.5.2, evaluation of the Land Use i

Census is made to determine if new location (s) have been identified for l

, the radiological environmental monitoring program pursuant to the ODCM, Section 6.5.2 requirements. Evaluation of the Land Use Census conducted  ;

in 1993 identified no change in sample locations for the radiological  ;

environmental monitoring program. j s

1 Section 6.5.1.b.4 of the ODCM requires identification of the cause(s) for the unavailability of milk or leafy vegetation samples, and the l 1

identification of new locations for obtaining replacement samples. Milk samples, as required by the ODCM, section 6.5.1, were available during the time period covered by this report. The leafy vegetation samples  ;

for vegetation station 14, 15, 16, 21 and 23 were not collected for the L

months of January, February and March 1993 due to seasonal  :

i unavailability. All other samples were obtained and analyzed as  !

! required during the time period covered by this report. 1 i

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ATTACHMENT 1 I EFFLUENT RELEASE DATA

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(01/93 -

06/93) i i

This attachment includes a summary of the quantities of radioactive liquid j and gaseous effluents and solid waste, as outlined in Regulatory Guide 1.21,  !

l Appendix B. I f

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TABLE 1A '. '

NORTH ANNA POWER STATION SIMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REEQBT SUMMATION OF ALL GASEOUS EFFLUENT RELEASES FOR (01/93 - 06/93) , ,

1st 2nd ESTIMATED TOTAL .

UNITS QUARTER QUARTER PERCENT EBBOR (%)

A. Eission and ActivatigIL9Agfa:

1. Total Release. Curies 8.27E+1 5.96E+1 1.80E+1
2. Averace Release Rate for Period uCi/sec 1.06E+1 7.58E+0 B. IgAinga:
1. Total. Iodine-131 Release. Curies 8.76E-4 _1.47E-4 2.80E+1
2. Averace Release Rate for Period uCi/sec 1.13E-4 1.87E-5 C. P_articulatas fTh > 8_dayal:
1. Total Particulate (T\ > 8 days)

Release Curies 3.67E-4 1.86E-5 2.80E+1

2. Averace Release Rate for Period uCi/sec 4.72E-5 2.36E-6 ,
3. Gross Aloha Radioactivity Release Curies 4.23E-5 5.34E-5 D. Tritium:
1. Total Release Curies 6.82E+0 3.59E+0 3.10E+1
2. Average Release Rate for Period uCi/sec 8.77E-1 4.57E-1 E. P_eIggntJge_of Techni_ cal Specification Limita
1. Total Body Dose Rate  % 3.95E-3 9.45E-4
2. Skin Dose Rate  % 1.61E-3 3.57E-4
3. Critical Oraan Dose Rate  % 1.63E-3 4.33E-4

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TABLE 2A ,

NORTH ANNA POWER STATION SLMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUINTS-SUMMATION OF ALL RET FASES FOR f01/93 - 06/93) ist 2nd ESTIMATED TOTAL .

UNITS OUARTER OQJ@TIR PERCENT ERROR f%)

A. Fission and Activation Producta:

1. Total release (not including tritium, noble gas, and gross aloha). Curies 1.36E-1 1.16E-1 2.00E+1
2. Average diluted concentration durina the Deriod, uCi/ml 4.38E-10 1.54E-10
3. Percent of aDolicable limit (T.S.)  % 3.38E-3 2.85E-3 B. Tritium:
1. Total release activity. Curies 1.15E+2 2.10E+2 2.00E+1
2. Average diluted concentration durina the Deriod. aci/ml 3.70E-7 2.79E-7
3. Percent of aDplicable Limit (T.S.)  % 1.23E-2 9.28E-3 C. Dissolved and_ Entrained Gangg:
1. Total release activity. Curies 1.17E-3 5.43E-2 2.00E+1
2. Average diluted concentration durina the Deriod. uCi/ml 3.75E-12 7.21E-11
3. Percent of apolicable limit (T.S.)  % 1.87E-6 3.61E-5 D. GIngs Alpha Radioactivity:
1. Total release activity. Curies 6.14E-5 3.07E-4 2.00E+1 E. Volume of waste released: (prior to dilution). Liters 5.98E+7 6.86E+7 3.00E+0 F. Total volume of dilution water used durine the period. Liters 3.11E+11 7.52E+11 3.00E+0

ZABLE 2B NORTH ANNA POWER STATION EEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT -

LIOUID EFFLUENT RELEASES FOR 01/93 - 06/93 Page 1 of 2 CONTINUOUS MODE BATCH MODE 1st 2nd 1st 2nd ELCLIQES ... RELEASED UNITS QUARTER OUARTER OUARTER QUARTER Fission & Activation Products:

Mancanese - 54 Ci 1.25E-3 5.54E-4 N/D N/D Iron - 55 Ci N/D N/D N/D N/D Cobalt - 58 Ci 5.52E-2 2.01E-2 1.33E-5 N/D Cobalt - 60 Ci 1.55E-2 1.48E-2 1.65E-5 3.04E-6

_ Strontium - 89

_ Ci N/D N/D ___ N/D N/D '

_Hirontium - 90 Ci N/D N/D N/D N/D Niobium - 95 Ci 5.07E-3 4.07E-3 N/D N/D Ruthenium - 106 Ci 2.00E-4 9.95E-4 N/D N/D Silver - 110m Ci 8.57E-3 1.26E-2 N/D N/D Iodine - 131 Ci 1.49E-3 5.10E-3 7.50E-4 N/D Iodine - 133 Ci 6.17E-4 2.52E-3 1.21E-4 N/D Cesium - 134 C1 1.95E-3 2.36E-4 1.03E-3 2.49E-5 Cesium - 136 Ci N/D N/D 6.39E-5 N/D Cesium - 137 Ci 2.88E-3 6.01E-4 1.15E-3 6.08E-5 Barium - 140 Ci N/D N/D N/D N/D Cerium - 141 Ci N/D N/D N/D N/D

_Rntimony - 125 Ci 2.04E-2 5.13E-2 N/D N/D Other (Scecifv1 Sodium - 24 (TN < 8 days) Ci N/D 7.22E-5 N/D N/D Antimony - 122 (Th < 8 days) Ci 9.93E-5 N/D 1.40E-5 N/D Chromium - 51 Ci 1.71E-2 1.46E-3 N/D N/D Iron - 59 Ci 1.29E-3 N/D N/D N/D

_ Zirconium - 95 Ci 8.79E-4 N/D N/D N/D Antimony - 124 Ci 9.15E-4 N/D N/D N/D

_ Zinc - 65 Ci N/D N/D 1.37E-7 N/D Rhodium - 106 Ci 2.00E-4 9.95E-4 N/D N/D Tellurium - 129 Ci N/D 3.17E-4 N/D N/D Tellurium - 129m Ci N/D 3.17E-4 N/D N/D Total for Period Ci 1.33E-1 1.16E-1 3.16E-3 8.88E-5 i

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TABLE 3 NORTH ANNA POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS FOR 01-01-93 THROUGH 06-30-93 Pace 1 of 2 A. SOLID WASTE SHIPPED OFFSITE FOR BUFIAL OR DISPOSAL (NOT IRRADIATED FUEL) 6-Month Estimated Total .

1. Type of Waste Unit Period Percent Error (%)
a. Spent resins, filter m8 6.28E+1* 2.50E+1 sludges, evaporator Ci 5.17E+2 2.50E+1
  • bottoms.etc.  ;
b. Dry compressible waste, m8 1.64E+3** 2.50E+1 contaminated equipment, Ci 6.56E0 2.50E+1 etc.
c. Irradiated components, m8 0.00E0 0.00E0 control rods. etc. Ci 0.00E0 0.00E0
d. Other (describe) m8 4.25E0*** 2.50E+1 '

Waste Oil Ci 3.42E-4 2.50E+1

2. Estimate of major nuclide composition (by type of waste)
a. Fe-55  % 1.56E+1 2.50E+1 Co-60  % 3.02E+1 2.50E+1 Ni-63  % 3.71E+1 2.50E+1 Ni-59  % 3.05E0 2.50E+1 Co-58  % 2.85EO 2.50E+1 '

4 Cs-137  % 5.27EO 2.50E+1 Cd-109  % 1.80E0 2.50E+1 Cs-134  % 2.47E0 2.50E+1

b. Fe-55  % 2.26E+1 2.50E+1 Co-60  % 1.54E+1 2.50E+1 Cs-137  % 1.45E+1 2.50E+1 Ni-63  % 9.92E0 2.50E+1 Co-58  % 1.96E+1 2.50E+1 Cr-51  % 4.29EO 2.50E+1 Zr-95  % 4.10E0 2.50E+1 Nb-95  % 5.70E0 2.50E+1 ,

C.

l

TABLE 3 NORTH ANNA POWEF; STATION RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS FOR 01-01-93 THROUGH 06-30-93 Pace 2 of 2

2. Estimate of major nuclide composition (by type of 6-Month Estimated Total waste) (cont.) Unit Period Percent Error (%)
d. Co-60  % 5.57E0 2.50E+1 Fe-55  % 4.59E+1 2.50E+1 Co-58  % 4.92E0 2.50E+1 Ni-63  % 2.19E+1 2.50E+1 Ag-110m  % 1 34E+1 2.50E+1
3. Solid Waste Disposition Number of Shionents Mode of Transoortation Destination 11 Truck Barnwell, SC 1 Truck Oak Ridge, TN (SEG) 31 Truck Oak Ridge, TN ,

(Quadrex)

B. Irradiated Fuel Shipments (Disposition)

Hu_mber of Shioments Mode of Transportation Destination N/A N/A N/A

  • 1 shipment of resin was shipped from . North Anna to a Licensed Waste Processor for volume reduction. Therefore, the volume listed for this type is not representative of actual volume buried. The total volume buried for this reporting period was 45.19 m8
    • 30 shipments of dry compressible waste / contaminated equipment were shipped from North Anna to a Licensed Waste Processor for volume reduction. Therefore, the volume listed for this type is not representative of the actual volume buried. The total volume buried for this reporting period was 105.7 m 8 .
      • 1 shipment of waste oil was shipped from North Anna to a Licensed Waste '

Processor for incineration and volume reduction. Therefore, the volume  !

listed for this type is not representative of the actual volume buried.

The total volume buried for this reporting period was 4.98 m 8.

t

ATTACIIMENT 2 ANNUAL AND OUARTERLY DOSES (01/93 -

06/93) l i

i An assesament of radiation doses to the maximum exposed member of the i i

public due to radioactive liquid and gaseous effluents released from the site l

for each calendar quarter for the calendar year of this report, along with an annual total of each effluent pathway, is made pursuant to the ODCM, Section j 6.6.2 requirements, in the Radioactive Effluent release Report submitted within sixty (60) days after January 01, 1994.

i I

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7

ATTACHMENT 3 i

REVISIONS TO OFFSITE DOSE CALCULATION MANUAL  !

(ODCM)

(01/93 -

06/93) }

As required by Technical Specification 6.15, revisions to the ODCM effective for the time period covered by this report, are summarized in this attachment.

l F

There were no revisions to the ODCM during this reporting period.

I f

f I

8

7 ATTACHMENT 4 ,

MAJOR CHANGES TO RADIOACTIVE LIOUID. GASEOUS. AND SOLID WASTE TREATMENT SYSTEMS (01/93 -

06/931 9

As required by 'he ODCM, Section 6.6.2, major changes to radioactive liquid, gasecus and solid waste treatment systems for the time period covered by this report are synopsized in this attachment. Supporting information as to the reason (s) for the change (s) and a summary of the 10 CFR 50.59 evaluation are included, as applicable.

No major changes to the radioactive gaseous and solid waste treatment systems were made for the time period covered by this report. ,

1 l

1 9

i i

i

r I

ATTACHMENT 5 {

INOPERABILITY OF RADlQACTIVE LIOUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATIOP{  !

(01/93 -

06/93)

As required by the ODCM, Sections 6.2.2.b.2 and 6.3.2.b.3, a list and explanation for extended inoperability of radioactive liquid and/or gaseous  :

effluent monitoring instrumentation is provided in this attachment. f I

t No extended periods of inoperability occurred with any of the Liquid or Gaseous Effluent Monitoring Instrumentation specified in the ODCM, !

Attachments 2 and 15, for the time period covered by this report.

[

h 10

I ATTACIMENT 6 UEPLANNED RELEASES f01/93 -

06/931 As required by the ODCM, Section 6.6.2, a list of unplanned releases, from i the site to unrestricted areas, of radioactive material in gaseous and liquid effluents occurring during the reporting period, is made in this attachment.

No unplanned releases, as defined by the criteria presented in the ODCM, Section 6.6.2, occurred during the time period covered by this report.

r 11

)

l

I- -

ATTACHMENT 7 LOWER LIMITS OF DETECTION FOR EFFLUENT SAMPLE ANALYSIS (01/93 -

06/93)

Gaseous Effluents:

Required L.L.D. Typical L.L.D.

Radioisotope fuci/ml) (uci/ml)

Kryoton - 87 1.00E-4 3.40E-7 -

4.34E-7 Krypton - 88 1.00E-4 4.65E-7 -

6.28E-7 Xenon - 133 1.00E-4 2.86E-7 - 3.89E-7 Xenon - 133m 1.00E-4 1.03E-6 -

1.51E-6 Xenon - 135 1.00E-4 1.36E-7 -

1.78E-7 Xenon - 135m 1.00E-4 1.27E-7 -

1.86E-7

__Xgngn - 138 1.00E-4 1.11E-6 -

1.59E-6 Iodine - 131 1. 0 0 E- 5.57E 7.59E-14 Manganese - 54 1.00E-11 4.35E 4.89E-14 Cobalt - 58 1.00E-11 3.83E 5.21E-14 Iron - 59 1.00E-11 7.21E 9.75E-14 Cobalt - 60 1.0DE-11 7.10E 1.52E Zinc - 65 1.00E-11 9.37E-14 -

1.19E-13 Strontium - 89 1.00E-11 4.00E 1.00E-12 Strontium - 90 1.00E-11 9.00E 6.00E-12 Molybdenum - 99 1.00E-11 2.31E 3.47E-13 Cesium - 134 1.00E-11 4.48E 5.68E-14 ,

Cesium - 137 1.00E-11 4.68E 5.77E-14 Cerium - 141 1.00E-11 4.86E 6.79E-14 Cerium - 144 1.00E-11 2.22E 3.22E-13 I

Gross Aloha 1.00E-11 6.70E 9.48E-15 Tritium 1.00E-6 4.22E-8 -

4.70E-8 I

12 l I

l

(.

ATTACHMENT 7 LOWER LIMITS OF DETECTION FOR EFFLUENT SAMPLE ANALYSIS (01/93 -

06/93)

Liquid Effluents:

Required L.L.D. Typical L.L.D.

Radioisotone fuci/ml) (nCi/ml)

Krynton - 87 1.00E-5 5.84E-8 -

7.29E-8 Kryoton - 88 1.00E-5 8.72E-8 -

1.15E-7 Xenon - 133 1.00E-5 5.79E-8 -

8.83E-8 Xenon - 133m 1.00E-5 1.91E-7 -

2.69E-7 Xenon - 135 1.00E-5 2.30E-8 -

3.14E-8 Xenon - 135m 1.00E-5 8.65E-8 -

1.13E-7 Xenon - 138 1.00E-5 1.85E-7 -

2.79E-7 Iodine - 131 1.00E-6 2.66E-8 -

3.43E-8 Mangangpe - 54 5.00E-7 2.52E-8 -

3.93E-8 Iron - 55 1.00E-6 6.00E-7 -

7.00E-7 Cobalt - 58 5.00E-7 2.32E-8 -

3.25E-8 Iron - 59 5.00E-7 4.87E-8 -

5.86E-8 Cobalt - 60 5.00E-7 3.16E-8 -

8.43E-8 Zin,- 65 5.00E-7 5.27E-8 -

6.83E-8 Strontium - 89 5.00E-8 2.00E-8 -

4.00E-8 Strontium - 90 5.00E-8 5.00E-9 -

1.00E-8 Molybdenum - 99 5.00E-7 1.50E-7 -

2.26E-7 Cesium - 134 5.00E-7 2.88E-7 -

5.57E-8 Cesium - 137 5.00E-7 2.66E-8 -

3.79E-8 Cerium - 141 5.00E-7 4.12E-8 -

5.47E-8 3 Cerium - 144 5.00E-7 1.81E-7 -

2.63E-7 Gross Alpha 1.00E-7 2.09E-8 -

2.94E-8 Tritium 1.00E-5 2.92E-6 -

3.24E-6 13

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