RNP-RA/18-0031, H.B. Robinson Steam Electric Plant (Hbrsep), Unit 2 - 2017 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual, Revision 35

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H.B. Robinson Steam Electric Plant (Hbrsep), Unit 2 - 2017 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual, Revision 35
ML18115A009
Person / Time
Site: Robinson Duke Energy icon.png
Issue date: 04/23/2018
From: Sherman C E
Duke Energy Progress
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RNP-RA/18-0031
Download: ML18115A009 (330)
v • d • e


Text

{{#Wiki_filter:Serial: RNP-RA/18-0031 APR 2 3 2018 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 H. B. ROBINSON STEAM ELECTRIC PLANT (HBRSEP), UNIT NO. 2 DOCKET NO. 50-261 / RENEWED LICENSE NO. DPR-23 Charles E. Sherman H. B. Robinson Steam Electric Plant Unit 2 Director-Nuclear Organizational Effectiveness Duke Energy 3581 West Entrance Road Hartsville , SC 29550 0 843 9511609 F: 843 951 1319 Chuck.Shermantldukfl-flnargy.com 1 O CFR 50.36a(a)(2) TS 5.5.1.c.3 TS 5.6.3 2017 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT AND OFFSITE DOSE CALCULATION MANUAL, REVISION 35 Ladies and Gentlemen: Enclosed is the Annual Radioactive Effluent Release Report for H.B. Robinson Steam Electric Plant, Unit No. 2 (HBRSEP2), for the period of January 1, 2017 through December 31, 2017. This report is submitted in accordance with 10 CFR 50.4, as required by 1 O CFR 50.36a(a)(2) and HBRSEP2 Technical Specifications (TS) Sections 5.5.1.c.3 and 5.6.3. Attachment 9 of the Enclosure contains a copy of the HBRSEP Offsite Dose Calculation Manual, Revision 35. This letter contains no new regulatory commitments. Should you have any questions regarding this matter, please contact Mr. Kevin Ellis, Manager -Nuclear Regulatory Affairs, at (843) 951-1329. Sincerely, Charles E. Sherman Director -Nuclear Organization Effectiveness CES/jmw United States Nuclear Regulatory Commission Serial: RNP-RA/18-0031 Page 2 of 2

Enclosure:

2017 Annual Radioactive Effluent Release Report c: NRC Regional Administrator, NRC Region II D. Galvin, NRC Project Manager, NRR (w/o Enclosures) NRC Resident Inspector, HBRSEP S. E. Jenkins, SCDHEC A. Nair, SCDHEC T. R Hornosky, P.G., SCDHEC United States Nuclear Regulatory Commission Enclosure to Serial: RNP-RA/18-0031 328 Pages (including this cover sheet) 2017 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2017-DECEMBER 31, 2017 

=       10

=

+

(+)

=()+

,+,,=,

=1.0 (+)<1(+)>1=[()+],,==()+

==

=

10 1 =()+()

= 10 1 =60

=()+()

==1.0

=(1.14 1021)+1.14 10100120.31

==1.0

1.5 5 3 10

=92(+)+

=3.17 10++/RRR/Q 

=       10 =

=4.662.22 10

=

=500/()/Q=3000/[(+1.11)] =2.12 10

= =+

=472 Containment Purge: Used for R -14 or R-12 when R-11/12 aligned to the Plant Vent. from analysis of Containment Vent0.366+from analysis of Plant Vent0.634, (,,) , (,,) Containment Pressure Relief: Used for R -14 or R-12 when R-11/12 aligned to the Plant Vent. from analysis of Containment Vent0.040+from analysis of Plant Vent0.960 , , , , , ,

Waste Gas Decay Tanks (WGDT). from analysis of WGDT0.0016+from analysis of Plant Vent0.9984 (,) , (,) WGDT during Containment Purge. from analysis of WGDT0.001+from analysis of Plant Vent0.633+from analysis of C.V.0.366 (,,) , (,,) , (,,) =/()/Q =/[(+1.11)]

500=3000 =

= += +

/+/500 /(+1.11)/+/3000 //Q/Q QQ /Q /Q /Q /Q/Q

/+/1500 //QQ/QQ

=3.17 10/+/+/=3.17 10/+/+//Q/q/QQ qQ/Q/Q

=92(+)+

=3.17 10/+/+/+ (+++)/+/+/+ +++/+/+//Q/q/Q D/Q

D/q D/QQqQQqQ

=92(+)+

=//Q=472When R-11 is sampling the Plant Vent for C.V. Purges: from analysis of Containment Vessel0.366DF+from analysis of Plant Vent0.634, (,,) , (,,)

When R-11 is sampling the Plant Vent for C.V. Pressure Relief: from analysis of Containment Vent0.040DF+from analysis of Plant Vent0.960 , , , , , , When R-11 is sampling C.V. : from analysis of Containment VentDF=1500 

    =C=     ( )+

=15//Q ,=

,=,

=,+

=3.17 10/ /q

Q

=3.17 10/ /Q

Q

,=(+)

=3.17 100.110.160.30/+0.30/

/q/Q

=

=

,=+,+,+()

,=,+, 

(1)  (1)+ (2)  (2)+1.0

=4.662.22 ()

,=,1.49+06,

"The gaseous and liquid radwaste systems at HBR are used to collect and treat gaseous and liquid chemical and radiochemical byproducts of unit operation. These systems produces effluents that can be discharged in small, dilute quantities to the environment. After processing, liquid wastes may be discharged from the Steam Generator Blowdown Flash Tank, a series of Waste Condensate Tanks, or a series of Monitor Tanks. Gaseous wastes are mainly discharged from the Plant Vent Stack. Less significant sources of gaseous waste may come from the Upper Fuel Handling Building Exhaust, Lower Fuel Handling Building Exhaust, E&RC Laboratory Exhaust, Radwaste Building Exhaust, or Building 457. Building 457 is used only intermittently mainly for pre -outage activities , therefore effluent accountability will be performed as needed. Additionally, secondary system steam releases may occur from normal plant operation or system response. Any secondary system steam releases containing licensed radioactivity are evaluated for inclusion in the site effluent release total."

"Unit 1""Retired Fossil Plant" "Unit 1""Retired Fossil Plant"

"Unit 1""Retired Fossil Plant"

"Unit 1""Retired Fossil Plant"

"Tritium released from each lake section is determined using lake evaporation, lake section area, and average monthly tritium concentration from REMP Surface Water location SW-40. Evaporation is derived using annual meteorological data, including wind speed and humidity, and average lake temperature. Lake section evaporation is determined annually from any of the following: a proprietary vendor method, Duke Energy internal calculation, values published by National Oceanic and Atmospheric Administration, or estimates from the State Climatology Office. Q i values use in Equation 2.5-9 are reported annually in ARERR. 

 =       10 (2.5-10) where:  Ai = Area of lake section 'i' listed in Appendix E (m 2). E i = Monthly evaporation of lake section 'i' (mm H 2O). C i = Monthly concentration of tritium from REMP Surface Water location SW

-40 (pCi/L). 10-6 = Conversion (1E -03 mm/m

  • 1E

-06 µCi/pCi

  • 1E+03 L/m 3)."

2.5.4 Dose from Tritium in Fish in Lake Robinson The concentration of tritium in fish is directly related to the concentration of tritium in the water. Equilibrium ratios between the concentration of tritium in the water and concentration of tritium in the flesh is based upon the bioaccumulation factor for tritium. Because the adult age group will always have the maximum dose from fish consumption, adult is only age group considered. This calculation is performed annually for inclusion in the ARERR. 

 =        (2.5-11) where: Rapj = Annual dose to organ 'j' from tritium ingestion to adult age group (mrem/yr).

Uap = Usage term for adult from Regulatory Guide 1.109 Table E -11 (21 kg/yr). Dapj = Adult dose factor for tritium ingestion, same for Total Body and all organs (1.05E-07 mrem/pCi). C ip = Concentration of tritium from REMP Surface Water location SW -40 (pCi/L). BF i = Bioaccumulation factor for tritium in fish from Regulatory Guide 1.109 Table A-1 (0.90 pCi/kg per pCi/L).

=

=3.7 10=1=8.76 101 =(+)

=2.4 10+ =2.8 10+

=0.750.5P

=()

=1 =()1+1+11+1

=()0.750.5R =()1+1+11+1

=()0.750.5R

=()1+1+1+1 UU

=+()0.750.5R

=4.662.22

=4.662.22 10

=4.662

Serial: RNP-RA/18-0031 APR 2 3 2018 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 H. B. ROBINSON STEAM ELECTRIC PLANT (HBRSEP), UNIT NO. 2 DOCKET NO. 50-261 / RENEWED LICENSE NO. DPR-23 Charles E. Sherman H. B. Robinson Steam Electric Plant Unit 2 Director-Nuclear Organizational Effectiveness Duke Energy 3581 West Entrance Road Hartsville , SC 29550 0 843 9511609 F: 843 951 1319 Chuck.Shermantldukfl-flnargy.com 1 O CFR 50.36a(a)(2) TS 5.5.1.c.3 TS 5.6.3 2017 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT AND OFFSITE DOSE CALCULATION MANUAL, REVISION 35 Ladies and Gentlemen: Enclosed is the Annual Radioactive Effluent Release Report for H.B. Robinson Steam Electric Plant, Unit No. 2 (HBRSEP2), for the period of January 1, 2017 through December 31, 2017. This report is submitted in accordance with 10 CFR 50.4, as required by 1 O CFR 50.36a(a)(2) and HBRSEP2 Technical Specifications (TS) Sections 5.5.1.c.3 and 5.6.3. Attachment 9 of the Enclosure contains a copy of the HBRSEP Offsite Dose Calculation Manual, Revision 35. This letter contains no new regulatory commitments. Should you have any questions regarding this matter, please contact Mr. Kevin Ellis, Manager -Nuclear Regulatory Affairs, at (843) 951-1329. Sincerely, Charles E. Sherman Director -Nuclear Organization Effectiveness CES/jmw United States Nuclear Regulatory Commission Serial: RNP-RA/18-0031 Page 2 of 2

Enclosure:

2017 Annual Radioactive Effluent Release Report c: NRC Regional Administrator, NRC Region II D. Galvin, NRC Project Manager, NRR (w/o Enclosures) NRC Resident Inspector, HBRSEP S. E. Jenkins, SCDHEC A. Nair, SCDHEC T. R Hornosky, P.G., SCDHEC United States Nuclear Regulatory Commission Enclosure to Serial: RNP-RA/18-0031 328 Pages (including this cover sheet) 2017 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2017-DECEMBER 31, 2017 

=       10

=

+

(+)

=()+

,+,,=,

=1.0 (+)<1(+)>1=[()+],,==()+

==

=

10 1 =()+()

= 10 1 =60

=()+()

==1.0

=(1.14 1021)+1.14 10100120.31

==1.0

1.5 5 3 10

=92(+)+

=3.17 10++/RRR/Q 

=       10 =

=4.662.22 10

=

=500/()/Q=3000/[(+1.11)] =2.12 10

= =+

=472 Containment Purge: Used for R -14 or R-12 when R-11/12 aligned to the Plant Vent. from analysis of Containment Vent0.366+from analysis of Plant Vent0.634, (,,) , (,,) Containment Pressure Relief: Used for R -14 or R-12 when R-11/12 aligned to the Plant Vent. from analysis of Containment Vent0.040+from analysis of Plant Vent0.960 , , , , , ,

Waste Gas Decay Tanks (WGDT). from analysis of WGDT0.0016+from analysis of Plant Vent0.9984 (,) , (,) WGDT during Containment Purge. from analysis of WGDT0.001+from analysis of Plant Vent0.633+from analysis of C.V.0.366 (,,) , (,,) , (,,) =/()/Q =/[(+1.11)]

500=3000 =

= += +

/+/500 /(+1.11)/+/3000 //Q/Q QQ /Q /Q /Q /Q/Q

/+/1500 //QQ/QQ

=3.17 10/+/+/=3.17 10/+/+//Q/q/QQ qQ/Q/Q

=92(+)+

=3.17 10/+/+/+ (+++)/+/+/+ +++/+/+//Q/q/Q D/Q

D/q D/QQqQQqQ

=92(+)+

=//Q=472When R-11 is sampling the Plant Vent for C.V. Purges: from analysis of Containment Vessel0.366DF+from analysis of Plant Vent0.634, (,,) , (,,)

When R-11 is sampling the Plant Vent for C.V. Pressure Relief: from analysis of Containment Vent0.040DF+from analysis of Plant Vent0.960 , , , , , , When R-11 is sampling C.V. : from analysis of Containment VentDF=1500 

    =C=     ( )+

=15//Q ,=

,=,

=,+

=3.17 10/ /q

Q

=3.17 10/ /Q

Q

,=(+)

=3.17 100.110.160.30/+0.30/

/q/Q

=

=

,=+,+,+()

,=,+, 

(1)  (1)+ (2)  (2)+1.0

=4.662.22 ()

,=,1.49+06,

"The gaseous and liquid radwaste systems at HBR are used to collect and treat gaseous and liquid chemical and radiochemical byproducts of unit operation. These systems produces effluents that can be discharged in small, dilute quantities to the environment. After processing, liquid wastes may be discharged from the Steam Generator Blowdown Flash Tank, a series of Waste Condensate Tanks, or a series of Monitor Tanks. Gaseous wastes are mainly discharged from the Plant Vent Stack. Less significant sources of gaseous waste may come from the Upper Fuel Handling Building Exhaust, Lower Fuel Handling Building Exhaust, E&RC Laboratory Exhaust, Radwaste Building Exhaust, or Building 457. Building 457 is used only intermittently mainly for pre -outage activities , therefore effluent accountability will be performed as needed. Additionally, secondary system steam releases may occur from normal plant operation or system response. Any secondary system steam releases containing licensed radioactivity are evaluated for inclusion in the site effluent release total."

"Unit 1""Retired Fossil Plant" "Unit 1""Retired Fossil Plant"

"Unit 1""Retired Fossil Plant"

"Unit 1""Retired Fossil Plant"

"Tritium released from each lake section is determined using lake evaporation, lake section area, and average monthly tritium concentration from REMP Surface Water location SW-40. Evaporation is derived using annual meteorological data, including wind speed and humidity, and average lake temperature. Lake section evaporation is determined annually from any of the following: a proprietary vendor method, Duke Energy internal calculation, values published by National Oceanic and Atmospheric Administration, or estimates from the State Climatology Office. Q i values use in Equation 2.5-9 are reported annually in ARERR. 

 =       10 (2.5-10) where:  Ai = Area of lake section 'i' listed in Appendix E (m 2). E i = Monthly evaporation of lake section 'i' (mm H 2O). C i = Monthly concentration of tritium from REMP Surface Water location SW

-40 (pCi/L). 10-6 = Conversion (1E -03 mm/m

  • 1E

-06 µCi/pCi

  • 1E+03 L/m 3)."

2.5.4 Dose from Tritium in Fish in Lake Robinson The concentration of tritium in fish is directly related to the concentration of tritium in the water. Equilibrium ratios between the concentration of tritium in the water and concentration of tritium in the flesh is based upon the bioaccumulation factor for tritium. Because the adult age group will always have the maximum dose from fish consumption, adult is only age group considered. This calculation is performed annually for inclusion in the ARERR. 

 =        (2.5-11) where: Rapj = Annual dose to organ 'j' from tritium ingestion to adult age group (mrem/yr).

Uap = Usage term for adult from Regulatory Guide 1.109 Table E -11 (21 kg/yr). Dapj = Adult dose factor for tritium ingestion, same for Total Body and all organs (1.05E-07 mrem/pCi). C ip = Concentration of tritium from REMP Surface Water location SW -40 (pCi/L). BF i = Bioaccumulation factor for tritium in fish from Regulatory Guide 1.109 Table A-1 (0.90 pCi/kg per pCi/L).

=

=3.7 10=1=8.76 101 =(+)

=2.4 10+ =2.8 10+

=0.750.5P

=()

=1 =()1+1+11+1

=()0.750.5R =()1+1+11+1

=()0.750.5R

=()1+1+1+1 UU

=+()0.750.5R

=4.662.22

=4.662.22 10

=4.662}}

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