ML20090A452

Rev 7 to Hb Robinson Steam Electric Plant,Unit 2 Odcm

ML20090A452
Person / Time
Site:	Robinson
Issue date:	07/30/1991
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML14174A256	List: ML20090A448 ML20090A452
References
PROC-910730, NUDOCS 9203020340
Download: ML20090A452 (53)

Text

Enclosura 2 to forfal: RNPD/92 0409 Pegs 4 of 48 H. B, ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 0FF SITE DOSE CALCUIATIONAL .%WAL (ODCM)

Revision 7 DOCKET NO. 50-261 4

PNSC Review  %) DATE 9 h3 /

N C Ch irman CAROLINA PO'.'ER & LIGHT COMPAFI HBRODC0 .

.I Enclosure 2 to Serial:

RNPD/92 040?

Pags 5 of 48 li l

i TABLE OF CONTENTS Ti.tle Page Section

.. ..... .. . . . . .... i TABLE OF CONTENTS..... .............

11 LIST OF TABLES... .... .......... . ..... ..... .............

...... .. iv LIST OF FIGURES., ...... ..... . ....... ...... ...

......................... 1-1

1.0 INTRODUCTION

......... ... . .... 2-1 2.0 LIQUID EFFLUENTS........ ......... ...... 2-1 2.1 Monitor Alarm Setpoint Determination....... ......... ....

2-11 2.2 Compliance with 10CFR20 (Liquids)............... . .. .... 2-16 2.3 Compliance with 10CFR50 (Liquids).............. ..........

31 3.0 GASEOUS EFFLUENTS . . . . . . . . . 3-1 3.1 Monitor Alarm Setpoint Determination... ..... .. ... .. ..

3-15 3.2 Compliance with 10CFR20 (Gaseous).... . .... .... .......

3-23 Compliance with 10CFR50 (Gaseous)... .....................

3.3 3-63 3.4 Methodolo,r for RMS-11 Setpoint (Air Particulate)...... .

3-67 3.5 . Methodology for R 14A Setpoint (Particulate Monitor)... ..

3-69 3.6 Methodology for R 14B Setpoint (Iodine Monitor)... ......

3.7 Methodology for R-22 and R 23 Setpoint Determinations 3-70 for-the . Iodine and Particulate Monitors....

..... .... 41 4.0 RADIOLOGICAL ENVIRONME AL MONITORING PROGRAM........

5-1 5.0 INAERLABORATORY COMPARISON STUDIES.. . ...... ... ......... .... 5-1 5.1 Objective................................ .............. . 51 5.2 Program...................... ... ..... ... .. .... ....

.......... .... . . . . . , , . 61 6.0- TdTALDOSE(40CFR190CONFORMANCE)....... ........., 6-1 6.1 Compliance with 40CFR190....................... 6-1 6.2 Calculations Evaluating Conformance with 40CFR190.........

I' 6-2 6'. 3 Calculations of Total Body Dose.... . ......... ......... 6-3 L

L 6.4- Thyroid Dose.................................. .......... 6-3_

6.5 Dose Projects................. .. ...... .... ...... .....

APPENDIX A Meteorological Dispersion Factor A-1 Computations................ ...... ...... .. .....

APPENDIX B Dose Parameters for Radiolodines. 'B 1 Particulates, and Tritium.. .... ........ ...... ...... .

C-1 APPENDIX C - Lower Limit of Detectability.... ....... ... ......

l 1

1 Rev. 7 HBRODCO-I l

Enclosure 2 to Serial: RNPD/92-0409 Page 6 of 48 l . .

2.0 LIQUID EFFLUENTS 2.1 MONITOR ALAR.M SETPOINT DETERMINATION This methodology determines the monitor alarm setpoint that indicates if the concentration of radionuclides in the liquid effluent released from the site to unrestricted areas exceeds the concentrations specified in 10CFR20, Appendix B, Table II, Column 2, for radionuclides other than concentration dissolved or entrained noble gases or exceeds a

2 x 10" uCi/ml for dissolved or entrained noble gases. Two methodologies may be utilized to calculate monitor alarm setpoints. Section 2.1.1 determines a fixed setpoint based on the worst case assumptions that 1 131 is the only nuclide being dischar5ed. This is consistent with the limit Appendix B, Footnote 3.a. Section 2.1.2 methodology of 10CFR20 determines the setpoint based on the radionuclide mix via analysis prior to release to demonstrate compliance with 10CFR20, Appendix B, limits and may also be used as an alternative method for calculating setpoints.

2.1.1 Setootnt Based on Iodine-131 The following method applies to liquid releases via the discharge canal when determining the alarm / trip setpoint for the Condensate Polisher Liquid 'Jaste Monitor (R-37) and the Steam Generator Blowdown Monitor  !

(R.-19A, R-19B, and R-19C) during c,perational conditions when there is no l primary to secondary leaks. This methodology complies with Specification ( .

3.9.1.1 of the RETS by satisfying the following equation:

d s:

F where:

The effluent concentration limit . Specification 3.9.1.1)

C -

implementing 10CFR20 for the site in uCi/ml. ,

21 Rev. 7 HBRODC2.R07

'h Enclosura 2 to Serial: RNPD/92 0409 Pege 7 of 48

- 160 gpm for each Steam Generator Blowdown Monitor.

- 130 gpm for each steam Generator Blowdown Monitor while draining a steam generator.

- 300 gpm for the Condensate Polisher Liquid Waste Monitor.

S - 0.5, safety factor used as a conservatism to assure that the radionuclide concentrations are less than the limits specified in 10CFR20, Appendix B, at the point of discharge.

2.1.1.2 Determine CR (calculated monitor count rate in corrected counts per minute [cepm]) attributed to the radionuclides for each of the ,

dilution water flow rates.

CR -

(c) (E)

E - The applicable effluent monitor efficiency located in the Plant Operating Manual, Volume 15, Curve Book. Use the radioactivity concentration "c" to find CR.

2.1.1.3 Determine SP (the monitor alarm / trip setpoint including background (cpm] for each of the dilution water flow rates.

SP = ( T,) (CR)

• Bkg + 3. 3 where: T, - Fraction of the radioactivity from the site that may be released via the monitored path-ay to ensure that the l site boundary limit is not exceeded due to simultaneous releases from several pathways. "

- .16 for each Steam Generator-Blowdown Monitor (R-19A, R-19B, and R-19C).

- .25 for the Condensate Polisher Liquid Waste (R 37).

Bkg - the monitor background.

HBRODC2.R07 2-3 Rev. 7

Enclosure 2.to Serial: RNPD/92 0409 Pegs 8 of 48 3.3 2r - statistical variance on the background (Bkg) count rate (CPM) at a 99.956 confidence level at a RC time constant r (minutes). This is included to prevent inadvertent high/ trip alarms due to random counts on the monitor.

2.1.2 Setooint Based on an Analysis of Licuid Prior to Dischargq The following method applies to liquid releases via the discharge canal when determining the alarm setpoint for the Waste Disposal System Liquid Effluent Monitor (R 18), the Steam Generator Blowdown Monitors (R-19A, R 19B, and R-19C), and the Condensate Polisher Liquid Waste Monitor (R-37) when an ano:ysis of the activity of the principal gamma emitters has been made prior to or during the release.

2.1.2.1 Determine D (the minimum acceptable dilution factor):

D = SD slp or

' + * + * + * +

"* ]

D = S [D

• MFC, MFC, MPC, HPC, MPCg,,,

Ci - Radioactivity concentration of radionuclidn "i" in the liquid effluent prior - to dilution (pCi/ml) from analysis of the liquid _ effluent to be released.

C, - The concentration of each measured gamma-emitting radionuclide observed by gamma spectroscopy including noble gases.

l C. - The measured concentration of alpha-emitting radionuclides observed - by gross alpha analysis of the monthly composite sample.

C. - The measured concentration of Sr-89 and Sr-90 in liquid waste as determined by analysis of the quarterly composite sample.

I HBRODC2.RC7 2-4 Rev. 7 l

Enclosura 2-to Serial: RNPD/92 0409 Pcgs 9 of 48 Cs

- The measured concentrations of H 3 in liquid waste as deter-mined by analysis of the monthly composite sample.

Cr.-ss-The measured concentration of Fe 55 in liquid waste as deter-mined by analysis of the quarterly composite sample.

MPC t - MPC,, MPC., MPC. , MPCs , and MPCr. ss are limiting concentrations of the appropriate gamma emitting radionuclides, alpha-emitting radionuclides., strontium radionuclides, tritium, and iron 55 from 10CTR20, Appendix B, repsectively.

S - 2, A safety factor used as a conservatism to assure that the radionuclide concentrations are less than the limits specified in 10CFR20, Appendix B, at the point ol' discharge.

2.1.2.3 Determine c the monitor setpoint concentration (pci/ml] attributed to the radionuclides for the dilution water flow rate available during the release, f

c = (E , c,) ( f) ( Dn)

-where:

- C.

- The total radioactivity concentration of gamma-emitting radio-nuclides in liquid effluent prior to dilution (pci/ml).

f - The maximum approved discharged flow rate prior to dilution (gpm).

3

- 60 gpm for the Waste Disposal System Liquid Effluent Monitor .

- 160 gpm for each Steam Generator, Blowdown Monitor.

- 130 gpm for each Steam Generator Blowdown Monitor- while i draining a-steam generator.

-- 300 gpm for the Condensate Polisher Liquid Waste Monitor.

HBRODC2.R07 5 Rev. 7

Enclosure 2 to Ssrial: RNPD/92 0409 Pegs 10 of 48

- . i F - Dilution water flow rate (gpm).

- 160,000 gpm from one circulating water pump , Unit 2.

1

- 250,000 gpm from two circulating water pumps , Unit 2.i

- 400,000 gpm from three circulating water pumps , Unit 2. 1 or 2

- 50,000 gpm from one circulating water pump , Unit 1.

2

- 80,000 gpm f om two circulating water pumps , Unit 1.

T. - Fraction of the radioactivity from the site that may be re-leased via the monitored pathway to ensure that the site boundary limit is not exceeded due to simultaneous releases from more than one pathway.

- ,25 for the Waste Disposal System Liquid Effluent Monitor (R-18).

1

- .16 for each of the Steam Generator Blowdown Monitor (R 19A, R 19B or R 19C).

- .25 for the Condensate Polisher Liquid Waste (R-37).

If it is determined that < 1, the release cannot be made. Reevaluate the discharge. flow rate prior to dilution and/or the dilution flow rates.

I f. > 1 , the release may be made.

HBRODC2.R07 2-6 Rev. 7

l Enclosure 2 to Serial: RNPD/92 0409 Pcgs 11 of 48

- The mixture of radt. >nuclides released must be of such concentrations that Equation 2.2 3 must be met.

For HBR, the liquid radwaste effluent line discharges to the circu.

lating water system. Therefore, the dilution flow rate (Dr,) is a function of the number of circulating water pumps operating. Unit 2 of the H.B. Robinson Steam Electric Plant has three circulating water pumps . Pump curves show that with three pumps operating, the circulating water flow is 400,000 gpm, with two pumps--250,000 gpm, and with one pump -160,000 gpm. Unit 1 of the H.B. Robinson Steam Electric Plant has two circulatin6 vater pumps. The circulating water flow is 50,000 gpm with one pump and 80,000 gpm with two pumps. At least one circulating water pump must be operating during any liquid waste discharge.

Batch releases from the HBR liquid radwaste system may occur from the waste condensate tanks, the monitor tanks, and the steam gener-ators (during drainage). Continuous release may occur from Steam Generator Blowdown and the Condensate Polisher Liquid Waste. The maximum administrative telease rate (R3 ) is 160 gpm for each of the steam generators, 60 gpm from the monitor and waste condensate tanks, and 300 gpm for the Condensate Polisher Liquid Wastes, and 130 for each of the steam generators during drainage.

2.2.2.2- Postrelease The Steam Generation Blowdown Monitor (R-19A, R 19B, and R-19C), the Waste Disposal System Liquid Monitor (R 18) , and the Condensate Polisher Liquid Waste Monitor (R-37) setpoint will each be limited

! to 50 percent of the 10CFR20 limits. These setpoints will ensure l

that 10CFR20 limits are met. However,.because they are based upon l a given mix, the possibility exists that the alarm trip setpoints may - be exceeded, while 10CFR20 limits are not exceeded. The following methodology is provided to determine whether actual releases exceeded 10CFR20 limits.

HBRODC2.R07 2-14 Rev. 7

Encionuro 2 to Seriel: RNPD/92-0409 Pegs 12 of 48 TABLE 2.3-1 Air VALUES FOR THE ADULT FOR THE H.B. ROBINSON STEAM ELECTRIC PLANT (MREM /RR PER MICRO-Ci/ML)

Liver T. Body Thyroid MidneY kggg Ql;LLI Huclide 12H1 2,26E 01 2.26E 01 2.26E-01 2.26E 01 2.26E 01 2.26E-01 H3 0.00E-01 6.2(C 03 6.26E+03 6.26E+03 6.26E+03 6.26E+03 6.26E+03 C 14 3.13E+04 4.07E 02 4.07E+02 4.07E+02 4.07E+02 4.07E+02 4.07E+02 Ns 24 4.07E+02 4.62E+07 2.87E 06 1.79E 06 0.00E 01 0.00E 01 0.00E 01 5.19E 06 P-32 0.00E 01 0.00E+01 1.27E 00 7.61E 01 2.81E 01 1.69E 00 3.20E 02 Cr 51 0.00E-01 4.38E 03 8.35E 02 0.00E 01 1.30E 03 0.00E 01 1.34E 04 Mn 54 0.00E-01 1.10E 02 1.95E 01 0.00E 01 1.40E 02 0.00E 01 3.51E 03 Mn 56 6.58E 02 4.55E 02 1.06E 02 0.00E-01 0.00E-01 2.54E 02 2.61E 02 Fe 55 1.04E 03 2.44E 03 9.36E 02 0.00E 01 0.00E-01 6.82E 02 8.14E 03 Fe-59 0.00E+00 2.09E+01 3.48E+01 0.00E+00 0.00E+00 0.00E+00 5.31E+02 Co 57 0.00E-01 8.92E 01 2.00E 02 0.00E 01 0.00E-01 0.00E 01 1.81E 03 Co 58 Co-60 0.00E 01 2.56E 02 5.65E 02 0.00E 01 0.00E-01 0.00E 01 4.81E 03 3.11E 04 2,16E 03 1.04E 03 0.00E 01 0.00E 01 0.00E-01 4.50E 02 Ni 63 1.26E 02 1.64E 01 7.49E 00 0.00E 01 0.00E-01 0.00E 01 4.17E 02 Ni 65 0.00E-01 9.97E 00 4.68E 00 0.00E 01 2.51E 01 0.00E-01 8.50E 02 Cu 64 2.32E 04 7.37E 04 3.33E 04 0.00E-01 4.93E 04 0.00E 01 4.64E 04 Zn 65 Zn 69 4.93E 01 9.43E 01 6.56E 00 0.00E 01 6.13E 01 0.00E 01 1.42E 01 0.00E-01 0.00E-01 4.04E 01 0.00E-01 0.00E 01 0.00E 01 5.82E 01 Br 83-Br-84' O.00E-01 0.00E 01 5.24E J1 0.00E-01 0.00E 01 0.00E-01 4.11E 04 Br-85 0.00E 01 0.00E 01 2.15E 00 0.00E 01 0.00E-01 0.00E 01 1.01E 15 0.00E-01 1.01E 05 4.71E 04 0.00E-01 0.00E 01 0.00E-01 1.99E 04 Rb 86 Rb-88 0.00E-01 2.90E 02 1.54E 02 0.00E 01 0.00E-01 0.00E 01 4.00E 09 0.00E-01 1.92E O2 1.35E 02 0.00E 01 0.00E-01 0.00E-01 1.12E-11

-Rb 89 2.21E 04 0.00E-01 6,35E 02 0.00E-01 0.00E-01 0.00E-01 3.55E 03 Sr 89 5.44E 05 0.00E-01 1.34E 05 0.00E-01 0.00E-01 0.00E-01 1.57E 04 Sr-90 4.07E 02 0.00E 01 1.64E 01 0.00E-01 0.00E-01 0.00E 01 1.94E 03 Sr 91 Sr 92 1.54E 02 0.00E 01 6.68E 00 0.00E-01 0.00E 01 0.00E 01 3.06E 03 5.76E 01 0.00E-01 1.54E-02 0.00E 01 0.00E 01 0.00E-01 6.10E 03 Y-90 5.44E-03 0.00E-01 2.11E-04 0.00E-01 0.00E 01 0.00E-01 1.60E-02 Y-91M 8.44E 00 0.00E-01 2.26E-01 0.00E-01 0.00E-01 0.00E-01 4.64E 03 Y-91 5.06E 02 0.00E-01 1.48E-03 0.00E 01 0.00E-01 0.00E 01 8.86E 02 Y-92 1.60E-01 0.00E-01 4.43E-03 0.00E 01 0.00E-01 0.00E 01 5.09E 03 Y 2.40E-01 7.70E-02 5.21E-02 0.00E 01 1.21E 01 0.00E-01 2.44E 02 Zr 95 1.33E-02 2.68E-03 1.22E 0.00E-01 4.04E-03 0.00E-01 8.30E 02 Zr-97 2.48E 02 1.34E 02 0.00E 01 2.46E 02 0.00E-01 1.51E 06 Nb-95 4.47E 02 0.00E 01 1.03E 02 1,96E 01 0.00E 01 2.34E 02 0 00E-01 2.39E 02 Mo 99 8.87E-03 2,51E-02 3.19E-01 0.00E-01 3.81E-01 1.23E-02 1.48E+01 Tc-99M HERODC2.R07 2 22 Rev. 7

Enclosure 2 to Serial: RNPD/92 0409 Pege 13 of 48 3.0 GASEOUS EFFLUENTS 3.1 MONITOR ALARM SETPOINT DETERMINATION This methodology determines the monitor alarm setpoint if the dose race in the unrestricted areas due to radionoble gases in the gaseous effluent released from the site to areas at and beyond the site boundary exceeds 500 mrem / year to the whole body or exceeds 3000 mrem / year to the skin using a conservative mix (GALE Code).

The methodology described in Section 3.1.2 provides an alternative means to determine monitor alarm setpoints when an analysis is perfor ed prior to release.

3.1.1 Setooint_3ased on Conservative Radionuclide Mix (Ground and M'.xed Mode Releases Releases through the steam generator flash tank vent can only occur through this vent when significant primary to-secondary leakage exists within the steam generators and the blowdown is r.ot going through heat recovery.

Detection of primary-to-secondary leakage is accomplished most effectively by continuously monitoring the condenser vacuum pump vent (R-15). Steam generator blowdown is continuously monitored by R 19A, R-19B, and R-19C as a-liquid pathway. The condenser vacuum pump vent discharges via plant vent which is monitored by R-14 The following method applies to gaseous releases via the plant vent when determining the high alarm setpoint for the plant vent gas monitor (R-14C) and the Fuel Handling Basement Exhaust Monitor (R-20), using the GALE code during the following operational conditions:

• Continuous release via the plant vent (R-14C).

• Continuous release via the Fuel Handling Basement Exhaust (R-20).

3-1 Rev, 7 HBRODC3.R07

Enclosura 2 to Serial: RNPD/92 0409 Pcgs 14 of 40 3,1,1,1 Determine the " mix" (noble gas radionuclides and composition) of the gaseous effluent.

Determine S , the fraction of the total noble gas radioactivity in the i

gaseous effluent comprised by noble gas radionuclide "i," for each individual noble gas radionuclide in the gaseous effluent or use the Si from Table 3.1 1 when using GALE Code.

A-Sj = 3r- - ( 3 .1 -1)

Ag - the radioactivity of noble gas radionuclide "1" in the gaseous effluent from Table 3.1-1.

3.1.1.2 Determine the Q,,, the maximum acceptable total release rate [pci/sec]

of all noble gas radionuclides in the gaseous effluent based upon the whole body exposure limit of 500 mrem / year by:

500 (3.1-2) 0" * (XTC) D g KgSg (X/Q) - The highest calculated annual average relative dispersion factor for any area at or beyond the unrestricted area boundary for all sectors (sec/m 3) .

- 8.1 E 5 sec/m3 (Continuous Ground Release) from Table A-1, Appendix A.

- 9.9 E 7 sec/m 3(Mixed Mode Release) from Table A-10, Appendix A.

Kt - The total whole body dose factor due to gamma emissions from noble gas radionuclide "i" (mrem /yr/ pCi/m3 ) from Table 3.1-2.

HBRODC3.R07 3-2 Rev. 7

Enclocuro 2 to'Soric1; RNPD/92 0409-Pcgo 15 of 48 3.1.1.3 Determine Q,, the maximum acceptable release rate ()Ci/sec} of all gas radionuclides in the gaseous effluent based upon the skin exposure limit of 3000 mrem /yr by:

3000 (3.1-3) 0* - (X7D) E ((L + 1.1 M ) S )

3 3 L + 1.1Mi-3 The total skin dose factor due to emissions from noble gas radionuclide "i" (mrem /yr/ Ci/m3 ) from Table 3.1 2. _

3.1.1.4 Determine C., the maximum acceptable total radioactivity concentration

[pci/ce] of all noble gas radionuclides in the gaseous effluent, c', = 2.12 E-3 , 0' ( T,) (SP) (3.1-4)

NOTE: Use the, lower of the Q, values obtained in Sections 3.1.1.2 and 3.1.1.3. This will protect both the skin and total body from being exposed to the limit.

where:

T- -

Fraction of the radioactivity from the site that may be released via the monitored pathway to ensure that the site ,

boundary limit is not exceeded due to simultaneous releases from several pathways.

- 0.92 for Plant Vent Gas Monitor (R-14C).

- 0.05 for the Fuel Handling Basement Exhaust Monitor (R-20).

HERODC3.R07 3-3 Rev. 7 1

1

_. . _~ ~ . . . . .-- . -. - - . - . . - .

Enclosura 2 to Sarici: RNPD/92 0409 Pegs 16 of 48 F - The maximum acceptable effluent flow rate at the point of release (cfm).

- 60,600 cfm for plant vent.

- 10,200 cfm for the fuel-handling building.

2.12 E 3 - Unit conversion constant to convert pCi/sec/cfm to pCi/cc, 8

g see - ft )

min - cc SF - An engineering factor used to provide a margin of safety for cumulated measurement uncertainties. - 0.5 3.1,1.5 Determine CR, the calculated monitor count rate above background at-tributed to the noble gas radionuclides [ cpm], by:

CR - (C,) (E ) (3.1 5) where: ,

l E, - Obtained from the applicable effluent monitor efficiency curve located in the Plant Operating Manual, Volume 15, Curve Book.

Use the radioactivity concentration "C " to find CR.

3.1.1.6 Determine the HSP,-the monitor high alarm setpoint including back-ground (cpm}, by:

HSP = CR + background + 3.3l I (3.1-6) i-l HBRODC3.R07 3-4 Rev. 7 l

I .:

Enclosurs 2 to Soricl: RNPD/92 - O'.o 9 Pcg2 17 of 48 where:

3.3 Statistical variance on the background (Bkg) counting 3 (E =

rate quoted at the 99.95% confidence level at a RC time constant t (minutes). This term is included to prevent inadvertent high alarm trips due to random fluctuations in the monitor background.

3.1.2 Setooint Based on Samole Analysis Prior to Release The following method applies to gaseous releases when determining the high-alarm setpoint with prior sample analysis and using the maximum acceptable effluent flow rate at the point of release. The method applies to the following conditions.

Batch Releases e Containment purge.

• Containment pressure relief.

e Waste gas decay tanks.

Continuous Releases e Plant vent.

e Fuel handling basement exhaust.

• Environmental and Radiation Control Building Hood Exhaust.

e Containment purge.

• Radwaste Building exhaust vent.

Batch containment purge is considered as 1 volume of containment air removed.

HBRODC3.R07 3-5 Rev. 7

~ - -- .

i Enclosuro 2 to Soriali /iD/92-0409  ;

j Paso 18 of 48 l3.1.2.1 Determine Rg, the noble gas release rate [pci/sec] for radionuclide "i":

R$ -

472 (Cs) (F). (3.1 7) where:

472 - A conversion factor to convert efm to cc/sec.

Ci - The radioactivity concentration of noble gas radionuclide "1" from analysis of gaseous effluent (pci/cc) from the Plant Vent (stack), Fuel Handling Basement Exhaust, Environmental &

Radiation Control (E&RC) Building Hood Exhaust, Radwaste Building Exhaust Vent and the Containment Vessel when R 12 is sampling from the Containment. If there are no isotopes identified in the sample, the LLD's for Xe-133 and Kr 85 may be used as actual values for the purpose of the setpoint calculation.

Containment Purge--

i I

(pCi/cci from analysis of Containment Vent) (0.366) +

(pC1/cc3 from analysis of Plant Vent) (0.634)

Containment Pressure Relief--

(pCi/cci- from analysis of Containment Vent) (0.040)-+

(yci/cci from analysis of Plant Vent) (0.960)

Waste Gas Decay Tanks -

l (pC1/cci from analysis of WGDT) (0.0016) +

(pCi/cci from analysis of Plant Vent) (0.9984)

L l

3-6 Rev. 7 HBRODC3.R07 l

Enclosuro 2 c.- Sorial:D NPD/92 0409 P:go-19 of-48

4. . 4 Waste Gas Decay Tanks during Containment Purge--

(pci/cci from analysis of WGDT) (0.0010) +

(pci/cci from analysis of Plant Vent) (0.633) +

(pCi/cci from analysis of C.V.) (0.366) 3 5 000 C*

0.366 - Dilution correction factor for =

gg g , ', 3 o g)

C.V. Purge 6o,6 00 Cm 0.634 - Dilution correction factor for =

gg g ,,9 Plant Vent during C.V. Purge 2500' Cm 0.040 - Dilution correction factor for =

(60,600 + 2500') m C.V. Pressure Relief 0.960 - Dilution correction factor for =

(60,6 o + 25 ) CFM Plant Vent during C.V. Pressure Relief 0.0016 - Dilution correction factor for =

(60,600 + 1 o) CrM

• Waste Gas Decay Tank 0.9984 - Dilution correction factor for = '

(60,60o 10 CrM Plant Vent during VCDT Release 100 Cm 0.0010 - Dilution correction factor for =

0,600 + 35,000 + 100) Cm Vaste Gas Decay Tank during a Continuous C.V. Purge and Plant Vent Release 0.633 - Dilution correction factor for =

(60,600 + 35,000 100) CrM Plant Vent during a Continuous C.V. Purge and Plant Vent Release Dilution correction factor for

=

0.366 - Mo,600 + 35,000 100) CFM Continuous C.V. Purge during VGDT Release HBRODC3.R07' 37 Rev. 7

- - .- . _-. -. ._-. -_ .. = . -

Enc 15sure 2 to Sorial: RNPD/92 0409 Pogs 20 of 48  :

F - The maximum acceptable effluent flow rate at the point of release (CFM)

- 60,600 CFM for the place vent

- 10,200 CFM for the fuel handling basement exhaust

- 11,500 CFM for the EERC building hood exhaust

- 15,000 C'fM for the Radwaste Building exhaust vent

- 95,600 CFM for the containment vessel purge plus plant vent

- 63,100 CFM for the containment vessel pressure relief

- 60,700 CFM for the vaste gas decay tank

- 95,700 CFM for the vaste gas decay tank during a continuous containment vessel purge

- 35,000 CFM for containment vessel purge or continuous release

- 2500 CFM for containment vessel pressure relief releases .

• 2500 CFM--Refer to Appenoix B.4 for additional information HBRODC3,R07 38 Rev. 7

Enclosure 2 to Serial: RNPD/92 0409 Page 21 of 46 3.1.2.2 Determine the monitor alarm setpoint based on total body and skin dose rate:

a. Determine dose rate for total body (arem/yr).

DRre - (K7Q) Et Kg Rg (3.1 8) where:

K74 - The highest calculated annual average relative dispersion factor for i

any area at or beyond the unrestricted area boundary for all sectors (sec/m3 ) from Appendix A.

- 8.1 E 5 sec/m (continuous ground release) from Table A 1, Appendix 3

A. To be conservative this can be used for all releases.

- 9.9 E 7 sec/m3 (continuous mixed mode re' 84e) from Table A 10 -

Appendix A, only with upper wind sys.os of s 9 mph.

- 5.1 E 5 sec/m3 (batch ground release) from Table A 7, Appendix A.

- 2.9 E 6 sec/m3 (batch mixed mode release) from Table A 16. Appendix A.

Ki - The total whole body dose factor due to gamma emissions from noble _

gas radionuclide "1" (mrem /yr/pC1/m 3

) from Table 3.1 2.

b. Determine dose rate for skin (mrem /yr).

DRsg -

E7Q 2 (La + 1.1 H ) R 3 3 i (3.1 9)

HBRODC3.R07 39 Rev 7

-Enclosure 2 to Serial: RNPD/92 0409 Pegs 22 of 48 l

vhore: ,

SF - An engineering factor ased to provide a margin of safety for cumulative uncertainties of measurements.

t

- .5 i

T. a Traction of tha radioactivity from the site that may be released via the monitored pathway to ensure that the site boundary limit is not exceeded due to simultaneous releases from several pathways.

- .r the Plant Vent Cas Monitor (R 14C).

- 0.05 for the Fuel Handling Basement Exhaust Monitor (R 20).

- 0.01 for other potential retoase points.

- 0.01 for the E&RC Building Hood Lxhaust Monitor (R 22).

- 0.01 for the Radwaste Building exhaust vent Monitor (R 23).

- 0,81 for C.V. releases via R 11 and R 12

[This indicates 0.81 of 10CTR20 limits for Containment releases and is also monitored by R 14C, 0.92 - 0.81 4 0.11 (Normal Plant ,

Releases))

e. Determine the maximum monitor setpoin'. (CPM) for te*.a1 body (Sg) and skin

-(S.).

(Maximum total body setpoint in pCi/ce) (monitor efficiency) +

akg + 3.3 f2hff (3.1-14) 3 11 Rev 7

'H6RODC3. R07 i

l-

_ ._ _ _ _ _ - . . _ _ _ _ _ . _ . - _ _ _ _ _ _ _ _ _ . _ _ . . . __ m _ __.

Enclocuro 2 to Seriel: RNPD/92 0409 Pcgo 23 of 48 1AstE 3.1 1 GA$ Ecus sauku 1ERM5' I

l Cordenser Vecwn Contelrv'ent Purge Plant Vent telease' Pwp vent' or Pressure Relief Cas Detey f orts' Redf oruc Lloe A. (Cl/yr) 8. A. (Ct/yr) 8 A. (Cl/yr) 5. A, (Cl/yr) 5.

$.26E 2 1.0E 0 4.35E 2 0.00 0.00 0.00 0.00 Kr 85m 2.0E0 ,

0.00 0.00 0.00 0.00 0.00 1.6r.1 8.00E 1 tr 85 0.00 2.63E 2 0.00 0.00 0.00 0.00 0.00 0.00 Kr 81 1.0E0 7.89E 2 2.0E0 8.70E 2 1.BE 0 2.90E 3 0.00 0.00 Kr 88 3.0E0 0.00 0.00 0.00 1.0E0 2.90E 3 9.0E0 4.50E 2 xe 151m 0.00 0.00 0.00 0.00 4.0E0 1.16E 2 0.00 0.00 Xe 131s 0.00 7.37E ' 1.8t+1 7.83E 1 3.1E2 4.99E 1 3.1E1 1.35E 1 xe 133 2.8E1 1.0$E 1 2.0E0 8.70E 2 4.0t0 1.16E 2 0.00 0.00 In 135 4.0E0 0.00 0.00 0.00 2.5E1 7.25E 2 0.00 0.00 Ar 41 0.00 2.3E1 3.45E2 2.0E2 107AL 3.BE1

• Source terms are based upon CA1.E Code (not actual releases) from the evaluation of H.B. Robinson Unit 2 to demonstrate conformance to the design objectives of 10CFR50, Appendix I, Table 2 4. These values are only for routine releases and not for a complete inventory of gases in an emergency.

1 These values are used to determine the monitor alarm setpoints for the Plant Vent Cas Monitor (R-14C).

2 These values are used to determine the monitor alarm setpoint for the Condenser Vacuum Pump Vent Monitor (R-15). R 15 is a process monitor and its effluents are monitored by R 14A, R 14B and R 14C. This column is intentiinally left for reference.

3 These values are used to determine the monitor alarm setpoint for the Fuel Handlin6 Basement Exhaust Monitor (R 20).

3 13 Rev. 7 HBRODC3.R07

Enclosure i to Serial: RNPD/92 0409 Page 24 of 48 3.2 COMPLIANCE WITH 10CFR20 (CASEOUS) 3.2.1 Noble Casca The gaseous effluent monitors setpoints are utilized to show compliance with 10CFR20 for noble gases. However, because they are based upon a conservative mix of radionuclides, the possibility exists that the setpoints could be ex-Therefore, the following ceeded and yet 10CFR20 limits may actually be met.

methodology has been provided in the event that if the alarm trip setpoints are exceeded, a determination may be made as to whether the actual releases have exceeded 100FR20.

The dose rate in unrestricted areas resulting from nobia gas effluents is limited to 500 mrem / year to the total body and 3000 mrem / year to the skin.

Based upon NUREG 0133, the following are used to show compliance with 10CFR20.

Ej Kj l (TTD), Dj,, + (77D), dj,1 s 500 miem/yr (3.2-1)

Ej (Lj + 1.1 M,) ( (77D) vdj, + (TTD) ,6 f,] s 3 000 mtem/yr (3.2-2) where:

(%7Q), - Annual average relative dilution for plant vent releases at the site boundary, sec/m .8

- From Table A+1 for ground level releases used for additional conservatism.

- From Table A 10 for mixed mode releases.

(R76), - Annual average relative dilution for the Fuel -

Handling Basement Exhaust, the Environmental and Radiation Control Building Exhaust, and Radwaste Building Exhaust releases at the site boundary, sec/m*.

• • From Table A 1 for ground level releases.

3 15 Rev. 7 HBRODC3.R07

_. .. . _.2.__.._-.-.._._.. , _ . . _ _ . _ . _ _ _ _ . _ u -- _ _ . _ _ . . . _ , _ _ _ . _ . -

.. .~ .. - ..- ~. -_ . - . _ - - __ _ . - _ _ _ - . _ - _ . . - - -.

Enclecuro 2 to Sorial: RNPD/92 0409 F:so 25 of 48

.. . Kg - The total body dose factor due to gemma emissions for noble gas radionuclide "i," mres/ year per pC1/m8 . ,

L3 - The skin dose factor due to beta emissions for noble gas radionuclide "1," arem/ year per pC1/m 8 Mg - The air dose factor due to gamma emissions for noble gas radionuclide "i," mrad / year per pCi/m 8.

1.1 - The ratio of the tissue to air absorption coeffi-cients over the energy range of the photon of in-terest, arem/arad (reference NUREC 0133, October 1978).

Di. - The release rate of noble gas radionuclide "i" in gaseous effluents from the radvaste building exhaust vent, fuel handling basement exhaust, and the environmental and radiation control building hood exhaust, yCi/sec.

kg, - The release rate of noble gas radionuclide "i" in gaseous effluents from the plant vent Ci/sec.

The determination of limiting location for -implementation of 10CFR20 for noble gases is a function of the radionuclide mix, release rate, and the meteoro-logy. For the mont limiting location, the radionuclide mix vill be based on sample analysis of the effluent gases.

The X/Q value utilized in the equations for implementation of 10CFR20 is based upon the maximum long term annual average (X7Q) in_the unrestricted area.

Table 3.2 2 presents the distances from HBR to'the nearest area for each of the 16 sectors as well as to the nearest residence, vegetable Sarden, cow, goat, and beef anical. Long term annual average (X/Q) values for the HBR release points to the special locations in Table 3.2 2 are presented in Appen-dix-A. A description of their derivation is also provided in this appendix.

HBRODC3.R07 3 16 Rev. 7

Enclosuro 2 to Seriel: RNPD/92 04t Pego 26 of 48 kg, = Release rate of radionuclide "i" from the plent vent, pCi/sec.

64, = Release rate of radionuclide "i" from the radwaste building exhaust vent, fuel handling building basement exhaust, and environmental and radiation control building exhaust pC1/sec.

(%7Q),- Annual average relative dilution for plant vent releases at the site boundary, sec/m 8.

(R7Q) - Annual average relative dilution for fuel handling building basement exhaust, environmental and radiation control building exhaust, and radwaste building exhaust vent releases at the site boundary, sec/m . 8 Pil- The dose parameter for Iodine 131. Iodine 133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days for the inhalation pathway only in the most restrictive sector in mrem /yr per pCi/m 3 The dose factor is based on the most restric-tive group (child) and most restrictive organ at the SITE BOUNDARY (see Table 3.2 4).

where:

In the calculation to show compliance with 10CFR20, only the inhalation is considered. A description of the methodology used in calculating the P 3 values is presented in Appendix B. Compliance with 10CFR20 is achieved if the dose rate via inhalation pathway to a child is 5 1500 mrem / year.

3 18 Rev. 7 HBRODC3.R07

Enclosare 2 to Sorial: RNPD/92 0409 Page 27 of 48 TABLE 3.2 1 RELEASES TROM H.B. ROBINSON UNIT NO. 2*

(C1/yr)

Condenser Vacuum Plant Vent Pump Vent Isotope (Q,) (Q,) Total Kr 85m 2.0E0 1.0E0 3.0E0 Kr 85 1.6E2 0.00 1.6E2 Kr 87 1.0E0 0.00 1.0E0 Kr 88 4.0E0 2.0E0 6.0E0 Xe 131m 1. vel 0.00 1.0E1 Xe 133m 4.0E0 0.00 4.0E0 Xe 133 3.7E2 1.8E1 3.9E2 Xe-135 8.0E0 2.0E0 1.0E1 1-131 3.6E 2 2.3E 2 5.9E 2 1 133 ,

5.4E 2 3.4E 2 9.8E 2 Mn 54 4.7E 3 0.00 4.7E 3 Fe 59 1.6E 3 0.00 1.6E 3 Co 58 1.6E 2 0.00 1.6E 2 Co 60 7.3E 3 0.00 7.3E 3 Sr 89- 3.4E 4 0.00 3.4E 4 Sr 90 6.3E 5 0.00 6.3E 5 Cs 134 4.7E 3 0.00 4.7E 3 Cs 137 7.8E 3 0.00 7.8E 3 .

i

• Calculations based upon GALE Code and do not reflect actual release data from the Evaluation Conformance to the Design Objectives of 10CFR50, Appen-dix I. These values are only for routine releases and not for a complete in.

ventory of games-in an emergency. Condenser vacuum pump vent is intentionally left in for reference.

l I

HBRODC3.R07 3 19 Rev. 7

Lu:lo.ure 2 $o Serial: RNPD/92 0409 Page 28 of 48 3.3 COMPLIANCE WITH 10CTR50 (CASEOUS) 3.3.1 Noble Cases 3.3.1.1 Cumulation of Dases Based upon NUREC 0133, the air dose in the unrestricted area due to noble gases released in gaseous efiluents can be determined by the following equations:

D, = 3.17 x 10 E, N, ( (77D) , D,, + (77q) , 54, + (77D), D,,) (3.3-1)

D, = 3.1*1 x 10 E j Nj l (X7D) , D , + (XFq) , Q,, + (YTD), D,,)

3 (3.3-2) i v5ere:

D, - The air dose from gamma radiation, mrad.

Do

- The air dose from beta radiation, mrad, Mi - The air dose factor due to gamma emissions for each identified noble gas radionuclide "i,," mrad / year per pC1/n.3 Ng - The air dose factor due to beta emissions for each identified noble gas radionuclide "t," mrad / year per 9C 1/m8 .

(RT), - The annual average dilution for areas at or beyond the unrestricted arraa boundary for long term plant vent releases

• (> 500 hrs / year), sec/m).

- From Table A 1 for ground level releases ased for conservatism.

HBRODC3.R07 3-23 Rev. 7

Enclosuro 2 to Serial: RNPD/92 0409 Page 29 of 48

- From Table A 10 for mixed mode releases.

(X/q), - The dilution for areas at or beyond the unrestricted area boundary for short tern plant vent releases (s 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> / year), sec/m3 .

- From Table A 1 for ground level continuous release for conse rva tism.

- From Table A 7 for ground level releases. ,

- F1>m Table A 16 for mixed mode releases.

(R7Q),- Annus1 average relative dilution for fuel handling basement exhaust, the environmental and radiation control building exhaust, and radwaste building exhaust vent releases at the site boundary,

(> 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> / yea.1, sec/m8.

- From Table A 1 for ground level releases; ,

qi, - The average release of noble gas radionuclide "i" in gaseous releases.for short term plant releases (s 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> / year), pCi; Qi, - The average release of noble gas radionuclide "i" in gaseous releases foc long term fuel handling basement e,xhaust, the environmental and radiation control building exhaust, and radwaste

• l building extaust (> 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> / year), 9C1:

Div - The average release of noble gas radionuclide "i" in gaseous effluents for long term vent releases (> 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> / year), pCi; 3.17 x 10 s - The inverse of the number of seconds in a year (sec/ year)" .

At HBR the limiting location is 0.26 miles SSE. Based upon the tables presented in Appendix A, substitution of the short term X/Q value into Equation 3.3 1 yields lower dose value than the long term X/Q values been used. In order to be.

conservative,- for purposes of this document only, long term annual HBRODC3.R07 3 24 Rev. 7

Enclosuro 2 to Social: RNPD/92 0409 Pac,o 30 of 48 If the projected doses exceed 0.6 mrad for gaan,a radiation or 1.1 mrad for beta radiation when averaged over a calendar quarter, the ventilation exhaust treatment system will be operated to reduce releases of radioactive materials.

3.3.2 Radioiodine. Particulates and Tritium 3.3.2.1 cumulation of DosesSection II.C of Appendix I of 10CFR50 limits the release of radioiodines and radioactive tasterial in particulate form from each reactor such that estimated annual dose or dose commitment to an individual in an unrestricted area from all pathways of exposure is not in excess of 15 arem to any organ. Based upon NUREG 0133, the dose to an organ of an individual from radiciodines, tritium, and particulates with half lives a 8 days in gaseous effluents released to unrestricted areas can be determined by the following equation:

D, a 3.17 x 10 E , R,, [ (Y7D) , 0,, + (X7D) , 0,, + (7q) , q,,) +

e 2, + Re, + R4 , + Rs,) 1 (D7D) , 0 4

, + (D7q-) , q,, + (D7D) , 0,,) +

( Rr , + R r, + Rr , Rr,) IIIID) v On'

• IEG) y Gn'

• IIID). Orrl (3.3-8) where: .

l D, - Dose to any organ r from I 131, I 133, particulates with a 8 day half lives, and Tritiura in arem.

L l

l l

liBRODC3.R07 3 27 Rev. 7

- - . . - . . = - --

Enclosuro 2 to Serial: -RNPD/92 0409 Pogs 31 of 48 3.17 x 10'3 *I

- The inverse of the number of seconds in a year, (sec/ year) .

(RTd), - Annual average relative concentration for plant vent releases

(> $00 hrs /yr) sec/m 3.

. From Table A 1 for ground level releases for conservatism.

- From Table A 10 for mixed mode releases.

(R~/Q), - Annual average dilution for radwaste building vont, fuel handling basement exhaust, and the environmental and radiation control building hood exhaust releases (> $00 hours /yr) sec/m3 .

- From Table A 1 for ground level relesses.

(R7q), - Annual average relative concentration for plant vent releases (s 500 hrs /yr) sec/m .3

- From Table A 7 for ground release.

- From Table A 16 for mixed mode releases.

(57d), -

Annual average dposition factor for plant vent releases

(>500 hrs /yr) m

- From Table A 3 for ground level releases for conservatism.

- From Table A 12 for mixed mode releases.

($), - Relative deposition factor for short-term plant vent releases

($ 500 hrs /yr), m-2,

- From Table A 3 for ground level continuous releases for conservatism.

- From Table A 9 for ground level releases.

- From Table A 18 for mixed mode releases (D/Q). - Annual average 1 elative deposition factor for radwaste building vent, fuel handling basement exhaust, and tha environmental and radiation control building hood exhaust releases (> 500 hrs / yr), m 2,

- From Table A 3 for ground level releases.

HBRODC3 R07 3-28 Rev, 7

_ _ _ . _ _ . _ _ _ _ _ . _ _ . . _ _.__ _ _ -- - _- _ . _ _ _ - _ . - _ . ___m_ - _ _ _ _ _ . _ . _ _ _

I Enclosura 2 to Serial: RNPD/92 0409 i Page 32 of 48 l Q3.

- Release of radionuclide "i' in gaseous effluents for long term I radwaste building vent, fuel handling basement exhaust, and j the environmental and radation control building hood exhaust releases (> 500 hrs /yr), 901.

Q3, - Release of radionuclide "i" in gaseous effluents for long term plant vent releases (> 500 hrs /yr), 901.

q, - Release of radionuclide *t" in gaseous effluents for short.

term plant vent releases (s 500 hrs /yr), pC1, R$g

- Dose factor for an organ for radio mc W e T for the ground plane exposure pathway, mrem /yr per pCi/sec per m 2, .

R ig - Dose factor for an otgan for radio wc W e " P for the inhalation pathway, mrem /yr per pCi/m3.

Riy - Dose factor for an organ for radionuclide "1" for the ogetshle pathway, mrem /yr per pCi/m*8 R Ty - Dose factor for an organ for tritium for the vegetable pathway, mrem /yr per pCi/m3 ,

- Dose factor for an organ for tritium for the inhalation RTI pat bvay, mrem /yr per pC1/m8 .

Qrv - Release of tritium in gaseous effluents for long term plant vent releases (> 500 hrs /yr), 9C1.

R ig - Dose factor for an organ for radionuclide "i" for the milk exposure pathway, mrem /yr per Ci/see per m2 .

RTg

- Dose factor for an organ for tritium for the milk pathway, mrem /yr per sci /m3 .

l l

HBRODC3.R07 3 29 Rev. 7

_ _ _ ~ . . _ _ . _ _ _ _ _ _ _ . _ _ . . ~ . . _ _ _ _ _ _ . - - . _ _ _ . _ _ _ _ - _ - _ . - . . .

Enclosure 2 to Serial: kNP's /92 0409 Page 33 of 48

- Dose factor for an or6an for tritium for the meat pathway, RTB mrem /yr per pCi/m 3 .

~

1. "" #E*" # ## ""# # * "'**

rib

~ ## #

exposure pathway, arem/yr per pCi/sec/m fl .

Qg, - Release of tritium in gaseous effluents for long term radwaste building vent, fuel handling basement exhaust, and the environmental and radiation control building hood exhaust

(>500 hrs / yr), pCL.

grv - Release of tritium in gaseous effluents for short term plant vent releases (s 500 hrs /yr), pCi.

To show compliance _with 10CFR50, Equation 3.3-8 is evaluated at the limiting pathway location. At HBR this location is the vegetable garden 0.3 miles in the SSE sector.

The critical receptor is a child. Substitution of the appropriate X/Q and D/Q values from tables in Appendix A into Equation 3.3-8 would yield an equation with the short term X/Q and D/Q value= being less than the long term values. Therefore, for this document, only long tert iual X/Q and D/Q values (i.e. , more conservative values) are used.

The determination of a limiting location for implementation of 10CTR50 for radioiodines a'n2 particulates is a function of:

1. Radionuclide mix and isotopic release

2. Meteorology

3. Exposure pathway

4. Receptor's age In the' determination of the limiting location, the radionuclide mix of radioiodines and particulates was based upon the source terms calculated using the CALE Code.

This mix is presented in Table 3.2 1 as a function of release point. The only "

• source of short term releases from the plant vent is containment purges.

determination of the limiting location, all of the exposure pathways, as presented in Table 3.2-2, were evaluated. These include cow milk, goat i

l HBRODC3,R07 3 30 Rev. 7 l

Enclosure 2 to Serial: RNPD/92 0409 Page 34 of 48 4

3.4 KETHODOLOGY FOR R 11 SETFOINT (Air Particulate)

Determine the Monitor Alarm Setpoint based on the inhalation pathway to the child.

The most restrictive organ "j" vill be determined from the following methodology.

R 3.4,1 Determine dose rate for organ "j" (arem/yr).

DRj = T/D Ej Rg, 0 4 (3.4-1) where:

R/Q - the highest calculated annual average relative dispersion factor for any area at or beyond the unrestricted area boundary for all sectors (sec/m ) 3from Appendix A.

- 8.1E 5 sec/m3 (continuous ground release) from Table A 1, Appendix A.

- the organ "j " dose f actor due to gamma einissions from Ri3 particulates greater than or equal to 8 day half life, I 133, 1 131. and H 3.

Qi

- the particulate release rate (uCi/sec) for radionuclide "i".

- 472 (C )(T) where; 472 - conversion factor to convert CTM to ec/sec.

C3 - (pC1/cc from analysis of containment vessel) (0.366) i

+ (DF) + uCi/ce, from anal'ysis of Plant Vent) (0.634) when R 11 is sampling the Plant Vent for CV purges.

3 63 Rev. 7 HBRODC3.R07

Enclosure 2 to Serial: RNPD/92 0409 Pego 35 of 48

= (pC1/cca from analysis of CV) (0.04) + (DF) + (pCi/ce; from analysis of Plant Vent) (0.960) when RMS 11 sampling from Plant Vent for CV pressure relief.

- (pCi/cci from analysis of CV) + (DF) when RMS 11 is sampling CV.

F - 95,600 cfm for CV purge when R 11 is sampling from Plant Vent. >

- 35,000 cfm for CV purge when R 11 is sampling from CV.

- 2,500 cfm for CV pressure relief when R 11 is sampling from CV. l

- _63,100 cfm for CV pressure relief when R 11 is sampling Plant Vent.

-DF - 1.0 for Tritium

- 10 for lodines when using characoal filters

- 100 for Particulates a 8 day half lives when using HEPA Filters.

3.4.2 Determine the particulate emission Projected Dose Rate Ratio (PDRR) for the most critical organ "j".

PDRR3 - DR3 /1500 (3.4 2) 1500 - the allowable organ dose rate due to particulates with > 8 day half-life, 1 131, 1 133, H 3 (mrem / year).

HBRODC3.R07 3 64 Rev. 7 l

Enclosuro 2 to Scrial: Raku/92 0409 Pogs 35 of 48 I

3.4.3 Determine the maximum monitor setpoint concentration (pci/ce) for most critical organ "j".

i Maximum Monitor Setpoint for organ "j" -  :

[(ri Cg) / (PDRRj)) (SF) (T.) (TL) where:

SF - an engineering factor used to provide a margin of safety for cumulative measurement uncertainties - 0.50.

T. - fraction of the radioactivity from the site that may be released via the monitored pathway to ensure that the site boundary limit is not exceeded due to simultaneous releases fton, several pathways.

- 0.81 for R 11 particulate monitor.

TL = total activity / Eg C where the total activity is the sum of all i

detectable particulates from analysis of particulate filter divided by the detectable particulates of a 8 day half lives. If thit .

ratio is not knowr, use 1.0.

- 1.0 when R.11 sampling from Plant Vent, f

t 1

3 65 Rev. 7 HBRODC3.R07

- . - , ..-.- . ,. - ~ - . . _ . . . - - - . . ,, - . . - . . - . . - - . . - . , - . , - , . - . .- .

Enclosure 2 to Serial: RNPD/92 0409 Page 37 of 48 3.5 dethqdnisev for n 14A Setooint (Particulate Monitor 1 This section describes the methodology in determining high alarm setpoint for the plant vent monitor (R 14A) based on the inhalation athway to the child.

The most restrictive organ "j" will be determined from a conservative six (CALE Code).

3.5.1 Determine si, the fraction of the total radioactivity in particulate form in l the gaseous effluents comprised by radionuclide "i" for each radionuclide in the gaseous effluent from Table 3.2 1.

Si - Al (3,5 1) <

Zi Al where: '

Al - The radioactivity of radioparticulate radionuclide "i" in the gaseous effluent from Table 3.2 1.

3.5.2 Determine Qm, the maximum acceptable total release rate (uct/see) of all the radioparticulate radionuclides in the gaseous effluent based upon the most restrictive organ "j" exposure limit of 1500 mrem / year by: ,

Qat - 1500 (3.5 2)

(R/Q) El Si Pir ,

where:

1500 - the maximum allowable dose rate in an unrestricted area in gaseous effluents due to radioparticulates with half lives greater than 8 days, redioiodines and tritium via the inhalation pathway to the child.

(X/Q) - The highest calculated annual average relative dispersion factor for any area at or beyond the unrestricted area boundary for all sectors (sec/m ). 3

- 8,1E 05 Sec/m3 (continuous ground release) from Table A 1.

Appendix A.

HBRODC3.R07 3-67 _Rev.-7

_ _ _ . _ _ _ _ _ _ _ . _ . _ . ~ . . _ _ - _ _ _ _ . _ _ _ . _ . _ . . _ _ . _ . _ . _ .

Enclosure 2 to serial: RNPD/92 0409 Page 38 of 48 Pig - 1he dose parameter for 1 131, 1 133, H.3, and all particulates in particulate form with half lives greater than 8 days for the inhalation pathway only in the most restrictive sector in ares / year per uCi/m8 . The dose factor is based on the most restrictive group (child) and most restrictive organ at the '

S'~r BOUNDARY (see Table 3.2 4).

3.5.3 Determine Qivg. fraction of plant stack release rate acquired on filter, by:

Qiv: - Qas (3.33E 05) (3.5 3, where:

3.33E 05 - fraction of monitor sample rate to plant vent flow rate (2.02 CFH/60,600 CFM) 3.5.4 Determine HCI, maximum acceptable concentration [uci) accumulated on the filter due to s11 radioparticulate radionuclides in the gaseous effluents based on the most restrictive organ "j", by:

HC1=- Qiv (T) (3.5 4) where:

• T - time in seconds

- 8.64E04 for one day

- 6.05E05 for one week 3.5.5 Determine HAC, high alarm' concentration [uci) from radioparticulate radionuclides in gaseous effluents, by:

HAC - (HC1) (SF) (Tm) (3.5 5) where:

SF = An engineering factor used to provide a margin of safety for cumulative uncertainties of measurements

- 0.5 i

L HBRODC3.R07 3 68 Rev. 7 l-. . - - - . . ~ , - _ _ _ , _ _ _ . _ _ , , _ _ , _ _ _ _ _ _ , _ _ _ _ _ _ _ _ _ , _

Enclosure 2 to Seria): RNPD/92 0409 Pegs 39 of 48 Tm - Fraction of the radioactivity from the site that may be eased to ensure the site boundary limit is not exceeded due to simultaneous releases from pathways

- .92 for the Plant Vent Monitor (R 14A).

3.5.6 Determine the HSP, liigh Alarm Setpoint including background (cpm], by:

RSP = (RAC/Dn) + BKG + 3. 3 (3.5-6) where:

Em - from monitor efficiency curve located in the Plant Operating Manual Curve Book.

3.6 Methodolorv for R 14B Setooint (todine Monitor)

This section describes the methodology in determining high alarm setpoint for the plant vent monitor (R 14B) based on the inhalation pathway to the child.

The most restrictive orSan "j" will be determined from a conservative six (GALE Code).

3.6.1 Determine Qmt, the maximum acceptable release rate [uci/sec) of I.131 in gaseous effluents based upon'the most restrictive organ "j" exposure limit of 1500 mrem / year, by:

Qm - 1500 (3.6 1)

(X/Q) Pig  ;

where:

Pig - The dose parameter for I-131 for the inhalation pathway only in the most restrictive sector in mrem / year per uCi/m3 . The dose factor is based on the most restrictive group (child) and most restrictive organ at the Site Boundary (see Table 3.2 4).

3.6.2 Determine QLv r . fraction of plant stack release rate acquired on the cartridge, by:

Qivg - Qmj(3,33E 05) (3.6 2)

HBRODC3.R07 3 69 Rev. 7

Enclosuro 2 to Serial: RNPD/92 0409 Pego 40 of 48 3.6.3 Determine HCI, maximum acceptable concentration [ucil accumulated on the .

cartridge due to 1 131 in gaseous effluents based on the most restrictive organ "j".

HCI - (Qiv ) (T) (3.6+3) whera:

T - time is seconds

- 8.64E04 for one day

- 6,0$E05 for one week 3.6.4 Determine HAC, hi 6 h alarm concentration [uct) from I 131 in gaseous ,f effluents, by:

HAC - (HCI) (ST) (Tm) (3.6 4) 3.6.5 Determine HSP, High Alarm Setpoint including background [ cpm), by:

1. SP = (HAC/Dn) + BKG + 3 . 3 (3.6-5) 3.7 Methodglory for R 22 and R 23 Setpoint Determination for the Iodine and Particulate Monitors This section describes the methodology in determining high alarm setpoint for the particulate and iodine channels for the Environmental and Radiation Control Building and Radwaste* Building exhaust vent (R 22 and R 23, respectively) based on the inhalation pathway to the most restrictive organ J and age group (child).

3.7.1 The dose rate in an unrestricted area resulting from the release'of radiciodines, tritium, and particulates with half lives a 8 days is limited to 1500 mrem /yr to any organ via inhalation (10CFR20). The iodine and particulate monitor setpoints for R 22 and R 23 are limited to 1.04- of 10CFR20 crer one hour period. Therefore. the iodine and particulats channels high alarm shall be set to 1.0% of 10CFR20 for any given hour.

HBRODC3.R07 3 70 Rev. 7 l

l i-

Enclocuro 2 to Ssrici: RNPD/92 0409 Pcgs 41 of 48 3.7.2 Determine Qg, the maxiaw.a release rate (uci/sec) for Iodine 131 and Cobalt 60 '

(the most restrictive particulate a 8 day half life) base on the most restrictive organ "j" via inhalation to a child.

IS (3. 7 -1)

Og =

(%) (X7D) i i

i where:

15 - 1.0% of the maximum allowable dose rate in an unrestricted area in gaseous effluents due to radioparticulates with half lives greater than or equal to 8 days, radiciodine, and tritium via the inhalation pathway to the child.

R$- The dose factor based on the most restrictive age group (child) and the most restrictive organ (thyroid) for lodine 131 (1.62E7 3

mrem /yr/pC1/m 3

) and lung for Co 60 (7.06E6 mrem /yr/pC1/m ) at the most rostrictive location (SITE BOUNDARY).

X/Q - Annual average relative dilution for continuous ground level releases for the most restrictive section at the SITE BOUNDARY 8

(8.08E 5 sec/m for the SSE sector from Table A 1).

Therefore:

Q'ts.ain. 23t - 1,15E.2 pC1/sec Qic.6.tg.en - 2.63E 2 pCi/sec i

HBRODC3.R07 3 71 Rev. 7

_ _ . _ _ _ _ . _ . _ _ _ . . . _ .. _ _ .._ _ __- - _________..~.-.m._____________.

Enclosure 2.to Serial: RNPD/92 0409 a Page 42 of 48 3.7.3 Determine Se,, the air particulate filter and charcoal cartridge sample collection rate (uci/sec) by:

Se, - Qi -f- (3.7 2) l vhere:

f - sampler flow rate (typically 2.$ CFM for R 22 and 2 CFM for R 23)

F - Radwaste Building exhaust vent flow rate (15,000 typically)

- Environmental and Radiation Control Building exhaust vent flow rate (11,500 typically)

Therefore:

The typical Co 60 sample collection rate is 5.72E 6 yC1/sec and 4.39E 6 pCi/sec, for R 22 and R 23, respectively.

The typical I 131 sample collection rate-is 2.5E 6 pCi/see and 1.91E 6 pCi/sec for R 22 and R 23, respectively.

3.7.4 Determine Qm,, the setpoint activity (pC1) accumulated on the air particulate filter and charcoal filter for any given hour by:

Qmi - (Sci) (T)

(3'7'3) where:

T - 3600 see in an hour.

Therefore:

The typical setpoint activity for the air particulate filter and the charcoal cartridge is:

Monitor Particulate Iodine.

R 22 2.06E 02 9.00E 03 R-23 1.58E 02 64 88E 03 i

3-72 Rev. 7 HBRODC3.R07

Enclosuco 2 to Serialt RNPD/92 0409 Pago 43 6' 48 3.7.5 Determine the HSP, High Alarm Setpoint including background (cpm) by:

HSP - (Qas ) (Em) 4 BKG (3.7 4) ,

where: i Em - efficiency of the detector BKG - the background of the detector 4

The above methodology shall be used for the iodine cartridge and air particulate filter setpoint determinations for the Environmental and ,

Radiation Control Building and Radwaste Building exhaust vent. The sampling and building vant flow rates-used in the above equations are subject to change and shall be controlled by plant procedures. If or when this occurrs, the recalculations of setpoints shall be pettormed by approved procedures ,

using the-above methodology.

l f

3 73 Rev. 7.

HBRODC3.R07 l

I l _ ~. -- ~ ~ . _ _ _ _ . . . - , , _ _ . . _ , . . , . _, . ,, ,, ,

.- . . - . - -__ ._.- =...-_ ..- . - -..-.-. - - - - - _ .

.Enclosuro 2 to Sorial: .NPD/92 0409 Pcgs 44 of 48 f

TABLE D 1 Liquid Process Monitors Hamt fL.*_ IIL* Dravine

• Containment Vessel 16 R 16 C997261 Fan Cooling Water Component Cooling 17 R 17 C997246 Vater Liquid Vaste Disposal 18 PI 871109 NRC Industries 4PI Liquid Sample Manual Condensate Polisher 37 R 37 Plant Mod. 723 Liquid Vaste H.B.R. 2-9065 Steam Cenerator 19A R 19A Mod 898 Blowdown 19B R 19B 19C R 19C Liquid Radwaste Flow Measurement Devices Liquid Radwaste Flow N/A FT 1064 (ITT Barton Flow Integrator) i HBRODC3.R07- D1 Rev. 7

[

iI

( .. _ _ , _ __ __ ,

. .. .- - - - - - - . . - - = _ - . _ _ - . . . - _. = - -_. . ._-

Enclosuro 2 to Sorial: RNPD/92 0409 Pego 45 of 48 TABLE D 2 Caseous Process Monitors Sample Flow System Flow Rate Measurement Rate Egg ]L,n 1D._,e Drawint

• Device Measurement Device 11 11 D997556 F6P Co. Flow Tube UCC Microflow 3000 Centainment Vessel (if sampling stack)

Perticulate FP 3/4 27 C 10/80 12 17 D997556 F6P Co. Flow Tube UGC Microflow 3000 Containment Vessel (if sampling stack) ccseous FP 3/4 27 C 10/80 Plcnt Vent Low Range 14C R 14 Mod 1005 Kurz 4200 Isokinetic F 14 Plant Vent Sample System Stsek Flow Monitor (Kurz)

Fusi Handling 20 R 20 C998233 Fisher Porter None (Use fan Building Basement Flowmeter ratings)

Exhaust Mod. 10A35755Z Serial 6908A0837Al Fuel Handling 21 R 21 C99E8233 Fisher Porter None (Use fan Building Upper Flowmeter ratings)

Level Exhaust Mod. 1043565 Mod. 6908A0837Al l

D2 Rev. 7 l HBRODC3.R07

Enclosure 2 to Serial: RNPD/92 0409 Pags 46 of 48 N.B. ROBINSON LIQUID RADWASTE PROCESS / EFFLUENT SYSTEM *

• m' GENE *B' GENEk 'O' RHR P!T SUMP -- [= k h (m BLORDCIN SL0fDCIN DENESLCthN I I 1 R.199 4 190 .g.

a.194 (DFF-LINE1 Sump W *A' -. - $v., m (OFF-i,lPfl (DFF.LINE) okkNkANg Oy $ UMP -. -

BL r N M ANK LAUNDAY AC $ PENT AES:N

$MCSER T4d -* - TAN (

RC$ ORRjN SA$T wDLDUP ANK TANC 1 1

.......... .............. spg' 1

ORUMMjNG 40CM OyC$

N'QyDRAltAjf[M LA MENI STaIL E'vAPORA CA$

t AA $

.sE MON! TOR TANK $

CON {EN$ AIE

'AN(5 l

Fs

stE;;arCa i

• 5:"P.!F:E? BLO;( FL 8 O!a5E'"

F13JE 0-1 a.:g .......,

4 I

,* l a;, .;;g

.E ........

s:-asE p.3 ggy, - 7 HBRODC3.R07

Enclosure 2 to Sorial: RNPD/92 0409 I Pcgs 47 of 48 H.B. ROBINSON GASEOUS RA0 WASTE EFFLUENT SYSTEM

• ANTvgNT costa wMENT 81)/a*12 Pj&l 5 i" QM ~

• Es c' l

I k! - $!O A* -

I#Mk!' CD SOURCE

[ ,

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1. 0" $OkB* -

I85DEhAf Arg * * - #85OEbAf YANK - -

(Elbgm*R*{*B* ,

1 i

HN3 GRAB $RMPLE MONffCA51 r:La( 0 2 e $1 A IFIED BLO ( (L:s O!A3aAm ,

l tHEGAS[SAAjems'ESvy{E""AY M hSSC Nb: EshkE3CE af l

l l

REV. 7 D-4 HBRODC3.R07

_m_ _ _ _ _ _ . . . _ . _ _ _ _ _ _ _ _ _ _ - - _ . _ _ _ .

Enclosure 2 to Serial: RNPD/92 0409 Page 48 of 48 II. CHANCES TO THE RADIDACTIVE WASTE SYSTEMS There were no changes to the Radioactive Waste System during this reporting period.

i 111. CHANCES TO THE PROCESS CONTROL PE9 GRAM There were no changes to the Process Control Program (PCP) during this repor : " ng period.

, IV. CHANCES TO Tile 1AND USE CENSUS

- There were no changes to the envirotusental sampling program as a restGt of the Land Use Census performed in the first six months of 1991.

V INSTRUMENT INOPERABILITY FI-1064, which is the liquid effluent flowrate measuring device, was declared inoperable in July of 1990 due to erratic readings. It was discovered that this monitor _is obsolete and repair parts are not available. Therefore, an engineering '

evaluation has been initiated to determine and procure a suitable replacement for this  ;

monitor.

i For the equipment inoperability shown, supplemental surveillances were initlated as required by Technical Specification Table 3.5 6.

VI. L10UID 110LDUP TANK CURIE LIMIT i

There were no outside liquid holdup tanks that exceeded the ten curie limit during this reporting period.

VII. WASTE CAS DECAY TANK CURIE L1 HIT There were no waste gas decay tanks with a curie content that exceeded the 1.90E404 curie limit during this reporting period.

VIII. INDEPENDENT SPENT FUEL STORAGE INSTALIATION The onsite independent spent fuel storage installation, license #SNM 2502/ docket #"/2 3.- became_ operational- during the first six months of 1989. See Addendum I for reporting requirements concerning this facility.

IX. DISPOSAL OF BOILER CHEMICAL CLEANING WASTE Pursuant to 30CFR20.302(a) and USNRC ' IE Information Notice No. ' 86 90, slightly contaminated waste from the acid cleaning of the Unit al boiler was released to the onsite Ash Ponds.under the approval of'the South Carolina Department of llealth and Envirotunental- Control . The approval was requested in al letter .of August -20. 1991-(Se rial: - RNPD/91 12 81)_. and received in a SCDilEC letter of September 16, 1991. The transfer consisted of approximately 30,200 gallons of waste containing a total of 63 pCi.

The above Curies released to the Ash Ponds onsite are not included in Section IV, -

Liquid Effluents, of Enclosure 1 of this report.

. -. a. ~ . . . ._ _ ___- - ,_.._-._. . _ - - _ . . . _ _ _ . . . . . _ _ . . _ . _ - . _ . -

" loru 3 to Set-lal: RNPD/92 0409 SUPPLEMENTS TO PREVIOUS SEMIANNUAL REPOR'iS

• 1 - TAB E OF CONTENTS

%9 Enclosure 3 Description

. l'qr,q I. P JION . . , . . . . 2

(. . . . . . . . , . . 2 R

=

. . _ . ~ . _ _ . _ . _ _ . . _ - . - _ - - - _ . _ _ _ _ . _ _ _ .___ __._ _ __._ _._._ _ _..- _ _._ .

Enclosure-3 to Serial: RNPD/92-0409 4

Page 2.of 4 e

I. DISCUSSION There were two changes to a previous report during this reporting period. The volume of-solid waste shipped as Waste Class "A", Type " b" in the first half of 1991 was ,

reported as 3.59E401 cubic meters. The actual volume shipped was 3.62E401 cubic meters. This was an addition error made while tabulating data for the first semiannual period of 1991. The table on page 3 of Enclosure 3 reflects this correction.

Also, 6.35E-06 curies of F-18 wa, reported in liquid ef fluents for the second quarter J of 1991. Upon further investigation, it was determined that the raported F-18 was

, actually caused by co-58 interference on the gamma spectroscopic analysis of an effluent sample. The table on page 4 of Enclosure-3 reflects this correction.  !

II. DATA TABLES the following tables provide correction to data reported in the first semiannual period of 1991. ,

SOLID WASTE AND IRRADIATED FUEL SilIPMENTS LIQUID EFFLUENTS a CONTINUOUS MODE AND BATCll MODE RELEASES l

l

, - , - g

~

Enclosure 3 to' Serial: .RNPD/92-0409 Page 3 of 4 ,

i V. SOLID WASTE AND IRRADIATED FUEL SHIPMENTS -['

REPORT TIME PERIOD JANUARY:1 THROUGH JUNE 30, 1991 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (not irradiated fuel) j WASTE CLASS A Type of Werte . Unit 6-Month Est. Total Solid. Cont. Form No.

Period Error (%) Agent Type Ship.

a. SpentLresins, filter sludges, m3 4.94E+00 2.00E+01 NA STP Dewatered 17 evaporator bottoms, etc uCi 6.23E-02 2.00E+01 Resin j

b. Dry compressible waste, m3 3.62E+01 2.00E+01 NA STP Compacted / 53 contaminated equip, etc Ci 4.32E+00 2.00E+01 Uncompacted _p

c. ' Irradiated components, control m3 NA NA NA NA NA NA rods, ete Ci

d. vther (describe) a3 NA NA NA NA NA NA Ci q STP . Strong Tight Package i

?

n

Enclosure 3 to Serial: RNPD/92 0409 Page:4~of 4 TABLE IV B EFFLUENT /.ND WASTE DISPOSAL SEMI ANNUAL REPORT - 1991 LIOUID EFFLUENTS - CONTINUOUS MODE AND BATCH MODE RELEASES CONTINUC'1S MOD,E BATCH MODE UNITS IST OUARTER 2ND OUARTER IST OUARTER 2ND OUARTE.8

1. PARTICUIATES Na 24 Ci <tLD <LLD 7.64E-06 1.24E-05 Cr.51 Ci <LLD <LLD k.56E-03 2.18E-04 Mn 54 Ci <LLD <LLD 3.85E-04 1.80E-05 Fe 55 C1 <tLD <LLD 1.61E-02 2.62E-03 Co 57 Ci ,

<LLD <tLD 7.03E-05 4.52E-06 Co 58 Ci <tLD <tLD 3.70E-02 2.12E-03 Co 60 Ci <LLD <L1.D 1.81E-02 1.32E-03 Nb 95 Ci <LLD <LLD 3.84E.04 <LLD Zr-95 Ci <LLD <LLD 5.87E-05 <LLD Tc-99m Ci <LLD <LLD 2.98E 06 <LLD Ag 110m Ci <LLD <LLD 1.4?E-03 -3.50E-05 Sn-113 Ci <tLD <tLD 2.59E-05 ,

<LLD Sb-124 C1 <iLD <LLD 4.11E-03 3.93E-04 Sb-125 Ci <LLD <LLD 2.73E-02 7.41E-03 Cs>134 Ci <LLD <LLD 4.60E-06 L.],2E-04 Cs-137 Ci <LLD <tLD 9.70E-04 1.03E-03 Total for Ci <LLD <LLD 1.08E-01 1.53E-02 Period

2. CASES

Xe-133 C1 <LLD -<LLD 1.57E-04 1.92E-03 Total for Period- Ci <tLD <LLD 1.57E-04 1.82E-03 k

5:

-s is

[-

L '

j:

-l Addendum.I to-Serial: ' RNPD/92-0409 j Page 1 of 4 1

l i

INDEPENLENT SPENT FUEL STORAGE INSTALLATION  !

i-  ;

!1 H B. ROBINFON STEAM ELECTRIC PLANT UNIT 2 j ': SEMIANNUAL ENVIRONMENTAL REPORT l:

! July 1, 1991 - December 31, 1991 i- ,

i.

i.

l

-FACILITY OPERATING LICENSE NO, SNM-2502 ,

l DOCKET NO, 72-3 {

i t

A h .-

i :.

[:

i~

b, -

l l

t I -..

~ .C J .. _ ,_,__.____i.m-..,.._.,___m__ew~,:,_A.,_ . , - . , - , , - _ . . . .

_ _ _ _ - ~ - _ . . . _ _ __ _

4 Addendum I to Serial: RNPD/92-0409

-Page-2 of 4-I -. HISTORY OF THE FACILITY The Independent Spent Fuel Storage Installation (ISFSI) is located wi thin the Protected area of HBR2. Currently, the installation contains eight (8) Dry Storage Canisters. The

. initial ' canister was loaded on 3/16/89 and other canisters were loaded on 4/11/89, ,

4/18/89, 4/24/89, 5/2/89, S/8/89, 6/28/89, and 7/3/89 II. EFFLUENT LIMITS AND CONTROLS This installation operates under effluent control limits as required by 10CFR72.44.

However, there are, by design of the sealed storage canisters at the ISFSI, no effluent releases, and all H. B. Robinson site cask loading and unloading operations and waste treatment therefrom will occur at the H. B. Robinson Steam Electric Plant Lnit 2 under the specifications of its operating license @PR-23).

III. RADIOLOGICAL EFFU'ENT RELEASES A review of the - quarterly surveillance tests performed during this reporting period indicates thet NO RADI0 ACTIVE LIQUID OR CASEOUS RELEASES OCCURRED DURING THIS REPORT PERIOD.

' IV, THE ISFSI ENVIRONMENTAL PROGRAM The ISFSI Environmental Program consists of two air samplers and three TLD's about the installation plus an unaffected air sampler and TLD site 26 miles ESE of_the facility.

Two of the environmental TLD's are maintained at the air sampling sites adjacent to the-plant boundary. _ These are located south at 0.2 miles and_ southwest at 0.3 miles from the ISFSI. A third TLD site is-located 0.1 miles north of the installation. The nearest residence-is located south to south-southeast approximately 0.25 milea from the facility.

Air samplers operate continuously and samples are changed weekly.

~~

TLD's are changed quarterly.

l l V, OTHER ENVIRONMENTAL PROGRAMS I-In addition - to the. ISFSI Environmental Program, the HBR2 Environmental Program is described--_-in Technical Specification 3.17 (see Carolina Power and Light = Company, l

" Technical Specifications and Bases _ for H. B. Robinson Unit No. 2," Appendix A to

-Facility Operating License DPR-23 Docket No. 50-261, Darlington County, S.C.). For a _

comprehensive. summary of this _ program and its results, .see also " Environmental Surveillance Report," H. B.-Robinson Steam Electric Plant, Unit 2 issued in compliance

--with the'above referenced Technical Specification for this_ report period.

L L

m-'m . . . , _ . . - - . , y _ . .- ,, . . - _ - --. ,,m--, :--.-.,

. _ - - ~ - . . - . . ~ - - - _- - . . - - . - . . - . - - . , -

.- _ .-~

s

' Addendum'I to Serial: RNPD/92.- 0_409

. PaSe '3 of 4 VI. ,LSJ&1 ENVIRONMENBL MEASUREMENTS l

A. Envirotunental TLD's TLD (Location) 3rd Qtr. 4th Qtr. i (mrem /wk.) (mrem /wk.)

1 (26 miles ESE) 1.20 1.00 (Control) 2-(0.2 miles S) 1,00 1,00 '

6 (0.3 miles SW) 1.10 1,00 56 (0.1 miles N) 1.00 1.00 B. Air Sampling Cross Beta Measurements - 3rd Qtr.

(picoeuries per cubic meter)

Air Sampler (Locatf..;;;; Averare Maximum l_(26 miles ESE) 1.55E-02 2.74E-02 (Control) 2 (0.2 miles S) 1.63E-02 2.70E-02 6 (0 3 miles SW) _1.70E 02 2.70E-02 Gross Bet. Measurements - 4th Qtr.

(picocuries per cubic meter).

Air Sampler (Location) Averate Maximum 1-(26 miles-ESE) 1.91E-02 2.67E-02 (Control) 2 (0.2 miles S)- _2.26E-02 - 3 '. 00E .6-(0.3 miles SW) 2.12E-02 2.76E-02 A composite analysis of air samples detected -_- no - radionuclides from - man made

-sources =for either quarter.

l i

l i

Addendum 1 to Serial: RNPD/92-0409 Page 4 of 4 VII, CONClMSIONS Based on the above measurements performed during this reporting period, it is our conclusion that the dose issuing from the ISFSI to the most exposed MEMBER OF Tile PUBLIC did not exceed 1 mrem. This is best estimated as presented in the ISFSI FSAR and compensated for eight canisters and a partial year of operation as 0.4 mrem per year.

VIII.

SUMMARY

i This report is submitted in compliance with IsrSI Specification 1.4.1 as required pursuant to 10CFR72.44(d)(3) . Paragraph III specifies liquid ano gaseous releases to the environment. Paragraphs VI and VII are provided f or estimation of potential radiation dose commitment to the public resulting from effluent release 1

1

- - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ , _ _ _ _ , _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __