Text

Rev 0 to Annual Radioactive Effluent Rept 960101-1231 Suppl Info
	ML20141A410
Person / Time
Site:	Prairie Island
Issue date:	12/31/1996
From:	; NORTHERN STATES POWER CO.
To:	;
Shared Package
ML20141A396	List: ML20141A393; ML20141A410; ML20141A414;
References
	NUDOCS 9705140283
	Download: ML20141A410 (22)
	v • d • e

. - -

1996 Annu21 Radio 2ctivo Efflu2nt Report REV. O Pcge 1 of 9 Retention: Lifetime i

l I

ANNUAL RADIOACTIVE EFTLUENT REPORT 01-JAN-96 THROUGH 29-DEC-96 SUPPLEMENTAL INFORMATION Facility:

Prairie Island Nuclear Generating Plant Licensee:

Northern States Power Company License Numbers: DPR-42 & DPR-60 A. Regulatory Limits 1.

Liquid Effluents:

a.

The dose or dose commitment to an individual from radioactive materials in liquid effluents released from the site shall be limited to:

for the quarter 3.0 mrem to the total body 10.0 mrem to any organ for the year 6.0 mrem to the total body 20.0 mrem to any organ 2.

Gaseous Effluents:

a.

The dose rate due to radioactive materials released in gaseous effluents from the site shall be limited to:

noble gases s 500 mrem / year total body f

$3000 mrem / year skin I-131, I-133, H-3, LLP s1500 mrem / year to any organ b.

The dose due to radioactive gaseous effluents released from the site shall be limited to:

noble gases s10 mrad / quarter gamma

$20 mrad / quarter beta s20 mrad / year gamma s40 mrad / year beta j

I-131, I-133, H-3, LLP s15 mrem / quarter to any organ s30 mrem / year to any organ 9705140283 970508 PDR ADOCK 05000282 R

PDR

1996 ANNUAL RADIOACTIVE EFFLUENT REPORT REV. O PAGE 2 B.

Maximum Permissible Concentration 1.

Fissior and activation gases in gaseous releases:

OLD 10 CFR 20, Appendix B, Table 2, Column 1 2.

Iodine and particulates with half lives greater than 8 days in gaseous releases:

1 OLD'10 CFR 20, Appendix B, Table 2, Column 1 3.

Liquid effluents for radionuclides other than dissolved or entrained gases:

OLD 10 CFR 20, Appendix B, Table 2, Column 2 4.

Liquid effluent dissolved and entrained gases:

2.0E-04 uCi/ml Total Activity C.

Average Energy Not applicable to Prairie Island regulatory limits.

D.

Measurements and approximations of total activity 1.

Fission and activation gases Total GeLi 125%

in gaseous releases:

Nuclide GeLi 2.

Iodines in gaseous releases:

Total GeLi 25%

Nuclide GeLi 3.

Particulates in gaseous releases:

Total GeLi 25%

Nuclide GeLi 4.

Liquid effluents Total GeLi 25%

Nuclide GeLi E.

Manual Revisions 1.

Offsite Dose Calculations Manual latest Revision number:

14 Revision date 05/15/96 Revision #14 of the ODCM and a description of the changes are submitted with this report for review.

4

)

f 1996 ANNUAL RADIOACTIVE EFFLUENT REPORT REV. O PAGE 3 e

3 1.0 BATCR RELEASES (LIQUID)

QTR 01 QTR 02 QTR: 03 QTR 04 1.1 NUMBER OF BATCH RELEASES 9.10E+01 2.30E+01 3.30E+01 3.30E+01 1.2 TOTAL TIME PERIOD (HRS) 1.75B+02 4.41E+01 6.07E+01 5.585+01 1.3 MAEIMUM TIME PERIOD (HRS) 3.50E+00

-3.83E+00 3.45E+00 3.88E+00 1.4 AVERAGE TIME PERIOD (HRS) 1.92E+00 1.92E+00 1.84E+00 1.69E+00 j

1.5 MINIMUM TIME PERIOD (HRS) 1.275+00 1.30E+00 1.43B+00 1.22E+00 i

1.6 AVERAGE MISSISSIPPI RIVER FLOW (CFS) 1.82E+04 4.60E+04 1.55E+04 1.78E+04 I

2.0 BATCH RELEASES (GASROUS)

QTR 01 QTR 02 QTR 03

w..: 04 I

t 2.1 NUMBER OF BATCH RELEASES 1.70E+01 1.00E+01 6.00E+00 0.00E+00 i

2.2 TOTAL TIME PERIOD (HRS) 4.18E+01 7.02E+01 1.40E+01 0.00E+00 2.3 MAEIMUM TIME PERIOD (HRS) 1.88E+01 2.42E+01 6.70E+00 0.00E+00 i

2.4 AVERAGE TIME PERIOD (HRS) 2.45E+00 7.02E+00 2.33E+00 0.00E+00 2.5 MINIMUM TIME PERIOD (HRS) 1.00E-02 8.00E-02 8.00E-02 0.00E+00 i

3.0 ABBOEMAL RELEASES (LIQUID)

QTR 01 QTR: 02 QTR 03 QTR 04 3.1 NUMBER OF RELEASES 0.00B+00 0.00E+00 0.00E+00 0.00E+00 3.2 TOTAL ACTIVITY RELEASED (CI) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.3 TOTAL TRITIUM RELEASED (CI) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.0 ABSORMAL BELEASES (GA8BOUS)

QTR 01 QTR 02 QTR 03 QTR 04 4.1 NUMBER OF RELEASES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 h

4.2 TOTAL ACTIVITT RELEASED (CI) 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1996 ANNUAL DADIOACTIV3 EFFLU2L'T REPORT RSV. O PAGE 4 TABLE 1A GASSOUS EFFLUENTS - EUmeATION OF ALL RELBASBS QTR: 01 QTR 02 QTR: 03 QTRI 04 t

f 5.0 FISSION AND ACTIVATION GASES 1

t 5.1 TOTAL RELEASE (CI) 7.143-01 0.00E+00 3.79E-01 0.00E+00

[

5.2 AVERAGE RELEASE RATE (UCI/SEC) 9.08E-02 0.00E+00 4.82E-02 0.00E+00 5.3 GAMMA DOSE (MRAD) 5.14E-05 0.00E+00 2.81E-05 0.00E+00

[

5.4 BETA DOSE (MRAD) 5.83E-03 0.00E+00 3.09E-03 0.00E+00 l

5.5 PERCENT OF GAMMA TECH SPEC (%)

'5.145-04 0.00E+00 2.813-04 0.00E+00 5.6 PERCENT OF BETA TECH SPEC (%)

2.92E-02 0.00E+00 1.55E-02 0.00E+nn 6.0 IODINES r

l8 LoE+03 6.1 TOTAL I-131 (CI) 0.00E+00 0.00E+00 0.00E+0C

-[

6.2 AVERAGE RELEASE RATE (UCI/SEC) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.0 PARTICULATES l

7.1 TOTAL RELEASE (CI) 7.90E-05 8.53E-05 7.943-06 0.00E+00 t

7.2 AVERAGE RELEASE RATE (UCI/SEC) 1.05E-05 1.095-05 1.01E-06 0.00E+00 h

i 8.0 TRITIUM 8.1 TOTAL RELEASE (CI) 1.04E+01 1.11E+01 1.22E+01 9.52E+00 8.2 AVERAGE RELEASE RATE (UCI/SEC) 1.32E+00 1.41E+00 1.55E+00 1.21E+00

[

t l

9.0 TOTAL IODINE, PARTICULATE AND TRITIUM (UCI/SEC) 1.32E+00 1.41E+00 1.55E+00 1.21E+00 i

I 10.0 DOSE FROM IODINE, LLP AND TRITIUM (MREM) 2.65E-02 6.35E-02 2.69E-02 1.?lE-02

[

t 11.0 PERCENT OF TECH SPEC (%)

1.773-01 4.23E-01 1.79E-01 1.14E-01 12.0 GROSS ALPHA (CI) 8.60E-09 0.00E+00 0.00E+00 1.76E-08 l

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_..m 1996 ASTUAL EADIOACTIV3 CFFLUENT EEPO2T K3V. O PAGJ 7 TABL3 2A LIQUID EFFLUENTE - SUIERATION OF ALL RELRASES QTR 01 QTR: 02 (t 4 P,3 QTR 04 l

16.0 VOLUME OF WASTE PRIOR TO DILUTION (LITERS) 8.34E+07 6.71E+07 7.21E+07 6.97E+07 17.0 VOLUME OF DILUTION WATER (LITERS) 8.983+10 8.51E+10 2.70E+11 1.995+11 18.0 FISSION AND ACTIVATION PRODUCTS 18.1 TOTAL RELEASE W/O H-3, RADGAS, ALPHA (CI) 2.203-01 4.45E-02 2.70E-01 2.273-02 l

18.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 2.455-09 5.22E-10 1.005-09 1.145-10 i

19.0 TRITIUM f

19.1 TOTAL RELEASE (CZ) 1.67E+02 1.28E+02 1.99E+02 1.33E+02 19.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 1.863-06 1.50E-05 7.37E-07 6.68B-07 20.0 DISSOLVED AND BETRAINED OASES 20.1 TOTAL RELEASE (CI) 6.33E-04 5.27E-04 6.575-04 7.973-05 20.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 7.04E-12 6.195-12 2.43E-12 4.01E-13 I

21.0 GROSS ALPHA (CI) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 22.0 TOTAL TRITIUM, FISSION AND ACTIVATION f

PRODUCTS (UCI/ML) 1.865-C6 1.50E-06 7.373-07 6.68E-07 23.0 TOTAL BODY DOSE (MREM) 4.655-03 3.81E-03 5.065-03 3.73E-03 24.0 CRITICAL ORGAN 24.1 DOSE (MREM) 1.86E-06 1.50E-06 7.37E-07 6.68E-07 24.2 ORGAN TOT BODY TOT BODY TOT BODY TOT BODY 25.0 PERCENT OF TOTAL BODY TECH SPEC LIMIT (%)

1.553-01 1.27E-01 1.69E-01 1.24E-01 26.0 PERCENT OF CRITICAL ORGAN TECH SPEC LIMIT (%)

1.55E-01 1.273-01 1.693-01 1.24E-01 I

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i 1956 AN2UAL RADIOACTIV3 EFFLUU2T REPO2T R3V. O PA23 8 TABL3 23

}

LIQUID BFFLUENTS - SUNRATION OF ALL RELEASES l

27.0 INDIVIDUAL LIQUID EFFLUBWT CONTINUOUS MODE BATCE MODE f

NUCLIDE UNITS QTR: 01 QTR: 02 QTR 03 QTR 04 QTR: 01 QTR: 02 QTR 03 QTR 04 AG-108M CI 9.34E-06 AG-110M CI 5.135-05 5.71E-03 3.16E-03 7.383-03 3.65E-04 BE-7 CI 3.013-05 6.955-05 4.535-06 j

CO-57 CI 2.85B-04 7.543-05 1.98E-05

'1.10E-06 CO-58 CI 6.02E-04 2.84E-05 1.135-05 1.18E-01 1.74E-02 7.03E-03 7.13E-04 t

CO-60 CI 4.17E-04 1.03E-02 4.585-03 6.78E-03 1.01E-03 CR-51 CI 7.673-03 4.575-04 1.993-05 2.262-04 CS-134 CI 1.095-04 2.36E-04 3.273-04 3.353-04 3.045-04 CS-137 CI 1.84E-04 3.84E-04 4.71E-04 6.32E-04 5.03E-04 FE-59 CI 1.26E-05 2.37E-03 1.40E-04 5.05E-05 I-131 CI 2.60E-06 i

LA-140 CI 2.74E-05 4.55E-06 MN-54 CI 3.30E-05 9.66E-04 6.78E-04 6.328-04 4.542-05 t

NA-24 CI 2.80E-07 4.008-06 NB-95 CI 4.285-06 2.22E-03 5.63E-04 2.29E-04 2.02E-06 l

NB-97 CI 2.63E-06 2.51E-05 2.88E-06 RM-105 CI 4.15E-05 1.02E-05 SB-122 CI 4.48E-03 2.59E-06 i

SB-124 CI 1.69E-02 2.05E-04 2.61E-04 4.27E-04 SB-125 C1 1.32E-05 1.77E-02 1.06E-03 3.095-03 1.40E-02 1

SB-126 CI 1.915-04 l

SC-47 CI 1.74E-04 4.085-05 f

SN-113 CI 1.20E-03 1.70E-04 1.74E-04 4.015-06 SR-92 CI 3.17E-05 1.943-05 9.70E-05 1.68E-C6 i

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i PINGP 753, Rev. 6 Page 1 of 7 Retention: Life PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1/1/96-12/31/96 5 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT i

i SOLID WASTE AND IRRADIATED FUEL SHIPMENTS I

A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)

1. Solid Waste Total Volumes and Total Curie Quantities:

' i ;,

'., a,'

.'/

CONTAINER '

e

:: 3 "',,

" PERIOD, EST. TOTAL','

, DISPOSAL' N, c4

,, '. ' ~

TYPE OF WASTE,,

UNITSt

, ' TOTALS

'; ERROR, % '

f V O L (fts)

,1 (0.00 E00)s,

< (0.00 E00)

- '(LIST)

A. Resins m

1.66t+01 135.8 3

ft3 5.86E+02 178.9 Cl 2.S3E+02 i 2.50E+01 3

g B. Dry-Compacted m

(

ft3 Ci 3

C. Non-Compacted m

7.02E+01 1200.0 ft3 2.48E+03 1280.0 Cl 1.24E-01 1 2.50E+01 3

D. Filter Media m

ft3 Ci S. Other (furnish description) m3 ft3 Ci 9 'TE:)

The solid waste information provided in this report is the volume and '

i:NO g

activity of the low-level waste leaving the Prairie Island site. No W ", "

allowance is made for off-site volume reduction prior to disposal.

=- --

PINGP 753, Rnv. 6 Page 2 of 7

(~x

's PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1/1/96-12/31/96 i NORTHERN STATES POWER License No. DPR-42/60 i

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)[ continued]

2. Principal Radionuclide Composition by Type of Waste:

(Bold letter designation from Page 1)

TYPE Percent (%)

Abundance NucIlde

{(LOOEO)

A Co - 60 3.41E+01 Ni - 63 2.97E+01 Cs - 137 1.25E+01 Fe - 55 1.02E+01 Co - 58 6.98E+00 Cs - 134 3.92E+00 p

Mn - 54 1.53E+00

\\

C - 14 6.40E-02 H-3 2.50E-02 C

Fe - 55 7.04E+01 Co - 60 9.60E+00 Ni - 63 8.23E+00 Co - 58 3.29E+00 Zr - 95 2.69E+00 Nb - 95 2.61E+00 Mn - 54 1.01E+00 Cs - 137 5.23E-01 C - 14 4.27E-01 H-3 2.80E-02

= Inferred - Not Measured on Site

PINGP 753, Rsv. 6 Page 3 of 7 f3 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1/1/96-12/31/96 NORTHERN STATES POWER License No. DPR-42/60 s

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL 4

(NOT IRRADIATED FUEL)[ continued].

2. Principal Radionuclide Composition by Type of Waste (Continuation):

(Bold letter designation from Page 1)

TYPE Percent (%)

Abundance Nuclide (0.00EO)

I O

l O

= Inferred - Not Measured on Site

~

PINGP 753, Rav. 6 Page 4 of 7 O

PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1/1/96-12/31/96 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL j.

(NOT IRRADIATED FUEL)(continued]

i

~

3. Solid Waste Disposition:

l Number of Shloments Mode Destination 4

Truck Barnwell 2

Truck Oak Ridge i

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-=

i PINGP 753, Rsv. 6 Page 5 of 7

-(

i

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PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1/1/96-12/31/96 '

NORTHERN STATES POWER License No. DPR-42/60 si EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID. WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)[ continued]

4. Shipping Container and Solidification Method:

Disposal No.

Volume Activity Type of Container Solidif.

l

' (Ft /m )

(Cl)

Waste Code Code 3

3 96-022 135.8/3.84 77.2 A

L N/A 96-023 135.8/3.84 72.1 A

L N/A 96-024 135.8/3.84 87.4 A

L N/A t

96-027 178.9/5.1 15.9 A

L N/A

_,96-029 1200/33.98 0.07 C

L N/A 96-030 1280/36.24 0.05 C

L N/A TOTALS 6

3066.3/86.8 252.72 CONTAINER CODES:

L = LSA (Shipment type)

A = Type A B = Type B Q = Highway Route Controlled Quantity SOLIDIFICATION CODES:

C = Cement TYPES OF WASTES:

A = Resins B = Dry Compacted C = Non-Compacted D = Filter Media S = Other

PINGP 753, Rev. 6 Page 6 of 7

~

PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1/1/96-12/31/96 '

NORTHERN STATES FOWER License No. DPR-42/60 h

i 1

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS B. IRRADIATED FUEL SHIPMENTS (DISPOSITION) j Number of Shloments Mode Destination 1 !

I i

4 1

!O i

i i

l l

l d

J C

O

PINGP 753, Rsv. 6 Page 7 of 7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1/1/96-12/31/96 j

NORTHERN STATES POWER License No. DPR-42/60 j

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS C. PROCESS CONTROL PROGRAM CHANGES f

TITLE:

Process Control Program for Solidification / Dewatering of Radioactive Waste from Liquid Syste es 4

Current Revision Number:

6 Effective Date:

5/10/95 i

A

\\

',T.. xNOTE!M #yreport, then a description and justification of the changes to the PCP is

_..._ n

.w...

1 if the effective date of the PCP is within the period covered by this 1

4

, [;,

required (T.S.6.5.D). Attach the sidelined pages to this report.

1 1

Changes / Justification:

L i

I I

O

i 1

NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT OFF-SITE RADIATION DOSE ASSESSMENT FOR January throuah December 1996 i

An Assessment of the radiation dose due to the release from Prairie Island Nuclear Generating Plant during 1996 was performed in accordance with the Technical Specifications.

Computed doses were well below the 40 CFR Part 190 Standards and 10 CFR Part 50 Appendix I Guidelines.

Off-site dose calculation formulas and meteorological data from the Off-site Dose Calculation Manual were used in making this assessment.

Source terms were obtained from the Annual Radioactive Effluent and Waste Disposal Report prepared for NRC review for the year of 1996.

Of f-site Doses from Gaseous Release Computed doses due to gaseous releases are reported in Table 1.

Critical Receptor location and pathways for organ doses are reported in Table 2.

Doses are a small percentage of Appendix I Guidelines.

Off-site Doses from Liould Release Computed doses due to Liquid releases are reported in Table 1.

Receptor information is reported in Table 2.

Doses, both whole body j

and organ, are a small percentage of Appendix I Guidelines.

l Doses to Individuals Due to Activities Inside the Site Boundary Occasionally sportsmen enter the Prairie Island site for recreational f

activities.

These individuals are not expected to spend more than a few hours per year within the site boundary.

Commercial and l

recreational river traffic exists through this area.

For purposes of estimating the dose due to recreational and river water transportation activities within the site boundary, it is assumed that the limiting dose within the site boundary would be received by an individual who spends a total of seven days per year on the river just off shore from the plant buildings (ESE at 0.2 miles).

The gamma dose from noble gas releases and the whole body and organ doses from the inhalation pathway due to Iodine 131, Iodine-133, tritium and long lived particulates ' were calculated for this location and occupancy l

time.

These doses were reported in Table 1.

Doses to Individuals Due to Effluent Releases from the ISFSI Two loaded fuel casks were placed in the storage facility during the 1996 calendar year bringing the total number of casks to 5.

There has been no release of radioactive effluents from the ISFSI.

4 Doses to Most Exposed Member of the General Public from Reactor Release and Other Uranium Fuel Cycle Sources There are no other uranium fuel facilities in the vicinity of the Prairie Island site.

The only other artificial source of exposure to the general public in addition to the plant effluent releases is from

)

direct radiation of the reactors.

This direct radiation from pressurized water reactors has been shown to be negligible.

An array of TLD monitoring stations around the perimeter of the site boundary has consistently indicated that plant operation in the past. years has no effect on ambient gamma radiation.

Therefore, the most exposed member of the general public will not receive an annual radiation dose f rom reactor effluent releasas and all other fuel ~ cycle activities in excess of the sum of the liquid and gaseous whole body and organ doses reported in Table 1 for the site boundary and critical receptor, respectively.

These doses are well below 40 CFR Part 190 standards of 25 mrem to the whole body, 75 mrem to tne thyroid, and 25 mrem to any other organ.

Radiation Environmental Monitorina Procram Samplina Deviations There were no milk or vegetable sampling deviations during this reporting period.

l 1

k i

l 1

i i

__.._____m.___

J Table 1 1.

OFF-SITE RADIATION DOSE ASSESSMENT - PRAIRIE ISLAND PERIOD:

JANHARY throuah DECEMBER 1996 i

10 CFR Part 50 Appendix I Guidelines per 2-units site per year Gaseous Releases Maximum Site Boundary Gamma Air Dose (mrad) 7.95E-05 20 Maximum Site Boundary Beta Air Dose (mrad) 8.91E-03 40 Maximum Off-site Dose to any organ (mrem)*

1.34E-01 30 Offshore Location Gamma Dose (mrad) 2.12E-04 Total Body (mrem)*

2.36E-01 Organ (mrem)*

2.39E-01 30 Liould Releases Maximum Off-site Dose Total Body-(mrem) 1.72E-02 6

Maximum Off-site Dose Organ - GI-LLI (mrem) 7.38E-03 20 Limiting Organ Dose Organ - Total Body 1.72E-02 6

Long-Lived Particulate, I-131, I-133 and H-3

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

i Table 2 OFF-SITE RADIATION DOSE ASSESSMENT - PRAIRIE ISLAND 1

SUPPLEMENTAL INFORMATION PERIOD: JANUARY throuah DECEMBER 1996 i

Gaseous Releases I

Maximum Site Boundary Dose Location (from Building Vents) e Sector WNW Distance (miles) 0.4 1

Offshore Location Within Site Boundary i

Sector ESE Distance (miles) 0.2 Pathway Inhalation Maximum Off-site Sector SSE Distance (miles) 0.6 Pathways

Plume, Ground, Inhalation, Vegetables Age Group Child Liould Releases Maximum Off-site Dose Location Downstream Pathway Fish

~.s+..,

,s.*

,u.

-. - ~.... - -..

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9

) W i

l'

SUMMARY

OF CHANGES TO OFFSITE DOSE CALCULATION MANUAL 1

REV 14 j

The Of fsite Dose Calculations Manual,ODCM, was revised to correct i

. typographical errors detected after the major revision 13 and to include items identified in an internal QA audit of revision 13.

Those items are as follows-4 2

J 1)

Tech Spec references made in sections 2 and 3 of the ODCM were upgraded to reference the specific TS section of TS.6.5.H.

l 5

2)

Table 2.3, Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements, was revised to 3

remove the requirement to calibrate the Turbine Building Sump Composite Sampler every 18 months.

The samplers are not i

actually calibrated.

They are monitored daily via plant procedure and there is actually nothing on the sampler to calibrate.

l I

i 3)

Bases section 2.0 was revised to change the units in the reference to primary to secondary leakage from gallons per minute to gallons per day, to be consistent with other plant procedures.

4)

Correct a Tech Spec reference in section 7 from TS.6.5.I to TS.6.5.E.

The final draft of the proposed tech spec change i

was not final when the ODCM rev 13 was completed and this reference was incorrect.

l 5)

Liquid Dose factors were added to Table 4.2 and corrections 4

were made to the dose factors for AG-110M and Nb-95.

These dose f actors were calculated and used in the past and had not been added to Table 4.2.

6)

Add R values for airborne dose factors to Table 5.5 for

Ground, Child Inhalation, and Child Vegetable pathways.

These factors were previously calculated and not added to the ODCM.

7)

Table 2.2, Action 6

revisec to recuire grabs samples collected when the discharge moaitor is out of service to be analyzed for individual gamma em'.tters '.ather than saved for weekly composite and analysis.

8)

Table 2.3 and 3.3 references to the National Bureau of Standards,

NBS, was corrected to National Institute of Standards and Technology, NIST.

The NBS no longer exists.

4 9)

Table 3.2, Action 5 was revised to clarify that the action is applicable when " containment integrity is required or the primary system is initially opened to the atmosphere."

1 a

d o

10)

The definition of the

" SITE BOUNDARY" was revised to reference the Figures 3.1 and 3.2.

11)

Typographical errors were corrected in the following sections:

Section 3.13.a.2

- the word " daily" was left out Section 4.1

- changed "will" to "SHALL" Section 4.3.4

- incorrect section reference Section 5.1

- changed "will" to "SHALL" and correct a misspelled word.

Section 5.1.3

- changed "that" to "than" Bases 3.9/3.10

- corrected poor sentence structure Table 2.3 - Note reference were incorrect Table 3.1 - Sentence typed twice in Note C Table 2.1 - Wrong LLD value listed for SGBD Table 3.1 - I-133 was added to I-131 for the LLD reference Table 3.3 - Incorrect note referenced An evaluation of the above listed changes results in the determination that the changes maintain the levels of radioactive effluent control required by 10 CFR 20.106, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, and do not adversely impact the accuracy or reliability of i

effluent dose or setpoint calculations.

[

4 1

4

ML20141A410

Text

SUMMARY

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