L-PI-09-055, 2008 Annual Radioactive Effluent Report and Offsite Dose Calculation Manual

From kanterella
Jump to navigation Jump to search
2008 Annual Radioactive Effluent Report and Offsite Dose Calculation Manual
ML091380425
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 05/12/2009
From: Wadley M
Northern States Power Co, Xcel Energy
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
FOIA/PA-2010-0209, L-PI-09-055
Download: ML091380425 (29)
v • d • e


Text

i, 01 XcelEnergyo L-PI-09-055 MAY 1 2 2009 TS 5.5.1.c TS 5.6.3 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282, 50-306 and 72-10 License Nos. DPR-42, DPR-60 and SNM-2506 2008 Annual Radioactive Effluent Report and Offsite Dose Calculation Manual Pursuant to the applicable Prairie Island Nuclear Generating Plant (PINGP) Technical Specifications (TS), Appendix A to Operating Licenses DPR-42 and DPR-60, and the requirements of the Offsite Dose Calculation Manual (ODCM), Northern States Power Company, a Minnesota Corporation (NSPM) submits the 2008 Annual Radioactive Effluent Report which is comprised of the following reports:

Enclosure 1 contains the Off-Site Radiation Dose Assessment for the period January 1, 2008 through December 31, 2008 in accordance with the requirements of the ODCM.

Enclosure 2 contains the Annual Radioactive Effluent Report, Supplemental Information, for the period January 1, 2008 through December 31, 2008 in accordance with the requirements of TS 5.6.3 and the ODCM.

Enclosure 3 contains the Effluent and Waste Disposal Annual Report, Solid Waste and Irradiated Fuel Shipments, for the period January 1, 2008 through December 31, 2008 in accordance with the requirements of TS 5.6.3 and the ODCM.

Enclosure 4 contains a complete copy of the entire ODCM (H4), Revision 22, dated 10/23/08. In accordance with the requirements of TS 5.5.1.c., the changes are identified by markings in the margin of the affected pages. The manual also contains a Record of Revisions which includes a summary of the revision changes (refer to page 8 of the ODCM).

1717 Wakonade Drive East

  • Welch, Minnesota 55089-9642 ir 11 Wkn eTelephone: 651.388.1121 A0oo

Document Control Desk Page 2 contains the Process Control Program (PCP) for Solidification/Dewatering of Radioactive Waste from Liquid Systems (D59), Revision 9, dated 4/15/08. In accordance with the requirements of the ODCM, the description of changes to the PCP is included in the Annual Radioactive Effluent report (refer to page 6 of Enclosure 1).

Summary of Commitments This letter contains no new commitments and no revisions to existing commitments.

/,//JCLO 2i Michael D. Wadley Site Vice President, Prairie Island Nuclear Generating Plant Units 1 and 2 Northern States Power Company - Minnesota Enclosures (5) cc: Regional Administrator, USNRC, Region III Project Manager, Prairie Island Nuclear Generating Plant, USNRC, NRR NRC Resident Inspector - Prairie Island Nuclear Generating Plant Department of Health, State of Minnesota PI Dakota Community Environmental Coordinator

ENCLOSURE 1 OFF-SITE RADIATION DOSE ASSESSMENT January 01, 2008 - December 31, 2008 8 pages follow

PRAIRIE ISLAND NUCLEAR GENERATING PLANT OFF-SITE RADIATION DOSE ASSESSMENT FOR January throug~h December 2008 An Assessment of the radiation dose due to releases from Prairie Island Nuclear Generating Plant during 2008 was performed in accordance with the Offsite Dose Calculation Manual as required by 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 2008.

Off-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. Gaseous release doses are a small percentage of Appendix I Guidelines.

Off-site Doses from Liquid Release Computed doses due to liquid releases are reported in Table 1. Critical receptor information is reported in Table 2. Liquid release doses, both whole body and organ, are a small percentage of Appendix I Guidelines.

Doses to Individuals Due to Activities Inside the Site Boundary Occasionally sportsmen enter the Prairie Island site for recreational activities. These individuals are not expected to spend more than a few hours per year within the site boundary. Commercial and 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- 13 3, tritium and long-lived particulates were calculated for this location and occupancy time. These doses are reported in Table 1.

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

Page 1 of 8

ABNORMAL RELEASES There were two (2) abnormal releases for 2008. Abnormal releases are summarized here:

1. Leak from Waste Gas System Catalytic Recombiner On 11/25/08 a leak was discovered on piping downstream of CV-31919, Oxygen Supply Control Flow Valve for 121 Catalytic Recombiner, where the oxygen flows into the waste gas stream.

The leak was from a crack in the piping. 121 Catalytic Recombiner was isolated the same day.

Engineering performed a data review and determined that the leak could have been present as early as 8/26/08 and that a maximum of 2,742 cubic feet (7.77E+07 cc) was potentially released. The release pathway was determined to be the Unit One Auxiliary Building Ventilation via the filter room.

Cause: Equipment failure.

Corrective Action: Repairs were implemented and the 121 Catalytic Recombiner was returned to service.

A release file was created to account for activity released as an Abnormal Release.

Release file inputs were as follows:

Total activity was calculated based on concentrations in 128 Waste Gas Decay Tank, released 10/3 1/08. Engineering provided released volume.

Kr-85 1.34E+05 uCi Xe-133 9.09E+01 uCi H-3 1.93E+02 uCi A Unit One Auxiliary Building Release File was created (RAC0257) for effluent week 45 (11/3/08 to 11/9/08), conservatively applying activity released to one effluent week.

Dose consequences were as follows:

Nuclide Activity Gamma Dose Beta Dose (uCi) (mrad) (mrad)

Kr-85 1.34E+05 2.47E-06 2.80E-04 Xe-133 9.09E+01 3.43E-08 1.02E-07 TOTAL 2.50E-06 2.80E-04 H3 1.93E+02 uCi 3.46E-07 mrem Event was captured in the site's Corrective Action Program: AR01 160402.

Result: The dose from the activity released represented a small percentage of the total dose and a very small percentage of limits. The dose did not impose upon the health and safety of the public.

The event was discussed with the NRC Region 3 Radiation Protection (RP) Inspector, at the time of the event.

Page 2 of 8

2. UNIT 2 STEAM GENERATOR B POWER OPERATED RELIEF VALVE, CV-31107 LEAKAGE Equipment failure. On 7/5/08 an alarm was received on the SG B PORV LEAK TEMP. A review of the Emergency Response Computer System (ERCS) trend plots indicated that, on a recurring basis, a change in relief valve position would occur, accompanied by a corresponding increase in down stream temperature.

Some small degree of leakage past the SG B PORV is anticipated. The leakage condenses and drains to the Turbine Building Sump (TBS) via a line designated for this purpose. The TBS is monitored and a release file is routinely prepared to account for volume and activity released.

It was determined that the drain line was plugging. Periodically as the undrained water accumulated, it would flash disrupting the PORV and releasing some small amount of steam.

This release is determined to be an abnormal release due to the line plugging.

Cause: Equipment failure Corrective Actions: Operations performed periodic manual draining of the drain line to the Turbine Building Sump until repairs could be performed, to preclude further release via this pathway.

The Turbine Building Sump is a monitored pathway.

Abnormal release file RAB0061 was created to document the release. The release volume was based on an engineering evaluation. Volume released was mimicked by creating RAB0061 as a release of 2 minutes, based on the relief being full open.

Activity concentrations were based on weekly sampling of the Steam Generators for Gamma Isotopic and tritium.

The dose consequences:

H3 5.15E+03 uCi 4.52E-05 mrem Result: The dose from the activity released represented a small percentage of the total dose and was a very small percentage of limits. The dose did not impose upon the health and safety of the public.

The event was discussed with the NRC Region 3 Radiation Protection (RP) Inspector, at the time of the event.

Page 3 of 8

40CFR190 COMPLIANCE The calculated dose from the release of radioactive materials in liquid or gaseous effluents did not exceed twice the limits of 10CFR50, Appendix I, therefore compliance with 40CFR190 is not required to be assessed, in this report.

SAMPLING. ANALYSIS AND LLD REQUIREMENTS The minimum sampling frequency and lower limit of detection (LLD) requirements, as specified in ODCM Tables 2.1 and 3.1 were not exceeded in 2008.

Analysis requirements, as specified in ODCM Table 2.1 and 3.1 were exceeded in 2008, as noted:

Composite samples for Quarter 1 were shipped to vendor for the performance of Sr-89, Sr-90 and Fe-59 analysis. These composites are in the form of liquid aliquots and particulate filters.

The vendor reported to Prairie Island Nuclear Generating Plant that the shipping container was significantly damaged in shipping and sample integrity was compromised. However, no radiological concern existed. Shipment was "exempt" by DOT criteria and no leakage outside the container was noted.

The vendor determined that only the Unit One Shield Building Ventilation Pathway particulate filters were compromised. Filters are shipped in planchets. Some of the planchets were crushed and filters were loose, while other filters and planchets remained intact. Of the 22 filters collected for composite, 5 were deemed intact.

Radiation Protection air sample records, ventilation effluent release samples and primary chemistry was assessed for the past year. It was determined that no reasonable expectation of atypical values was warranted. No significant/atypical conditions could be identified that would create an expectation that these filters would be greater than typical.

Corrective Actions:

1. The event was captured in the site's corrective action program to document the event and corrective actions taken (AR 01138552).
2. The event was determined to be a missed sample per H4, Offsite Dose Calculations Manual (ODCM), Table 3.1, Radioactive Gaseous Waste Sampling and Analysis Program.
3. The highest postulated value was used for the missing analysis based on:
a. The five intact filters were analyzed by the vendor.
b. The highest Sr-89 and Sr-90 for all ventilation pathways for a one year period was determined.
4. A robust repeat use shipping container was purchased for future composite shipping.

Page 4 of 8

MONITORING INSTRUMENTATION There were two (2) occurrences when less than the minimum required radioactive liquid and/or gaseous effluent monitoring instrumentation channels were operable as required by ODCM Tables 2.2 and 3.2, as noted:

1. Unit Two Turbine Building Sump Compositor The Unit Two Turbine Building Sump Compositor is defined as a process radiation monitor.

Operability requirements are defined by ODCM TABLE 2.2, Radioactive Liquid Effluent Monitoring Instrumentation. If the TBS Compositor is out of service and not restored within 30 days, an explanation must be included in the next Annual Radioactive Effluent Release Report, as to why this inoperability was not corrected in a timely manner.

The Unit Two Turbine Building Sump Compositor was declared out of service on December 27, 2007 at 06:30, due to a perceived failed timer: Delays in ordering and receiving parts exceeded 30 days. Once parts were obtained and work begun, it was discovered that it was a switch, not the timer in failure, causing additional delays.

The compositor was returned to service on February 11, 2008 at 12:00, for a total of 46 days 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> and '30 minutes out of service.

Compensatory sampling was performed during the out of service period, per ODCM Table 2.2.

2. R-35, Radwaste Building Ventilation Monitor R-35, Radwaste Building Ventilation Monitor is defined as a process radiation monitor.

Operability requirements are defined by ODCM Table 3.2, Radioactive Gaseous Effluent Monitoring Instrumentation. If R-35 is out of service and not restored within 30 days an explanation must be included in the next Annual Radioactive Release Report, as to why this inoperability was not corrected in a timely manner.

R-35 was declared out of service on October 13, 2008 at 23:15, due to Bistable causing a control board high radiation alarm when no high radiation condition existed. The receipt of parts was delayed.

The monitor was returned to service December 12, 2008 at 11:51 for a total of 59 days 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and 36 minutes out of service.

Radwaste Building Ventilation was not in service during the out of service period and no compensatory sampling was required.

Page 5 of 8

Doses to Individuals Due to Effluent Releases from the Independent Spent Fuel Storage Facility (ISFSI)

Zero (0) fuel casks were loaded and placed in the storage facility during the 2008 calendar year. The total number of casks in the ISFSI is twenty-four (24). There has been no release of radioactive effluents from the ISFSI.

CURRENT ODCM REVISION The Offsite Dose Calculation Manual was revised in 2008. The current revision is 22. The revision date is October 23, 2008. A copy is submitted with this year's report as Enclosure 4.

PROCESS CONTROL PROGRAM, The Process Control Program was revised in 2008. Current manual revision is 9. The revision date is April 15, 2008. A copy is submitted with this year's report as Enclosure 5.

Revisions to Process Control Program:

The following two abandoned processes were deleted from the procedure:

" Solidification of Liquid Waste Concentrates

" In-Container Solidification of Bead Resin The attachments that these abandoned processes referenced were also deleted:

  • Figure 1 Solid Radwaste Flow Diagram

" Attachment A Sample Verification Form

" Attachment B Sample Verification Form Page 6 of 8

Table 1 OFF-SITE RADIATION DOSE ASSESSMENT - PRAIRIE ISLAND PERIOD JANUARY throiu.h ....

EC E.M_.

.... . .....0....8.

1L k f P a.r 5 0 Ap~~

ui d el i s, f r a -nt f7te p ry va r

. G.A

...e=. ! _ ...... .e....

.... .e........

Maximum Site BEqoundary Gamma Air Dose (mrad) 3 18E--05 20 Max i mum Si te Boundary Beta Air Dose (mrad) 3,53E -03 40 Maximum Off -ite Dose to any organ (mrem)* 4,37E--02 30 Offshore Locat ion Gar ma Dose (mra d 1, 69f." 06 Total Body (morem) " 47E 03 (mrad), A ,r..'.03  ?:,fl OrqCn *.,) '-

Liqui Releases Maximum Off-site Dose.

Total [~odV (mrem) 1,64E--03 Maximum Off-site Dose3 Organ - ,_CI TRACT ('m,r, 7 ,37-- 03 I:

.. imit in Organ DoRA.f e Orqan - C.] TRACT (mr e m)

  • Ionq'~ Particulate, .1. J.3 1. and a3. tii um, Page 7 of 8

Table 2 OFF-SITE RADIATION DOSE ASSESSMENT - PRAIRIE ISLAND SUPPLEMENTAL INFORMATION PERIOD: JANUARY through DECEMBER 2007 Gaseous Releases Maximum Site Boundary Dose Location (From Building Vents)

Sector WNW Distance (miles) 0.4 Offshore Location Within Site Boundary 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 Liquid Releases Maximum Off-site Dose Location Downstream Pathway Fish Page 8 of 8

ENCLOSURE 2 ANNUAL RADIOACTIVE EFFLUENT REPORT SUPPLEMENTAL INFORMATION January 01, 2008 - December 31, 2008 9 pages follow

zuou? Annual Radioactive Effluent Report REV. 0 Page 1 of 9 Retention: Lifetime ANNUAL RADIOACTIVE EFFLUtENT RElPORT 01-A, N TO 3.TRE .08 SUPPLEWNTAL INFORIMTIO Facility: Prairie Island Nuclear Geheratihg- Plant Licensee: Northern States- Power Company.

License Numbers: DPR-42 & DPR-60

-A. .Regulatory Limits

1. Liquid Ef ffluents:"
a. The dose r dose .:commitment to an idividual ftrom radioactive materiain li,quid, effluents rel6 eased from thesite b1e limited t~o:

for the quarrter 3.0 mrem i" to the total body 10.0' m"rem to any organ for the year 6.0 mrem. to the total body 20.0 mrem to any organ

2. Gaseous Ef f I uents::
a. The dose rate due to radioactive .iMaterials released:in gaseous effluen:*ts from the si.-te: shal: be limited to:

noblea gasles - *50.0 mr~emi/year total body.

  • <3000 mr em/year skin 1-13.1, 1-133, H-3, LLP <1500 mrem/year to any organ,:
b. The. dose due to radioactive gaseous effluents released from the site shall, be limited to:

noble gases .<1-0 mrad,,/quarter gamma

<20 mrad/!qua rater beta

<-20 mrad/year gamma

<40 mrad/year beta 1-131, 1-133, H-3, LLP U15 mrem/quarter to any organ

<30 mrem/year to any organ

2008 Annual Radioactive Effluent Report Re v. 0 PAGE 2 B. Water Effluent Concentration

1. Fission and activation gases in gaseous releases:

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

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

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

.3. Liquid effluents for radionuclides other than dissolved or entrained 'gases:

10 CFR 2.0, 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 apprpoximations of total activity

1. Fission and activation gases Total Gem +25%

in gaseous releases: Nuclide Gem

2. Iodines in gaseous releases: Tota1 Gem +/-25%

Nu*clide Gem

3. Particulates in gaseous releases: Total Gem +/-25%

Nuclide Gem

4. Liquid effluents Total Gem +/-25%

Nuclide Gem E. Ma nual Revisions

1. Offsite Dose Calculations Manual latest Revision number:;___--

Revision date  : /_____"__

2008 ANNUAL RADIOACTIVE EFFLUENT REPORT REV. 0 PAGE 3 1.0 BATCH RELEASES (LIQUID)

QTR: 01 QTR: 02 QTR: 03 QTR' 04 1.1 NUMBER OF BATCH RELEASES 8.00E÷-01 2.20E+01 3.70E+01 3.90E+01 1.2 TOTAL TIME PERIOD (HRS) 1.55E+02 3.83E+01 6.67E+01 7.27E-01 1.3 MAXIMUM TIME PERIOD (MRS) 3.22E+00 2.05E+00 2.28E+00 4.07E+00 I-- ------ I-+ --

1.4 AVERAGE TIME PERIOD (HRS) 1.93E+00' 1.74E+00 I-I- + 1.80E+00 1.86E+00 1.5 MINIMUM TIME PERIOD (MRS) 1.50E+00} 1.57E+00 1.05E+00 9.17E-01 1.6 AVERAGE MISSISSIPPI RIVER FLOW (CFS) 8.52E+03. 4.07E+04 J 1.01E+04 j 1.02E+04

_ _ __ _1 I. L J 2.0 BATCH RELEASES (AIRBORNE)

QTR: 01 QTR: 02 QTR: 03 j QTR: 04 2.1 NUMBER OF BATCH RELEASES 3.50E+01 0.OOE+00 t4.00E+00 2.20E+01 2.2 TOTAL TIME PERIOD (MRS) 5.69E+02. 0.00E+00 1.71E+00 3.43E+02 2.3 MAXIMUM TIME PERIOD (HRS) 3.02E+01- 0.OOE+00 I 1.47E+00 I 2.60E+01 2.4 AVERAGE TIME PERIOD (MRS) 1.62E+01 0.OOE+00 4.26E-01 1.56E+011 2.5 MINIMUM TIME PERIOD (MRS) 1.17E-03'1 0.OOE+00 3.33E-02 6.97E-02 3.0 ABNORMAL RELEASES (LIQUID)

QTR: 01 QTRTR: 03 QTR: 04 3.1 NUMBER OF BATCH RELEASES 0.OOE+00 0.OOE+00 0.0OE+00 0.OOE+00 3.2 TOTAL ACTIVITY RELEASED (CI) 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 3.3 TOTAL TRITIUM RELEASED (CI) 0.00E+00 0.00E+00 0.O0E+00L 0.0E0 J 4.0 ABNORMAL RELEASES (AIRBORNE)

QTR: 01 QTR; 02 QTR: 03 QTR: 04 4.1 NUMBER OF BATCH RELEASES 1 0.OOE+00 0.OOE+00 1.00E+00 1.OOE+00 4.2 TOTAL ACTIVITY RELEASED (CI) 0-O0E+00 0.OOE+00 5.15E-03 J1.34E-01

2008 ANNUAL RADIOACTIVE EFFLUENT REPORT REV. 0 PAGE 4 TABLE IA GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES QTR" 01 OTRE 02 QTR: O QTR. 04 5.0 FISSION AND ACTIVATION GASES 5.1 TOTAL RELEASE (CI) 0.100E O 0. Go~~o . 67802 wE 0.O0E+00 f0. 00oE+oo0 0.0OE+0.0 5..33E-0*1 1

5.2 AVERAGE RELEASE RATE (UCI/SEC) 0. 00E+0.0 0.E00-E-ýo 0.00E+00 .. 53E-02 5.3 GAMMA DOSE (MRAD) 0.00E+00 0.00E4+00 0.00E+00 3.18E-054 5.4 BETA DOSE (MRAD) 5.5 PERCENT OF-GAMMA. TECH SPEC (%)

SI I I.

0.00E4-00 0O00E+00 0 .O:OE+4,00 0..O00E+00 0 j0.0.0°E+00OOE+0ý0 1.7- E-02

,3.18E-04 E.- }

5.6 PERCENT OF BETA TECH SPEC (%.) I f _ _ I1 I 6.0 IODINES 6.1 TOTAL 1-131 (CI) 3.27E-07 0.60O 0 .00E00

[f oIOOE+OO 1:O0.0E"05+

0.+00.0 00E+00 O0 : 0-00*E.

0 0E00

~1 "0E00 00 5ý31.. 7-6-0 9I 0.0.0500

-0 6.2 AVERAGE RELEASE RATE (UCI/SEC) 7.0 PARTICULATES 7.1 TOTAL RELEASE (CI) S3.27E-071 0.050E+00. 2.0051+00, I .3..-08 40.002+00, O.00gE+0,0: 10.0E+00 0-.00E+00j 7.2 AVERAGE RELEASE RATE (UCI/SEC). 4. 16.E-08 ..ooE+00 0-0E+00 6.76-09

5. 4E 0 ' __________I
  • 54 .- . _________

,.. 51 40 ______

3.0 Eý  :

8.0 TRITIUM 8.1 TOTAL RELEASE (CI) I. 4.0-*E+00 1.i99+0'0' I 1..985+00 j 2..3-95+00 I I . . .. I 8.2 AVERAGE RELEASE RATE (UCI/SEC.)

9.0 TOTAL IODINE, PARTICULATE AND TRITIVM (UCI/SEC). .1 z.*<*

5.1E *0.j .450 j .1-i I .450 10.0 DOSE FROM IODINE., LLP, AND TRITIUM, (MREM) 2.-50 02 3- S.8E-0-3 2 11.0 PERCENT OF TECH SPEC (%) 1.67E-01 2.I,3E.02 38.E-02 6.152-02 12.0 GROSS ALPHA (CI) 0 .002+00 0..000E+000 00.00E+00 ,1 0.OOE+00

2008. ANNUAL RADIOACTIVE EFFLUENT REPORT REV. 0 PAGE 5 TABLE IC GASEOUS EFFLUENTS - GROUND. LEVEL RELEASES (CI).

13.0 FISSION: AND ACTIVATION GASES CcYNTlNUOUS MODE BATCH MD NUCLIDE UNITS T 0.

Q R 0 3  : QTR. TR 03 TR: 0 KR-.85 ci .* 1I.4EO.[ 3. 98E-01 XE-133 CI. J 9.09E-05 4 36Eý04 TOTALS [ CI 0.OOE+00 0*.OE+0 I1 o D0E+O00 .34E-01 0..O0.E+00 0.OOO00 0OE+00 j. 3.98E-01 14.0 IODINES CONTINUOJU-S MODE ..B4ATCH. MODE SNcLIDoE TOTAL U . QTR: .0 1...

0 o. - " .O i

QT*R..02

". O; J- 0 311.

I. DIO9+

04 QTR.

01 QTR:

02.:

,iI 3 QTR....04 Q

  • LT°TA LSLILC.I!:° ...

7,."OT'°°+00": 0.o'o~oE+oo,. "0:.o0*:05+0 0.o.ooE+DOO o.OE+0o-.0 0:....- , *O.O*OE.+00

.-. 00'I 0..005.-0:0 .

- O~.0O**OE

2008 ANNUAL RADIOACTIVE EFF.,LUENT REPORTý REV. 0 TABLE IC GASEOUS EFFLUENTS -GROUND PAGE *6 LEVEL RELEAS'ES (,CONT1NU-ED) 15.0 PARTICULATES CONTINUOUS MýQDE:

NUCLIDE UNiTS QTR: BATCH -MODE 01 QTR:02 0 QTR: 03: QTR: 0*4. TR: 0 LQTR:~

02 O 'T 03 QT:0 c-5 CIý 3,02E-~07.

- -I:, I . ---

. . I*... I -  :* 5 I. .

E-.

NB-95 CI + D5 l . 2.49,E-08

.. . .. , t.

ITOTALS . .' ..

CI I .27E-07 0"-00 *0.0!E+0 0."O"E+.0.0 " .OOO+,0"

____ ___ ___ _______~iI__________

0 0.. ,-.. O.00*.0:+0 5..31E-08

  • __________J _______- -I

2008 ANNUAL RADIOACTIVE EFFLUENT REPORT REV.. 0 PAGE 7 TABLE IA LIQUID EFFLUENTS -SUMMATION OF ALL ýRELEAS)ES

.QTR:..01 QR Q'2R:

OTE 03 IQTR: .0:4 16.0 VOLUME OF WASTE.PRIOR TO DILbTION" (LITERS)

P 76E

' .2. :3;3.E 6-7 :2 7 Ot4-7 I.17E O07 17.0 VOLUME OF DILUTION WATER (LITERS)

I1.-35E+111.4E+1 .2.58E+11 1.86E+11 18.0 FISSION AND ACTIVATION PRODUCTS 18.1 TOTAL RELEASES W/0 H-3, RADGAPS, AL-PHA (CI) 18..2. AVERAGE -DILUTION CONC7EN.TRAT-ION (UCI0ML)

.F1 .7275-0l :6.1459E-i0,

.67E1o* * *.17-E-09 I I . -

19.0 .TRITIUM "

19.1 19.2 TOTAL RELEASE AVERAGE DILUTION (CI)-

CONCENTRATION (UCI/ML)

I.

9. 03E+O1 i-v A.

6.23E 7:,

" 2 " :"0___7_

__.23, 2.147-*0*7'

.1 1.05E-06 8. 665-07 20.0 DISSOLVED AND..ENTRAI.ND GASES

.i.

20.1. TOTAL RELEASE: (Cl2) i: 0.0 z + 0ý 1 77&-04. 1, 9:85-0:4 1" . ,- - .

20.,2 ' AVERAGE DILUTION CONCENTRATI.,ON. (UCI/ML). 6.875-ý13. 1. 0 6E- 1:2 0 00E+"0 0 0 . 00E+00"I 21.0 GROSS ALPHA (CI) L 0. ;OE+00, 0 00E+00 I

-I

.8*67*E--07 22 .0 TOTAL TRITIUM, FISSION & ACTIVATION PRODCTS (UCI/ML) 1. 05E-06 .6i24E-07 2.,49E-07

'I

2. 67SErnO 4 23.0. TOTAL BODY DOSE (MR'EM) 5,. 4,2E,.04 3. 05E,+-0,4 24 .0 CRITICAL.ORGAN.

24..1 DOSE (MREM) :I- 2. 63E-03 2 .. 75E-0. 21 ITRA.To:.3.

I:

24 .2 ORGAN G1 TRACT GI T2ECTa TOT BODY 1.G 50 25.0 PERCENT OF TECHNICAL SPECIFICATIONS LIMIT (%) 1.81E-.02 1f* -I.02E-0.2 26.0 PERCENT.OF CRITICAL ORGAN TECH. SPEC. LIMI (%T) 2.63E-'*"2 9.. 16*E-03.*E 1. -702 2.37E-02

2008 ANNUAL RADIOACTIVE EFFLUENT REPORT REV.- 0 PAGE 8 TABLE 2A LIQUID EFFLUENT-S- SUMMATION1 OF ALL REgEASRS (IC) 27.0 INDIVIDUAL LIQUID EFFLUENT CONTINUOUS MODE BATCH MODE NUCLIDS UNIT~S II I QTR: 01 iTRI QTR.04 QTR,,. 01 QTR; 02 QTR: 03 QTR: 04 AG-IIOM CI S5"5.3E-03-'" 1.09E-03 2.45E-03 8"17E-03 BE-7 F CI 1 1 8 8,0.E- 0S--

F 2.86E-06 F F CO-57 CI 9.44 E-.0S 3,.:74E0 3.;S7t-04_. 6. 76.E-05 CO-58 CI F 3.06E-02 F 9.53E-03 5.924E-02 F 3.S6E-02 CO-60 CI I-.

3.92E-0'03 57.3E-04 2.63E-03 3.09E-03 CR-51 CI 2 .19 E 9ý.8 2H4-04 1. 1,6E- 0 2.06E-01 CS-134 CIl .2-0

[2.-4E-06 CS-137 CI K -+ 4-3;E-0 62- F FE-55 CI FE-59 CII 3.30E-04.O- 5 3.12E 1.13E-04 32.07E-0 1-131 CI F F3.0,8E-0 5 FF 1-132 CI 763.12E706F0 1-133 CI I- F

~LA-i40 FCI] 9.522-03

.E-05 2.20E-04. l .3203.94°E-061I[

8.02E-06 9______

.16, E- 5 MN-54 CI F. 3 ..317.E-04 -I9.12E-O0 5 4.360E-0 5 -2.89E-041 NA-24 Cd F~~~~~ ______..j.

7 1 E-05 NB-95 CI

-97 CI

, F 1 .

I3.45E-032 49.E5806

.0..E F

.15E-034 22E-0 6 5.822S-06 F3.94-E-06 F 2.09E-23

¢* o RH-105 CI F .

i- . .. +- S7. 6 OE-0*6 RU-105 *C I

_________' I_________________ F8.37E-05F SB-122 CI F.F5. 07E-05 6 .0 42E-05 SB-124. CI 7.04E-04 1 1.16-4F 5.0E-04 3 .310E-02 SB-125 [CI 3.16E-,0 2 F7.31E-03 F3.882E-02 88. 222- 02F SB-126 CI F4.OOE-06 1. 6~.7E-06 j5.292-.0 4

2008 ANNUAL RADIOACTIVE" EFFLUENT REPORT R EV.: :0 P-AGE 9 TABLE 2.A, LIQU-ID-EFFLUTENTS SUKKATIOXN OF A^LL RLES ]RONIPE) 27.0 INDIVI:DUAL LIQUID EFFLV'ENT CO0NTI*NHO:U'S" MOD*E""

BATCB I:-MODE;.

F-Nu CLIDE" UNITS 0QTR: o04 .t QTR~O3.[ QTR.:. :0-.2- QTR: 03 QTrR:

WSE-75.

CI 4-S .. " ... i r*. . -t 6.;37E-04 j 4.625E05 3.5E-0"5 2.4E-,04 ZR-92 CIT. 6 -12E -'O 1. 2 5E- 05S,j 3-1:1 E-0O5 1 . 2-4F14 TE 123M _____ _______F 1 36*-4

.. QA I. 5..43E-04 TE-125M CI -4. -o .- 2-~0 226 E- 03.

2.271-0o6. 67E-0,06*:1 5.-89E-06 TE-132 I . . . . . . . . .. . . . . . . . . ... F--. { ...

} . F 1.*.

"+ . .

W-187 CI .__ ___ 8.54E-O5 8.24E-06, 8.86-06 4.02:-OS 4.87-05 ClI ~

4 k ZN-6 5 ZR-95 ~CIl____ . ____ __

}

8.47522-04_-1.,: 6.3:2E.04:2 S2.67E:-0:6 _____

TOTALS .1CI 0 O0E4-00 0.0OE+00 0.OE0 6.05i-0:6 1*.725-0 [ 6.455-*02 1.20-5-01: j4.055*0.O1 I ~ ~ ~ L I___ "Et__ :0__________

P+_____

28.0 DISSOLVED: AND EN TRA Il4ED CASES CONTINUOUS MODE BATCH MODE NUCLIDE UNITTS QTýR 01* QTR:0 Q-TR: 03 QTR: 04 F-ýR-0.1 QTR: 02 .:0 QTR:: 04ý

1. 7.77-E04 XE--31M ,1 CI 9' + 0 - I - - I j XE-1 3'3 CI 1. SSE 1..9ý3 E-.04 XE-135. CI em÷o I- . .-. . -.j.. .j .

T*OTALS - CI K. 8 - - 5 _. .-- -0.. . . , . -1.0 [

". I. .8 4

ENCLOSURE3 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS January 01, 2008 - December 31, 2008 7 pages follow

PINGP 753, Rev. 8 Ref. RPIP 1314 Page 1 of 7 Doc. Type/Sub Type: RPC/DATA Retention: Lifetime +

PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1/01/08-12/31/08 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 (NOT IRRADIATED FUEL)

1. Solid Waste Total Volumes and Total Curie Quantities:

................ PERI0DP.. E 8T7J0TGAL,' 0SO TYPEý F WASTE UNITSSRROR6ý% TOTALS VOL A. Resinsm 1.02E+01 179.4 ft3 3.59E+02 Ci 1.58E+00 2.50E+01 B. Dry-Compacted m _ _

ft 3 __ _ _ _ __ _ _ _ _

Ci C. Non-Compacted m 2.54E+02 1280 ftW 8.96E+03 Ci 5.76E-01 2.50E+01 D. Filter Media ms3 1.02E+01 179.4 ft 3.59E+02 Ci 3.23E+00 2.50E+01 S. Other (furnish description) m3 3.62E+01 1280 Combined package, charcoal and ftW 1.28E+03 DAW Ci 5.36E-02 2.50E+01 _

The solid waste information provided in this report is the volume NOTE: and activity of the low-level waste leaving the Prairie Island site.

No allowance is made for off-site volume reduction prior to disposal.

PINGP 753, Rev. 8 Page 2 of 7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1/01/08-12/31/08 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 (NOT IRRADIATED FUEL) [continued]

2. Principal Radionuclide Composition by Type of Waste:

(Bold letter designation from Page 1)

TYPE Percent %

Abundance Nuclide (0.00E0)

A

  • Fe-55 4.38E+01 Co-58 1.50E+00 Co-60 1.60E+01 Percent Cutoff 1% Ni-63 2.58E+01 Sb-1 25 2.05E+00 Cs-137 1.78E+00 Cr-51 C 1.50E+00 Fe-55 5.71E+01 Co-58 1.22E+01 Co-60 7.33E+00 Ni-63 1.10E+01 Zr-95 2.76E+00 Nb-95 4.60E+00
  • = Inferred - Not Measured on Site

PINGP 753, Rev. 8 Page 3 of 7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1101108-12131108 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 (NOT IRRADIATED FUEL) [continued]

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

(Bold letter designation from Page 1)

TYPE Percent %

Abundance Nuclide (0.00E0)

S

  • Fe-55 1.32E+01 Co-58 3.99E+00 Co-60 1.63E+00 Percent Cutoff 1% " Ni-63 2.33E+00 Nb-95 1.44E+00 D

" Ni-63 2.58E+01 Sb-125 2.05E+00 Cs-1 37 1.78E+00

  • = Inferred - Not Measured on Site

PINGP 753, Rev. 8 Page 4 of 7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1/01108-12131108 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 (NOT IRRADIATED FUEL) [continued]

3. Solid Waste Disposition:

Number of Shipments Mode Destination I Hittman Transport Barnwell Disposal Facility Services 3 Hittman Transport Studsvik Processing services Facility, LLC 4 StudsvikLogistics, StudsvikRACE, LLC LLC

PINGP 753, Rev. 8 Page 5 of 7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1101108-12131108 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 (NOT IRRADIATED FUEL).[continued]

4. Shipping Container and Solidification Method:

Disposal No. Volume Activity Type of Container Solidif.

(Ft 3Im3) (Ci) Waste Code Code 08-014 2560/72.5 0.133 C,S L N/A 08-028 2560/72.5 0.243 C L N/A 08-032 179.4/5.08 0.748 A L N/A 08-036 2560/72.5 0.149 C L N/A 08-038 179.4/5.08 1.770 D L N/A 08-039 179.4/5.08 1.460 D L N/A 08-040 179.4/5.08 0.836 A L N/A 08-045 2560/72.5 0.105 C L N/A TOTA 8 11000/310 5.44 LS 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. 8 Page 6 of 7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1/01108-12131108 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS B. IRRADIATED FUEL SHIPMENTS (DISPOSITION)

Number of Shipments Mode Destination 0

I

PINGP 753, Rev. 8 Page 7 of 7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1101108-12/31108 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS C. PROCESS CONTROL PROGRAM CHANGES TITLE: Process Control for Solidification/Dewatering of Radioactive Waste from Liquid Systems Current Revision Number: 9 Effective Date: 4/15/2008 If the effective date of the PCP is within the period covered by this report, NOTE: then a description and justification of the changes to the PCP is required H4 (ODCM) 8.1 m. Attach the sidelined pages to this report.

Changes/Justification:

Deleted abandoned processes from procedure. Minor editorial changes.

/1 Reviewed By: Reviewed By: Date: - .3 / 0 ý J/0A

Retrieved from "https://kanterella.com/w/index.php?title=L-PI-09-055,_2008_Annual_Radioactive_Effluent_Report_and_Offsite_Dose_Calculation_Manual&oldid=2653388"