ML12138A136
| ML12138A136 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 04/27/2012 |
| From: | Weber T Arizona Public Service Co, Pinnacle West Capital Corp |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 102-06515-TNW/RAS | |
| Download: ML12138A136 (79) | |
Text
Technical Specification 5.6.2 A subsidiaryof Pinnacle West Capital Corporation Thomas N.Weber Mail Station 7636 Palo Verde Nuclear Department Leader Tel. 623-393-5764 PO Box 52034 Generating Station Regulatory Affairs Fax 623-393-5442 Phoenix, Arizona 85072-2034 V
102-06515-TNW/RAS April 27, 2012 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Dear Sir:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2, and 3 Docket Nos. STN 50-528/5291530 Annual Radiological Environmental Operating Report 2011 In accordance with PVNGS Technical Specification (TS) 5.6.2, enclosed please find the Annual Radiological Environmental Operating Report for 2011.
No commitments are being made to the NRC in this letter. Should you need further information regarding this submittal, please contact Russell A. Stroud, Licensing Section Leader, at (623) 393-5111.
Sincerely, 62l A . U)d')tbd-2 I TNW/RAS/hsc Enclosure cc: E. E. Collins Jr. NRC Region IV Regional Administrator B. K. Singal NRC NRR Project Manager for PVNGS L. K. Gibson NRC NRR Project Manager J. R. Hall NRC NRR Senior Project Manager M. A. Brown NRC Senior Resident Inspector for PVNGS A. V. Godwin Arizona Radiation Regulatory Agency (ARRA)
T. Morales Arizona Radiation Regulatory Agency (ARRA)
A member of the STARS (Strategic Teaming and Resource Sharing) Alliance I1Z~
Callaway
- Comanche Peak
- Diablo Canyon
- Palo Verde
- San Onofre
- South Texas
- Wolf Creek A4~
ENCLOSURE Units 1, 2, and 3 Annual Radiological Environmental Operating Report 2011
NUCLEAR GENERATING STATION ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 2011
(
Reference:
RCTSAI 1643, Legacy Item No. 036843.01)
D.Digitally signed by Drinovsky, Louis Drinovsky, J(Z33699)
DN: n=Drinovsky, Louis J(Z33699)
Louis X 3699 )Date:
R9)Reason:lam the author ofthis document 2012.04.05 14:26:57 -07'00' Prepared by:
Gray, Thomas Digitally signed by Gray, Thomas 5(Z9961 0)
DN: cn=Gray, Thomas S(Z9961 0)
Reason: I have reviewed this document Reviewed by:.
S(Z9961 0) Date: 2012.04.05 14:45'28 -07'00' Digitally signed by Moeller, Carl Moeller, Carl (Z091119)
DN: cn=Moeller, Carl (Z09119)
Approved by: (Z09119) Date: 2012.04.11 10:24:21 -07'00' Director, Radiation Protection
TABLE OF CONTENTrS
- 1. IN TRO D U CTION ............. ................... ................................................... I....... 3...................
3.
- 2. DESCRIPTION OF THE MONITORING PROGRAM .......... ........................... .. 4
- 2.1. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ................................................... 4 2.2. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM CHANGES.FOR 2011 .................... 4 2.3. REMP DEVIATIONS/ABNORMAL EVENTS
SUMMARY
....................... ............... 5 2.4. G ROUND W ATER PROTECTION .................... ..................... .................. .. .................. "5 5.
- 3. SAM PLE CO LLECTION PRO GRAM ....... .......... ..............: ........................................................... 12
- 3. 1. W ATER ....................................................................................................................................... 12 3.2. V EGETATION .............................................................................................................................. 12 3.3. M ILK .......................................................................................................................................... 12 3.4. A IR ............................................................................................................................................. 12 3.5. SLUDGE AND SEDIM ENT ......................................................................................................... 13
- 4. A NA LY TICA L PRO CED U RES .............................................................................................. 13 4.1. A IR PAR TICULATE ...................................................................................................................... 13 4.2. A IRBORNE RADIGIODIN E...: ..................................................................................................... 13 4.3. M ILK .......................................................................................................................................... 13 4.4. V EGETATION .............................................................................................................................. 14 4.5. SLUDGE/SEDIM ENT .................................................................................................................... 14 4.6. W ATER ....................................................................................................................................... 14 4.7. SOIL ........................................................................................................................................... 15
- 5. N U CLEA R IN STRU M EN TA TION ....................................................................................... 15 5.1. G AM MA SPECTROM ETER ......................................................................................................... 15 5.2. LIQUID SCINTILLATION SPECTROM ETER ................................................................................. 15 5.3. GAS FLOW PROPORTIONAL COUNTER .................................................................................... 15
- 6. ISOTOPIC DETECTION LIMITS AND REPORTING CRITERIA ..................................... 16 6.1. LOW ER LIM ITS OF D ETECTION ................................................................................................ 16 6.2. D ATA REPORTING CRITERIA .................................................................................................... 16 6.3. LLD AND REPORTING C RITERIA O VERVIEW ........................................................................... 17
- 7. INTERLABORATORY COMPARISON PROGRAM .......................................................... 22 7.1. Q UALITY CONTROL PROGRA M ................................................................................................ 22 7.2. INTERCOMPARISON RESULTS .................................................................................................. 22
- 8. DATA INTERPRETATIONS AND CONCLUSIONS .......................................................... 26 8.1. A IR PARTICULATES .................................................................................................................... 26 8.2. A IRBORNE RADIOIODINE ............................................................................................................ 26 8.3. V EGETATION .............................................................................................................................. 27 8.4. M ILK .......................................................................................................................................... 27 8.5. D RINKING W ATER ...................................................................................................................... 27 8.6. G ROUND W ATER ........................................................................................................................ 27 8.7. SURFACE W ATER ....................................................................................................................... 27 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 ii
TABLE OF CONTENTS 8.8. SLUD G E AN D SED IM EN T ............................................................................................................. 28 8.9 . D A TA T R EN D S ............................................................................................................................ 28
- 9. . THERMOLUMINESCENT DOSIMETER (TLD) RESULTS AND DATA..... .......... 55
- 10. LAND USE CENSUS....: .... ................. ' I ........................ ..... 61 10 .1. IN TRO D U CTIO N ........................................................................................................ ... 1.........
10.2;.* C EN SU S RESO LTS :.!..... .......................................
2.. '............ .... ......................................... 6 1
- 11.
SUMMARY
AND CONCLUSIONS ........................................ 66
- 12. REFEREN CES ....... ...... ...... . ......... .......... . .... 71
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- . - - - PVNGS ANNUAL_RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2011
LIST OF TABLES TABLE 2.1 SAMPLE COLLECTION LOCATIONS . .7 TABLE 2.2 SAMPLE COLLECTION SCHEDULE ......... ............................................................... 8 TABLE 2.3 SUMMARIES OF REMP DEVIATIONS/ABNORMAL EVENTS .... :.. ............ 9 TABLE 6.1 ODCM REQUIRED LOWER LIMITS OF DETECTION (A PRIORI). . . .. 19 TABLE 6.2 ODCM REQUIRED REPORTING LEVELS ............................................................. 20 TABLE 6.3 TYPICAL M DA VALUES -. ;......... ............................ ............................................... 21 TABLE 7.1 INTERLABORATORY COMPARISON RESULTS ................................. ........................... 23 TABLE 8.1-PARTICULATE GROSS BETA IN.AIR,, I ST -;2NP QUARTER ................. ............ 29 TABLE 8.2 PARTICULATE GROSS BETA.IN AIR3 ... , . ............... . 30 TABLE 8.3 GAMMA IN AIR FILTER COMPOSITES ..,.. ... ...... ....................... 31 TABLE 8.4 AIR PARTICULATE GAMMA DUE TO FUKUSHI*A RELEASES......................... .32 TABLE 8.5 RADIOIODINE IN AIR, 1ST - 2' QUARTER ........................ ;. ....s ................... 33 A*..I .*" 4TH Q UýA R E . ... ,................................... ,. .. .......
TABLE 8.6 RADIOIODINE.INA1ZR RTER . 34 TABLE 8.7 VEGET.ATON ......... .. . ...... " ........
TABLE 8.8 MILK ... ,........ .... 36 TABLE 8.9 D RIN KIN G W ATER ....................................................................................................... 37 TA BLE 8.10 GRO UND W ATER ........................................................................................................ 39 TA BLE 8.11 SURFA CE W A TER ....................................................................................................... 40 TABLE 8.12 SLUDGE/SEDIM EN T .................................................................................................. 44 TABLE 8.13 HARD-TO-DETECT RADIONUCLIDE RESULTS ................................................... 47 TA BLE 9.1 TLD SITE LO CA TION S ................................................................................................... 56 TABLE 9.2 ENVIRONMENTAL TLD RESULTS .............................................................................. 58 TA BLE 10.1 LAN D U SE CEN SU S ..................................................................................................... 62 TABLE 11. 1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL S U M M A R Y ............................................................................................................................................... 67 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 iv
LIST OF FIGURES FIGURE 2.1 REM P SAM PLE SITES - M AP (0-10 miles) ................................................................... 10 FIGURE 2.2 REMP SAM PLE SITES- MAP (10-35 miles) ...... .............................. ;....... 1...
11.............11 FIGURE 8.1 GROSS BETA IN AIR, lSt-2nd Quarter, ......................................................................... ;.48 FIGURE. 8.2. GROSS BETA, IN AIR, 3 r- 4 th Quarter: ...... :49........................... ! ........................... 49 FIGURE 8.3 HISTORICAL GROSS BETA IN AIR, (WEEKLY SYSTEM AVERAGES) ......... 50 FIGURE 8.4 HISTORICAL GROSS BETA IN AIR (ANNUAL SITE TO SITE COMPARISONS),
CO M PA RE D TO PRE-O P ....................................... ................................
. ... ...................... 51 FIGURE 8.5 GROSS BETA? IN DRINKING WATER ............ ............ ;............. ..... : ............ 52 FIGURE 8.6 EVAPORATION POND'TRITIIUMACTIVITY - , "'+ ...... ' 53 FIGURE 8:7 SEDIMENTATION BASIN 2-Cs-137.'.. ' .... .......................... .54 FIGUREg9.1 NETWik"'ElqVIR*bNE:NrAI TLD ExPOSUR PATES .-......... .59 FIGURE 9.2 ENVIRONMENTAL TLD COMPARISON -'PRE-6PERlATIONAL VS 201 i ......... 60 FIGURE 10:1 HISTORICAL COMPARISON 'OF NtAREST RESIDENT DiOS ........... .4..63 FIGURE 10.2 HISTORICAL COMPARISON"OF NEAREST MILK ANIMAL DOSE'....... .. 4 FIGURE 10.3 HISTORICAL COMPARISONOF NEAREST GARDENDOSE..................... 65
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". " , .. I ' o PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011
ABSTRACT' The Radiological Environmental Monitoring Program (REMP) is an ongoing program conducted by Arizona Public Service Company (APS) for the Palo Verde Nuclear Generating Station (PVNGS).
Various types of environmental samples are collected near PVNGS and analyzed for plant related radionuclide concentrations. . . ..
During 2011, the following categories of samples were collected by APS:
- Broad leaf vegetation
- Ground water . , ,. . . .
- Drinking water
- Surface water
- Airborne particulate and radioiodine
" Goat milk
- Sludge and sediment Thermoluminescent dosimeters (TLDs) were used to measure environmental gamma radiation. The Environmental TLD program is also conducted by APS.
The Arizona Radiation Regulatory Agency (ARRA) performs radiochemistry analyses on various duplicate samples provided to them by APS. Samples analyzed by ARRA include onsite samples from the Reservoirs, Evaporation Ponds, and two (2) deep wells. Offsite samples analyzed by ARRA include two (2) local resident wells. ARtRA also performs air sampling at seven (7) offsite locations identical to APS and maintains approximately fifty (50) environmental TLD monitoring 'ocations, eighteen (18) of which are duplicates of APS locations.
A comparison of pre-operational and operational data indicates no changes to environmental radiation levels.
The Fukushima-Daiichi nuclear plant in Japan suffered major damage due to a natural disaster.
REMP samples obtained from air, vegetation, and milk samples in March and April indicated elevated radionuclides that were attributed to reactor releases. It was determined, and is well established across the nuclear industry, that these radionuclides were the result of radiological releases from the Fukushima-Daiichi plant, and were not due to the operation of the PVNGS.
These conclusions are based on the following facts:
(1) The quantities of radioactive airborne effluents from PVNGS during 2011 did not increase significantly compared to previous years.
(2) Prior and subsequent REMP sample results have not detected the presence of these radionuclides in PVNGS samples.
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 1
(3) The radionuclides detected in the indicator samples were also identified in control samples.
(4) Discussion with other US nuclear plants identified similar sample results.
(5) A review of USEPA RADNET data during the same time period identified similar sample results.,
REMP samples containing radiological materials attributable to Fukushima-Daiichi releases are identified as such on data tables.
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... PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 2
OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
' I.- . *.. -
- 1. Introduction .. . :'; -
This report presents the results of the operational radiological environmental monitoring program conducted by Arizona 'Public S'rvice Company (APS). The' Radiol6gical Environmental Monitoring Program (REMP) was established for the Palo Verde Nuclear Generating Station (PVNGS) by APS in 1979.
This report contains the measurements and findings for 201 L'All references are specifically identified in Section 12. . . ....
The REMP provides representative measurements of rdia'ti6at anp0 of. radiokctive materials in those exposure pathways. and 'for, those,: radionuChide of.mem ers oh tfat .I::leadj. to. the . highest*ih;s.
pdtentil radiatin tntalrditoprogram e
exposures members of ulli'..; ':. reulting
.""cposures,,:
of .. i from the statin.,operation.") "
Thisgmonitorig ippendix Ixto 10CFR Part 50 and thierby supplements the radiological effluent Tonitorinn program by verifying th the measurable concentrations of radioactive materials and levels of radiation are not higier than expected' on, the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for this monitori~g prograr* is provided by the US Nuclear ýegulatory Commission (USNRC) in their
,Ra'diological "NoembrAssessment 9',9 Brancf:Feciial n~c ori~lif'to NREG"'o.sitio13l)
A es'uits fimto f :.e' ,EM 'el' Revision to evaluate1,
- November j1979 ,n chio~tq iecnto l~~iii ntiirifeitab IýMoiiP g Reiso 1, sources of elevated levels of radioactivity in the envir6onent .g.Eamospheric nuclear detonations or abnormal plant releases).
he Use s 'euensures that.cnanges in the use ofareas I at and
- d beyond by' t6e1, siteof boundary e reslt thi census. are identified and that modifications to *the REMP are madeif requi'ed by the results of this census.
This census satisfies the requirements of Section IV.B. 6f Appendix I to 10 CFR Part 50.
The Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and ýaccuracy of the measureirienta of radioactive hiaterial'in :environmental sample matrices are performed as part. of the quality assurance program for, environmental monitoring in order to demonstrate thatthe results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.
Results of the PVNGS pre-operational envii'onmental monitoring :program are presented in Reference 1. '- .
The initial criticality of Unit 1 occurred May 25, 1985.'Initial criticality for Units 2 and 3 were April 18, 1986, and October 25, 1987, respectively. PVNGS operational fihdings (historical) are presented in Reference 2.
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 3
- 2. Description of the Monitoring Program APS and vendor organizations performed the pre-operational radiological environmental monitoring program between 1979 and 1985. APS and vendors continued~the program into the operational phase.
.2 1.,Radiological. Environmental Monitoring Program The assessnient program consists of routine measurements' of enviroimnental gamma radiation and of radionuclide concentrations in media such as air, ground water, drinking water, surface water, vegetation, milk, sludge, and sediment.
Samples were collected by APS at the monitoring sites shown in .igures ,2.1 and"2.2. The specific sample types, sampling locations, and sampling frequencies, as. set forth in the
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6' Offsifeb6se' C'aJIii'latidn Man~uidai (ODCM),,the 'Ref~ee'nce 4; Ai'&priesente'd in 'Tables 2.1, 2.2 and 9.1. Additional onsite saminifYg (oitside scope of the ODCM) is Performed to supplement the ,*.EMP, All results-are i ie this report Routine sample analyses wiere perfonied at tle. onsite Cenirgl C'iýemistry. Laboratory and Operating Unit S. laboratores.' Anaraunusfesnalyses hdt. detect were peirfmrme oby'Eberline 3
..Analy'tical ervices. .. " "
i....nwrfnmnt~gamma
. . radiation measuremrents were performed'by 'APS using TLDs at fnTQm t n rc eVN6$' P-osimetty Departmient is accredited by the "eS Nation4Cl Voluntary LabordatoIry'Accredtation' Program (NN:LAP) to perform ionizing
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_t ~ Acrdth n .. : pe or*inzn radiation dosimeter ana yses.
Jn addition to monitoring environmental media, a land use census is performed annually to identify thenearest, imilk animals, residents, -adgardenS. This informiati6n -is used to evaluate the potentiil dose to'meffibers of the public for those expostire pathways that are
" in dicated. " '" " .. ""
2.2. .Radiological Environmental Monitoring ProgramChanges for 2011
- .. * ' . ' '"** .... ' ' ': ' ] 26 n~l eremade as a esult of the The, following change's implement.ODCM Revis ion 26 and were m' as a rs t annual Land Use Census (reference Corrective Action"Program document CRDR 3824797);
Replaced Site #47 vegetation lpcation ....
>' Replaced Site #51 goat milk location'
> Deleted Site #52 goat milk location
> Changed designation of goat milk location at Site #54 from supplemental to
. required Refer to Table 2.1 for a description of all current sample locations (except TLDs).
- -" PVNGS
.::,, ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 Z..L.,I, 4 : ' /
2.3. REMP Deviations/Abnormal Events Summary During calendar year 2011, there were fi&', (5) deviations/Abnormal events with regard to the monitoring program. Refer to .Table 2.3 for more detIail and any cdrrective actions taken. " : ' -
- 1. The 45 acre Reservoir exceeded the quarterly 1-131 reporting level of 20 pCi/liter. ""
- 2. Air. sample site #14A equipment was ,out of *ervice due to'a power outaige.
- 3. Air, veg tationf, and 'milk samples'. indicated radi'dnuclide'activity due to the
'l.ukushima-Daiichi planit releases.
4 . Resident well water Site #49 no long'er available.
- 5. One Interlaboratory comparison sample analysis failed the acceptance criteria (Cs- 134 in water).
2.4. Ground Water Protection (Follow-up from past reports)
NOTE:
Although not part of the REMP, this information is being provided due to the identification of low level tritium in the onsite environs (within the Radiological Controlled Area) and heightened sensitivity to communicate the potential to affect ground water.
On February 15, 2006 Palo Verde personnel observed water leakage into the Unit 2 Essential Pipe Density Tunnel thaough1 the 'B' Spray Pond (SP) supply line penetration seal (documented on Corrective Action Program Significant CRDR No. 2869959). Low level tritium was identified in this water. It has been determined that the water was not the result of leakage from a plant system, but more likely due to previous operating conditions combined with precipitation. The investigation revealed that Unit 3 had a similar situation.
PVNGS initiated OE22651 and follow-up OE24237 to describe the incident of low level tritium at Unit 3 since the concentration exceeded a reporting threshold.
Several monitoring wells have been installed to monitor the subsurface water and shallow aquifer at Units 1, 2, and 3. These wells are sampled monthly and quarterly for chemical and radiological parameters. The State of Arizona Aquifer Protection Permit (Area-Wide)
No. P-100388 (APP) provides agreed upon monitoring parameters and reporting thresholds. Sample results for the shallow aquifer wells are reported in the PVNGS Annual Radioactive Effluent Release Report (ARERR). The State of Arizona APP provides specific regulatory criteria for ground water protection. PVNGS is working with the Arizona Department of Environmental Quality (ADEQ) to prevent this tritiated water from affecting the local aquifer.
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 5
PVNGS has implemekted' a ground water protection initiative developed by the Nuclear Energy Insti1tye (NEI). The implementation of this initiative, NEI 07-07 (Industry Ground Water Protection Initiative - Final Guidance Document, August 2007), provides added assurance thaf ground water will not be adversely affected by PVNGS operations.
Three subsuirface. s'ampiles were'obtained, one each from Units 2 and 3 tritium monitoring wells, and one from the.shallow aquifer outside of the Unit 1 radiological controlled area (RCA). These sarpples were analyzed for hard-to-detect radionuclides (e.g. C-14, Fe-55, Ni=63, Sr-90) as a verification that there are no.underground leaks from plant systems that may affect ground water. All results * *
- were
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to Table 8.13 for,sample results.
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PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -. 201.1 1.. v%, ! , 1;'6
Table 2.1 SAMPLE COLLECTION LOCATIONS SAMPLE SITE # SAMPLE TYPE LOCATION LOCATION DESCRIPTION 4 air E16 APS Office 6A* air SSE13 Old US 80 7A air ESE3 Arlington School 14A air NNE2 371 Ave. and Buckeye-Salome Rd.
15 air NE2 NE Site Boundary 17A air E3 351st Ave.
21 air $3W.. . .
S3, S Site Boundary 29 air W Site Boundary 35 air NN8 Tonopah 40 air !N2 Transmission Rd 46 drinking water local resident
- 47 vegetation local resident (new location as of September) 48 drinking water local resident t 49
- drinking water N2 (b). Local resident (new location as of December) 51 milk NINE3,(b) local resident- goats (new location as of September) 53* NE30 milk local resident- goats 54 milk NNE4 local resident-goats (supplemental) 55 drinking water SW3 local resident (supplemental) 57 ! ground water ONSITE
- Well 27ddc 58 ground water Well 34abb 59 surface water Evaporation Pond 1 60
- surface water ONSITE:. 85 acre Reservoir 61 surface water 45 acre Reservoir 62* vegetation ONSITE I Commercial farm 63 surface water ONSITE Evaporation Pond 2 64 surface water Evaporation Pond 3 NOTES:
- Designates a control site (a) Distances and direction are from the center-line of Unit 2 containment and rounded to the nearest mile (b) Denotes a change in location or a new sample location Air sample sites designated with the letter 'A' are sites that have the same site number as a TLD location, but are not in the same location (e.g. site #6 TLD location is different from site #6A air sample location; site #4 TLD location is the same as site #4 air sample location)
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 7
Table .2.2 SAMPLE COLLECTION SCHEDULE SAMPLE AIR AIRBORNE GROUND DRINKING SURFACE SITE # PARTICULATE MILK RADIOIODINE VEGETATION WA TER WA TER WA TER 4 W W 6A W W 7A W w 14A W .
15 W W; 17A w 21 W ,..W 29 W !'.W '
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47 .- :'4)... " a . J.:, A.A.
48 W 49 ::" .. -* :- ' }'. ) *'"t' ,. ,! , " XV,**'r.
W 51 M/AA ' . .
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54 M/AA ;. .
55 .. w 57.. '. ' .
58 .... ,. Q 59 : " , '.., '".. Q!
60 Q 61 Q 62 M/AA 63 Q 64 Q W = WEEKLY ;' :, M/AA - MONTHLY AS.AVAILABLE Q = QUARTERLY
............ .. PNGS .,(A ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011
-.. 8' . .
TABLE 2.3 SUMMARIES OF REMP DEVIATIONS/ABNORMAL EVENTS Deviation/Abnormal Event Actions taken
- 1. The 45 acre Reservoir exceeded 1. The initial sample result was 27 - 10 pCi/liter. The the quarterly I-131 reporting level verification analysis result was 24 - 10 pCi/liter. The of 20 pCi/liter. elevated 1-131 concentration is due to radiopharmaceutical I7131 that is present in the reclaimed sewage water that' supplies Circulating Water and is not the result of plant effluents. Refer to Corrective Action Program document CRDR 3739206 for the evaluation of excebding -the ODCM Reporting Level. No additional actions are necessary.
- 2. Air sample site #14A equipment. 2. Corrective Action Program documents CRDR 3574902 was out of service due to a power .,.and. Corrective .Maintenance Work Order 3573475 were outage. initiated to !ociUnent and correct the loss of power to the sampling: equipment, between 12/28/10 and 1/13/11. The cause of.iLhe"outage was storm related. The air sample
- equ~ip,*-ent was returnd'to normal operation once the
. damage to the power lines wVas corrected. No additional
.acticnsri aier4ecessary.
- 3. Air, vegetation, and milk sample 3. 'SSeveral,,REMP sample.'media indicated man-made indicated radionuclide activity. due. radionuclidesý-ieginning in March. The radioactivity was to 'the Fukushima-Daiichi plant, S- attributed to releases from the damaged' Fukushima-
- Daiichi..nuc!earplants -in Japan and are not the result of releases.
PVNGS:,effluents. Specific data are included within Tables 8.1, 8.3.,.8.4, 8.5, 8.7, and 8.8 of this report.
Corrective Action Program documents CRDR 3739206 andCRDR 3812184 provide evaluations for REMP data that indicate radioactivity resulting from the Fukushima-Daiichi releases. No additional actions are necessary.
- 4. Resident well water Site #49 no 4. The resident at Site #49 moved in September and the longer available. land was repossessed. A replacement well water location was determined and is in the same relative distance/direction from the site. Refer to Corrective Action Program document CRDR 3882110.
- 5. One Interlaboratory comparison 5. Corrective Action Program document CRDR 3980064 sample analysis failed the was initiated. Subsequent analysis of this sample (3 more acceptance criteria (Cs- 134 in times) passed the acceptance, criteria. Another water). interlaboratory comparison sample (E8164-1 11) was ordered and passedthe acceptance criteria. The low result for Cs-134 was attributed to coincidence. summing that sometimes occurs with low activity samples analyzed using a high efficiency detector. No additional actions are necessary.
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 9
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KEY TO MAP SarmpldSite *D , i Slh'6o "A Air ,ý: I. Airstrip -, REMP SAMPLE SITES
. V Vegetation..
Y. .I .. , -, 0-10 MILES W Water I I T. TLD M Milk, .
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2010
','10
51 NE I.....
ESE 35 ..miles SE 5 miles 10 miles /35 miles i miles .: miles f." KEY TO MAP Sample Site CD Sc6hool -1 A Air Airstripg V-Vegetation REMP SAMPLE SITES W Water 10-35 MILES SSE T TLD M Milk I -
.1
[
3.1. Water Weekly samples were collected from four (4) residence wells for monthly and quarterly composites. Samples were collected in one-gallon~contiiners and 500 ml glass bottles. The samples were analyzed for gross beta, gamma emitting radionuclides and tritium.
Quarterly grab samples were collected from the 45 arid 85 acre Reservoirs, Evaporation Ponds 1/2A/3A/3B, and onsite wells 34abb and 27ddq, Samples were -collected in one-gallon containers and 500 ml glass bottles. Samples were analyzed for gamma emitting radionuclides and tritium.
'Treated sewage effluent from the City of PhoMinix was: sampled as a weekly composite at the onsite Water Reclamation Facility (WRF), and analyzed -for gamniý emitting radibnuclides. A monthly compos'ie was analyzed for tritium. -. . -
3.2. Vegetation .
m"vaible,as aalbe and Vegetation samples werewercollected mothly,* n were analyzed for gamma emitting eailzdfrgmaeitn
".adionuclides.
3.36.. Milk i .
Goat milk samples were collected monthly, 'as available, and were analyzed for gamma emitting radionuclides, including low level 1`,131:.
3.4; -Air-..................
Air particulate filters and charcoal cartridges were collected at ten (10) sites on a weekly basis.
Particulate filters were analyzed for gross beta. Charcoal cartridges were analyzed for 1-131.
Particulate filters were composited quarterly, by .location, and analyzed for gamma emitting radionuclides.
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 12 ...
3.5. Sludge and Sediment Sludge samples were obtained weekly from the WRF waste centrifuge (whenever the plant was operational) and analyzed for gamma emitting radionuclides.
Cooling tower sludge was analyzed for gamma emitting r'adionuclides prior to disposal in the WRF sludge landfill. . ... '
- 4. Analytical Procedures The procedures described in this report are those used by APS to routinely analyze samples.
4.1. Air Particulate,.. ., ;.'
4.1.1. Gross Beta A giass fiber filter sample is placed in a stainless steel pianchet and counted for gross beta activity utilizing a low background gas flow proportional counter.
- 4.1.2. Gamma.Spectroscopy. .. , ,..
The glass fiber filters are counted on a multcannel equipped with an HPGe detector. The resulting spectrum is analyzed by a computer for specific radionuclides.
4.2. Airborne Radioiodine .
The charcoal cartridge is counted on a multichannel anialyzer equipped with an HPGe detector. The resulting spectrum is analyzed by a, computer for I 131..,
4.3. Milk 4.3.1. Gamma Spectroscopy The sample is placed in a plastic marinelli beaker and counted on a multichannel analyzer equipped with an HPGe detector. The resulting spectrum is analyzed by a computer for specific radionuclides.
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 13
4.4. Vegetation S, 4.4.1. Gamma Spectroscopy The sample is pureed in a food processor, placed in a one liter plastic mriarinelli beaker, weighed, .and counted on a multichannel analyzer equipped with an HPGe detector. The resulting spectrum is'analyzed by a computer' for ipecific radionuclides.
4.5. Sludge/Sediment 4.5.1. Gamma Spectroscopy The wet samfple is plac'ed in a one-liter plastic marifielli 'e'aker, Weighed, and counted on a multichannel analyzer equipped with an HPGe detector. The resulting spectrum is analyzed by a computer for specific radionuclides..
4.6. Water 4.61. ap ectrosco The sample is placed in a one-liter plastic marinelli beaker and counted on a multichannel analyzer equipped with an HPGe detect&. *.;The: iteultin 'solectrum 'is :analyzed by a computer for specific radionuclides.
4.6!. Tr~itlu'm The sample is evaluated to determine the appropmiate method of preparation prior to counting. If the sample contains suspended solids or is turbid, it may be filtered, distilled, and/or de-ibnized, as appropriate. Eight (8) milliliters of. sample. are mixed with fifteen (15) milliliters of liquid scintillation cocktail. The mixture: is dark adapted and counted for tritium activity using a liquid scintillation counting system.
. .. ... -.....-.- P-VNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011
.14
4.6.3. Gross Beta A 200-250 milliliter sample is placed in a beaker. Five (5) milliliters of concentrated nitric (HNO 3) acid is added and the sample is evaporated down to about twenty (20) milliliters. The remaining sample is transferred to a stainklss st6el planchet. The sample is
- heated to dryness and counted for gross beta in a gas flow proportional counter.
4.7.ý Soil' " . ' *. ,%..
4.7.1. Gamma Spectroscopy The samples are sieved, placed in a one-liter plastic mariinelli beaker, and weighed. The
- samplesare then counted on a multichannel analyzer equipped with an HPGe detector. The
!,resulting spectrum is analyzed by a computer for speceic radionuclides.
- 5. Nuclear Instrumentation 5.1. Gamma Spectrometer The Canberra Gamma Spectrometer consists of a Can'berra'System equipped with HPGe detectors having resolutions of 1.73 keV and 1.88 keV (as determined by full width half max with an energy of 0.5 keV per channel) and respective efficiencies o12 15 A and- 38.4/a (as deterrmined by the manufacturer with Co-60). The Canberra * . ,.System I, is used
', l. ';I 01 for all1. 1'.gamma t *'Jý,.;it' " '1 ' ,-couting.
. Thd system uses Canberra developed software to search, iden'tify, and OU ythe peakss ot interest.
5.2. Liquid Scintillation Spectrometer!,
A Beckman LS-6500 Liquid Scintillation: Counteris used for tritium determinations, The system background averages approximately 12-16 cpm with. a counting efficiency of approximately 40%
using a quenched standard. *...
5.3. Gas Flow Proportional Counter The Tennelec S5E is a low background gas flow proportional counter for gross beta analysis. The system contains an automatic sample changer capable of counting 50 samples in succession.
Average beta background count rate is about 1-2 cpm with a beta efficiency of approximately 30%
for Cs-137.
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 15
- 6. Isotopic Detection Limits and Reporting Criteria 6.1. Lower Limits ofDetection The lower limits of detectioi (LLD) and the method for calculation are specified in the PVNGS ODCM, Reference 4. The ODCM required a priori LLDs are presented in Table 6.1. For reference, a priori LLDs are indicated at the top of data tables for samples having requircd LLD values.
6.2.'. . . .Data l l" Reporting f~ h*
Criteria t , *eu ,Ie'g~
t e r ' "m
, u m" ." ." , . ; d + .
S'All re'sults,that ae'greater thah ihe Min ium iDetectable Activity (MDA)' (a posteriori LLD) are reported as positive activity With its associated 2&"c&ýinting error. All results, that are less than the MDA are reported as less than values at the associated MDA. for example, if the MDA is 12 pCi/liter, the value is reported as <12. "' '" . . .
Typical MDA values are presented in Table 6.3. ,'2" ..7*`, -' '. . " : . a
,Occasionally,the PVNGSODCM .apriori LLDs may not be achieved as a result of:
- j. ,j ' - Ba cKgro u n d tl c a m s , . . . .. ~ i ;.. i....* ,. -,: . , ...
Bak h41iictuapiions nayy '1ls.. ' .d . .. .. . . .
- " 1'4re presence ot.interferingadioucnIes- "
S el absoip'tlo" correc:lor;s.
- Decay corrections for short half-life radionuclides Other uncontrollable circumstances , , .. . ,*
In the'seiiis tadnes, the cbntribufirig factors x~ill'be; noted in' the tabfe where the data are presented.
'A -*summai-y 'ofdeiati6nis/abnormal events is presented in Table 2.3 and includes a description of any sample results that did not meet a priori LLD requirements. "
. .+ ... ,
+: '",'* .; .
- '.. . . . . . . . . . . F.".;' .. . . ; '*
P.VNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011
,. "' : I,* .. 16 "
6.3. LLD and Reporting Criteria Overview Making a reasonable estimate of the limits of detection for a counting procedure or a radiochemical method is usually complicated by the presence of significant background. It'must be considered that the background or blank is not a fixed value but that a series of replicates would be normally
, distributed.: The desired .net activity .is the difference between the gross and background activity distributions. .The* interpretation of this difference, becomes a :problem. if the two distributions
- intersect as indicated in the diagram; . . ' . .
'BACKGROUND GROSS It
.... ,,, . .. C.i 4....
If a sufficient number of replicate analyses are run, it is expected that the results would fall in a normal Gau'ssian ditsibution': Standard' 9tatistics9 0*Wlow' anestimate of the, probability of any particular de'4atioii 'froifi th&' mean' value: It is co.rifotio Iptaetice, to, report the,.mean 'one or two standard deviations as the result. In routine analysis, such replicationis-not carf'ied:out,. and it is not possible to report a Gaussian standard deviation. With counting procedures, however, it is possible to estimate a Poisson standatd deviation dirctly-frcom tae count: Data tare; commonly i-epbrted as the measured value +/- one or two Poisson standard deviations. The reported values are then considered to give some 'indication of the range :in whichithe tru_'vai-L;e riight be expected to-occur.
A LLD is the smallest amount of sample activity that will::yield a ne*. count for which there is colffidence at a predetermined 'level., that, activity is preseent. LLDs ',are. calculated values for individual radionuclides based on a number of different factors including sample size, counting efficiency and background count rate of the instrument, the background and sample counting time, the decay time, and the chemical recovery of the analytical procedures. A minimum detectable activity value (MDA) is the smallest amount of activity that can be detected in an actual sample and uses the values obtained from the instrument and outcome of the analytical process. Therefore, the MDA values may differ from the calculated LLD values if the sample size and chemical recovery, decay values, or the instrument efficiency, background, or count time differed from those used in the LLD calculation.
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 17
The factors governing the calculation of the LLD and MDA values are discussed below:
- 1. Sample Size
- 2. Counting Efficiency.
The fundamental quantity in the measurement -of a radioactive, substance is the: number of disintegrations per -unit time. As with most physical measurements in analytical chemistry, an absolute measurement of the disintegration rate is seldom possible, rather it is necessary to compare the sample with one or more standards. The standards determine the counter efficiency that may then be used to converts sample counts per minute (cpm) to disintegrations per minute (dpm).
- 3. Background Count Rate Any counter will show a certain counting rate without a sample in position. This background counting rate comes fron several sources: 1) natural environmental radiation from the surrounding materials, 2) cosmic radiation, and 3).,the natural radioactivity in the counter material itself. The background counting rate will depend on the amounts of these types of radiation and the sensitivity of the counter to the radiation...... " .. . -
- 4. Background and Sample Counting Time j ~ '~ 3 . ) ( J' H E ** ) 1 i,- * . . i ... . .
,,;The 'amount; Mftieujideyvoted tQ4l oointing of,,thexaclqg.und d.elneds onithe, .level of activity
,* t. -being measured);h genera1,- wit-.]w 1 leyt stime sho.ld he abot -mples, equal to that devoted
.1';
, + ..-ito co u n ti hg .:a s~ mple ;.,:jj :,-.,-1.. : ; ;,j?.) . :i ,- . n* *, ,i , .* , , . ! j , , , .l+ : , *: , ,
-. 5..:Time Interval between SampleCollection and .ounting h. ., ,. .
Decay- measurements are useful ,in .identifying certain short-lived nuclides, The disintegration constant is one of the basic characteristics of a specific radionuclide and is readily determined, if the half-life is .sufficiently rshort. To. ensure the,.required ...LL~s are achi9ved, appropriate decay correc.tion.i values are used,,to account for .radi~oactive.,decay during transit.,time and sample
, ,.ocessing-. . . , .
.. ... . * ,. r.'
.. .+:' * '
- " 18ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011
Table 6.1 ODCM REQUIRED LOWER LIMITS OF DETECTION (apriort)
AIRBORNE ANALYSIS/ WATER.' PARTICULATE or MILK. VEGETATION NUCLIDE (pCiter.-...) GAS (pci/m3 ) .(pCi/liter) . (pCi/kg, wet)
Gross Beta 4 .. 0... 01 . ... i " I __ _
H-3 ........... 2000* . ...
.............. IF ...............
I M n-54 [. 15 i. ..... ____ __.
Fe-59 30 .................. 1. " " _l, ' ':
4]
Co-58,60 15 _ _ _ _ _1 . ..._. . _1_...
Zn-65 30 . . 7_..
... 1F_ "" __........ . _"
Zr-95 30 . _ _._ _ I Nb-95 __[15[-
1-131 [ 1"* [ 0.07 1' 60 Cs-134" [ 15 3/4 [ 0.05 [ 15 - 60-Cs-137 [. 18_ ". 0.06 80"_
Ba-140 -[ 60 J . 60
[ La-140 15 :F- 15 NOTES:
- If no drinking water pathway exists, a value of 3000 pCi/liter may be used.
- If no drinking water pathway exists, a value of 15 pCQ/!itemay be used. ::
This list does not mean that only these nuclides are to be detected and reported. Other peaks that are measurable and identifiable, together with the above nuclides, shall also be identified and reported.
PVNGS, ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2011
'19
, ,Table 6.2 ODCM REQUIRED REPORTING LEVELS 1 ý'
AIRBORNE ANALYSIS/ WATER PARTICULATE MILK VEGETATION NUCLIDE (pCi/liter) or GAS (pCi/m) __.. (pCi/kg, wet)
FCI/iter).
_j _. 0-,000* _ _ _ _ _ _
..Mn-54 1_,000 Co-58 il lOOt I _ _
300 F
.. . . . . .. ... .. . ..... 30.....0........
Zr/Nb-95
.... 40_0 . . "" . . .. .... .
1-!31_. 2*t 09 3. - - 00.
Cs-!'34 30 10 . 60 - 1,000,.*
Cs-13,7 50- .. 20 ,. T7 70 ,. 2,000 Ba/Lart.40 -'200, :.- c, 300,., f,..
NOTES: i
- For drinking water samples. This is a 40CFR141 value. If no drinking water pathway exists, a value of 30,000 pCi/liter may be used.
- If no drinking water pathway exists, a reporting level of 20 pCi/liter may be used.
" .
- f.
The values in this table are quarterly dVera!e v*lues, as stated in the ODCM.
B 15 a. -~
- . . . I. . .
- - .. .' ' '-; ,-*.PVNGS RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011
- ' " ' * ++ 2'0ANNUAL '
Table 6.3 TYPICAL MDA VALUES AIRBORNE ANALYSIS/ WATER MILK PARTICULATE or VEGETATION NUCLIDE' (pCi/litei/l] .(pC'liter) . GAS (pCi//m3 ) . (pCi/kg,Jwet) I Gross. Betfa 18 .8 ..
1 7'- 0.002'
[7. I...-.. ..... ... . ..... '".
Fe-59 "' 19 ' . J
. ' ý.." " / ..
Co-60 F 13 Zn-65 '. ... . .F726. _ .____ ,. _ _ _
Zr-95 F 19 ...........
1i-13 F
- 1. .10 I 1 _ i 0.04 , .3 --
Cs-134 10 1 00.02b ., 38 .
Cs-137 11 1 0.03b ,.52 Ba-140 f 37 [ 3 K ___" __________
La-140 12 [ 1 NOTES: -".1 2's V' t a - low level 1-131 is'not required sine there is no drinkinigwater pathway b - Based on 433 in3 , the normal weekly sample volume PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 21
- 7. Interlaboratory Comparison Program 7.1. Quality Control Program
,APS, maintains an extensive QA/QC. Program to provide assurance that samples. are, collected, handled, tracked, and ahalyzed,. to specified requirements. This program includes appropriate elements of USNRC Regulatory Guide 4.15, Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams and the Environment, Rev. 1.'Included in the program are procedures for sample collection, preparation and tracking, sample analysis, equipment calibration and checks, and ongoing participation in an interlaboratory comparison program. Duplicate/replicate samples are analyzed to verify analytical precision and sample methodology. Comprehensive data reviews are performed including trending of data where appropriate.
During 2011, APS analyzed the following sample types under the- interlaboratory comparison program;
- Beta/Gamma/ in Air Filtq .
S1-131 in Air oBeta in Water
- Gamma in Water 1;.I
- Tritium in Water
- Gamma in Milk 7.2. Intercomparison Results APS participates in a crosscheck program using vendor supplied blind radionuclide samples.
Results for the interlaboratory comnparison program are presented in Table 7.1.
-* S"- .' ' . ** ; .. '1*. " , t Z' * * . ; ' . .*.; ' , .. . . )
. . PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 S .-. ,. ' .22
TABLE 7.1 INTERLABORATORY COMPARISON RESULTS Type. - Type Nuclide Value Value Error..*. Resolution* Ratio' Accept/Reject Mixed Milk Gamma 1-131 1.89E+01 1.88E+01 1.76E+00 11 0.99 Accept E8030-1 11 Ce-141 2.17E+01 2.71E+01 2.01E+00 13 1.25 . Accept Cr-51 7.38E+01 .6.63E+01- 8.62E+00 8 0.90 Accept Cs-134. 4.18E+01 .3.77E4-01 2.39E+00 16 0.90 Accept Cs-137. 3.71E+01 .3.75E+01 2.45E+00 15 1.01 Accept Co-58 3.18E+01 3.23E+01 2.24E+00 14 1.02 Accept Mn-54 4.92E+01 5.48E+01 3.41E+00 16 1.11 Accept Fe-59 1.79E+01 2.07E+01 2.59E+00. 8 1.16 Accept Zn-65 5.88E+01 7.50E+0 1 5.05E+,00 15 1.28 Accept Co-60 5.12E+01 5.15Ei 01, 2.89E+00...: 18 1.01 Accept Mixed Air Gamma E8027-111 Ce-141 7.19E+01. 7.16E+01 3,48E+000. 21 1.00 Accept Cr-51 2.44E+02 ,2.58E,+q2 ;1.73E+0i_. 15 1.06 Accept Cs-134,. 1.38E+02 ,1.22E+Q02ý *6.10E+00., 20..:. 0.88 Accept Cs-137; 1.23E+02 1.31E+02. 6.70E+00. 20 1.07 Accept Co-58 1.05E+02 L11E+,Q2.)-58E+00_ý. 19 1.06 Accept Mn-54 1.63E+02 .1.67E+jq2 _,8.i10E+09Q 21 1.02 Accept Fe-59 5.91E+0._, ?.P7.8E1P.tQl..1E 0.:J. 12 -.. 1.20 Accept Zn-65 1.95E+02, 2A14Eq24,.,1j3E+01.-,, 19 1.10 Accept Co-60 - 1.69E+02 .. 68E+,02. 7.,60E+90 22 3.99 Accept Mixed Water - Gamma 'Ce-141 9.15E+01, 9.88E+01 9.59E+00 10 1.08..- -Accept E8026-111 Cr-51 3.10E+02 2.77E+02 5.36E&F01 5 0.89.; Accep -
Cs-134 1.76E+02 1.48E+02 1.16E+01 13 0.84' Accept Cs-137 1.56E+02 1.61E+02 1.17E+01 14 1.03 Acqept Co-58 1.34E+02 1.26E+02 1.04E+01 12" "0.94' A c*pt Mn-54 2.07E+02 1.95E+02 1.43E+01 14 0.94 Accept Fe-59 7.52E+01 6.94E+01 1.32E+01 5 0.92. Accept Zn-65 2.47E+02 2.47E+02 2.49E+01 10 1.00; Accept Co-60 2.15E+02 2.20E+02 1.31E+01 17 1.02. Accept 1-131 8.01E+01 7.20E+01 9.41E+00 8 0.90 Accept Air Cartridge 1-131 8.05E+01 8.25E+01 5.58E+00 15 1.02 Accept E8028-111 ,. .. . t'.
Air Gross Beta 7.18E+01 8.73E+01 2.20E+00 40 1.02 Accept E8029-111 Water Tritium 9.01E+03 7.67E+03 2.64E+02 29 0.85 Accept E8119-111 Water Gross Beta 2.49E+02 3.17E+02 6.49E+00 49 1.27 Accept E8118-111 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 23
TABLE 7.1 INTERLABORATORY COMPARISON RESULTS Sample Analysis Knowri PVNGS 1 Sigma Type pe e **Nuclide '-.Value Value . Error Resolution* Ratio Accept/Reject Mixed Air" Gamma E8166-111 Cr-51 3.07E+02 3.01E+-b2 2.80E+01 11 0.98 Accept Cs-134 9.30E+01 8.62E+01 5.16E+00 17 0.93 Accept Cs-137 1.14E+02 1.09E+02 6.50E+00 17 0.96 Accept Co-58 1.20E+02' 1.21E'+02 &.80E+00 18 1.01 Accept Mn-54' 1.31E+02.: 1.30E402 7.50E+00 17 0.99 Accept Fe-59 9.95E+01 9.,84E+01 8.75E+00 11 0.99 Accept
- Zn-65 1.58E&02 "1.61E-02 `1.10E+01 15 1.02 Accept Co-60. 1.47E'62..-' 1.46E4-'02 8.IOE+00 -18 . 0.99 Accept Mixed .
Water Gamma E8164-111 Cr-51
- 5.66E, -6.37E+' "02, '84E1- 171.12 Ae Cs-134r 1.71E4-02" i.66E+02 6.'80E+00 24 0.97 Accept Cs-137 t 2.10EQO0"2.21E-i02 "8.20E+ .:0 27 1.05 Accept
...": 'Co-58
"*":"*:"" Mn-54 ';': 2.21E','62- 2.20E+02" 2.1E9E'" = ' 8.60E+00 * "" 26 : 1.00 Accept
.59E2.41E-2"" 9.kOE"-0Ob f 26 1.07 Accept Fe-59 1.83E0ý2'"1.96E+02 11..0E+01 - 18 1.07 Accept Zn-65 2.91Ei-- 15 E402"-i"-37E+01 23 1.08 Accept Co-60 2.70E÷0t' 2.84E;02' 1.01E+01-': 28 1.05 Accept
. - ?. 1-131 8.87E 6-1.iil.00E'+02 6.O0E÷00.. 17 . ' 1.13 Accept Air ,,. Cartridge
- . 1-131 ., 8.97EQl.+,ý,1OOE.+02. ,4,10E+00 24 1.12 Accept E8165-111 -..
calculated from PVNGS value/1 sigma error value NRC Acceptance >
Criteria"' ,, .-. ., * , ', *-
Resolufi6o Ratio -) ' :1 4-7 0.5-2.0' 8-5 :" 0.6-1.66 16-50 0.75-1.33 " "51-200 0.80-1.25
>2i00 0.85-1.18 ,. .
From NRC Inspection Manual, procedure 84750, "Radioactive Waste Systems; Water Chemistry; Confirmatory Measurements
'- - . .... ,PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011
.24'
TABLE 7.1 INTERLABORATORY COMPARISON RESULTS Sample . Analysis . I . :., .. . . . i .-
Type .. Type . Nuclide PVNGS Value Assigned Value Acceptance Limit 2 Results Water Tritium H-3 6860 7620 6600 - 8370 Accept RAD 86 ERA PT Study . .
Water Gamma Ba-133 50,5 , 51.6 42.5- 57.2 Accept Cs-1 34 68.3 84.1 ' 6*8.9 - 92.5 Not Acce'pt 3 Cs'-7' Cq-60 . 10104 109 109 98.
98.11-122
-122 Accept Accept Zn-65" '50.4 52..'8 46.3-'64:8 .- Accepot RAD 80ERAPTStud ' ,
':'Tritium . .. .H-3. 13100,i,, i2.." 1 '9900-22500 , Accept Water Gross Beta .58.4- 146 ;Accept Filter Gross Beta 91.2 69.5 428-102 Accept MRAD-014 ERA PTStudy' ., ' - " - ' .. " .
The ERA assigned values are established per the guidelines contained in the National Environmental Laboratory Accreditation Conference (NELAC) program criteria as applicable.
2 "Acceptance Limits" have, been calculated per ERA's Standard Operting. Proced"re for the Generation of, Performance Acceptance Limits:
Corrective Action Program document CRDR 3980064 was initiated. Subsequent analysis of this; samplei(3'more times) passed the acceptance criteria. Another inter;aboratory comparison sample (E8164-1 11) was ordered and passed acceptance criteria. The low result for Cs-134 was attributed to coincidence summing that sometimes occurs with low activity samples analyzed using a high efficiency detector. -
.' "' i. , i ' .1 "' ! " , L . . "'
4' , . , . .
(,. .'; * ; . 4. . . . . .. .
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 25
- 8. Data Interpretations and Conclusions Associated with the analytical process are potential random and systematic errors. Systematic errors can be caused by instruimenft malfunctions;' incomplete precipitation, backscattering, and self-absorption: Random errors are beyond the control of the analyst.
Efforts are made to minimize both systematic and random errors in the data reported. Systematic errors are minimized by performing reviews throughout the analysis. For example, instruments are checked routinely with radioactive sources, and recovery and self-absorption factors based on individual sample analyses are Mqinrporated into the calculation equations where necessai-y. Randdm errors are reduced by comparing all data jto historical datai for the same site and performinig comparisons between analytical results when available. In addition, when data do not appear to match historical results, analyses may be rerun on a separate aliquot. Qf-,the sample to verify the presence ofjihe activity. The acceptance of data is dependent upon the results of quality control samples and is part of the data review process for: all analytical results.
The "plus or nminus val uIe" reported'"Vilfi each analytiaT result repf,ýsents the, counting error associated with the result afid gives the 95% confid9nce (2(y) interVal around the data.
Most samples contain iadioactivity associated with natural background/cosniiic' radioactivity (e.gI K-40, Th-234, and Be-7). Gross beta results for drinking water and air are due t9-natural background. Gamma emitting radionuclides, which can be a-ttribuited t6 natiral backgroiund sources; afe not indicated in this Resulfs dii rt fi *Af l- a iilyed duti-g 2011 are presented inthe f0jlowing sections;., , , , . . .:.*;,..... . . . F' 8.1. Air Par'i'ulates :
Weekly gross beta results, in quarterly format, are presented in Tables 8.1 and 8.2. Gross beta activity at indicator locations ranged from 0.016 to 0.372 pCi/m 3. This range is atypical and due to airborne releases from the Fukushima-Daiichi plants in Japan as discussed previously. Samples from the control location identified similar results. The associated counting error ranged from 0.001 to 0.004 pCi/m 3. Mean quarterly activity is normally calculated using weekly activity over a thirteen (13) week period. Also presented in the tables are the weekly mean values of all the sites as well as the percent relative standard deviation (RSD %)for the data.
Tables 8.3 and 8.4 display the results of gamma spectroscopy on the weekly and quarterly composite samples. Cs-134, Cs-137, 1-131, 1-132, and Te-132 were identified on particulate samples. The presence of man-made radionuclides on particulate filters is atypical and due to airborne releases from the Fukushima-Daiichi plants in Japan as discussed previously.
8.2. Airborne Radioiodine Tables 8.5 and 8.6 present the quarterly radioiodine results. Radioiodine was identified during a three-week period between March 15 and April 5. The radioiodine concentration ranged from 0.037 to 1.258 pCi/mi3 at indicator and control locations. The identification of radioiodine is atypical and due to airborne releases from the Fukushima-Daiichi plants in Japan as discussed previously.
- * - ......PVNGS. ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 26
8.3. Vegetation Table 8.7 presents gamma isotopic: data'for the vegetation' samlles. One 'sample firm the control
, location indicated 1-131 at a concentration of 53 pCi/kg on March 24 1. This was the same time period that airborne samples also conftained 1-13 1, Cs-134, Cs-137, Te-132,' and 1-.132. There were no indicator samples available in 2011. ýThe identificatio;i of 1-131 is atypical and due to airborne releases from the Fukughima-Daiichii plantts in Jhpan as discussed previously..'
8.4. Milk, ,
-Table 8.8 presents gamma, isotopic data for, the goat milk s~amples. Two samples from the control location and.two samples from an, indicator, location had 1-131 during the same time period as the airborne samples (airborne. samples also, contained.; Cs-13.4,,.Cs-137, Te-1.3:2,.:and 1-132). The concentration of 1-131 ranged from 1.3 to 6 pCi/liter. One indicator sample indicated Cs-134 and Cs-137 in the range of 1.5 to 2.0 pCi/liter. All goats that provide milk for the REMP are fed stored feed (hay) and are not pastured. Hay from this location was sampled and-indicated Cs'i37 at a concentration of 13 pCi/kg. The identification of 1-131, Cs-134, and Cs-137 in milk is atypical and due to airborne releases from the Fukushima-Daiidhi pfaiits in Japan as discussed previously.
8.5.,. Drinking Water 5. ....
. .. .. . . . . . I ' :i.'*.b*.,:, .i
- A, * '. "
Samples were analyzed for gross beta, tritium, and gamma emitting radionucli.des. Results of these analyses are presented in Table 8.9. No tritium or gamma emitting radionuclides were detected in any samples. GrossPbeto activity. ranged from less than..detectableto aohigh ,f 8.4 pCi/liter. The gross beta activity is attributable to natural (background), radioactiy e.paterials, 8.6. Ground Water Ground water samples were analyzed from two onsite wells (regional aquifer) for tritium and gamma emitting'radionuclid~s. Resuits 6btained fromn the analysis of the s*'mples are presented in Table 8.10: , . _ :A,,.
No tritium or gamifna emitting radionucliides'were observed in any of the saniples.
8.7. Surface Water Surface water samples from the Reservoirs and Evaporation Ponds were analyzed for tritium and gamma emitting radionuclides. The two Reservoirs contain processed sewvage water from the City of Phoenix and are approximately 45 and 85 acres in size. The three Evaporation Ponds receive mostly circulating water from main turbine condenser.cooling ard are about 200-250 acres each.
Sample results are presented in Table 8.11. 1-13 1 was observed in Evaporationpond 2A in one (1) sample (18 pCi/liter) and in one (1) of the Reservoir samples (27 pCi/liter). 1-131 in these surface water locations is a result of radiopharmaceutical 1-131 in the Phoenix sewage effluent and is not attributable to plant effluents. ,,-
'Tritium was routinely -observed in the Evaporation Ponds. The highest concentration was 956 pCi/liter. Tritium was not detected in the Reservoirs. The tritium identified in the Evaporation Ponds has been attributed to permitted plant gaseous effluent releases and secondary plant liquid PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 27
discharges (e.g. condensate overboard discharge, secondary side steam generator drains, secondary plant sumps, demineralizer regeneration waste). The tritium concentrations were compared to historical values and are considered typical for the Evaporation Ponds.
WRF Influent (Phoenix sewage effluent containing radiopharmaceutical 1-131) samples collected by the WRF were anal*rzed, for gamma, emitting radionuclides and tritium. The results, presented in Table 8.11, demonstrate that I-131 was .observed routinely. The 1-131 concentration ranged from 9 to 51 pCi/liter. None'of the samples analyzed indicated the presence of tritium.
Table 8.11 also presents gamma spectroscopy and tritium measurements of samples collected from Sedimentation Basin 2. This basin collects rain water from site runoff and was dry for most of the
'year. Low concentrations. of tritium were identified in three (3) of'five (5) samples ranging from 291 t6 425 pCi/liter. The tritiumwas attributed to rain washout-of plant gaseous effluent releases.
- -No'gam.ha emitting radiohublideswere observed in the samples;., 1,
" i .'b 1, I. Y 8.8. Sludge anlt,Sedimet,,, Wf Y; '
ý.JR,wwa Sludge samples were obtained from the WRF centrifuge and analyzed by gamma spectroscopy.
1-131 activity in the sludge is consistent with historical values"'and;s'previously'discussed, is due to radiopharmaceuticals in the WRF Influent. The 1-131 concentration ranged from 178 to a.I,f" ,,.
- n 1..'y*, as " " 1 : . '-, r .
.. .. I 1'W alsso identifeie.--in the sludge ifti One sample')At 35: pCi/kg Awas It previously establihhed that Iki 1 '1s i stud in'the 'Pho11ni area as-a!radiopharmaceutical. Sample results can be found in Table 8.12.
8.8.2. Cooling Tower sludge Sludge/sediment originating from the Unit 2 and Unit 3 Cooling Towers and Circulating Water canals was disposed of in the WRF sludge landfill during 2011. Low levels of Co-60, Cs-134, and Cs-137 were identified in the sludge. The Co-60 and Cs-137 activity can be attributed to the ,1993 Unit 2,steam generator tube rupture, event. The Cs-134 is atypical and due to airborne releases from the Fukushima-Daiichi plants in Japan as discussed previously. Sample results can be found in Table 8.12.
8.8.3. Sedimentation Basin 2 sediment Sediment samples w'eiIe corlleted from Sedimentition Basin 2. This basin collects storm water ruinoff from the site draffiage didlces. Low le',el Cs-137 v'as identified in these samples. The results are consistent with histonical 'valuesand ard attributed to previous atmospheric bomb testing. Samplejresults can be found in Table 8.12. Refer to Figure 8.7 for a historical trend
". . h ; :I ' : !. " -: ,.. * .
.ý . . , . ,.-
8.9. Data Trends Figures 8.1-8.7 present data in graphical format. Historical data are displayed for comparison where practical..
TABLE 8.1 PARTICULATE GROSS BETA IN AIR 1st - 2 nd QUARTER ODCM required samples denoted 3 by
- units are pCi/m 1st Quarter (control).
START STOP Site Site - Site - Site Site Site Site --Site Site - Site RSD Week # DATE DATE 4 6A* 7A 14A* 15* 17A 21 29" 35 40* Mean (%)
1 28-Dec-10 4-Jan- Il 0.036 0.034 0.033 oosa . 0..034 0.034 .0.029 0.032 0.033 0.031 0.033 6.2 2 4-Jan- 11 Sli-Jan-Il 0.051 0.054 .0.053, -,oosa* 0.053 0.054 .0.054 0.056 0.053 0.055 0.054 2.6 3 I l-Jan-l I 18-Jan- Il 0.043 .0.042 0.041.. OOS .0038 0.039 0.038 0.041 0.039 0.039 0.040 4.5 4 18-Jan-I l 25-Jan- 1I 0.040 *0.039 9.035 0.031 'p,0.032 0.033 ,0.031 0.033 0:031 0.036 0.034 9.7 5 25-Jan-l I -Feb-1i 0.042 0.041 0.040 0.038 ,, i,0:040. 0.039 0.039 0.041 .0.039 0.040 0.040 3.0 6 1-Feb- 11 8-Feb- Il 0.050 0.047 0.040 09:041 .,0.042 0.045 0.043 .0.040 :0.043 0.039 0.043 8.1 7 8-Feb- Il 15-Feb-Il " 0.037 ,0.033 '.0.032 , 0:034 - 0.030
- 0.031 0.033 0.036 ..0.033 0.031 0.033 6.7 8 15-Feb- 11 22-Feb- 11 0.021 0.018 0.019',10:018 :'0.017 0.016 0.018 10.018 .0.018 0.022 0.019 9.6 9 22-Feb-11 I-Mar- Il ý0.031 -0.032 `.0.031 .: - 0.029 '0:029 0.028 ,0:028 0.028 0.030 0.029 0.030 4.9 1-Mar- Il 8-Mar 11 0.034 7.4 10 0.032 0.038 0.035'! . 0.032 10.035 0.031 0:030 0.036 0.035 0.034 11 8-Mar-l Mar-I 0.040 0.043 _ 0.042: 0.038! "-0:046 C_0.036 0.041 0.040 0.036 0.039 0.040 7.7 12 15-Mar-I l 22-Mar-II 0.346 0.388 0.369 "0.358 0.360 0.355 0.372 -0.353 0.325 0.320 *0.355 5.8 13 22-Mar-i I 29-Mar- 11 0.305 0.279 0.263 '"r 0.273 - 0.313 0.329 0.299 0.326 0.305 0.317 0.301 7.5 Mean 0.083 0.084 0.079 ,.0.089 0.082 0.082 0.081 0.083 0.078 0.079 0.082 3.7 2nd Quaiter (control) ."*
START' STOP Site Site Site .Site Site Site Site Site ' Site Site RSD Week # DATE DATE 4 6A* 7A .. 14A*. 15* 17A `21 29* 35 40* Mean (%)
14 29-Mar-II 5-Apr-Il .0.043 0.047 . 0.048.. .0-045 P045 6.. 46 40041 0.043 0.045 4.9 15 5-Aprl;I1 12-Apr-i l 0.029 .. 0.032 ,0.030. .0.031 0.034 , 0.030 ,0.032 0.029 0.028 .0.032 0.031 6.0 16 12-Apr- Il 19-Apr- Il 0.037 -0.037 . 0.038 .0.039, 0,.041 .-,,0.035 0.036 0.041 .0.038 .0.040 0.638 5.4 17 19-Apr-11 26-Apr- I l 0.024 0:024 :.026
.- ,0.021. j,0.021. .0.026 0.022 0.022 0.027 0,.020 .0.023 10.5 18 26-Apr-11 3-May-l 0.024 *; 0.030 0.0281. ,.. 0.024 , 0.024. 0.026 0.023 ....0.028 -0.026 0.026 0.026 8.6 19 3-May- II 10-May-11 0.036 "0.035 ;0.036:O,,A.036. 0.035 .0.035 0.032 0.035 0.036 0.040 0.036 5.5 20 1O-May- Il 17-May-i l .0.025 0:027 ;:0.025 .*,.,0.025 ."0.024. 0.023 0.024 0.026 ý 0.024 !0.022 0.025 5.9 21 17-May-Il 24-May- I l 0.023 0.021 G.025 '-0.021 E. 0.025?' 0.024 0.021 0.024 0.024 0.022 0.023 7.1 22 24-May-11 31-May- I1 0.028 0F.022 -0.022.`C-0.023' Y'*0:022 0.022 0.021 0.023 .,0.023 0.025 ,0.023 8.8 23 3 i-May-i I 7-Jun- Il 0.028 0.028 .-0.030! .-0.022". 0.0287 0.028 0.029 0.029 0.028 0.027 0.028 7.8 24 7-Jun-il I 14-Jun-Il 0.032 0.030 -:'0.029 0.031 , 0.031 0.026 0.029 0.032 0.032 0.034 0.031 7.3 25 14-Jun-i 1 21-Jun-Il 0.028 0.033 -'0.030 '".'0.026 '0.031 0.032 ' 0.030 '0.025 '0.028 0.030 0.029 -8.7 26 2 1-Jun-Il 28-Jun-Il 0.034 01038 0.038 0.037 0.038 0.034 0.035 0.030 0.036 0.040 0.036 8.0 Mean 0.030 0.031 0.3 1i -60.0(29 .0.031 0.030 0.029 0.030 0.030 0.031 0.030 2.4 a Power was lost to equipment. Corrective Action Program CRDR 3574902 and CMWO 3573475iifitiafed.
All elevated sample results in weeks 12 and 13 have been att ibuted to the FukuIshima-Duichi event. Refer to Corrective Action Program document CRDR 3739206. " --. , .
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 29
TABLE 8.2 PARTICULATE GROSS BETATIN AIR"3 rd - 4 th QUARTER ODCM required 'sanmples dnbtfidby *.
.-units
. are- pOi/m3 3.yd Quarter -
(control)";
START STOP Site Site";-, Site*:-,j Site:- Site site , Site,- Site -
Sifi Site Site
- RSD Week # DATE DATE 4 "- 6A*.'. 7A:. .<14A* .;; 15*; 3. 17A'ý. 21-.- 29*- 35 40* Mean (%)
27 28-Jili-lI 5-Jul-Il. 0.033 0.035'- 0.033 . 0.036 Z0.034,- .0.036..
- 0.025'.> 0.031 -; 0.039 0.026 0.033 13.5 28 "5-JuI-I I 12-Jul- 1-l 0.031 0.030;'-. 0.024 . '0.029, ..,0.029C- 0.02'1.:*3 0.021 0.027' 0.031 0.02& 0.027 14.1 29 12-Jul- 11 19-Jul- 11 0.032 0.024:." 0.024 ,;.3.0.03'5 i, 0.035'.:.P 0.02,8 :. 0.022.:. 0.026 0.030: 0.028 0.028 16.1 30 .:19-Jul- 11 26-Jul41 0.032 0.029.3,. 0.03.1 .0.03:1ý. ,.0.033.,7:0.03,1k' 0.032,7 0.031 0.033 0.033- 0.032 4.0 31 Jul. 11 1-Aug- Il 0.027,: 0.023v*:- 0.024 .0.025:,!V0.027 * '0.028,-. 0.Q29 0.024.. 0.029 0.027 0.026. 8.2 32 1-Aug-i1 9-Aug-I 1 0.038 0.040,,..- 0.035 ;0.03.1 :10.035:, 0.033-..- 0.Q35 1: 0.035 0.038 0.038 0.036 7.5 33 .9-Aug- Il 16-Aug- Il 0.033-- 0.032. 0.030, 0.029 .- , 0.032:.;- 0.0.34,:. 0.030.-- 0.027- 0.030 0.034, 0.031 7.3 34 16-Aug-I 1 23-Aug- I, 0.042 0.040.,-j 0.035 ,,.0.03 _.., 0.034 . 0.03- w.. 0.038$.. 0.037., 0.036, 0.044, 0.037. 10.3 35 23 7Aug- 11 30-Aug- 11 0.040. 0.043 0.044 ¶0.04;i-j:, 0.04*4,,,, 0.044- 0.04A 0.043 0.042. 0.046 0.043, 3.7 36 30-Aug-Il 6-Sep-l.1 0.046 0.049, :. 0.04,. 0.044.4, 0.049? .,: 0.045., 0.044, 0.049. 0.045 0.048. 0.0.46.. 5.5
" . 37..8 .--Sep. -13-Sep-1I 0.028 --0.032->- 0.0 37 --- 0.0*9P. -0.03-7---0315...0 0.036 0.034.- 0.034 9.3 3 13-Sep-.1l 20-Sep-l1 0.038*' 0.0371 0.039 0.038.. 0.034 .-.. 0.03:7:': 0.036 0.037 0.039. 0.035 0.037 4.4 39 20-s8ip-11 27-Sep-I 1 0.032 0.032 0.029 0.026 0.038" 0.030'V 0.0o1." 0.605 0.026 0.037 0.031 14.5 Mean 0.035 0.034 0.033 0.033 0.035 0.033 0.032 0.033 0.035 0.035 0.034 3.5
'START STOP- Site Site"' Site'" Site- ': Site*, Site' Sitei -. Site . Site Site RSD Week # DATE DATE 4: - 6A* 7A' "0 14A*-' 1'*' 17Ai": 21 ' - 29*.- 35 40c Mean- (%)-
40 27-Sep-I 1 4-Oct-I l 0.042 ' 0.03871 0.041 - 0.041*," 0.03'20`1 0.038 . 0.038 0.042 0.045 0.041 0.040 8.8 41 *4-Oct-i 1 1i-Oc-1I 0.024; 0.022 0.026 0.022":. 0.022*2 0.024- 0.024 0.025' 0.022. 0.022' 0.023 6.4 42 Il-Oct-1I 18-Oct- Il 0.049,; 0.055)" 0.052 0.050 0.049 _ 0.050 3 0.049' 0.049. 0.050 0.051 0.050. 3.8 43
- 18-Oct- II 25-Oct-Il 0.051 0.057 *' 0.051 0.0521. 0.052: 0.0521: 0.048 0.053 - 0.052 0.053. 0.052 4.3 44 25-Oct- 11 I-Nov- II 0.047 0.051!1' 0.0481 0.048". . 0.046.-f 0.0431- 0.044,: 0.047 0.049 0.048 0.047 4.9 45 1-Nov- II 7-Nov-1I 0.031 0.032 0.035 0.033::. 0.036, 0.032" 0.032- 0.034 0.032 0.033 0.033 4.7 46 7-Nov-Il 15-Nov-11 0.035 0.040, 0.037. ,., 0.036: . 0.037.,: 0.036, .', 0.036 0.039 0.039 0.036 0.037 4.5 47 15-Nov- II 21 -Nov-Il 0.041. 0.042 0.041 0.042 : 0.045:;.- 0.043.ý. 0.043. 0.043 . 0.041 0.043. 0.042 3.0 48 21-Nov- Il 29-Nov-11I 0.03,1,. 0.032. 0.033,,.: 0.030 .0.029..,,. 0.030.,. 0.030... 0.032. 0.029 0.031 0.031 4.4 49 29-Nov-1I 6-Dec-il 0.042 0.046..- 0.041 : 0.039_..,, 0.042,. 0.0.40 0.039- 0..042 0.038 0.036 0.041 6.8 50
- 6-Dec-!,l 137Dec-I 1 0.050 invalid' . 0.052 0.050 . 0.050,, 0.042 0.050 0.052.. 0.052 0.047 0.049 6.5 51 13-Dec-il 20-Dec-II 0.030 0.030 0.031 0:028 0.030.. 0.030.,:- 0.025, 0.026 0.027 0.028 0.029...- 7.1 52 20-Dec- 1I 27-Dec- 11 0.045 . 0.050 0.045 0.0471 0.049 0.045 0.044 0.048 0.044 0.044 0.046 4.8 a Sample invalidated due to sample pump malfunction.
Mean 0.040 0.041 0.041 0.064b 0.040 0.039 0.039 0.041 0.040 0.039 0.040 2.2 AnnualAverage 0.0468 0.0477 0.0461 0.04.54. 0w0471 0.0461 0.0453 0.0467 0.0459 0.0462 0.046 1.6 PVNGSJ ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 30
TABLE 8.3 GAMMA IN AIR FILTER COMPOSITES ODCM required samples denoted by
- units are pCi/mr3 -.
(control)
QUARTER Site Site Site Site Site Site Site Site Site Site ENDPOINT NUCLIDE 4 6A* 7A 14A*. 15s* 17A 21 29* 35 40*
ENDPOINT 4 6A* 7A 29-Mar-I I Cs-134 0.007 +/- 0.004 0.008 +/- 0.004 0.010 +/- 0.004 <0.010 0.008:+/- 0.003. 0.008 +/- 0.003 0.007 +/- 0.003 <0.007 0.010 +/- 0.004 0.010 +/- 0.004 Cs-137 0.009 +/- 0.005 0.006 +/- 0.004 0.010 +/- 0.004 <0.01.3 <0.007 -. 0..008 +/- 0.005 <0.010 0.007 +/- 0.004 <0.009 0.011 +/- 0.005 1-131 0.016 +/- 0.012 0.032 +/- 0.010 0.017 +/- 0.007 0.022-+/- 0.011 0.029 +/-0.009 0.024 +/- 0.014 0.025 +/- 0.011 0.020 +/- 0.014 0.016 +/- 0.012 0.020 +/- 0.011 28-Jun-I I Cs-134 <0.0039 <0.0035 <0.0030 <0.;0025 <0.0034 <0.0035'"- <0.0035 <0.0044 <0.0027 <0.0034 Cs-137 <0.0043 <0.0036 <0.0028 <0.0064' <0.0040 <0.00471 <0.0046 <0.0042 <0.0044 <0.0036 27-Sep-I I Cs-134 <0.0036 <0.0031 <0.0024 <0.0042 <0.0023 <0.0030 <0.0029 <0.0037 <0.0039 <0.0034
<0.0048 Cs-137 <0.0048 <0.0011 <0.0047 <0.0029- <0.0036 <0.0029' <0.0043 <0.0037 <0.0031 27-Dec-I I Cs-134 <0.0014 <0.0026 <0.0026 <0.0046 <0.0013 <0.0014 <0.0028' <0.0019 <0.0030 <0.0010 Cs-137 <0.0030 <0.0027 <0.0016 <0.0046 <0.0030 <0.0035.. <0.0035 <0.0023 <0.0057 <0.0016 All positive sample results in the 1st quarter have been attributed to the Fukusiiima-Daiichi event. Refer to Corrective Action Program document CRDR 3739206.
- . *: "*' *. :.. ;. .: .." :'.-
"!, " " ' I. ~ ~~~~I*
- .* "*,, :: -G **
IA PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 31
TABLE 8.4 AIR PARTICULATE GAMMA DUE TO FUKUSHIMA RELEASES 3
units are pCi/m 1st Quarter START STOP
!)ATE DATE SITE 1-131 1-132 Cs-134 Cs-137 Te-132
-Mar-II 22-Mar-11 4 0.29 +/- 0.08 0.04 +/- 0.02 0.07 +/- 0.03 6A 0.22 +/- 0.06 0.06 +/- 0.03 0.08 +/- 0.03 0.06 +/- 0.03 7A 0.23 +/- 0.06 0.06 +/- 0.03 0.07 +/- 0.02 14A 0.28 +/- 0.07 0.03 +/- 0.02 0.04 +/- 0.03 15 0.24 +/- 0.08 0.06 +/- 0.03 0.075 +/- 0.03 17A 0.30 +/- 0.07 0.08 +/- 0.03 0.06 + 0.03 21 0.33 +/- 0.07 0.05 +/- 0.05 0.08 + 0.05 0.03 +/- 0.02 29 0.31 +/- 0.06 0.06 +/- 0.03 0.09 +/- 0.03 0.03 +/- 0.03 35 0.37 +/- 0.08 0.06 +/- 0.03 0.06 +/- 0.03 0.07 +/- 0.03 0.05 +/- 0.03 40 0. 22 +/- 0.05 0.03 +/- 0.03 0.06 +/- 0.03 0.07 +/- 0.04 0.04 +/- 0.03
-Mar-Il 29-Mar-11 4 0.14 +/- 0.06 0.07 +/- 0.03 0.07 + 0.03 6A 0.10 +/- 0.06 0.05 +/- 0.02 0.05 + 0.02 7A 0.14 +/- 0.60 0.03 +/- 0.02 0.06 + 0.03 11 :- -
14A-
. . : I . f .I , , - . . . '.. -0.12 +/- 0.071 .0.05 +/- 003 0.08 +/- 0.03:.
15 0.16 +/- 0.08 0.05 +/- 0.03 0.06 +/- 0.03 17A " 0.16 +/- 0.05 .- 0.07+/- 0.02 0.06 +/- 0.03 21 0.17-+/- 0.05 0.03-+ 0.02 0.08.+/- 0.03
.29 0.16 +/- 0.06 0.07 +/- 0.03 0.05 +/- 0.03 35 0.10 +/-'0.06 0.05 + 0.03 0.05 +/- 0.02 40 0.12 +/- 0.07 '0.05"+/- 0.03 0.05f 0.03 29-Mar-1I 5-Apr-liI 4 none'dietected, no requifed LLD :--z.019 <0.'041 6A none detected, no required LLD ' "'<0.024 <0.030 7A none detected, no reqtired LLD .<0.019 <0.028
,.14A *nond detected, no required LLD.';i <0:026 <0.025 15 nonedetected, no required LLD ,0..026 <0.043 17A none detected,,nowrequired.LLDI ... <0.024 <0.043.
21 none detected, no required ELD - <0.020-- .<0.033-29 none detected, no required LLD <0.025 <0.030 35 none detected, no required LLD <0.020 <0.029 none detected, no required LLD <0.025 <0.032 All positive sample results have been attributed to the Fukushima-Daiichi event. Refer to Corrective Action Program document CRDR 3739206.
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 32
TABLE 8.5 RADIOIODINE IN AIR 1st - 2 nd QUARTER ODCM required samples denoted 3 by *
..units are pCi/m 1st Quart er.
(control) required LLD <0.070 START STOP Site Site Site Site. Site Site Site Site Site Site Week# DATE DATE 4 6A* 7A 14A* 15** -.
17A 21 29* 35 40*
1 28-Dec-10 4-Jan- Il <0.051 <0.056 <0.067 OOS3a 0.062 <0.044 <0.035 . <0.045. <0.066 <0.035 2 4-Jan- Il SlI-Jan- 11 <0.045 <0.035 <0.063 OOS a .<0.064 <0.057 <0.064 <0.054 <0.047 <0.046 3 I l-Jan-I1 18-Jan- Il <0.050 <0.056 <0.033 OOS. <0.049 <0.043 <0.034 <0.048 <0.042 <0.050
<0 .049 4 18-Jan-I 1 25-Jan- I1 <0.061 .<0.067 <0.069 <0.069 <0.038 <0.057. <0.068 <0.049 <0.064 5 25-Jan-I I 1-Feb- Il <0.047 <0.058 <0.065 <0.053 <0.046 <0.060"' <0.065 <0.045 <0.054 <0.060 6 1-Feb-11 8-Feb-I I <0.014 <0.051 <0.045 <0.052. <0.053 <0.03.7 *0.060 <0.063 <0.065 <0.046 7 8-Feb- Il 15-Feb-I l <0.054 <0.040 <0.040. <0.054 <0.041 <0.046 <0.070 <0.062 <0.066. <0.057 8 15-Feb- 11. 22-Feb-I l <0.043 <0.055 <0.038 <0.061 . <0.022 <0.034 <0.044 <0.042 <0.036 <0.041 9 22-Feb-I l I-Mar- 11 <0.052 <0.013 <0.052 <0.058, .50.053 <0.041 <0.053 <0.044 <0.059 <0.039 10 I-Mar-i 8-Mar-I l <0.057 <0.036 <0.041 <0.034-- <0:029- <0.052 - <.039 <0.043 <0.037 <0.043 11 8-Mar- Il 15-Mar-I l <0.038 <0.038 <0.048 <0.05,4 <0.066 <0.0 .- 0.043 <0.051 <0.062 <0.054 12 15-Mar-il 22-Mar-I 1 0.92 +/- 0.17 1.26 +/- 0.15 1.18 +/- 0.19 1.19"+/-0.14 1.17 +/- 0.14 1.24+/--0.16 1.17 +/- 0.13 1.14 +/- 0.14 1.00 +/- 0.14 0.97 +/- 0.12 13 22-Mar- I1 29-Mar-I l 0.53 +/- 0.12 0.53 +/- 0-12 0.55 +/- 0.12 0.61 +/- 0.13 0.55 +/- 0.13 0.57 +/- 0.13 0.61
- 0.14 0.51 +/- 0.11 0.66 +/- 0.13 0.58 +/- 0.12
- -... .... . . 2nd-Quarter-.:.-
required LLD
-(control) , . , , <0.070" .
START': :STOP Site Site " Site Si'te'- Site . Site. Site -Site Site Site DATE 4.. 6A* * , 7A' 14A,* *':(T4.f5* j.-:*, 1-7A* 21 35 " 40*
Week # DATE . " 29*
- 14 29-Mar-I 1 5-Apr-I 1 0.05 +/- 0.0 14 (0.10 +/- 0.03 ' ;0.06 +/- 0.04 ' 0.04 +/- 0.04 0:04 - 0.03 <0.068 0.06 +/-,005 0.06 +/- 0.04 15 5-Apr-il1-' 12-Apr- 11 <0.056 <0.065 <0.056 <G.049 <0o068 ' -<0.065 '" <0.052 <0 .054 <0.053
.<0.049 16 12-Apr-11l J 1'9-Apr- Il' <0.035 <0.066 <0.042 <0.061tj <0.054 "<0.053. . ".<0.067 <0.050 <0.048 17 19-Apr-I l 26-Apr- 1i <0.066 ,<0.059 <0.668' <0:642"- <0.059- <0.068' <0.060 -" <0.064 <0.055 <0.064 18 26-Apr- Il 3-May- 1I.1 <0.047 <0.038 <0.049 <0.046., ,..'<0.048 <0.046 !<0.058 <0.023. <0.053 <0.047 19 3-May- IlY 10-May- 1' <0.055 <0.052' <0:065,1. <0.0387 :<0.047 <0.045 <0'051 <0.057 <0.059 <0.053 20 I0-May- Il 1!-May- 1l <0.047 <0.047; <0.041* <0.042 .5,0.049 <0.040' <0.045 <0.043 <0.041 <0.047 21 17-May-Il 24-May- 11 <0.038 <0.039 <0.038 <0'.038. <0.039 <0.048- <0.030 <0.048 <0.048 <0.047 22 24-May- 1.1 3 1-Miy-f I <0.049 <0.056 <0:050 <0.057: ' .<0.049 <0.032 <0.021 <0.050" <0.062 <0.048 23 31-May-I l 7-Jun-Il <0.034 <0.069 <0.0*4 <0.0.38 <0.037 <0.040" <0.047 <0.047 <0.059 <0.050 24 7-Jun-I I 14-Jun- 11 <0.039 <0.060 <0.038' <0:035 -c:0.038 <0.034 <0.054 .. <0.051 <0t061 <0.050 25 14-Jun-I 1 21-Jun-I 1 <0.048 <0.062 <0.059 <0.038 <0.046 <0.059 <0.063 <0.042 <0.061 <0.044 26 21-Jun-I l 28-Jun-I 1 <0.054 <0.052 <0.067 <0.044- : z <0.067 <0.043 <0.054 <0.048 <0.064 <0.041 a Power was lost to equipment. Corrective Action Program CRDR 3574902 andCMW 0 3573475 iiiitidtd, All positive sample results in weeks 12, 13, and 14 have been attributed to the Fukushima-Daiichl event. Refer to Corrective Action Program document CRDR 3739206.
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 33
TABLE8.6 RADIOIODINE IN AIR ý3*-4tQUARTER ODCM required -samples den6ted by
- 3 . .
units are RCi/m .
',. 3rd'Quarter ,
-(control) - .070
- .*START STOP Site Site Site Site.. TV Site -.. Site Site: Site Site Site Week# DATE DATE 4 .6A* -7A," 14AM.:,*. 15* .17A 21 29* 35 40*
'27 28-Jun-i l 5-Jul-11 -<0.041 :<0.038 <0.043 <0.053' %<0.056 <0.021 <0.05.4 <0.068 <0.058 <0.018 28 5-Jul- II 12-Jul-l1 <0.041 <0.061 <0.039 <0.047 '" <0.046 * <0.049 <0:039 <0.045 '<0.046 <0.047 29 12-Jul- Il 19-Jul- 11 <0.025 <0.046 <0.038 <0.033 w"<0.044 <0.044 <0.049' <0.044' <0.042 <0.040 30 S.19-Jul- 11 26-Jul-11 .:_ -<0.050 '<0.052 <0:045 <0.044 <0.069 :<0.050 <0.065<-' <0.048 ,<0.063 <0.040
- 31 26-'Jul-li 1-Aug- 11 <0.039 <0.059 <0.058 <0.047": -0.058 <0.052 <0.041 <0.039 ;<0.052 <0.027
" 32 I-Aug- II 9-Aug-1I I ' <0.046 <0.060 <0:0.55 <0.039 1' <0.039 <0.040 <0.03I <0.037 '<0.051 <0.032
.'33 9-Aug- Il 16-Aug-li <0.036 <0.038 -4.026 <0.051 <0.038 <0.040 <0.043' <0.039. <0.033 <0.036
- 34 16-Aug- II 23-Aug-i1 '<0.047 <0.031 <0.040 <0.041 <0.047-<0.036 <0.043 <0.033 <0.044 <0.039 S " 35 . 2"3-Aug-lI 30-Aug-11i <0.031'i-. <*0.067 t<0:0501 <0JD.: 4Y040.048';*. O046 <0.041Y' :<0.041 -<0.065' <0.03.1
... , ."'. , v 36 30-Aug-1I 6-Sep-l 1 `<0.038 <0.051 -<(0.043 <0.028* <0.050 .. 0.039 <0.0*44 <0.039 '<0.042 <0.060
37 6-Sep-1I 13-Sep-1 <0.051 "<0.040 <60 045 <0.0462;: <0.044 <0"052 <0.065 <0.056 .. <0.054 <0:068 38 13-Sep-lI 20-Sep-lI1' <0.047 <0.064 <0.064 <0.053 *'-,.<0.052 <0.053 <0.059 <0.053 <0.053 <0.064 39 20-Sep-Il 27-Sep-1 1 <0.057 <0.061 <0.054 <0:04."I ý0.049 <0.042 <0.049 <0.049 <0.051 <0.038
... .. -4th7Quarter... .. .
(control) 0.070 START STO] P Site Site Site Sitei 7_ Site' Site Site Site" Site Site Week # DATE DAT]E 4 6A* 7A 14A*. 15* .. 17A 21 2 9* '35 40*
.40 27-Sep-i 1 4-Oct-il1 <0.045 .<0.049 60.q5.1 <0.04-. <0.055 <0.034 <0.066 <0.045 <0.060 <0.035 "41 4-Oct- I 1 li-Oct-il <0.062 <0.061 <0.013 <0.035 <0.061 <0.052 <0.04.5 <0.046 .<0.068 <0.068 42 lI -Oct-il I 18-Oct-i 1 <0.056 <0.050 <0.059 <0.0,56.. <0.053 <0.067 <0.062 <0.064,' <0.060 <0.062 43 18-Oct-IlI 25-Oct-ilI *0.055 .*50.067 <0.060 <0.0,42ý,_ <0.067 <0,059 <0.041 <0.053 <0.053 <0.068 44 25-Oct-i I I-Nov-i1 _<0.066 <0.042 <0.064 <0.034,.. <0.034 <0.948 <0.034 <0.052 <0.020 <0.053 45 I-Nov-iI 7-Nov-il1 <0.031 .<0.068 <0.008 <0.069 <0.049 <,'0.024 <0.066 <0.024 <0.067 <0.046 46 7-Nov-lI iS1-Nov-il1 <0.053 <0.016 <0.029 <0.029 <0.029 *;0.027 <0.044 <0.020 <0.043 <0.024
- 47 15-Nov-il1 21 -Nov-il1 <0.029 <0.068 <0.067 <0.033. <0.068 <0.033 <0.043 <0.029 <0.069 <0.037 48 21-Nov-IlI 29-Nov-li1 <0.024 .. <0.042 <0.029 <0.026 . <0.050 <0.021 <0.037 <0.015 <0.056 <0.023 49 29-Nov-iI I 6-Dec-lII <0.032 .<0.033 <0.034 <0.055 -- <0.039 -<0.041 .<0.036 -<0.059 - <0.027 <0.055 50 6-Dec-iI . 13-Dec-li1 <0.033 invalid' <0.014 <0.049 <0.039 c<O.049 <0.050 <0.020 <0.041 <0.029 51 13 -Dec-IlI 20-Dec-li1 <0.026 <0.0 18 <0.027 <0.030 <0.034 <0.030 <0.034 <0.039 <0.029 <0.031 52 20-Dec-i1 I 27-Dec-i i <0.032 <0.049 <0.033 <0.038 <0.042 <0.017 <0.041 <0.017 <0.046 <0.026 a Sampie invalidated due to sample pump malfunction.
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 34
TABLE 8.7 VEGETATION ODCM required samples denoted by
- units are' pCi/kg, wet
- <60 <60 <80 LOCATION TYPE DATE COLLECTEDb '1-131 ' ..Cs-134 'Cs-137 LOCAL RESIDENCE . NONE .AVAILABLE .
(Site #47)*
red.cabbage .. 20-Jan-1.1 <49 <36 ',. <70 green cabbage 24.:.Mar-1 I -- t 53'- 20 <17 <20 redicabbage 22*Apr-11 I<52 <33 <52 green cabbage *22'Apf-11I I .<59 <46 <64 COMMERCIAL green cabbage 20-OCcGt II <26 <41.,... .. 28 FARM red cabbage 17-Nov-Il <53 <38,:;. <68 (Site #62)*" green cabbage 17-Nov-11I . *39 5.,51 <48
" green cabbage 1-Dec- I .: '<55 <48 <76 red'cabbage I-Dec-1I <44 <12 <40 All positive results have been attributed to the FukushimL-Daiichi;event. Refer to Corrective Action Program documents CRDR 3739206 and 331.2184. .. ",::L.
-A' , . .: * . . A A C- .
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 35
TABLE 8.8 MILK .
ODCM required samples denoted by.*
units are pCi/liter.
SAMPLE -. DATE <1 <15 <18 <60 <15
. LOCATION COLLECTED 1-131 Cs-134 Cs-137 Ba-140 La-140 Local Resident NONE AVAILABLE Goats (Site #51)* . . , .
Local Resident Goats NONE AVAILABLE, DELETED 9/30/11 (Site #52)* . .. .. .
20-Jan-i I xi1, <1 . ,.. <3 <1
.1-8-Feb-11 . <. " <1 <3 <1 24-Mar-11 '4.6&4.0;9 <1 <3 <1 Local Resident .22-Apr-iI I .0+1.1 <1 <3, Goats. :20-May-II <1 <1 <3 <1 (Site #53)* .. 23-Jun- I I1 ...,<, 1' <1 <3.
22-Jul-i I <1 ,.1
<4 <1
- 418-Aug-l1 F... F <1 <3 <1
<1 2 2 -Sep-.l <1 <1 <3
<1 <1 <3 <1 20-Oct-II <1 17- ov*lF:ii-' -* <1 "," < 1 ý',, ,. -. < 1 -',. ..,,,3 15-Dec-Il <1 ;' : Ii"< ' 3 " <F "
Local Resident 31-Mar-i1 2.0+/- 0.7 <1 <1 <3 <1 Goats 14-Apr-11 1.3 +/- 0.7 <1 <1 <3 <1 (Site #54) 13-May-lI <1 <1 <1 <3 <1 09-Jun-11 <1 1.5+/-0.6 2.0+/-0.7 <3 <1 07-Jul-I1 <1 <1 <1 <3 <1 12-Aug-il <1 1.7 +/- 0.6 2.0 +/- 0.7 <3 <1 09-Sep-II <1 <1 <1 <3 <1 13-Oct-11I <1 <1 <1 <3 <1 10-Nov-1I <1 1.3 +/- 0.6 1.9 +-0.9 <3 <1 15-Dec-ll <1 <1 <1 <3 <1 Notes:
All positive results have been attributed to the Fukushima-Daiichi event. Refer to Corrective Action Program documents CRDR 3739206 and 3812184.
PVNGS ANNUAL-RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 I *:.,36
TABLE 8.9 DRINKING WATER ODCM required samples denoted by
- units are pCilliter
<2000 SAMPLE I MONTH <15 <15 <30 <15 <30 <15 <30 <15 <15 <18 <60 <15 Qtrly <4.0 LOCATION ENDPOINT Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Tritium Gross Beta 25-Jan-11 <13 <12 <22 <14 <27 <14 <24 <12 <13 <14 <45 <14 <3.8 22-Feb-11 <12 .<11.. <25 <13 <29 <12 <21-. <12. -<11 <14 <42 .<15 <3.6 29-Mar-11 <14 <11 <26 <15 <27 <12 <16 <10 <10 <11 <37 <14 <262 5.6 +/- 2.4 267Apr-11 <12 <12 <26 <14'. <30 <13- <-23 <13 - <11- <13 .. <45-- <15 - . 5.9+/-2.5 LOCAL 31-May-11 <12 <11 <23 <12. <24 <11 <18 <10. <10 <12. <34 <13 3.8+/-2.1 RESIDENCE 28-Jun-ll' <15 <11 <25 <15 <27 <12. <15 <9.. <11. <11 <31 <15 <253 <3.1 (Site #48) 26-Jul-ll <12 <12 <24 <12 <29 <11 <20. <12. <11 <12- <39 <12 3.7+/-2.0 30-Aug-11 <11 <11 <21 <13 <30 <12. <20 <12 <10 <113 <38 <13 <3.1:,
27-Sep-11 <10 <il <23. <13 <22 <10 <17 <8 <9. <11 <30 <15 <254 <3.6 25-Oct-11. <10 <9, <23 <11 <24 <11 <18 ' <9' <8 <10.- <34 <14 <3.8
- 29-Nov-11 <10 <12 <24 <15 <23, <11. <19. <11. <10 <12' <40 <14 8.4 +/- 212
.27-Dec-li <14 <11, <25 <15 <25 <15.. <190 <11i <11 <12"' <39, <28 <269 <3.0 25-Janll <.15 <14. <28 <14 <25 <15. <27, <11., <12 <14 <46. <15 3.2 +/- 1.7 22-Feb-ll <13 <10 <24, <15 <28-" <12-- - <20--- <11'-I <10 <13 -'- <40 -- <14 4.8 +/- 1.7
.29 Mar-lI <15 <13 <25 <03. <29. <13 <17 <11 <12 <14, <32'" <11 <261 6.0 +/- 1.7 26-Apr-11 <12. <10 <21. <13 <25 <1. <19. <11.. <10- <12 <39 <15. 4.1 +/-.1.6 LOCAL 31-May-Il. <13., <12 <28, <1' <<4 <13 <i <'I <12 <39' <12 4.3 +/--1.5 28-Jun-llI <11 <12 <20 <13 <26 <13* <21 <[1, <10;. <'I0 <40 <15. <251 RESIDENCE 3.3 +/-1.4 (Site #55) 26-JUl-11 <15 <11 <24 <10 <24 <11* <18.. <1iF <10; <1i <43 <11 3.6 1.4 30-Aug-il <15- <9 <27 <15 <26 <i' <24. <11. <13- <11 <33' <14 3.8 +/- 1.4 27-Sep-11 <9 <12 <18: <21 <20" <11,;. <17. <9 <106 <12' <38 <15 <255 3.6 +1.6 25-Oct-l1 <12 <10 <23 <11 <2., <12. <17 <10i <9 <9 <37 <15 <2.6 29-Nov-11 <9 <11 <16. <13. <20 <11'. <16'. <9. <10 <10 <36 <15 2.8 +/-1.4 27-Dec-11. <13 <12 <26. <13 <24' <12' <21.- <11. <10.. <13- <36 <15 <271 5.1 +/-1.5
- .- "'."
- F ' ,' --
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 37
TABLE 8.9 DRINKING WATER "t. ".'," ' "s¢ ;:"
ODCM required samples denoted by
- units are pCi/liter
<2000 SAMPLE MONTH <15 <15 <30 <15 <30 <15 <30 <15 <15 <18 <60 <15 Qtrly <4.0 LOCATION ENDPOINT Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Tritium Gross Beta 25-Jan-11 <15 <13 <29 <14 <24 <8 <26 <13 <14 <14 <44 <15 <2.4 22-Feb-il *.*.515 <13- <22.- <11 <28 ---.-- -25 <11--- <.12--... <15 - <29 .<15 - 3.5 +/- 1.5 29-Mar-11 <14 <13 <26 <11 **.0 1 "<22 <.15 <13 <14 <53 <13 <261 <2.3
. r-l 1. 10 <10 <25 <fi *23 <11 .<18 ..<9 <10 <11 <-36 <15 2.5 - 1.4 3.-May-l < 1 < <10 <1221 .1 <8 <13 <28 <15 2.7 1.4 LOCAL .28-Jun-11 <14 <14 *28 -<15 <27 .*<13 "524 <13 <12 <12, <49 -15 <250 <2.0 RESIDENCE 26-Jul-lI <10 <10 -21 <10 <20 $l1 <,15 <10 <9 <9 <32 <10 3.5 :L 1.4 (Site #46) ,* .o-`AiIg-11 <12 <11 <22 <14 <28 <12 '*20 <.12 <12 "<13 <'42 <12 3.8 +/- 1.4 27-Sep-Il <10 <11 *23 *8 -<30 <12 3/4<2 <10 <11 <1 .-"35 <10 <254 <2.3 25-0ct-11 <13 <12 !.<25 <13 <29 . <14 .*ý22< 15 <15 -1 51 <11 <2.4 229,-Nov-lI <11 <11 <23 <12 "<24 . io <20 1 <9 <12 <40 < 15 3.3 +/- 1.3 27-Dec-1I <11 <.11 -20 -13 .24 *11 *-ý20 <10 ý0 *10 <37 <15 "<271 2.6 +/- 1.3 25Jan-1 1 <12 *9 <20 .59 <25 <11 *18 <10 <11 <9 <34 <i5 <2.5 22-Feb-lI -"*13 .. 11-. *25 -<15- ---<24 .--*:12 --<*-22 <-10 -... <10 .. <13-. <37.- <14 <2.3
_29-Mar-11 <12 <12 <27 <11 530 <14 <22 <1 <11 <12 ý44 <13 <263 <2.3.
"26-Apr-il <11 <12 <23 *13 <27 <15 .$18 <12 <11 <1i2 <38 <14 <212 31-May-li <13 <13 <27 <15 <30 <13 <.<20 <13 <12 <15 !,48 <12 <2.0 LOCAL .28-Jun-lI <9 <10 <25 <.14 *24 <I1 *15 <10 <10 <11 <36 <14 <247 <2.0 RESIDENCE 26-Jul-11 <12 <13 .!27 <i4 *,28 <14 <21 ..<15 .-<3 .<13 <51 "<,5 <2.0 (Site #49)
- 3.0-AugIl <12 <9 <19 <12 !25 <12 .<17 <11 *10 <10 <44 <14 <2.0 13-Sep-llV <10 58 -19 <11 <21 '*9 <16 ..<15 s8 <9 <44 <12 <252 <2.4 27-Dec-llb <10 <12 <17 <14 <30 <13 <17 11 <11 *13 <41 <15 <272 2.8 +/- 1.3
'Permanently unavailable as of 9/20/11, refer to Corrective Action Program document CRDR 3882110. bNew location as of .12/6/11.'
.. . "7".
.. .. . " i. :,! .
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 38
TABLE 8.10 GROUND WATER ODCM required samples denoted by
- units are pCi/liter SAMPLE .DATE <15 <15 .<30 - <15 ' <30 - *15 :30
.- <15 <15 <18. <60 <15 <2000 LOCATION COLLECTED Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Tritium 15-Feb-11 <14 <13 '<25 <15 <28 <15 :<22 <14 <12' <14 <46'. <15. <271 WELL27ddc 26-Apr-lI <10 <10 <19 <12 <21 <ilI 16 <11 <9 - .- <39I -<12 <260 (Site #57)* *26-Jul-11 <13 <13 -<28 <9 <30 <13 z*23 <13 <12. <14. <44 <13 <250 25-Oct-ll <10 <10 <21 <15 <23 <11 <15 <10 <8 <8 <35. <13 <260
<.4 0.
WELL 34abb 26-Apr- 11 <11 <12 <21, <12 <24 <12 <'fi -<8
<10 <40 <15 <263 (Site #58)* 26-Jul-i1 <12 <10. -<19 -: -<11 <27 <12 <19 <11 <10 <10 <40 <15 <250 26-Oct-11 <9 ,<9., -<17 <26 <11 <15 <10 <15 <10 <34 <10 <260
- 5: C."
., .o: : .. 3...
. ;"
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011
'39
TABLE 8.11 SURFACE WATER . ...
ODCM required samples denoted by
- units are pCi/liter SAMPLE DATE <15 <15 <30 <15 <30 <15 <30 <15 <15 <18 <60 <15 <3000 LOCATION COLLECTED Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Tritium 45ACRE 15-Feb-11 <12 <12 <25 <11 <23 <13 <21 27 +/- 10a <10 <13 <44 <12 <278 RESERVOIR 26-Apr-11 <11 <12 <21 <11 <24 <12 <20 <15 <10 <12 <41 <13 <264 (Site #61)* 26-Jul-11 <13 <12 <24 <10 <26 <12 <24 <15 <12 <13 <41 <12 <245 25-Oct-11 <10 <11 <24 <13 <23 <12 <21 <12 <10 <12 <35 <13 <263 85ACRE 15-Feb-11 <10 <12 <24 <15 <28 <13 <19 <12 <11 <12 <44 <14 <273 RESERVOIR 26-Apr-11 <11 <11 <26 <15 <29 <13 <22 <15 <11 <11 <48 <11 <264 (Site #60)* 26-Jul-11 <11 <11 <17 <13 <28 <10 <21 <10 <11 <11 <40 <15 <248 25-Oct-11 <11 <12 <22 <11 <30 <12 <21 <14 <12 <13 <45 <12 <264 EVAPPOND1 15-Feb-11 <13 <11 <27 <13 <24 <11 <21 <11 <11 <14 <41 <14 956 +/- 172 (Site #59)* 26-Apr-11 <13 <12 <30 <12 <29 <11 <23 <15 <10 <12 <43 <10 936 +/- 181 26-Jul-1I empty for re-lining 25-Oct-I 1 empty for re-lining EVAP POND 2 15-Feb-Il empty for re-lining (Site #63)
- 26-Apr-Il empty for re-lining CELL2A 26-Jul-11 <13 <13 <24 <15 <30 <12 <23 18 +/- 10 <12 <13 <40 <14 334 +/- 176 25-Oct-11 <10 <10 <21 <11 <22 <11 <19 <12 <10 <11 <39 <10 317_+/- 189 CELL 2B 15-Feb-Il empty for re-lining 26-A r-li empty for re-lining .. *. .. - . . . . .
26-Jul-I I empty for relining. ,
- 25:-Oct-lI empty for re-lining ., r .
EVAPPOND3 15-Feb- 11 <9. <11'i. <23 <12.' <30,' <11,ý <21, <9 <9 *<12 <35 <11 613 +/- 167 (Site#64)* 26-Apr-l1 <12 <13 <25 <12 <30, <13: <21. <13 -.<1 <13 <46 <14 607_+/- 171 CELL3A 26-Jul-11 <12 <13 <24: <15. <29- <121 <23, <11 <12 <15 <45 <14 500+/- 179 25,-Oct-li <14 <12 <29 <15 <29 <12. <20!, -*<10 <10 <13 <43 <15 <308 CELL3B 15-Feb-11 <10 <10' <23 <14- <30.: <112 <18.. <9 -1.59 <12 <35 <9 812+/- 171 26-Apr.-11 <9 <9 <'24 <11-'<24...... <16 <9 7 '"<11 <34 <12 56"_170 26-Jul-Il <10 <11 <23 <11 .; <30 <1ii <171 <9 <9 <12 <35 <10 604+/- 179 25-Oct-11 <10 <11 <29 <13 <30 <11 <18 <10 <9 <13 <36 <7 <308 a Verification analysis result was 24 +/- 10 pCi/liter. Refer to Corrective Action Program document CRDR 3739206 for evaluation of Reporting Level exceedance. * ..
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 40
TABLE 8.11 SURFACE WATER ODCM required samples denoted by
- units are pCi/liter SAMPLE DATE LOCATION I COLLECTED Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Tritium**
4-Jan-Il <11 <11 <20 <11 <29 <12 <17 13 +/- 11 <10 <12 <33 <15 Il-Jan-i1 <13 <12 <26 <13 <29 <11 <21 43 +/- 11 <9 <13 <35 <9 18-Jan-Il <13 <9 <25 <14 <27 <12 <22 22 +/- 11 <11 <11 <44 <15 25-Jan-I l <12 <11 <21 <15 <27 <15 <20 13 +/- 10 <11 <13 <40 <13 <278 I-Feb- I1 <14 <15- <27 Yt1- <25. <1 . 19 31+/-14, <11 . <12 <48, <15 "
8-Feb-I 1 <14 <11. <28 <12 <22. <10I <22, 25 +/--10. <13 <12 <43 <15 15-Feb- Il <1-2 <1:4 <19 <14 <26 <1-1, <17 16 +/-9 <10k, <14 <36 <12 22-Feb-lI. <8 <9 18. <9. <23 <10 <16 15 +/-8. <8: <9 <34 <15 <274 WRF 1-Mar- I1 <12 <9 <20. <10 <29; *9. <20. 43+/- 13 <10 <12 <34 <1.5 INFLUENT 8-Mar- i . <12 <13 <29. <14 <27 <l:1; 1 18, 23+/- 13 <12 <13. <36, <15 15-Mar- I1 <10 *12 <23 <1;3. <28- <9, <19. 23+/- 11 <10 <11 <37 <12 22-Mar- 11 <14 <13 <25 <1-2 <29 <14. <19 15 +/-9,, <11 <13. <43 <15 29-Mar-I 1 <11 <11, <26 <12 <25f <13 *21.. -. 13.. <11 <13 <39 <14 <272 5-Apr-Il <12 <10 <24 <14 <30 <12- <19,_23.+/-12 <9,, <11 <42 <15 WRF OOS grab sample 19-Apr- I <11t- <12 <23, <1.5: <25. <.10 <16 18 +/-9 <11- <11 <33-- <.I 4 26-Apr- 1i. <12 <13 <25 <14. <2'! 514: -2& 42.+/-.1-5 <-I, <13. <46 <10 <26 7 3-May- Il <15 <11 <25 <12 *
<29 *14 *T23h 33 +/--li <7.. <12 <42. <13 10-May- 11 <11 <13 <24 <12- <25- <I+ <1-7 37 +/-1 <10 <11 <37 <13 17-May-1I <14, <14 <26 <13 <30 <13. <21. 17 +13- <13 <14, <39,. <14 24-May- II <13 <12 <26 <15 <29 <12- <21 .18 +9- <12, <11 <40 <14 31-Mayr 1I1 <12. <11 <24 <15 527 *13 <19. 25+/-+11 <10 <11 <39 <14- <26 4 7-Jun;11 <12 <12 <23. <11 <24 *12 <19. -<15 <11 <12 <45 <12 14-Jun-11 <13. <12 <25 <15 <26. <13. 523 -<13 <14 <14 <43 <13.
<9. <23 <13 <21 <10 <20 13+/-8 <11, <10 21-Jun-I l <11 <31 <15 28-JunI 1, <10 <11 <27 <13 *30 <131 <20 1i9+/- 11 <13 <13 <40 <15, <25 6 5-Jul- II <10- <11 <21 <11 <28 <12 <18 20 +/-9. <9. <12 <36 <14
<12 -Q24- <iB, 25:'<9- .<18. - <12 .. <9 .... *12 12-Jul4 II <39 - <15 ..
19-Jul- 11 <10 <12 <27 <14 <29 <15 <23 12 +/- 10 <13 <14 <43 <14
- monthly composite
, PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011
TABLE 8.11 SURFACE WATER ODCM required samples denoted by
- units are pCi/liter SAMPLE DATE - .: ...
LOCATION COLLECTED Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Tritium**
26-Jul-I 1 <14 <13 <27 <14 <30 <13 <21 i-4+/-12 <13 <15 <45 <11 <268 2-Aug- II <9 <10 *19 <11 <21 <10 <16 209+/-9 <10 *13 <33 <15 9-Aug- 11 <11 <'10 <23 <13 <19 <1.0 <7 35t I11 <11 <11 <38 <14
.16 Aug- 11 <14 <13 *25 <13 <29 <15 -23 22+/- 13 <12 <14 <48 <13 23-Aug- Il <13 <12 <25 <15 <22 <14 <22 26 12 <11 <14 <44 <15
.30-Aug- 11 <9 <9 <23 <12 *21 59 <,i17 .33-+/-9 _<9 :10 <34 <12 <259 6-Sep- 1I <12 <12 <25 <15 <23 <11 <24 t+/-3 <11 <13 <36 <10 13-Sep-11 <11 .11 <23 <11 <26 <j1 !21 334: 12 <13 <13 *40 <12 20,Sep- Il -<11 <11 <24 <12 <20 <12 <21 20 +/-9 <10 <12 39 <15 27-Sep- Il <13 <11 *24 <13 <30 ý13
ý-3 22 +/-.13 514 <15 <*43 1i3 <261 4Oct,1 I I- <13 <9 <24 '<, :.612 -8 -,1 <;0 <14 <32 <*1.5 S11-Oct-li -<15
".WRF <15 <11 <22 <13 <29 <19 ý23 9,+/- 10 <13 <12 <43 INFLUENT 18-Oct- II WRF OOS <15 25-Oct- 11 <11 <11 <24 <14 <25 .ý<12 -<29 2,0+/-i1 <10 <12 <39 <268 1-Nov:- 11 <11 <11 <23 <10 *23 -.7 <20 33;+/- 11 <10 .<11 <35 <15 8-Nov-11 <I1 <11 <26 <.10 <24 .<13 .20 .17,.+/-8 .*11 <12 <26 <13 "155-Nov-1 I :11 <11 <24 <15 <22 <10 6+/- 8 -9,4
<*0 <11 <40 <15 22-Nov- Il <10 <10 <21 <13 .<30 <11 .<16 .21+/- 10 <9 <11 <34 **13 29-Nov- I I <9
<12 <8 <15 <13 .<21 <S <15 23+/- 10 r8 <10 <31 <9 <269
<13 <24 <15 <20 .<I 1 .I! 5 15 +/-10 6-Decý I 1 <11 <12 <36 <15 13-Dec- I1 7<12 <13 <-22 <14 <30 .<13 <20 44-+/-'14 .<10 -12 .<41 <10 20-Dec-i 1 <14 <13 <25 <J.0 <27 <14 *19 -23ý+/- 12 <12 <15 <47 <15 27-Dec-11 <10 <8 <17 .<13 <26 <13 <20 -33 +/-11 <10 <11 -<39 <8 <281
- ,monthly composite
- A-~ I. .- V PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 42
TABLE 8.11 SURFACE WATER ODCM required samples denoted by
- units are pCi/liter SAMPLE DATE LOCATION COLLECTED Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Tritium 4-Jan- 1I <14 <13 526 <12 <30 <14 _.<24 -<*1 <I1: <15 <42 <13 343 +/- 171 SEDIMENTATION 1-Mar- Il <12 <12 <26 <14 <27 <12 <20 <12 <13 <14 <47 : <12 <280 BASIN 2 7-Nov- I1 <14 <15 <26 <14 <25 <13 <18 <12 <11 <14 <46 <13 425 +/- 174 13-Dec-I 1 <11 <10 <20 <10 <21 - <10 <16. - <9 .<9 <11 <33 <15 <274 20-Dec-1 I <25 :<13 <1I1.
8\<-18 ,<11- <12 <36 <15 291 +/- 166
<11 <11 <24 <14 The tritium in Sedimentation Basin 2 can be attributed to the rain washout effect during gaseous effluent releases. Normally, Boric Acid Concentrator (BAC) operations are curtailed during rain events to prevent this from occurring. Additionally, the Unit cooling towers re-entrain tritium and some washout of cooling tower vapor also contributes to..the low levels of mttium identified in Sedimentation Basin 2.
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 43
TABLE 8.12 SLUDGE/SEDIMENT ODCM required samples denoted by units are pCi/kg, wet SAMPLE DATE <150 <180 LOCATION COLLECTED 1-131 Cs-134 Cs-137 In-Ill LO ATION .
3-Jan- Il 1019 +/- 139 <29 * <30 35 +/- 43 Il-Jan-1I 612 +/- 94 <30' <32 17-Jan-Il 863 +/- 117 <21 <34 24-Jan- Il 761 +/- 1:13 <16 <30. 7 1-Feb- Il 658 99 <19 <33.
WRF 7-Feb- II 478 195 <133 <163 497 +/- 131, <1 20, ,<1.71, I
CENTRIFUGE 15-Feb- Il WASTE SLUDGE 22-Feb- 1I 812 +/-221- . <1.-50v <103 28-Feb- Il 613 195 <56 <141 7-Mar- 1I 743 +/- 214= <145.- "<151 374+/- 192 15-Mar- Il <150 <168 -
21-Mar-11 559 +/-242. <141 29-Mar- 1I 560 +/- 243 <138 <177.';
5-Apr- 11 541 +/- 170 * <111 <148' WRF OOS
- <ii6* <174 19-Apr- Il 211 +/- f10 26-Apr-I 1 None detecu ed .<104 <139 3-May-l None Detect 6d <12$ ' .<177" 10-May- Il 397 +/- 170 * <189 <184 I0-May- Il Grab sample 839 +/- 182 <148 <135
<145 ..<82 ;
17-May- 11 472 +/- 150 24-May- 1I 424 +/- 1.34 <98 <178,"
31-May-11 421 +/- 162 <135 .<165 7-Jun- Il 538 +/- 180 <114 <138 520 +/- 1.69 <119 <174 14-Jun- Il 456 +/-
21-Jun-11 147 <148 <152" 28-Jun-Il 324 +/- 118 <108 <169 5-Jul-11 332 +/- 125 <146 <148 12-Jul- 11 262 +/- 105 <100 <36 19-Jul- 11 379 +/- 159 <103 <137 26-Jul- 11 413 +/- 148 <143 <99 2-Aug- 11 744 +/- 201 <123 <165 9-Aug- I1 878 +/- 189 <90 <164 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 201 I 44
TABLE 8.12 SLUDGE/SEDIMENT ODCM required samples denoted by
- units are pCi/kg, wet SAMPLE DATE LOCATION COLLECTED 1-131 Cs-134 Cs-137 In-Ill 16-Aug- Il 912 + 203 <147 <179 23-Aug- 11 1070 +206 <126 <174 30-Aug- 11 1455 +277 <99 <172 6-Sep-Il 1030 +242 <149 <145 13-Sep-i I 1423 +/--277 <143 <133 WRF 20-Sep- I1 1734 +/- 251 <142 <132 CENTRIFUGE 26-Sep- I1 10,57+/-+/-268 <148 <52 WASTE SLUDGE 3-Oct- I1 850+/-207 <134 <177 11-Oct-11 44i +113 <146 <132 WRF OOS 25-Oct- Il 322 + 139 <144 <169 I-Nov- I1 178 + 103 <134 <140 8-Nov- I1 S43-1256 <106 <114 15-Nov- I1 * <94, <115 22-Nov- I1 2ai172 ,. <116 <169 29-Nov- II 86+/-223 <149 : <165 6-Dec- I1 :627 190 <143 <177 13-Dec- I1 618 150 <161 20-Dec- 11 793+174 <i16- <118 27-Dec-i 1 648 -211 <137- <134 SEDIMENTATION BASIN 2 4-Oct- 11 sample, 1 <11 <12 49 +/- 13 sample 2 <36 90 +/- 17 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 45
TABLE 8.12 SLUDGE/SEDIMENT
- - * *'. ,. -
- t-.- V' COOLING TOWER SLUDGE UNIT APPROXIMATE ISOTOPE ACTIVITY RANGE SAMPLE TYPE CYCLE VOLUME (yd3 ) (pCi/g)
U2R16 253 Co-60: <MDA to,0.090, Cs-134_ 0--A f6 719 . ; 7Towers/canail ludgei ivo -O.39'-
0.18_6C'll9"2 U3R15 379 All A NA NTowers/canal sludge
_<MDA Note: The Cs-134 identified in U2R16 cooling tower sludge is' atypical and is attributed to the effect of air being drawn across the cascading water containing radioactivity from the Fukushima-Daiichi event.
I - S.
I.
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 46
TABLE 8.13 HARD-TO-DETECT RADIONUCLIDE RESULTS Units are PCi/liter Sample Location Well number -'Sample-Date C-14 Fe-55 Ni-63 Sr-90 Unit 1 (outside RCA) A]PP-2 10/28/-2011 -: - <36- <3 <0.19
-,; * '
-2 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 47
LOGDATE ENTRY 11/6/2010 Entered LCO: 3.6.3 Condition C 12:26:46 PM Equip 0OS None Declared SGE-UV-169 and SGE-UV-183 INOPERABLE in anticipation of entering Mode 4. SGE-UV-169 and SGE-UV-183 are not analyzed to close against full system D/P.
Entered Condition C and complying with Required Action C.1 with 3.6.3 permit #175197.
TSCCR #3473269.
- Un-planned LCO entry: - NO
- RMAL Impact: -NO-
- PVAR: N/A
- Initiate a PVAR for emergent issues that result in a LCO entry with an action time of
<=72 hours or any shutdown LCO.
- 3/19/2011 Surveillance completed satisfactorily thereby satisfying LCO 3.6.3, REQUIRED ACTION 2:02:38 AM C.2 to verify the containment penetration flow paths associated with SGE-UV-169 and SGE-UV-183 remain isolated once per 31 days. SGE-UV-169and SGE-UV-183 remain closed and deactivated under permit #175197. Reference TSCCR.#3473269.
Performed: 40ST-9ZZ13 Section 8.0 CONTAINMENT ISOLATION VALVES 7/9/2011 Surveillance 40ST-9ZZ13 (STW0348950) completed satisfactorily thereby satisfying LCO 3:08:28 AM 3.6.3, REQUIRED ACTION C.2 to verify the containment penetration flow paths associated with SGE-UV-169 and SGE-UV-183 remain isolated once per 31 days. SGE-UV-169 and SGE-UV-183 remain closed and deactivated'under permit #175197.
Reference TSCCR #3473269. This also satisfies LCO 3.6.3, Required Action A.2 to verify the containment penetration associated with INOPERABLE valve SGA-UV220 is isolated by 3.6.3 permit #218568 (Reference TSCCR #3803984) and -INOPERABLE valve .GB-UV226 is isolated by 3.6.3 permit #218548 (Reference TSCCR#3803969).
8/6/2011 Surveillance 40ST-9ZZ13 (STW03465074) completed satiSfa-ctorily tlhereby satisfying 5:53:45 AM LCO 3.6.3, REQUIRED ACTION C.2 to verify the containment penetration flow p'aths associated with SGE-UV-169 and SGE-UV-183 remain isolated once per 31 days. SGE-UV-169 and SGE-UV-183 remain closed and deactivated under permit #175197.'
Reference TSCCR #3473269.
10/29/2011 Surveillance completed satisfactorily thereby satisfying LCO 3.6.3, REQUIRED ACTION 3:24:47 AM C.2 to verify the containment penetration flow paths as.sociated With SGE-UV-169 and SGE-UV-183 remain isolated once per 31 days remain closed and deactivated under permit #175197 and LCO 3.6.3, Required Action A.2 for SGB-UV-226 under permit
- 218548. Reference TSCCRS #3473269 & #3803969.
Performed: 40ST-9ZZ13 Section 8.0 CONTAINMENT ISOLATION VALVES 11/26/2011 Surveillance completed satisfactorily thereby satisfying LCC) 3.6.3, REQUIRED ACTION 4:13:00 AM C.2 to verify the containment penetration flow paths associated with SGE-UV-169 and SGE-UV-183 remain isolated once per 31 days remain closed and deactivated under permit #175197 and LCO 3.6.3, Required Action A.2 for SGB-UV-226 under permit
- 218548. Reference TSCCRS #3473269 & #3803969.
Performed: 40ST-9ZZ13 Section 8.0 CONTAINMENT ISOLATION VALVES 12/24/2011 Surveillance Test 40ST-9ZZ13 completed satisfactorily thereby satisfying LCO 3.6.3, 3:15:22 AM REQUIRED ACTION C.2 to verify the containment penetration flow paths associated with SGE-UV-169 and SGE-UV-183 remain isolated, under administrative control of permit
- 175197. Also satisfying LCO 3.6.3, REQUIRED ACTION A.2 to verify the containment penetration flow paths associated with SGB-UV-226 remains isolated, under administrative control of permit #218548. Reference TSCCR# 3473269 & TSCCR#
3803969.
FIGURE 8.1 GROSS BETA IN AIR, 1St- 2 nd Quarter 0.450 0.400 0.350 --o- Site 4 t-Site -- 6A*
0.300 Site 7A
.* 0.250 ---- Site 14A*
U 0.200 _--Site ... 15*
SSite 17A 0.150 0 Site21 0.100 - Site 29*
Site 35 0.050.-.-- Site 40*
-Mean 0.000 . loss
-°slýower 4 J- 16 Cl The abnormally high gross beta results between March 15 and April 5 are attributed to the Fukushima-Daiichi releases.
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 48
FIGURE 8.2 GROSS BETA IN AIR, 3 rd-th Quarter 0.080
.0.070
- '.00
- Site 4 0.060 __.
_/ /____\
¶ Site..
Site 6A*
0.050 . -! Site 7A 0.040 //Site 14A*
....- Site 15"
_~~
-/ Site 17A.
-~ i ' -4Site 21 0.020 :..Site -. 29*
- .
- Site 29*
0.010 -Site35 invalid Site 40*
0.000 Mean
. . . -. 0 0 0 0 a 0 0 0 0 1 6 A 8 6,1 A 4N>
- qe - " -q r'J -1 c
-- :S. ANNUAL RADIOLOGICA ENVIRONMENTAL OPERATING RE.... 2.0....
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 49
FIGURE 8.3 HISTORICAL GROSS BETA IN AIR (WEEKLY SYSTEM AVERAGES)
Gross Beta in Air 2002-2011 (weekly average) 1.000 Elevated due to Fukushima-Daiichi releases
- . - ._ 0.355.
~0.100 i0.010 C4 (~1 ~. ~ 00 0
- 0. 0 0.. . 0 ~0 0 0 0 -
I I I - I -I-~ I-~~ I C.)
C.) C.) 0 C.) C.) C.) C.) C.) C.)
~.) C.) C.) C.)
7' *~ '12:
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 50
FIGURE 8.4 HISTORICAL GROSS BETA IN AIR (ANNUAL SITE TO SITE COMPARISONS) COMPARED TO PRE-OP 0.050 0.040
- Site 4A
- ý. 0.030- -Site St14 16A U
C.
_ 0................... ...........- " ... .... "*S 'Site t l 215
- Site 17A 0.020 -
-Site 21
-Site
-? 29 0.010 Zý N. n to -n 00 a 0 - -Site 35 00 ,. 0 0 .. .. 0S . .. . . . . . . . .. . . it.40 N N r4 N C_
N. N~ (Nl (Nl 0 (N r - e4
'-4 Co 0.
oJ Site 7A is not included since the location changed since the pre-operational period A known high bias has occurred in gross beta data since the onsite laboratory began analysis in 1994. This was a stepwise increase that has carried forward since 1994.
TAe 2011 annual average values are higher due to the Fukushima-Daiichi releases.
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 51
FIGURE 8.5 GROSS BETA IN DRINKING WATER 9
8 7
6
._-5 04 3
2 1
nio samples 0
Jan Feb Mar Apr May Jun"-.'-,-JulI--,...Aug.. Sep Oct Nov Dec NOTES: MDA values plotted as activity (e.g. <2.3 is plotted as 2.3)
The action level is 30 pCi/liter PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 52
FIGURE 8.6 EVAPORATION POND TRITIUM ACTIVITY 4000 3000
~2000.,
1000 0
00 00 N
r-\
00 N
00000000 00 00 00 00 000000 0.4 0. <D0 O\
0 (71 Oý1 C,
-- t'I e ~00 0\ 0-) CJ fn~ 't~ r- 000 ~ 0 12,O' C~l cý 0' 0' 0' ý 0\N 0, ý 0 0 0 0 C' 0 0 0 0
= .~~: =~ ' Z 0 0 0 j 0 0 = 0L 00s 0 0 0, z 0 0 0, I ..L.i~. .1 - -t -
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 53
FIGURE 8.7 SEDIMENTATION BASIN 2 Cs-137
, C7 2 5 0 ..- . . 2 38 .7--
200-10 -
.*,,1,50..
100 -. 40 4 . -
- ,67 *!0 63'. 60 ý"60 :*.66 '7
'* *47 ' '/. 46 4 40-4-4 17
<MDA <MDA 1976 1984 1990 1992 1993 1994 1995 1996 1997 1998 2001 2002- 2003 -2005 2008 2011 onsite onsite soil avg. soilavg...... ... . ...
( n i (Sedimentation Basin #2 accepts site storm runoff, no other gamma emitt'erspresent) ,
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 54
- 9. Thermoluminescent Dosimeter (TLD) Results and. Data The environmental TLD used at PVNGS is the Panasonic Model 812 Dosimeter. The Model 812 is a multi-element dosimeter combining two elements of lithium borate and two elements of calcium sulfate under various filters.
TLDs were placed in fifty locations from, one to thirty-five miles from the PVNGS. TLD locations are shown in Figures 2.1 and 2.2 anid are described in Table 9.1. TLD results for 2011 are presented in Table 9.2. Historical environmenal gamma radiation results for 1985 through 2011 are presented in graphical formr on Figure 9 1 (excluding transit control tLD #45).
Figure 9.2 depicts the environmental TLD results from2:2011 as compared to the pre-operational TLD results (excluding sites #41 and #43, as they were deleted and later assigned to a new location, and #46-50, as. they had no pre.-op TLD at theocation for comparison). The site to site comparisons indicate a direct correlation with respoct to pre-operational, results. It is evident that the offsite dose, as measured by TLDs, has not chan ed, since Palo Verde became operational.
t.-,
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 55
TABLE 9.1 TLD SITE LOCATIONS (distances and directions are relative to, Unit 2 in miles) -
TLD SITE LOCATION LOCATION DESCRIPTION 1 E30 Goodyear 2 ENE24' Scotf-fibby School' 3 E21 Liberty School 4 E16 Buckeye.
5 ESEil" 'Palo Verde'Schobi.i 6* SSE31 APS Gila Bend subs'tation 7 " SE7 ' Old US 80 andA'rlington SdhoolRd.
8SSE4 *' Southen 'Pacific Pipeline Rd. ,.
9 S5 Southern Pacific Pipeline Rd.
'g 3 5 9th AVe.and Rd , . -L`
bmliot ',A..
12 E5 Ave " dBtickkeye-8albriie Rd::
14 -', *.Esi IA oundary.'- . ., ',..
15 NE2 NE site boundary, WRF access road 16 ENE2 ENE site boundary 17 E2 E site boundary 18 ESE2 ESE site boundary 19 SE2 SE site boundary 20 SSE2 SSE site boundary 21 S3 S site boundary 22 SSW3 SSW site boundary 23 W5 N of Elliot Rd 24 SW4 N of Elliot Rd 25 WSW5 N of Elliot Rd 26 SSW4 S of Elliot Rd 27 SW1 SW site boundary 28 WSW1 WSW site boundary 29 WI W site boundary 30 WNW1 WNW site boundary 31 NW 1 NW site boundary 32 NNW1 NNW site boundary 33 NW4 S of Buckeye Rd 34 NNW5 3 9 5 th Ave. and Van Buren St.
35 NNW8 Tonopah 36 N5 Wintersburg Rd. and Van Buren St.
37 NNE5 3 6 3rd Ave. and Van Buren St.
38 NE5 3 5 5 th Ave. and Buckeye Rd.
39 ENE5 3 4 3rd Ave. N of Broadway Rd.
40 N2 Wintersburg 41 ESE3 Arlington School 42 N8 Ruth Fisher School 43 NE5 Winters Well School 44* ENE35 El Mirage
- - .,- - .-;PGS-ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 2011 1C ,.56
TABLE 9.1 TLD SITE LOCATIONS (distances and directions are relaiive:0to Un it, 2 in miles)
TLD SITE LOCATION LOCATION DESCRIPTION 45** Onsite Central Laboratory (lead pig) 46 ENE30 Litchfield Park School 47 E35 Littleton School 48 E24 Jackrabbit Trail 49 ENE 11 Palo Verde Rd.
50 WNW5 S of Buckeye-Salome Rd.
- Site #6 and site #44 are the control locations.
g PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 57
TABLE 9.2 ENVIRONMENTAL TLD RESULTS Units are mrem/std qtr TLD Site # 1st Quarter 2nd Quarter 3rd'Quarter 4th Quarter .Average 21.,8, .21.8 .. 21.9 -26. 1 22.9 22.5:
2 ' 21..8
- 19.4 21.0 21.2 3 2 09,115'. ,."22 .1 25'73 22.6 21.0 4 20.8 23.5 24.3 .22.4 5 21.5 20.8 21.5 23.6 21.9 6 (control) 25.5 24.1 23. 26.9 -25.1 7 23.3 22.7 1 23.15 25.1 23.7 8 21.5 20.7 22.-8, 22 23.3 22.1 9 25.9 25 ..0, 229.2 28.1 a 7 .I 10 22.3 21.2 23.4 25.3 23.1 11 22.2. 23.2
'21.2 22.3 22.3I 23.9 22.9
- f2 1'.6 22.8 22.0 12 13 : ' :2;2'YI4 * "283.
222.93 23.6 23.,8 14 23.3 22.7 24.8 24.5 23.8 15 22.3 21.5 21.8 24.8 22.6 16 18.1 20.4 21.4 21.8 20.4 17 23.3 22.6 24.4 25.9 24.1 18 22.5 21.3 23.2 23.1 22.5 19 24.0 22.9 23.4 26.1 24.1 20 22.9 21.5 24.1 25.1 23.4 21 24.6 22.6 24.7 26.3 24.6 22 25.1 23.5 25.6 24.8 24.8 23 21.4 20.6 22.6 23.2 22.0 24 21.9 20.4 20.4 22.0 21.2 25 22.4 20.8 21.3 23.8 22.1 26 25.7 25.0 26.0 27.3 26.0 27 27.0 25.0 25.2 27.0 26.1 28 24.9 23.2 24.7 25.2 24.5 29 23.0 21.7 24.0 25.5 23.6 30 25.0 23.6 23.8 26.4 24.7 31 21.8 21.2 21.8 23.4 22.1 32 23.1 22.8 24.3 25.5 23.9 33 23.5 23.4 25.2 27.1 24.8 34 26.8 25.5 25.8 28.5 26.7 35 28.5 27.7 30.2 30.0 29.1 36 23.7 24.6 24.9 25.0 24.6 37 23.2 22.3 21.7 23.4 22.7 38 24.4 25.2 25.6 28.4 25.9 39 22.5 21.8 23.0 23.7 22.8 40 23.9 22.5 23.8 23.4 23.4 41 25.2 25.0 25.8 26.9 25.7 42 28.0 29.1 27.5 29.8 28.6 43 25.9 25.5 26.9 28.0 26.6 44 (control) 18.7 18.6 18.9 20.0 19.1 45 (transit control) 5.2 5.8 5.8 7.6 6.1 46 25.5 25.0 24.3 25.9 25.2 47 21.7 22.7 22.1 22.9 22.4 48 22.1 23.0 22.4 23.8 22.8 49 20.0 20.6 20.5 21.4 20.6 50 18.5 17.8 17.0 19.6 18.2
- PTS
, ANNUAL.RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -2011 58
FIGURE 9.1 NETWORK ENVIRONMENTAL TLD EXPOSURE RATES 30.0 28.0 26.0 24.0 O"
22.0 20.0 18.0 1 CI* .'0 r-. 00 (ON CD - e' rn 'n j- 'c r- Co a, o M~ -rt V)
It 'o - 00 0 00 00 00 00 00 c' ' 0 ' 0 0 17, 0 Q' C> 0 0 . 9 The 10-year mean value is for the date range 2002-2011.
," L °' " . . .. .. * . " '. - , . ,.S.
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 59
FIGURE 9.2 ENVIRONMENTAL TLD COMPARISON - PRE-OPERATIONAL VS 2011 3.5 ControlITLD 30 c25.
20
- 15 10
--- Pre-op (1984-1985)
..- 2011 Average Transit C ontrorTLD 5 ' t . i ,
i; i * ; I; ' . Ii '\J '
0 ll*llllIB*lllllWl*14111111111wll 1 3 5 7 9 11 13 15 17 '19 21 23 25 27 29 31 33' 35 37 39 42 45 TLD Number....
I --....... : "' *1, I]. .
The following TLDs are not included on this graph; TLD #41 monitoring location was deleted in June, 2000 diie-to sch661 closiifg (this-TLD wasplaced at new school in 2004)
TLD #43 monitoring location was deleted in 1994 due to school closing (this TLD was placed at a new school in 2007)
TLDs #46-50 are not included since they were not included in the pre-op monitoring program . .
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 60
- 10. Land Use Census 10.1. Introduction In accordance with the PVNGS ODCM, Section" 6.2, the annual Land Use Census was performed in April 2011.
Observati"ons were made in each of the 16 meteorological sectors .to determine the nearest milking animdfs, residences, and gardens of greater than 500 square feet. This census wis completed by driving the roads and speaking with residents.
The -results of the Land Use Census are presented in Table 10.1 and discussed below.
The directions and distances listed ar .in sectors and miles from the Unit 2 containment.
-. ,~ .- , .
.10.2. Census Results Nearest'Resident Jii ;. .
There. was one (1) change in nearest resident status from the previous year. Dose calculations indicated the highest dose to be 0.228 mrermi.'
Milk Animal i ..- :
There, was one (1): change in milk animal status from the previous year. Dose calculations indicated the highest dos'e to be 0.371 mrem. -'
Vegetable Gardens '
There were three (3) changes in nearest garden status. .Dose calculations indicated the highest dose to be 0.683 mrem.
See Table 10.1 for a summary of the specific results and Table 2.1 for current sample locations.
Figures 10.1 through 10.3 provide graphs depicting historical calculated doses for nearest residents, nearest milk receptor, and nearest garden[ receptor locations in'each sector. .'.
Differences in calculated doses are the result of many variables, including;
" Changes in receptor locations from year to year (proximity to the power plant)
- Changes in local meteorology (wind direction, wind speed, precipitation, temperature)
" Concurrent meteorology at the time of effluent releases
- Exposure pathways PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 61
TABLE 10.1 LAND USE CENSUS (Distances and directions are relative to Unit 2 in miles)
NEAREST NEAREST NEAREST MILK . CHANGE RESIDENT GA"RDEN ANIMAL CALCULATED DOiS'E., FROM SECTOR _.... .. .. ...... ._ (COw/GOAT) _ (m0em) 2010 N . 155,. 3.10 .3.66 Resident. 4.15E&02 Garden II.,' ~Garden 2.05E13
.t . .7
!.'. -- "' '"__" _ "I."M ilk 1 62E 01"-
NNE 330 I 305 Resident 7.87E2 Garden 3.5613-01
... .; E. ... I:." I.6L. __ __1_ NOi*
N E* : "iR&',deitufT" '" i 2'lE-'I' E2.16 2.63 4.84 Resident 1.06E-01 Garden GardenAL~ ,*p 6.83E-01 . -Wfilk
_.._............ .. ... ..M ilk
........... . 2.3 6 E -0 1..
I. - 2.81 NONE J. NONE .. Resident
- -9!..6A°. .
ESE 1.89 NONE NONE. Resident 2.28E-01 Resident F _SSE I NONE __NONE NONEt NA t S ,I NONE NONE NONE NA '"
.ssw I NONE NONE NONE NA
.. . J, i i - .1. "' -, 1i ,E.. ." i ' .1. '
WSW 0.751 4.82 NONE Resident 1.18E-01 d
________ I_________
_________ -~_jGarden , 2 .13E -01 -
S0.70 _NONE . I NONE N 'e.sidentr':
R 5..66E-02 WN ;NN.E ,NONE 4, NONE .
.. L 0.93 NONE.: Resident. 370E-02 3:NONE NNW 1.30 4.34 NONE Resident 2.42E-02 GGarden 8.38E-02 .-
COMMENTS:
Dosecalculationsý were performed using the,.GASPAR code and.2010 meteorological data and source term. Dose reported for each location is the total for all three PVNGS Units and is the highest individual organ dose identified.
., ( j ~I' U
S , :.,R A* ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011
.6,2
-FIGURE 101 HISTORICAL COMPARISON OFNEAREST RESIDENT DOSE 4.OOE-01 3.50E-01 3.OOE-01 0 2011 2.50E-01 U 2010 E 2009 2.00E-01 M 2008 I- .2007, E.1.50E-01 m2006 1.O0E-01 . .. 2005
=* ;
- ki 2004 5.OOE-02 ' 2003 O.OOE+O0 02002
.. .,X-.. .... ,.XX ,*.. .XX .,,XX .,*' .:001
- -. S*
Historical annual average most prevalent wind direction is from the SW, next highest is from the N.
This is one reason forthe"higher Gose3-assigned to resideiitsinftlhe S§or.- : .'
K- . a .. 1 Historical annuai average least prevalent wind direction is fi-om the SE, next highest is from the ESE.
This is one reason for the lower doses assigned to residents in the WNW, NW, ard NN1V sectors.
- "* "* . .. . . : ",'2. ,. a .{ * .. ' ' " " . L .*
- , " ' . ; ', .' : / , i *L.' - ,. ' ..
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 63
FIGURE 10.2 HISTORICAL COMPARISON OF NEAREST MILK ANIMAL DOSE 1.40E+00 1.20E+00 02011
.... :M 2010 1.OOE+00 K 2009
.:8.00E-01
.. " 2008 fl,;In 2007 n 2005
)!'4.00E-01
_no milkanimals identified in these secitorsE 2004 2003 ji.g W2002
-2001
..,,O.OOE+OO' 0. O E 0 * .: .,.L"' ' *'2 .
OC(~. 4 4S' 4.
Milk animals include goats and/or cows; Several newjnilk animals -were identified in 2009 that were closer to the power plant than in the past, resulting in generally higher calculated doses in that calendar.year;,._' .-7, ., , ,' .,,l . .
H, .. . .. . .
In 2002 and 2004 the combination of meteorology, milk animal proximity to the plant, and gaseous effluent releases resulted in higher calculated doses in the NNE and NE sectors.
No milk samples have indicated any plant related radionuclides. Additionally, milk animals in the desert environment are normally fed stored feed and are not on pasture. The calculated doses are conservative since they include pastured feed as part of the calculation.
1 ....
"!.GANNUAL
.. RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT- 2011
,6.4
FIGURE 10.3 HISTORICAL COMPARISON OF NEAREST GARDEN DOSE 8.00E-01 7.00E-01 I~ *2011 iq 2009 5.00E-01.. -m-2008 S400OE-01's20 J". x 2006 3!OO-O1 I2005 -
2.OOE-x 2003 lOCE-O - ~ *--- - 2.001 0.u I.I j V. .. '. ; , *I- ' i * .' " 3( j [C* . * , . . '" ' ' ', , ,
Gardens were sporadically identified from year to year. Gardening is not prevalent in the desert environment. In 2001 and 20.O.Z,tbe combination, of mete.roa9gy--.ga&rden proximity. to.,the plant, and gaseous effluent releases resulted in higher calculated doses in the NE and ESE sectors. ,.,
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 65
- 11. Summary and Conclusions The -conclusions are based on a review of -the radio assay results and environmental gamma radiation measurements for the 2011 calendar year. Where possible, the data were compared to pre-operational sample data.
All sample results for 2011 are presented in Tables 8.1-8.13 and do not include observations of
,,naturally occurring radionuclides, with the exception of gross beta in air and gross beta in drinking water. Table 11.1 summarizes the ODCM required samples and is in the format
.required by the NRC BTP on Environmental Monitoring.
1i 131 identified in the Evaporation Ponds, WRF Influent,:WRF Centrifuge ,,sludge'.iand Reservoirs is the result of offsite sources and appears in the effluent'sewage from Phoenix. !The levels of 1-131. detected in these locations are consistent with levels.identified in preyious years.
ý'Tritium concentrations identified in surface water onsite have been attributed:-toi PVNGS
,permitted gaseous effluent releases and secondary plant releases. These *concentrations! are consistent with* historical values. '* 4,2 *' , "I, *"
4 EnvironmentaL radition levels-ate co.nsistenL with measuuumpeU~s_. repo~Qrted jn previous Pre- .
operational and Operational Radiological Environmental annual reports, References I and 2.
- Theý'r-'e -i~as;w
ý eas-rable #diolbdai aimpacthni'the'enviriomeeniin'2011,resultingfrom the operation* J -f. -I ,. i -- , . I. , ,. .9 ,
.. ... PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011
.'66
TABLE 11.1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL
SUMMARY
Palo Verde Nuclear Generating Station Docket Nos. STN 50-528/529/530 Maricopa County, Arizona Calendar Year 2011 Medium or Lower Limit of All Indicator Location with Highest Annual Mean Control Locations Pathway Sampled Type and Total Detection (LLD) Locations Number of (Unit of Number of (from Table 6.1) " Name Mean (W.. Mean (f)a Nonroutine Measurement) Analyses Mean Distance and Range Range. Reported Performed Range Direction Measurements Direct Radiation TLD- 200 NA 23.6 (1881188) Site #35 29.1 (4/4)1 22.1 (8/8) 0 (mrem/std. qtr.) 17.0 -30.2 8 miles 3300 27.7 -30.2 18.6-26.9 Air Particulates Gross Beta- 516 0.010 0.046 (465/465) Site #6A 0.048(151i5) 0.048 (5i/51) 0 (pCi/m 3) 0.016 -.0.372 13 miles 158' 0.018 - 0.388 0.018 - 0.388 Gamma Spec. - 70 1-131 (weekly) NA 0.213 (18/27) Site #21 0.250 (2/3) 0.160 (2/3) 30 0.100 - 0.370 3 miles 1800 0.170 - 0.330 0.100 - 0.220 1-132 (weekly) NA 0.045 (2/27) Site #35 0.060 (1/3) <LLD 30
-... 0.030- 0.060 - 8 milts 330. 0.06070.0.6.0 .-
Te-132 (weekly) NA 0.038 (4/27) Site #6A 0.060(1/3) 0.060 (1/3) 30 0.030 - 0.050 13..n-iles. 158' 0.060- 0.060 0.060 - 0.060 Cs- 134 (weekly) 0.05 0.054 (18/27) Site!7A 0.075 (2/3) 0.055 (2/3) 30' 0.030 - 0.080 3 miles 900 0.070 - 0.080 0.050 - 0.060 Cs-137 (weekly) 0.06 0.066 (.18/27). Site #21 0.080 (2/3) 0.065 (2/3) 30 0.040 0.090
- 3 miles 180? 0.0*80 0.680 0.050 - 0.080 1-131 ..(quarterly) NA 0.021 (9/36) . ,, Site #6A - 0.032.(1/4) 0.032 (1/4) 0, 0.016*-0.029 13 miles 158' 0.032 - 0.032 0.032 - 0.032 Cs-134 (quarterly) 0.05 0.009 (7/36-) Site #7A 0.010'+) 0.UU8kI/4) 0 0.007.--0.010. 3 miles 124, .. 0.010-0.010 0.008-0.008 Cs- 137 (quarterly) 0.06 0.009 (5/36) Site #40 0.011(1/4) 0.006(1/4).' 0 0.007- 0.011 2 miles 3580 0.011 - 0.011 0.006 - 0.006 -
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 67
TABLE 11.1 ENVIRONMENTAL RADIOLOGICAL.MONITDR1NG PROGRAM. ANN.UAL
SUMMARY
Palo Verde Nuclear Generating Statiqn " Docket Nos. STN 50-528/529/530 Maricopa County, Arizona ' Calendar,Year 2011 Medium or Lower Limit of 411 Indicator Location výi' Highest Annual Mean Control Locations Pathway Sampled Type and Total Detection (LLD) :Locatio0ns.4Number of (Unit of Number of (from Table 6.1) Name M fi((f)a Mean (f)' Nonroutine Measurement) Analyses ýMean (9' Dista0ce and Range Range Reported Performed Range" Direction. I.Measurements Air Radioiodine Gamma Spec. - 516 (pCi/m3) 1-131 0.07 0.601 (27/464) ,;Site #29 0Q.825 (2/52) 0.630 (3/51) 0
(,0 040- 1.J40 *1mile 27 0 " 0.510- 1.140 0.100 7' 1.260 Broadleaf . Gamma Spec. -99.
Vegetation 1-131 60 <LLD- Site #62 53 (1/9) '53 (1/9) 0 (pCi/Kg-wet) ,, .;26,miles,75' , 53 .3 53-53
$. . ,- .,-..-..-. o Cs-134 60 <LLD NA <"'LLD <ýLLD 0 Cs-137 80 <LLD NA, .. <LLD. <LLD 0 Ground Water H 8 2000 <LLD NA <LLD NA 0 (pCi/liter)
Gamma Spec. - 8 Mn-54 15 <LLD-
<. . -NA'- .- <LLD. NA 0 Fe-59 .30 < NA 0 Co-58 15 <LLD NA <LLD NA- 0 Co-:60 15 . <LLD. -. iA" . - . -<LLD- NA 0-Zn-65 30 ... <LLD' .,NA .<LLD NA 0 Zr-95 30 <LLD $1LbA ' NA 0
- Nb-95 15 ' <LLD- ,-----NA -.. .. <LLD ._..... NA 0 1-131 15 .<LLD .<LLD NA
' .0 NA Cs-134 15 <LLD ,.' - .. :4<LLD "RA 0 Cs-137 _.18 ..:<LLD NA <LLD NA 0 Ba-140 60 <LLD a6 NA <LLD NA La-140 .... 15 <LLD LD_...D . ' NA 0
., .. . a: .- - .,a- ' '-a ) I. ,. . . ". , " , :, .,' . : . .
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 68
TABLE 11.1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL
SUMMARY
Palo Verde Nuclear Generating Station Docket Nos. STN 50-528/529/530 Maricopa County, Arizona " ' Calendar Year 2011 Medium or Lower Limit of All Indicator Location with Highest Annual Mean Control Locations Pathway Sampled:' Type and Total Detection (LLD) Locations Number of (Unit of Number of (from Table 6. 1) - 'Naxe Mean (f, Mean (f)a Nonroutine Measurement) Analyses Mean (f)a Distance and Range Range Reported Performed .... Range . Direction.--- - -Measurements Gross Beta - 46 4.0 4.0 (24/46) Site #48' 5.5 (5/12).7 NA 0 2.5 -8.4 1 rmi.e 2360, 3.'8 -8.4 H 16 2000 <LLD NA <LLD NA 0 Gamma Spec. - 46 Drinking Water Mn-54 15 <LLD NA'. <LLD..- NA 0 (pCi/liter) Fe-59 30 <LLD. NA <LLD'.' NA 0 Co-58 15 <LLD: NA <LLD NA 0 Co-60 15 <LLD NA <LLD NA 0 Zn-65 30 <LLD 'NA <LLD"- NA 0 Zr-95 30 <LLD !qA <LLD NA 0 Nb-95 15. <LLD NA <LLD. NA 0 1-131. 1is <LLD Nk." <LLD-. NA 0 Cs-134 15" <LLD-. NA', <LLDL NA 0 CS4137 18 <LLD. NA <1LD0 NA 0 Ba-140 60.. <LL.D NM <LLD' NA 0 La4140 15 <LLD NA <LLD: NA 0 Gamma Spec.'- 22.
Milk 1-131 1.0 1.7 (2/10) Site #53 4.8(2/12) 4.8(2/12) 0 (pCi/liter) 1.3-2.0 30 miles 450 4.6-5.0 4.6-5.0 s- 134 15 1.5.(3/10) # 5i4,
, 1.5 (3/10) <LLD 0
.1'3 - 1.7 -4hmiesZ22. _ 1.3 -1.7 Cs-137 18.' 2:10(3(:10)
- 2. Sitefl54 - 2..0(3/10) <LLD 0 1.9:2.0_ 2'20 .9- 2.0 "
Ba-140 60 <LLD NA <LLD <LLD 0 La- 140 15 <LLD NA <LLD <LLD 0 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 69
TABLE 11.1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL
SUMMARY
Palo Verde Nuclear Generating Station . Docket Nos. STN 50-528/529/530 Maricopa County, Arizona Calendar Year 2011 Medium or Lower Limit of All'Indi'oator Ldociii6n 3rith Highest Annual Mean Control Locations Pathway Sampled Type and Total Detection (LLD) Locati6ons - " Number of (Unit of Number of (from Table 6.1) Na e Mean (f)a Mean (f)a Nonroutine Measurement) Analyses .Kean' Di~tance and Range Range Reported Performed kan e Direction Measurements Gamma Spec. -.20 Mn-54 15 <LLD NA <LLD NA 0
.Fe-59 30 <LLD ---. . NA . -.....<LD - NA- 0 Co0.58 ,.15 <LLD ýILA ":LED :'-NA 0 Co-60
.. 15 <LLD 'j ,A "<LD 'NA 0
.Znz65 ;30 .L4D "NA NA N<LED 0 Zr-95 30 :<LLD "'NiA -<LLD NA 0 Nbn951 5 <LLD <.A<LLD NA 0 Surface Water 1-131 15 23 (2720) Site #61 27 (1/4) NA 0 (pCi/liter) 18 -'27 Onsile 670 27 -27
-. .. Cs-134 , 15 '.<LD '1A _<LLD NA 0 Cs-137 18 <LD 'NA .<LLD "NA 0 Ba-140 60 " <LLD NA <LLD NA 0 La- 140 15 <LLD NA <LLD NA 0 H 20 3000 624 (0/20)A 0 62 (i62). ýite-.#'9j*6(i)N
-- *.... 317-956 --. .nsite-180°--.....
- 0. 9.36 -.956- .....
(a) Mean and range based upon detectable measurements only. Fractio-6f-det-ctable measurements at specified locations is indicated in parentheses. (f) -:
NOTE: Miscellaneous samples that are not listed on Tables 2.1 and 9.1 (not ODCM required) are not inclhded on this table.
PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 70
- 12. References
- 1. Pre-Operational Radiological Monitoring Program, Summary Report 1979-1985
- 2. 1985-2010 Annual Radiological Environmental Operating Reports, Palo Verde Nuclear Generating Station
- 3. Palo Verde Nuclear Generating Station Technical Specifications and Technical Reference Manual
- 4. Offsite Dose Calculation Manual, PVNGS Units 1, 2, and 3
- 5. Regulatory Guide 4.1, Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants
- 6. Regulatory Guide 4.8, Environmental Technical Specifications for Nuclear Power Plants
- 7. NRC Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979 (Incorporated into NUREG- 1301)
- 8. NEI 07-07, Nuclear Energy Institute, Industry Ground Water Protection Initiative - Final Guidance Document, August 2007 PVNGS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 71