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                   --      -        :                              TABLE OF CONTENTS                                                                    -                      .-
                   --      -        :                              TABLE OF CONTENTS                                                                    -                      .-
TABLE OF CONTENTS.
TABLE OF CONTENTS.
TABLE O F CO  NTENTS
TABLE O F CO  NTENTS LIST OF FIGURES ............................-------------------------------------                                                                                                                      ii LIST O F TA      BLES ......... ..;::;;::....................................................................'
                      .        ...................................  .  ...  ... ...        . ...........            . ........        .... ... ......................
LIST OF FIGURES ............................-------------------------------------                                                                                                                      ii
                                                                .
LIST O F TA      BLES ......... ..;::;;::....................................................................'
LIST~                          OF                  TA.E
LIST~                          OF                  TA.E
                                                                          .        .
                                                                                    ... . .
                                                                                          '.
                                                                                                              ,
                                                                                                                              ..    ..                          .    -
                                                                                                                                                                                                       .'iv I. EXECUTIVE  
                                                                                                                                                                                                       .'iv I. EXECUTIVE  


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FIGURE B-4    RADIOLOGICAL ENVIRONMENTAL SAMPLING'LOCATIONS 5 TO 25 MILES FROM THE REACTOR BUILDING                            ----                  B-6 z~~~-      .~- -o            p I48;s
FIGURE B-4    RADIOLOGICAL ENVIRONMENTAL SAMPLING'LOCATIONS 5 TO 25 MILES FROM THE REACTOR BUILDING                            ----                  B-6 z~~~-      .~- -o            p I48;s
                                                                     ..      I '      ...
                                                                     ..      I '      ...
                                                                                                     , I
                                                                                                     , I Rancho Seco Nuclear Station              *111
                                                            . .                    ;
Rancho Seco Nuclear Station              *111
* 2004 AREOR
* 2004 AREOR


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  *.11
  *.11
                       ~.                            ., -....... .  ....... -. -....
                       ~.                            ., -....... .  ....... -. -....
                                                                              ,. ..... ,..
B-1      RADIOLOGICAL ENVIRONMENTAL MONITORING SITES AND MAP LOCATIONS                                          *B-7 C-1      2004 INTERLABORATORY.COMPARISON.PROGRAM                                .          .                  .-4 E-1      REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES                .              .                                              E-1 0 E-2    .MAXIMUM (REQUIRED) LLD VALUES FOR ENVIRONMENTAL SAMPLES',- ...                                      E-1I:
B-1      RADIOLOGICAL ENVIRONMENTAL MONITORING SITES AND MAP LOCATIONS                                          *B-7 C-1      2004 INTERLABORATORY.COMPARISON.PROGRAM                                .          .                  .-4 E-1      REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES                .              .                                              E-1 0 E-2    .MAXIMUM (REQUIRED) LLD VALUES FOR ENVIRONMENTAL SAMPLES',- ...                                      E-1I:
F-1      2004 WEEKLY AIR SAMPLE  
F-1      2004 WEEKLY AIR SAMPLE  
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*F-7      2004 RUNOFF WATER                  '                                                                    F-7 F-8    2004 SURFACE WATERE;                                                                                    F-8 F-9    2004 DRINKING WATER                                                                                    F-10
*F-7      2004 RUNOFF WATER                  '                                                                    F-7 F-8    2004 SURFACE WATERE;                                                                                    F-8 F-9    2004 DRINKING WATER                                                                                    F-10
                                                                                                       . i
                                                                                                       . i
                                . .
                                                                                                         . .. 1, T
                                                                                                         . .. 1, T
                                             . N Ranc'ho- Se'co'Nu'clear Station            ' iv                                                2004 AREOR
                                             . N Ranc'ho- Se'co'Nu'clear Station            ' iv                                                2004 AREOR
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                                       -ri. .
                                       -ri. .
C*            .                                                                  .
C*            .                                                                  .
                                                                                                                                                                          .,
                                                                               '1 V.
                                                                               '1 V.
                                                                                                       ,.  'C''
                                                                                                       ,.  'C''
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Station proper did not contribute an observable component to-the recorded direct gamma radiation field. This Luxel data supports the Gaseous Effluent Exposure Pathway conclusions and supports. the conclusion that the Plant has no-direct radiation effect on the.;environment.
Station proper did not contribute an observable component to-the recorded direct gamma radiation field. This Luxel data supports the Gaseous Effluent Exposure Pathway conclusions and supports. the conclusion that the Plant has no-direct radiation effect on the.;environment.
Luxel monitoring badges placed near the effluent stream Was used to evaluate the dose from this area. Dose levels at these locations are higher than the mean of the control and indicator locations reported. This above average dose is due to elevated soil activity due to historic liquid effluent releases. Luxel badge locations around the ISFSI outside fence (required by the ISFSI License) show higher readings, attributed to the fuel stored in the ISFSI, and are within design calculations.
Luxel monitoring badges placed near the effluent stream Was used to evaluate the dose from this area. Dose levels at these locations are higher than the mean of the control and indicator locations reported. This above average dose is due to elevated soil activity due to historic liquid effluent releases. Luxel badge locations around the ISFSI outside fence (required by the ISFSI License) show higher readings, attributed to the fuel stored in the ISFSI, and are within design calculations.
                                                            . ,
                                                                                   .    : .    . 2004. R  -
                                                                                   .    : .    . 2004. R  -
R Rancho Seco Nuclear Station                                    4                              2004 AREbR
R Rancho Seco Nuclear Station                                    4                              2004 AREbR
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The 2004 Land UCse Census indicates the liquid/ fish and liquidl irrigated vegetation pathways are potential exposure pathways. Thefish pathway-ddse commitment calculation uses conservative default fish consumption factors instead of using actual Land Use Census data. Also, fhdose commitnent calculation'uses fish sample analysis data derived from fish samples collected from the plant effluent stream in 2004. 1,Vegetation sample, analysis results indicated no radioactivity attributable to station operatlbnin 2004via thie liq'uid!  -
The 2004 Land UCse Census indicates the liquid/ fish and liquidl irrigated vegetation pathways are potential exposure pathways. Thefish pathway-ddse commitment calculation uses conservative default fish consumption factors instead of using actual Land Use Census data. Also, fhdose commitnent calculation'uses fish sample analysis data derived from fish samples collected from the plant effluent stream in 2004. 1,Vegetation sample, analysis results indicated no radioactivity attributable to station operatlbnin 2004via thie liq'uid!  -
irrigated vegetation pathway;. therefore, no dose commitment calculations were performed for this pathway. A"          '            ;' -                  '          .
irrigated vegetation pathway;. therefore, no dose commitment calculations were performed for this pathway. A"          '            ;' -                  '          .
                                   .N                                        ...          4
                                   .N                                        ...          4 I.
                                                            -  .
I.
Rancho Seco Nuclear Station                          5        '2004                    AREOR
Rancho Seco Nuclear Station                          5        '2004                    AREOR


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I .1                      11-1
I .1                      11-1
                                                         ; -, V, .-
                                                         ; -, V, .-
                                                                        .;    ,
Notes:'        (a)      Reported in'the'20'04 Annual Radiological Effluent Release Report (b)    'Calculated using Cs-1 37 activity for fish samples (Appendix F, Table F-5).
Notes:'        (a)      Reported in'the'20'04 Annual Radiological Effluent Release Report (b)    'Calculated using Cs-1 37 activity for fish samples (Appendix F, Table F-5).
(c)      The observed dose commitments for doses reflect the age group that could have received the highest annual dose commitment from the liquid source term Rancho Seco Nuclear Station                        6                              2004 AREOR
(c)      The observed dose commitments for doses reflect the age group that could have received the highest annual dose commitment from the liquid source term Rancho Seco Nuclear Station                        6                              2004 AREOR
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         => F-7                                  'Runoff          Water
         => F-7                                  'Runoff          Water
         =>        F-8                          -Surface Water
         =>        F-8                          -Surface Water
         => F-9                                    Drinking Water
         => F-9                                    Drinking Water I .
                                        ,.                      ;.      - .
I .
                .    .                    .  .  .            ..
                         , . S            .    .          .
                         , . S            .    .          .
                            .      .              . - .                ,
                        ,            ,      -          ::        ....
          .  ..........                          .        .
* 5        ,      .  . .
* 5        ,      .  . .
Rancho Seco Nuclear Station                                                _ 10    2004 AREOR
Rancho Seco Nuclear Station                                                _ 10    2004 AREOR
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95.2 (12/12)          RMS0.6MO            120.6 (8/8)          NA                    0' Co                150 (19.9-315)            0.6[mies 2480 (19.9-315)
95.2 (12/12)          RMS0.6MO            120.6 (8/8)          NA                    0' Co                150 (19.9-315)            0.6[mies 2480 (19.9-315)
IC                15:0          130.5 (12112)        RMSO.6MO            156.8 (8/8)          NA
IC                15:0          130.5 (12112)        RMSO.6MO            156.8 (8/8)          NA
                                                         -    (59.5-268)            0.6 miles  2480  (109-268)            NA                    0
                                                         -    (59.5-268)            0.6 miles  2480  (109-268)            NA                    0 1
_
4Cs.            150 .                LLD                          <LLD                      NAO Fish-*,,,
1 4Cs.            150 .                LLD                          <LLD                      NAO Fish-*,,,
(pCi/kg)            y-spec    '
(pCi/kg)            y-spec    '
130                <LLD                            <LLD                      NA                    0
130                <LLD                            <LLD                      NA                    0
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ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL 2510 Name of Facility Rancho Seco Nuclear Station Docket No. DPR-541.SNM Location of Facility Sacramento, California                                Reporting Period Januarv - December 2004 (County,        State)
ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL 2510 Name of Facility Rancho Seco Nuclear Station Docket No. DPR-541.SNM Location of Facility Sacramento, California                                Reporting Period Januarv - December 2004 (County,        State)
                                   -    .        .    -    ~ . I    , i~, 70*;;
                                   -    .        .    -    ~ . I    , i~, 70*;;
                                                                                                               .11 .                                              l Number of
                                                                                                               .11 .                                              l Number of Lower. - .. All Indicator                        Location with Highest-Annual              Control locations Medium or ' ': , Type and                                                                                                                                    Nonroutine Pathway      -    .Total . . !.imit of . -I.. .'Locations                --" ar"':'                      Mean                        Mean (f) a Range              Reported Sampled'          Number of Detection                              Mean (f)                  Name' '            : Mean (fl a                              Measurements
                                                                                                              . *    .
     - (Unit of -. I Analysis                ,, (LLD) b                      Range                Distance                Range Measurement)        Performned                                  .        .4  I~        ..
Lower. - .. All Indicator                        Location with Highest-Annual              Control locations Medium or ' ': , Type and                                                                                                                                    Nonroutine Pathway      -    .Total . . !.imit of . -I.. .'Locations                --" ar"':'                      Mean                        Mean (f) a Range              Reported Sampled'          Number of Detection                              Mean (f)                  Name' '            : Mean (fl a                              Measurements
     - (Unit of -. I Analysis                ,, (LLD) b                      Range                Distance                Range
:' - -
Measurement)        Performned                                  .        .4  I~        ..
                                                                                                   .& Direction' -''
                                                                                                   .& Direction' -''
RWW0.8DO: 3.84 (3/4)                      3.27 (3/4)              0 Well Water          Gross 3                    4.                  3.84 (3/4)
RWW0.8DO: 3.84 (3/4)                      3.27 (3/4)              0 Well Water          Gross 3                    4.                  3.84 (3/4)
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                                                                                                                                                     <LID                  0 Tntium                  1000                  -LLLDD
                                                                                                                                                     <LID                  0 Tntium                  1000                  -LLLDD
                                                                                                                     <LLD      .
                                                                                                                     <LLD      .
                                                                                      ,.                                -      -      -
                             'y-spec        ,
                             'y-spec        ,
                                                                                                                     <LLD                          <LLD                  0
                                                                                                                     <LLD                          <LLD                  0
Line 321: Line 291:
0-
0-
                           'Cs___ .            '10                              <LLD                                  <LLD          ;<LD; LLD                              <LLD                          <LLD                  0 Cs                      10            ;
                           'Cs___ .            '10                              <LLD                                  <LLD          ;<LD; LLD                              <LLD                          <LLD                  0 Cs                      10            ;
                                                                                                                     <LD                            NA                    0 Runoff Water          Tritium                2000                      <LLD
                                                                                                                     <LD                            NA                    0 Runoff Water          Tritium                2000                      <LLD (pCi/L              (31)          _:                                  ;    .
                                                                                                            ,      .,    ,      _                                  .-
(pCi/L              (31)          _:                                  ;    .
y-spec,
y-spec,
                                                                                                                     <LLD                            NA.                  0 5                      <LLD
                                                                                                                     <LLD                            NA.                  0 5                      <LLD
Line 343: Line 311:
All Indicator        Location with Highest Annual        Control locations      Number of Medium or            Type and                Lower Locations                          Mean              -      Mean    a          Nonroutine Pathway                Total            Limit of Mean                      ame                                                    Reported Sampled          Number of            Detection (LLD)                  Range          Distance            Range                                  Measurements (Unit of          'Analysis' Measurement)          Performed                                                      & Diieutqon
All Indicator        Location with Highest Annual        Control locations      Number of Medium or            Type and                Lower Locations                          Mean              -      Mean    a          Nonroutine Pathway                Total            Limit of Mean                      ame                                                    Reported Sampled          Number of            Detection (LLD)                  Range          Distance            Range                                  Measurements (Unit of          'Analysis' Measurement)          Performed                                                      & Diieutqon
                                                                             <LLD                          <LLD                        <LLD                  0 Surface Water            Tritium              2000.
                                                                             <LLD                          <LLD                        <LLD                  0 Surface Water            Tritium              2000.
_
_(pCi/L)                t64) y-spec
_(pCi/L)                t64) y-spec
                                                                                             =            <LLD                        <LLD                  0 4Mn                          1
                                                                                             =            <LLD                        <LLD                  0 4Mn                          1
                                                         ).                  <LLD          -
                                                         ).                  <LLD          -
                                                                                                                                .
                                                                                     -                    <LLD                        <LLD                  0
                                                                                     -                    <LLD                        <LLD                  0
                           - Go                        15                  <LLD i            <LLD,                        <LLD                      -<LLD                  0
                           - Go                        15                  <LLD i            <LLD,                        <LLD                      -<LLD                  0
Line 360: Line 326:
                                                       ;15          '      <LLD                          <LLD                        <LLD                  0 bD
                                                       ;15          '      <LLD                          <LLD                        <LLD                  0 bD
                                                       .'30-.
                                                       .'30-.
                                                            *
                                                                   -'        <LLO        -        -      <LLD                        <LLD                  0 Zn
                                                                   -'        <LLO        -        -      <LLD                        <LLD                  0 Zn
_            -
                                                                             <LLD'                        <LlD-    '-'              <LLD                  0 1                      J/Cs                        10              -
                                                                             <LLD'                        <LlD-    '-'              <LLD                  0 1                      J/Cs                        10              -
4 a acs            l          10                  <LLD                          <LLD                I      <LLD                  0 at specified Mean and Range based upon detectable measurements'only. Fraction of detectable measurements locations is indicated in parentheses. (f) for information on determining LLD values from Table E-2. See page E-8, 'SENSITIVITY OF THE REMP MEASUREMENT PROCESS',
4 a acs            l          10                  <LLD                          <LLD                I      <LLD                  0 at specified Mean and Range based upon detectable measurements'only. Fraction of detectable measurements locations is indicated in parentheses. (f) for information on determining LLD values from Table E-2. See page E-8, 'SENSITIVITY OF THE REMP MEASUREMENT PROCESS',
Line 405: Line 369:
==SUMMARY==
==SUMMARY==


Inhalation, Ground Plane and Water Consumption The 2003/ 2004 census determined that seven of tlie 16 radial sectors have residences that are within the 2-mile (3219 meters)Land Use Ce'nsus radius. The closest residence in each of the seven sectors is identified below-
Inhalation, Ground Plane and Water Consumption The 2003/ 2004 census determined that seven of tlie 16 radial sectors have residences that are within the 2-mile (3219 meters)Land Use Ce'nsus radius. The closest residence in each of the seven sectors is identified below-Sector              Dlsi't6e          Ranking (Nearest to
                                                                                  .
Sector              Dlsi't6e          Ranking (Nearest to
                               . ___L____      -              .Farthest)
                               . ___L____      -              .Farthest)
A                >3219              NA B                -. 219              NA-C                    42              3
A                >3219              NA B                -. 219              NA-C                    42              3
Line 490: Line 452:
B-3                                  2004 AREOR Rancho Seco Nuclear Station
B-3                                  2004 AREOR Rancho Seco Nuclear Station


S
S Figure B-2  Radiological Environmental Sampling Locations within I mile from the Reactor Building Rancho Seco Nuclear Station            B-4                          2004 AREOR
                                            -------
Figure B-2  Radiological Environmental Sampling Locations within I mile from the Reactor Building Rancho Seco Nuclear Station            B-4                          2004 AREOR


           - - -  BMW PAoPEKrY Figure B-3  Radiological Environmental Sampling Locations from I to 5 miles from the Reactor Building Rancho Seco Nuclear Station            B-5                          2004 AREOR
           - - -  BMW PAoPEKrY Figure B-3  Radiological Environmental Sampling Locations from I to 5 miles from the Reactor Building Rancho Seco Nuclear Station            B-5                          2004 AREOR


    .
             -- SUMC PROMMTY DOtDRY Figure B-4    Radiological Environmental Sampling Locations 5 to 25 miles from the Reactor Building I
             -- SUMC PROMMTY DOtDRY Figure B-4    Radiological Environmental Sampling Locations 5 to 25 miles from the Reactor Building I
Rancho Seco Nuc!ear Station            B-6                          2G04 AREOR
Rancho Seco Nuc!ear Station            B-6                          2G04 AREOR
Line 518: Line 477:
Table B-1 (Continued)
Table B-1 (Continued)
Radiological Environmental Monitoring Sites and Map Locations Collection                          Description of Location                Miles  Sector Sample Type        ID Code        Class  Map Location No.
Radiological Environmental Monitoring Sites and Map Locations Collection                          Description of Location                Miles  Sector Sample Type        ID Code        Class  Map Location No.
                                                                                                                                                          .
                               ,_ ,_        _Frequency
                               ,_ ,_        _Frequency
_    NNW        Permeter Fence N/O Spray Ponds; #1        0.3    R LUXEL.      RTLO.3RO        IND.              31                Quarterly Quarterly              NE Perimeter Fence/ parking lot NE comner; #2        0.3    C LUXEL        RTL0.3C0      IND.              32 Quarterly              W Perimeter Fence road/ pole/ top of hill; #3        0.3    N LUXEL        RTL0.3NO        IND.              17 Quarterly          SW Perimeter Fence road near RS lake filters; #4        0.3    L LUXEL        RTLO.3LO        IND.              20 Quarterly                Perimeter Fence/ S/O of Admin. Bldg.; #5            0.3    H LUXEL.      RTLO.3H;0      IND.              33 Quarterly              Photovoltaic Facility/ HcfthLFnc6 (NRC); #        -  0.4    F LUXEL        RTLO.4F0      IND.              34 Rt. 104 entrance to Rancho Seco #7"              0.5. C LUXEL        RTLO.5CO        IND.        -      35Quarterly.
_    NNW        Permeter Fence N/O Spray Ponds; #1        0.3    R LUXEL.      RTLO.3RO        IND.              31                Quarterly Quarterly              NE Perimeter Fence/ parking lot NE comner; #2        0.3    C LUXEL        RTL0.3C0      IND.              32 Quarterly              W Perimeter Fence road/ pole/ top of hill; #3        0.3    N LUXEL        RTL0.3NO        IND.              17 Quarterly          SW Perimeter Fence road near RS lake filters; #4        0.3    L LUXEL        RTLO.3LO        IND.              20 Quarterly                Perimeter Fence/ S/O of Admin. Bldg.; #5            0.3    H LUXEL.      RTLO.3H;0      IND.              33 Quarterly              Photovoltaic Facility/ HcfthLFnc6 (NRC); #        -  0.4    F LUXEL        RTLO.4F0      IND.              34 Rt. 104 entrance to Rancho Seco #7"              0.5. C LUXEL        RTLO.5CO        IND.        -      35Quarterly.
Quarterly                            Tokay Substation; #11      .I  -      0.8    K LUXEL        RTL6.6KO        IND.              36 Quarterily      'In Clay atTfpling's Residence 11633 Clay Station Rd;-      2.1    M LUXEL        RTL2.7MO        IND.              14
Quarterly                            Tokay Substation; #11      .I  -      0.8    K LUXEL        RTL6.6KO        IND.              36 Quarterily      'In Clay atTfpling's Residence 11633 Clay Station Rd;-      2.1    M LUXEL        RTL2.7MO        IND.              14
                                           .        _      _                            .-.                              ..    .. . -#16
                                           .        _      _                            .-.                              ..    .. . -#16
                      .._____  _
                                                                       -- _Quartedy  _              Elliott Cemetery NearAngelo Dairy; #17          .8.2    K LUXEL        RTL8.2KO        IND.            -37        -  -
                                                                       -- _Quartedy  _              Elliott Cemetery NearAngelo Dairy; #17          .8.2    K LUXEL        RTL8.2KO        IND.            -37        -  -
Quarterly -      Sam Jaber Residence/ 60i Carbondale Rd/ lone; #18          7.8    C LUXEL        RTL7.8CO        IND.              38    --
Quarterly -      Sam Jaber Residence/ 60i Carbondale Rd/ lone; #18          7.8    C LUXEL        RTL7.8CO        IND.              38    --
Line 580: Line 537:
Water.                5/6/04      Zri-65                - 320.0 L                      341.5        224.00-416.00- - -
Water.                5/6/04      Zri-65                - 320.0 L                      341.5        224.00-416.00- - -
                   ,    ,    ~~~I  ;      '    '            -'a'"'
                   ,    ,    ~~~I  ;      '    '            -'a'"'
                                                              '"'-:-  '-                  -'''''--
                                                                           .    . . I ..            . .
                                                                           .    . . I ..            . .
I.  ..        .    ..
I.  ..        .    ..
                                                    ,.....
                                                                            ..
Rancho Seco Nuclear Station                                                              C-5                                      2004 AREOR
Rancho Seco Nuclear Station                                                              C-5                                      2004 AREOR


Line 607: Line 561:
2004 INTERLABORATORY COMPARISON PROGRAM Sample          Assay                DOE          Eberline      Control.Limits Sample Type                                                                                                    ll (DOE MAPEP-04-MaW12)                  Date              Type            Result          Result 11/19/04        Cs-134              208        209.2        145.60-270.40 Water 11/19/04        Cs-137              250        253.3        175.00-325.00 Water 11/19/04 Co-60                      163        171.3        114.10-211.90 Water Water                                11/19/04 Tritium                    82.9      84.55        58.10-107.90 11/19/04        Mn-54              267        281.6        186.90-347.10 Water Water                                11/19:04 Zn-65                      208        209.2        145.60-270.40 (DOE MAPEP-04-GrWI2.
2004 INTERLABORATORY COMPARISON PROGRAM Sample          Assay                DOE          Eberline      Control.Limits Sample Type                                                                                                    ll (DOE MAPEP-04-MaW12)                  Date              Type            Result          Result 11/19/04        Cs-134              208        209.2        145.60-270.40 Water 11/19/04        Cs-137              250        253.3        175.00-325.00 Water 11/19/04 Co-60                      163        171.3        114.10-211.90 Water Water                                11/19/04 Tritium                    82.9      84.55        58.10-107.90 11/19/04        Mn-54              267        281.6        186.90-347.10 Water Water                                11/19:04 Zn-65                      208        209.2        145.60-270.40 (DOE MAPEP-04-GrWI2.
11/19104        G-ross              4.07      4.35          2.05-6.15 Water
11/19104        G-ross              4.07      4.35          2.05-6.15 Water
_ _
___        Beta                      -      ____-_-__      --
___        Beta                      -      ____-_-__      --
                                                                             -..                                              -l (DOE N!APEP-04-MaS12)                                      _-
                                                                             -..                                              -l (DOE N!APEP-04-MaS12)                                      _-
Line 614: Line 567:
                 .                                11/19/04 1,Mn-54                  '485        3a6.4,        339.29-630.11
                 .                                11/19/04 1,Mn-54                  '485        3a6.4,        339.29-630.11
_          11/19/04        Zn-65              699        576.9        489.51-909.09
_          11/19/04        Zn-65              699        576.9        489.51-909.09
_ .__ _ _ _ _ _ _  _  _  _            _
                                                           '''__ I  '" -        _
                                                           '''__ I  '" -        _
_ _ '---_      _ _ '  _ - -__ __      _''_  _'_ _'_ _. _  I C-8                                        2004 AREOR Rancho Seco Nuclear Station r
_ _ '---_      _ _ '  _ - -__ __      _''_  _'_ _'_ _. _  I C-8                                        2004 AREOR Rancho Seco Nuclear Station r
Line 626: Line 578:
I Rancho Seco Nuclear Station2                                                            ? C-9                                2004 AREOR
I Rancho Seco Nuclear Station2                                                            ? C-9                                2004 AREOR


____
__ ____ ____
___ ____
____ ___I
____ ___I
___ i2 L.
___ i2 L.
Line 655: Line 604:
_, ,, i .1 ! . ,,
_, ,, i .1 ! . ,,
: .              ,            ,  _                  ,        l        ;    . i,  ;      . ^, !
: .              ,            ,  _                  ,        l        ;    . i,  ;      . ^, !
                                              ,    ,            _                                        .              .
                                             ; t  _.  ,.            ,,,              .                ,  .        -,
                                             ; t  _.  ,.            ,,,              .                ,  .        -,
                                      .  ..            .      .          .                                                      .
_      ,:    ;                  .                                .      .
Rancho Seco Nuclear Station                                                                                D-2                                            2 AREOR 2004
Rancho Seco Nuclear Station                                                                                D-2                                            2 AREOR 2004


                                                                          .___
APPENDIX E ENVIRONMENTAL MONITORING PROGRAM DESIGN PROGRAM BASIS The Sacramento Municipal Utility District conducts a continuous Radiological Environmental Monitoring Program.(REMP) at the Rancho Seco Nuclear Station to assess the impact of Station operation on the surrounding environment. The current Post-Operational REMP is a continuation of a similar program initiated prior to and during operation of the Station. Samples of the surrounding environment are collected on a routine basis and analyzed to determine the amount of radiation and radioactive materials present in the exposure pathways.
APPENDIX E ENVIRONMENTAL MONITORING PROGRAM DESIGN PROGRAM BASIS The Sacramento Municipal Utility District conducts a continuous Radiological Environmental Monitoring Program.(REMP) at the Rancho Seco Nuclear Station to assess the impact of Station operation on the surrounding environment. The current Post-Operational REMP is a continuation of a similar program initiated prior to and during operation of the Station. Samples of the surrounding environment are collected on a routine basis and analyzed to determine the amount of radiation and radioactive materials present in the exposure pathways.
During 2004 the program was directed and executed by the Radiation Protection/ Chemistry Superintendent. Decommissioning Chemistry/ Radiation Protection Technicians perform sample collection. The Radiological Health Supervisor performs data review and Program maintenance! oversight. The Program is operated with primary accountability and cognizance of the Manager, Plant Closure and Decommissioning.
During 2004 the program was directed and executed by the Radiation Protection/ Chemistry Superintendent. Decommissioning Chemistry/ Radiation Protection Technicians perform sample collection. The Radiological Health Supervisor performs data review and Program maintenance! oversight. The Program is operated with primary accountability and cognizance of the Manager, Plant Closure and Decommissioning.
Line 767: Line 712:
                 ' H-3'    tH-3    20000a':: \ . > -
                 ' H-3'    tH-3    20000a':: \ . > -
Mn-54'                                .i'                    '30000 Co-60.                  300              ,      -            10000 Zn-65                    300                .                20000    ....
Mn-54'                                .i'                    '30000 Co-60.                  300              ,      -            10000 Zn-65                    300                .                20000    ....
Cs-! 34            .    .30            ,,  10                    1000              1000 Cs-137                      50                l20                20002000 Gross Beta                    40 h2            C
Cs-! 34            .    .30            ,,  10                    1000              1000 Cs-137                      50                l20                20002000 Gross Beta                    40 h2            C Notes:      .For drinking water samples, this is a 40.CFR Part 141 value Gross Beta activity in water of ten times the yearly mean of the control samples is indicated as the level, that gamma isotopic analysis should be performed on the individual sample (NRC79a). Gamma isotopic analysis on each water sample is required by the REMP and therefore this requirement does not apply.
                                                                                                            .',.'
Notes:      .For drinking water samples, this is a 40.CFR Part 141 value Gross Beta activity in water of ten times the yearly mean of the control samples is indicated as the level, that gamma isotopic analysis should be performed on the individual sample (NRC79a). Gamma isotopic analysis on each water sample is required by the REMP and therefore this requirement does not apply.
c Gross Beta activity is air of ten times the yearly mean of the control samples is indicated as the level that gamma isotopic analysis should be performed on the individual sample. The value indicated is Site specific.
c Gross Beta activity is air of ten times the yearly mean of the control samples is indicated as the level that gamma isotopic analysis should be performed on the individual sample. The value indicated is Site specific.
: nI -    I    N    l        Statio Rancho Seco Nuclear Station                                ..E-1 0 E1020                                      RO 2004 AREOR
: nI -    I    N    l        Statio Rancho Seco Nuclear Station                                ..E-1 0 E1020                                      RO 2004 AREOR
Line 788: Line 731:


APPENDIX F 2                            .  ; A        Y. R.A
APPENDIX F 2                            .  ; A        Y. R.A
                                                                                    --
                         - 2004 SAMPLE ANAW-sis -RAW DATA TABLES I i . : -    .  . . ._..          ; . !.  , I .  . I i .
                         - 2004 SAMPLE ANAW-sis -RAW DATA TABLES I i . : -    .  . . ._..          ; . !.  , I .  . I i .
i f
i f
f                  .  .
f                  .  .
                  .  .            ....
                           .I  .;          ..      ..
                           .I  .;          ..      ..
                     . I
                     . I
Line 823: Line 764:
               .11/2/2004        -    0.043          0.002              0.038      0.002 ,  0.043          0.002 11/912004              0.067          0.002              0.029    : 0.002    0.032          0.001 11(16/2004                0.068          0.003              0.029  . 0.006      0.064          0.003 11/23/2004      ,.      0.084          0.002    :        0.0351    0.002          0.2020.007 11/30/2004                0.038          0.002          . 0.035. 0.002    0.040          0.002 12/6/2004      ,0:044                  0.002              0.046      0.002    0.045          0.002 12/14/2004                0.023          0.001          . 0.022      0.001    0.024          0.001 12/21/2004                0.036          .0.002        .. 0.031      0.001    0.037          0.002 12/28/2004    '          0.043  '0.002                    0.041      0.002    0.075  .      0.003 anh. Sn Rancho Seco Nuclear Station                                        F-3                                          2004 AREOR
               .11/2/2004        -    0.043          0.002              0.038      0.002 ,  0.043          0.002 11/912004              0.067          0.002              0.029    : 0.002    0.032          0.001 11(16/2004                0.068          0.003              0.029  . 0.006      0.064          0.003 11/23/2004      ,.      0.084          0.002    :        0.0351    0.002          0.2020.007 11/30/2004                0.038          0.002          . 0.035. 0.002    0.040          0.002 12/6/2004      ,0:044                  0.002              0.046      0.002    0.045          0.002 12/14/2004                0.023          0.001          . 0.022      0.001    0.024          0.001 12/21/2004                0.036          .0.002        .. 0.031      0.001    0.037          0.002 12/28/2004    '          0.043  '0.002                    0.041      0.002    0.075  .      0.003 anh. Sn Rancho Seco Nuclear Station                                        F-3                                          2004 AREOR


__  __ _ _ _  _ _ __ __ _  _    _  _ _ _
Table F-2 2004 Luxel Summary (Direct Radiation)
Table F-2 2004 Luxel Summary (Direct Radiation)
Quarterly (mRem)
Quarterly (mRem)
I    RTL0.3RO    Site fence north of spray ponds.              _      16            19            20          20 2    RTLO.3CO    NE corner of parking lot.                    I      17          21            19          21 3    RTLO.3NO    Site fence west near south of rail spur      I    *22            30            25          24 4    RTLO.3LO    Site fence south of canal pumps              I      16            18            19          20 5    RTLO.3HO    Site sduth of Admin. Bldg.                  :I      16            21            19          20 6    RTLO.4FO    NE cornerof PV-1                              I. 18          22              18          19 7    RTLO.5CO    RS entrance sign                              I      17          23              19          19 11    RTL0.6KO    Tokay substation                              I      17            17            17          19 16    RTL2.7MO    Tippling's residence                -          I      18            15            15          17 17    RTL8.2KO    Elliott Cemetery                                      25 C                    22            21          22 18    RTL7.8CO    Sam Jaber residence                          C      1_5          1        _9  1_7          1_7 19    RTL1.8FO    RS Lake Maint. Bldg.                          I      18            16            14          16 20    RTL1.5MO    Clay/ Kirkwood streets                        I      22            2_1            19
I    RTL0.3RO    Site fence north of spray ponds.              _      16            19            20          20 2    RTLO.3CO    NE corner of parking lot.                    I      17          21            19          21 3    RTLO.3NO    Site fence west near south of rail spur      I    *22            30            25          24 4    RTLO.3LO    Site fence south of canal pumps              I      16            18            19          20 5    RTLO.3HO    Site sduth of Admin. Bldg.                  :I      16            21            19          20 6    RTLO.4FO    NE cornerof PV-1                              I. 18          22              18          19 7    RTLO.5CO    RS entrance sign                              I      17          23              19          19 11    RTL0.6KO    Tokay substation                              I      17            17            17          19 16    RTL2.7MO    Tippling's residence                -          I      18            15            15          17 17    RTL8.2KO    Elliott Cemetery                                      25 C                    22            21          22 18    RTL7.8CO    Sam Jaber residence                          C      1_5          1        _9  1_7          1_7 19    RTL1.8FO    RS Lake Maint. Bldg.                          I      18            16            14          16 20    RTL1.5MO    Clay/ Kirkwood streets                        I      22            2_1            19 Missing 26    RTL3.9KO    Borden Road                                          14            20          116            16 30    RTL7.4MO    Herald Fire Staticnr                          C    .16            21            21          19 31    RTL3.7NO    Folsom South Cana! backentrance                I      16            22            21          19 33    RTL3.8MO    Folsom South Canal/ H'wyv 104                  1      20            22            19          20 35    RTL1.9NO    Hadselville/ Clay Creeks                      Ir    15            23            21          21 43    RTL1.7FO    RS.Lake Well Encl.      -I                      I  17.          15            18          17 46    RTL1.4DO    Hwy-104 mile marker 13.15                  : I      20            21            19          20 55    RTL8.OPO    Dillard School        ._                _C          16            18        _    20          1_8 63    RTLO.8DO. Marciel Ranch:                                I      14          - 17            IS          17 65    RTLO.6MO    Site Boundary'Garden. -1i                            15                      _17
                                              -.
Missing 26    RTL3.9KO    Borden Road                                          14            20          116            16 30    RTL7.4MO    Herald Fire Staticnr                          C    .16            21            21          19 31    RTL3.7NO    Folsom South Cana! backentrance                I      16            22            21          19 33    RTL3.8MO    Folsom South Canal/ H'wyv 104                  1      20            22            19          20 35    RTL1.9NO    Hadselville/ Clay Creeks                      Ir    15            23            21          21 43    RTL1.7FO    RS.Lake Well Encl.      -I                      I  17.          15            18          17 46    RTL1.4DO    Hwy-104 mile marker 13.15                  : I      20            21            19          20 55    RTL8.OPO    Dillard School        ._                _C          16            18        _    20          1_8 63    RTLO.8DO. Marciel Ranch:                                I      14          - 17            IS          17 65    RTLO.6MO    Site Boundary'Garden. -1i                            15                      _17
_  16          1_7 66    RTLO.4NO    Soil depression area                          I:    26            35
_  16          1_7 66    RTLO.4NO    Soil depression area                          I:    26            35
                                                                                           --            35          27 67    RTL0.4N01  Dredge pile '                                        18 '          _21          20          20 68    RTLO.3PO    Site fence west by ISOB      _                        19          20_            21          23 88    RTLO.3NP    ISFSI south fence                    -  .__2_'23                        -_23                23 89    RTL0.4NP    ISFSI south fence                      -            21            22            21          20 90    RTLO.5NP    ISFSI west fence                        -_I_          20            25            25          22 91    RTLO.3QP    Site fence NW corner                          I      1_8          20            1_9          21 92    RTLO.7QP    Railroad spur                                          16
                                                                                           --            35          27 67    RTL0.4N01  Dredge pile '                                        18 '          _21          20          20 68    RTLO.3PO    Site fence west by ISOB      _                        19          20_            21          23 88    RTLO.3NP    ISFSI south fence                    -  .__2_'23                        -_23                23 89    RTL0.4NP    ISFSI south fence                      -            21            22            21          20 90    RTLO.5NP    ISFSI west fence                        -_I_          20            25            25          22 91    RTLO.3QP    Site fence NW corner                          I      1_8          20            1_9          21 92    RTLO.7QP    Railroad spur                                          16
Line 867: Line 805:
RSWO.7NO                                                                  <9.5 3/30/2004 <170        <7.7    <7.9 - <17    <9.3 RSWN3;7NO                                                                  <6.9 3/3012004 <160. - <7.5.. <8.0          <15  <9.0 RSW1.3FO                                                                  <7.0 3/30/2004 <160        <12 _ <7.8.      <18  <8.2 RSWO.3MO                                                                  <6.7 3/30/2004 <160        <9.2.    <9.1:  <19.  <9.&
RSWO.7NO                                                                  <9.5 3/30/2004 <170        <7.7    <7.9 - <17    <9.3 RSWN3;7NO                                                                  <6.9 3/3012004 <160. - <7.5.. <8.0          <15  <9.0 RSW1.3FO                                                                  <7.0 3/30/2004 <160        <12 _ <7.8.      <18  <8.2 RSWO.3MO                                                                  <6.7 3/30/2004 <160        <9.2.    <9.1:  <19.  <9.&
           'RSW1.8N0                                                                  <8,5
           'RSW1.8N0                                                                  <8,5
: 1. 3/30/20041<160          <9.9' 1<10
: 1. 3/30/20041<160          <9.9' 1<10 1<19  <11 .      <9.1 RSWI.8NO I 4/28/2004 <170<' <44                  1<4.9    <8.4  <5.3      <4.3 RSW1.8MOQ _ 4/2812004 <170 _<6.8                  <7.1    <16  <7.&      <6.9 RSWO.7NO .        4/28/2004 <17-        <4 4: <4.2 RSW1.3FO
                                                .
1<19  <11 .      <9.1 RSWI.8NO I 4/28/2004 <170<' <44                  1<4.9    <8.4  <5.3      <4.3 RSW1.8MOQ _ 4/2812004 <170 _<6.8                  <7.1    <16  <7.&      <6.9 RSWO.7NO .        4/28/2004 <17-        <4 4: <4.2 RSW1.3FO
                                                                     <9.9  <5.6.      <4;2 4/2812004 <170        <4.1    <4.6  1<88.8 <5.2 RSWO.3MO                                                                  <4.3 4/29/2004 <170      I <6.6    <7.S    <15  <12, RSW3.7NO                                                                    <6.7 4/29/2004 <170        <6.6    <7.7 * <14    <6.9 RSW1.3FO                                                                  <6.7 5126/2004 <150        <7.3,- <8.3    <16    <9.2 RSW1.8NO                                                                    <16.2 5/26/2004 <160        <6.6    <7.9    <15  <8.8 RSWO.7NO                                                                    <7.1 5/26/2004 <160        <3.5    <3.6    <7. 8 _<49 _ <&deg;.6 RSW3.7NO          5/26/2004 <160      1<54      <6.5.. <14    <6.5        <6.0 RSWO.3MO        -'5/26/2004 <160.        <5.8    <6.5    <13    <7.1      <5.6 RSWO.7NO          6129/2004 <210        <6.3-    <7.6. <14    <7.9      '6.0 RSW0O.3MO          6129/2004 <200        <6:8    -8.0    <16  <9.3        <7.0 RSWI.3FO          6/29/2004 <200        <6.3    <6.6    <1 3  <72.3      <6.5 RSW1.8NO          6/2S(2004 <200        <3.7    <4.0    <7.4  <4.6        <3.8 RSW3.7NO j        6/29/2004 <210        <8.4    <9.0    <17    <:9.2      <8.8 Rancho Seco Nuclear Station F-8                        . . 1    2004 AREOR
                                                                     <9.9  <5.6.      <4;2 4/2812004 <170        <4.1    <4.6  1<88.8 <5.2 RSWO.3MO                                                                  <4.3 4/29/2004 <170      I <6.6    <7.S    <15  <12, RSW3.7NO                                                                    <6.7 4/29/2004 <170        <6.6    <7.7 * <14    <6.9 RSW1.3FO                                                                  <6.7 5126/2004 <150        <7.3,- <8.3    <16    <9.2 RSW1.8NO                                                                    <16.2 5/26/2004 <160        <6.6    <7.9    <15  <8.8 RSWO.7NO                                                                    <7.1 5/26/2004 <160        <3.5    <3.6    <7. 8 _<49 _ <&deg;.6 RSW3.7NO          5/26/2004 <160      1<54      <6.5.. <14    <6.5        <6.0 RSWO.3MO        -'5/26/2004 <160.        <5.8    <6.5    <13    <7.1      <5.6 RSWO.7NO          6129/2004 <210        <6.3-    <7.6. <14    <7.9      '6.0 RSW0O.3MO          6129/2004 <200        <6:8    -8.0    <16  <9.3        <7.0 RSWI.3FO          6/29/2004 <200        <6.3    <6.6    <1 3  <72.3      <6.5 RSW1.8NO          6/2S(2004 <200        <3.7    <4.0    <7.4  <4.6        <3.8 RSW3.7NO j        6/29/2004 <210        <8.4    <9.0    <17    <:9.2      <8.8 Rancho Seco Nuclear Station F-8                        . . 1    2004 AREOR



Latest revision as of 13:55, 14 March 2020

2004 Annual Radiological Environmental Operating Report
ML052710320
Person / Time
Site: Rancho Seco, 07200011
Issue date: 04/27/2005
From: Redeker S
Sacramento Municipal Utility District (SMUD)
To:
Region 4 Administrator
References
MPC&D 05-041
Download: ML052710320 (74)


Text

SMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT 0 6201 S Street, P.O. Box 15830. Sacramento CA 95852-1830. (916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA MPC&D 05-041 April 27, 2005 U.S. Nuclear Regulatory Commission Region IV Administrator 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064 Docket 50-312 Rancho Seco Nuclear Station License DPR-54 2004 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Attention: Region IV Administrator In accordance with Rancho Seco Quality Manual Appendix A, Section 1.5.3, the District submits the enclosed Rancho Seco Annual Radiological Environmental Operating Report for the period January 1, 2004 through December 31, 2004.

You or members of your staff requiring additional information or clarification may contact Steve Nicolls at (916) 732-4850.

Sincerely, Steve J. Redeker Manager, Plant Closure and Decommissioning Enclosure cc: Document Control Desk, NRC, Washington DC J. Hickman, NRC, Washington DC R. Hall, NRC, Rockville MD

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

-fbe, JANUARY - DECEMBER 2004 Rancho Seco Nuclear Station Herald, California 10 CFR Part 50 License Number DPR-54 10 CFR Part 72 License Number SNM 251 0

2004 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

-- -  : TABLE OF CONTENTS - .-

TABLE OF CONTENTS.

TABLE O F CO NTENTS LIST OF FIGURES ............................------------------------------------- ii LIST O F TA BLES ......... ..;::;;::....................................................................'

LIST~ OF TA.E

.'iv I. EXECUTIVE

SUMMARY

................. . .1 II. LAND USE CENSUS .....................- ..... 3

. .... . . .. . ... .. .. .. ........ ......... ... . .......... 3 III. RADIOLOGICAL IMPACT EVALUATION .. .  ;...3  ;

PREDICTED POTENTIAL RADIOLOGICAL IMPACT ..................................... .3 , .;

FUEL CYCLE DOSE EVALUATION ....................... .:  ;.;.;. 4 OBSERVED POTENTIAL RADIOLOGICAL IMPACT ................................ . . 4 IV.PROGRAM ANALYSIS RESULTS

SUMMARY

.................................... , . 7 IV-A: ATMOSPHERIC MONITORING ....................................  :. 7:

7 IV-B. DIRECT RADIATION MONITORING .................... 8...........:..8 IV-C. TERRESTRIAL MONITORING ..........................  ;..8 IV-D. AQUATIC LIFE MONITORING  ; .. 9 IV-E. WATER MONITORING ....................  ;.9 V. REFERENCES ............ 16 VI. APPENDICES ......  :,18 2003/2004 LAND USE CENSUS RESULTS ........................................................ ....................... A-1 SAMPLE SITE DESCRIPTIONS AND MAPS................................................................................. B-1 QUALITY CONTROL SAMPLE ANALYSIS RESULTS .......... ............................. C-1 SAMPLE COLLECTION AND ANALYSIS METHODS .............. D-1 ENVIRONMENTAL MONITORING PROGRAM DESIGN................................I ............................ E-1 2004 SAMPLE ANALYSIS RAW DATA TABLES .................................... F-1 2004 MISSED SAMPLE REPORT............................................................................................... G-1 Rancho Seco Nuclear Station 1.ii

IIIL LIST OF FIGURES .

FIGURE TITLE PAGE FIGURE B-1 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS ON AND NEAR THE SITE B-3 FIGURE B-2 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS WITHIN i MILE .

FROM THE REACTOR BUILDING. , -- .-- B4 FIGURE B-3 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS FROM 1 TO 5 MILES FROM THE REACTOR BUILDING -B-5 S- . 4.  : .

FIGURE B-4 RADIOLOGICAL ENVIRONMENTAL SAMPLING'LOCATIONS 5 TO 25 MILES FROM THE REACTOR BUILDING ---- B-6 z~~~- .~- -o p I48;s

.. I ' ...

, I Rancho Seco Nuclear Station *111

LIST OF TABLES TABLE TITLE PA ,GE I 2004 LIQUID EFFLUENT PATHWAY POTENTIAL DOSE COMPARISON 6 2 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

  • .11

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

B-1 RADIOLOGICAL ENVIRONMENTAL MONITORING SITES AND MAP LOCATIONS *B-7 C-1 2004 INTERLABORATORY.COMPARISON.PROGRAM . . .-4 E-1 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES . . E-1 0 E-2 .MAXIMUM (REQUIRED) LLD VALUES FOR ENVIRONMENTAL SAMPLES',- ... E-1I:

F-1 2004 WEEKLY AIR SAMPLE

SUMMARY

F-2 F-2 2004 LUXEL

SUMMARY

(DIRECT RADIATION) . .: .  :,. F-4 F-3 2004 GARDEN VEGETABLES F-5 F-4 .2004 SEDIMENT - - - . . .- F-5 F-5 2004 FISH F-6 F-6 2004 WELL WATER F-6

  • F-7 2004 RUNOFF WATER ' F-7 F-8 2004 SURFACE WATERE; F-8 F-9 2004 DRINKING WATER F-10

. i

. .. 1, T

. N Ranc'ho- Se'co'Nu'clear Station ' iv 2004 AREOR

I...

2004 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

1. EXECUTIVE

SUMMARY

This report contains results from the Radiological Environmental Monritoring Program (REMP) for the Rancho Seco Nuclear Statton (RSNS) boomripled for the' pe'riod 'January 1, 2004. through December 31, 2004. The Radiation Protection/ Chemistry Group' at R SNS conducts this program in accordance with the REMP'manual. This report is'compiled and submitted in accordance with the Rdncho Seco Quality Manual, Appendix A, Section 1.5.2.3 LRS021.

The results of the 2004 Radiological Environmental Monitoring Program showed that the operation of Rancho Seco Nuclear Station' had no significant radiological impact on the environment.

Currently, the Plant is permanently shutdown and undergoing' Decommissionirng. Fuel trarisfer

  • to the Independent Spent Fuel Storage Installation (ISFSI),was completed on August 21, 2002.

On August 26, 2002, the Offsite Dose Calculation Manual (ODCM),was revised. As part of the revision, the Auxiliary Building gaseous effluent pathway was removed'from the effluent program. This revision was due to the evaluation, which showed that no gaseous effluent, pathway is present from the Auxiliary Building discharge point. In 2004 the Auxiliary Building

' Discharge Point was removed. The only remaining airborne release point is from the Reactor Building. No gaseous effluents activity was detected in REMP samples conducted during 2004; therefore no evaluation of this pathway was conducted in this report.'

During the reporting period, the atmospheric, terrestrial and aquatic environs adjacent to RSNS were monitored. The sample measurements showed that the levels of radioactivity in the..

sampled media were consistent with previous years evaluations. AI! detected nuclides (greater

. than minimum detected activity) were' below the required Nuclear Regulatory commission (NRC) reporting levels. All Lower Limits of Detection (LLD) were at or lower than the maximum required by the NRC:

In 2004, all administratively controlled samples were discontinued, except for 33 direct radiation monitoring locations.

Doses resulting from ambient exposure to terrestrial and atmospheric direct radiation sources were measured through the placement and retrieval of Luxel monitoring badges.' Direct radiation measurements' attributable-to Station operations; based on control and indicator locations, were indistinguishable above background levels. Two monitoring badge locations, placed in an area near the effluents discharge stream are being 'used to evaluate the higher than average soil activity. This activity is a result of historic monitored liquid effluent releases during Station operation. One monitoring badge location in this area is indicating dose higher than the indicator average. The dose at this location does not exceed the regulatory limits of 10 CFE Part 20. Onsite' Luxel badge locations near the.ISFSI access road show slightly higher readings, attributed to the ISFSI, and are within design calculations.

Rancho Seco Nuclear Station 1 2004 AREOR

_~~~~ *, i* *.* ~ , -

I. EXECUTIVE

SUMMARY

(Continued)

Isotopic identifications were'consistent with' knowvn releases of radioactive'material frorn the  :

  • Station to the atmos~pheric andaquatic environments. As expected,.fish and sediment samples obtained.from the environment of the No Nameand ClayCreeks contributed the majority'of positive isotopic identifica'ions. Cesiurm-137:and Cobalt-60 are thepredominant nuclides identified in the aquatic environment. ,.r:';. . '

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Rancho Seco Nuclear Station 2' 2004 AREOR

I - ~ ' I__1L II. LAND USE CENSUS The 2004 Land Use Census was conducted in accordance with the Rancho Seco Quality Manual [RS02] Section 1.4.3.2 and the Radiological Environmental Monitoring Program (REMP) manual section 4.0. This evaluation is in accordance with the requirements of 10 CFR Part 50, Appendix I, section IV.B.3. The land use 'census is performed on a biennial schedule and was performed ddring 2003/ 2004 'ad then'comripleted'in 2005. The next land use census is scheduled to be condu'cteddu ring 2005i 200&d ard'completed in 2007. '

1 * -* * ' , 1i X ~~*' r;Xal sz:

I ~' V . AT Ill. RADIOLOGICAL IMPACTEVALCJATION: "  ::.

PREDICTED POTENTIAL RADIOLOGICAL IMPACT S.

Gaseous Effluent Exrosure;Pathways The maximum calculated annual organ dose' commitment due to gaseous releases of tritium

and particulate isotopes was 1.42 E -02 mRem (as calculated using-ihe Rancho Se6o Offsite Dose Calculation Manual (ODCM)). This calculated organ dose commitment was 0.405% of-the associated Rancho. Seco Quality Manual (RSQM) [RS021 limit (1bCFR50,'Appendix I guideline).

Noble gases were not released in 2004 and therefore no dose calculations for noble gases were necessary. . ' .i i Liquid Effluent Exposure Pathwayse Th .. i -  : .

During 2004, 428 E+06 liters of wastewater V!ete'released into uNo lNamer Creek from the two-onsite Retention Basins.~ This volume of wastewaterwas dispersed into 1.76 'E+10 tersof dilution water. The estimated error associated with determining these volumes were 5%and' 20%, respectively. .;::  ; . .

The Liquid source term resulted in a calculated annual adult total body dose commitment of 0.0104 mRem and a calculated child bone dose commitment of 0.0234 mRem (as calculated using the ODCM). These calculated dose commitments were 0.345% and 0.234%,

respectively, of the associated 10 CFR Part 50, Appendix I guidelines. The quarterly dose commitments reflect the-age group(s) that could have received thi:hi%.oest annual dose commitment from the liquid source te.-m , - . .-

This information is summarized in Table 1. ' - '. . -.

Rancho Seco Nuclear Station 3 2004 AREOR

Ill. RADIOLOGICAL IMPACT EVALUATION (Continued)

FUEL CYCLE DOSE EVALUATION REMP Manual section 8.14 requires each Annual Radiological Environmental Operating Report (AREOR) to include inforrationjrelated to REMP. manual section-5.0;. uel Cycle Dose.

The Fuel Cycle Dose Specificationi limits the.dose or dose cormimitment to any'real member of the public to 25 mRem to the total body or any organ, except the thyroid which is limited to 75 mRem. This' specification implements requirements promulgated'by the United States',

Environmental Protection Agency [CFRd]..

Consistent with REMP.manual section 5.0, no fuel cycle dose evaluation was required to be performed during 2004 since no REMP measurement exceeded the established reporting levels. Additionally, the Station effluent dose predictions did not exceed twice the dose-,

guidelines of 10CFR.-Part 50, Appendix I [CFRc].. The station operated within the Appendix I guidelines envelope forradioacti-ve effluents (a condition suppbrted by Promra . .

measuremdents);thereforedetermination ofan actu al dose commitment delivered to a real member of the public was not required .,-  ; ,,

OBSERVED POTENTIAL RADIOLOGICAL IMPACT Gaseous Effluent Exposure Pathways

.:. .* i ,,: .. ... . . - * . . ..

The calculated gaseous effluent dose commitment of 1.42E -02.mRem [RS01] is based on tritium and particulate activity., Cesium 137 particulate activity was released during the first quarter of 2004.,!The observedI dose .comrnmitment~dose, calculation, if completed,' using the gross beta data'(Which is:primarily.'due'to-naturallyotcurring radioisotopes) would not provide, an accurate correlationwith.the ~predicted.tritium ,and particulate activity dose calculations.'

Also, none of the REMP quarterly air filter composite gamma isotopic analysis results for.the.

airborne pathway indicated the presence of nuclides of Station origin. 'Therefore, no dose comparison was~completed. . .-. ' , .. ,.

Direct Radiatior Exposure PAthway e} , ,r; ir;:':t.'.:. .;'

Based on Luxel control arid indicator locations measurement results obtained.during 2004, the.

Station proper did not contribute an observable component to-the recorded direct gamma radiation field. This Luxel data supports the Gaseous Effluent Exposure Pathway conclusions and supports. the conclusion that the Plant has no-direct radiation effect on the.;environment.

Luxel monitoring badges placed near the effluent stream Was used to evaluate the dose from this area. Dose levels at these locations are higher than the mean of the control and indicator locations reported. This above average dose is due to elevated soil activity due to historic liquid effluent releases. Luxel badge locations around the ISFSI outside fence (required by the ISFSI License) show higher readings, attributed to the fuel stored in the ISFSI, and are within design calculations.

.  : . . 2004. R -

R Rancho Seco Nuclear Station 4 2004 AREbR

Un-L Ill. RADIOLOGICAL IMPACT EVALUATION (Continued)

OBSERVED POTENTIAL RADIOLOGICAL IMPACT Liquid Effluent Exposure Pathways To evaluate the impact on the ehvironment from the liquid effluent pathway,' dose calculations were performed and dompared with the annual dose commitment calculations reported in the January -December 2004 RanchoSecoAnnual oadiacve Cuent Release Report [RSO1].

The observed results presented in Table 1 were obtained using thie Cs&137 activity reported for the fish samples from 2004 (AppeirdiX'F, able F-'),'defau t &iinsiinition quantities for fish (ODCM), and nuclide-specific dose factors [NfRC77]. - '

As in past reports, the observed potential dose commitments listed in Table I are subject to uncertainty, principally due to thie' asisu'rptiof thathe ob'served radioactivity was dde t' 2004 Station operations only and was not affected by radioactivity introduced into the environment prior to 2004. A portion of the'&ctivity identified by Program measirements in 2004 is attributable to historical releasei documented ieviousaririal reports. Additionally,-the

observed dose commitment calculations are based on conservative default consumption factors for fish.;

The 2004 Land UCse Census indicates the liquid/ fish and liquidl irrigated vegetation pathways are potential exposure pathways. Thefish pathway-ddse commitment calculation uses conservative default fish consumption factors instead of using actual Land Use Census data. Also, fhdose commitnent calculation'uses fish sample analysis data derived from fish samples collected from the plant effluent stream in 2004. 1,Vegetation sample, analysis results indicated no radioactivity attributable to station operatlbnin 2004via thie liq'uid! -

irrigated vegetation pathway;. therefore, no dose commitment calculations were performed for this pathway. A" '  ;' - ' .

.N ... 4 I.

Rancho Seco Nuclear Station 5 '2004 AREOR

lit. RADIOLOGICAL IMPACT EVALUATION (Continued)

OBSERVED POTENTIAL RADIOLOGICAL IMPACT TABLE, 2004 Liquid Effluent Pathway Potential Dose Comparison POTENTIAL DOSE COMMITMENT (Based on the maximally exposed group)

PREDICTED DOSE OBSERVED DOSE PERCENT OF -THE10 CFR COMMITMENT (a) COMMITMENT (b) (c) PART 50 APPENDIX I (mRem) (mRem) DOSE LIMITS 0.0104 "0.238- 7.93 %

(Adult total body for 2ndd 3rd and (Adult Total Body) Total Body 49quarters) ,- ,-. mRem guideline) 0.0234 '.378 3.78,%

(Child bone for -2d 3 and 4th (Teen Liver) . Organ

-'quarr ) (10- mRem' guideline)

I .1 11-1

-, V, .-

Notes:' (a) Reported in'the'20'04 Annual Radiological Effluent Release Report (b) 'Calculated using Cs-1 37 activity for fish samples (Appendix F, Table F-5).

(c) The observed dose commitments for doses reflect the age group that could have received the highest annual dose commitment from the liquid source term Rancho Seco Nuclear Station 6 2004 AREOR

IV. PROGRAM ANALYSIS RESULTS

SUMMARY

This section compiles Program data with corresponding evaluations. Each of the following five subsections presents information about each of the principal environmental exposure pathways monitored by the Program:

=> Atmospheric (Section IV-A)

=, Direct Raidition (Sectfoon IV-B)

=, Terrestrial (Section IV-C)

=> 'Aquatic Life (Section IV-D)

> Water (Section IV-E)

Each of these sections contains a data evaluation subsection, which provides a summary of the data collected.

Table 2 is a comprehensive, all-media data summary presented in a format.considered acceptable by the US' Nuclear Regulatory Commission. Inkormation contained in Table 2 was derived from data presented in Appendix F.

IV-A. ATMOSPHERIC MONITORING' DATA EVALUATION i No radionuclides attributable to the operation of Rancho Seco were observed in gamma-spectrometry analyses of the quarterly composites of the particulate filters.

Cs-137 was ihitially identified in the second quarter composite' report and a recount of the sample was requested. Upon evaluation of the counting data it was noted that the analysis error on the first count was 49% and the error on the second count analysis was 75%.

Based on the analysis error, the Cs-1 37 identification will be considered an anomaly and will not be reported.

Therefore, since all remaining data was reported as being below the associated minimum detectable activity (MDA) for the nuclides of interest, no table is presented for the composite air filter data. The data indicates that there was no measurable contribution to the airborne radioactivity inventory that could reasonably be attributable to Station operations.

The results of the gross beta analyses of the particulate samples are given in Appendix F, Table F-1.

Rancho Seco Nuclear Station 7 2004 AREOR

IV-B. DIRECT RADIATION MONITORING DATA EVALUATION A comparison review of all Luxel data for the indicator and control locations during 2004 showed that there was no obserVable direct radiation component due to Station operations (i.e., storage or utilization of licensed radioactive material within the restricted area.).

Two Luxel locations are being used to evaluate the dosein areas next to the effluent stream.

The data from these locations indicates doses are'within regulatory limits of 10 CFR Part 20.

Luxel badge locations on the outside fence of the ISFSI show higher readings, but this is expected due to the spent fuel storage in the ISFSI. The results are within the design criteria and no license or regulatory limits were exceeded.  ;

The summary data for 2004 direct radiation monitoring is presented in Table 2.

Comprehensive data tables are given in Appendix F, Table F-2.

IV-C. TERRESTRIAL MONITORING- .

DATA EVALUATION Garden Vegetation -- Five (5) garden vegetation samples were ,colleotedand analyzed for nuclides of interest during 2004. No gamma emitting isotopes were found in any of the samples analyzed. A site boundary irrigated garden has been utilized as a conservative method for evaluating the liquid effluent pathway. This method meets the requirement of the Land Use Census.for monitoring gardens.. This site boundary garden is used for the Land Use Census. .

The summary data for 2004,terrestrial monitoring is presented in Table 2. Comprehensive data tables are given in the following AppendixF. table:

=>F-3 (Garden Vegetables) - -;,, . - -

Rancho S'eco ula tto 8 2004 AREOR

. ___ .. ot-IV-D. AQUATIC LIFE MONITORING DATA EVALUATION Sediment - Twelve (12) samples of sediment were collected from the onsite discharge canal during 2004. Gamma spectrometry analysis of these samples indicated the presence of Cs-137 (12 samples, 59.5 to 268 pCi/kg, 130.5 pCi/kg mean), and Co-60 (12 samples, 19.9 to 315 pCi/kg, 95.2 pCi/kg mean).

The presence of nuclides of interest in sediments is attributed to historical permitted liquid effluent discharges.

Fish - Two (2) fish samples were collected during 2004 and analyzed for nuclides of interest by gamma spectrometry. Samples were collected in the effluent creek. Gamma spectrometry analysis of these samples indicated the presence of Cs-137 (2 samples, 50.3 to 267 pCi/kg, 159 pCi/kg mean).

The summary data for the aquatic life-monitoring program is shown in Table 2.

Comprehensive data tables are given in the following Appendix F Tables:

=, F-4 Sediment

> F-5 Fish IV-E. WATER MONITORING DATA EVALUATION Well Water - Eight (8) well water samples were collected at indicator and control locations around the site during 2004. Tritium and gamma spectrometry analysis of the samples indicated results less than LLD. Gross beta activity levels for all samples were within regulatory limits.

Runoff Water - Thirty One (31) runoff water samples were collected at the site boundary during 2004. Tritium and gamma spectrometry analysis of the samples indicated results less than LLD.

Surface Water - Five locations (3 indicator and 2 control) were included in the surface water-monitoring Program. Composite samplers located at the Plant intake (Folsom South Canal) and effluent discharge provide monthly composite samples. During 2004, 64 samples were collected and analyzed for nuclides of interest. Tritium and gamma spectrometry analysis of the samples indicated results less than LLD Rancho Seco Nuclear Station 9 2004 AREOR, -

IV-E. WATER MONITORING DATA EVALUATION (continued)

Drinking Water - Water supplied from two site.wells is distributed in a potable water supply system for Station personnel consumption and.use:. On a monthly frequency, samples were collected and analyzed for nuclidesbof iflterest. A sample from the Ra'ncho Seco Reservoir Well is collected as a control location. No gamma emitting isotopes were found present in the 36 samples collected in 2004. Gross.Beta analysis showed activity within regulatory limits.

The summary data for the water-monitoring program is'shown in Table 2. Comprehensive data tables are-given in the following Appendix F Tables:

= F-4 Sediment

=> F-6 Well Water

=> F-7 'Runoff Water

=> F-8 -Surface Water

=> F-9 Drinking Water I .

, . S . . .

  • 5 , . . .

Rancho Seco Nuclear Station _ 10 2004 AREOR

TABLE 2 PROGRAM ANNUAL

SUMMARY

ENVIRONMENTAL RADIOLOGICAL MONITORING

. A :

. ., I

.. 1 I

I-,

11 2 2004 AREOR Rancho Seco Nuclear Station

TABLE 2 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility Rancho Seco Nuclear Station Docket No. DPR-541 SNM 2510 Location of Facility Sacramento. California _ Reporting Period JanuarV - December 2004 (County, State)

Medium or Type and Lower All Indicator Location with Highest Annual Control locations Number of Pathway Total Limit of Locations Mean Mean (fa Nonroutine Sampled Number of Detection Mean (fa Name Mean . a Range Reported (ntof An~ilysis, (LLD) Meang(fiNamtMancef Range Measurements Measurement) Performed & Direction Air Particulates (pCi/M 3 ) Gross P 0.01 0.024 (106/106) RASO.ICO 0.084 (53/53) -0.029 (53/53) 0 (159) (0.008- 0.084) 0.1 miles 450 (0.008-0.084) (0.008-0.202)

_ A~yspec (12)..

_3/ Cs: 0.01 <LLD <LLD <LLD

. -- lc 0.01 <LLD <LLD <LLD Direct Radiation Luxel NA 19.6 (115-115) RTLO.4NO 30.8 (414) 19.2 (16/16) 0 (mRem/qtr.) (131) (14-35). 0.4 miles 2700 (26-35 Gardeni Vegetables y-spec (pCi/kg) (5)

_Co, 60 <LLD . <LLD <LLD 0

_ _ _ _60 <LLD <LLD <LLD 0

__ Cs 60 <LLD <LLD <LLD 0 a Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses. (f) b LLD values from Table E-2. See page E-8, 'SENSITIVITY OF THE REMP MEASUREMENT PROCESS", for information on determining LLD and Minimum Detectable Activity (MDA).

Rancho Seco Nuclear-Station 12 - 2004 AREOR

TABLE 2

  • ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility Rancho Seco Nuclear Station Docket No. DPR-54/ SNM 2510 Location of Facility Sacramento.-California _ Reporting Period Januarv - December 2004 (County, State)

Lower All Indicator Location with Highest Annual Control locations Number of Medium or Type and -

Limit of Locations Mean Mean (f)a Nonroutine Pathway Total Mean (f) a Name Mean (f)a Range Reported Sampled Number of Detection (Unit of Analysis (LLD) Range Distance RangeMeasurements Measurement) Performed R Distan

- - -& Direction Sediment y-spec (pC i/kg) __ _ __12_ _ _ __ _ __ _ _

95.2 (12/12) RMS0.6MO 120.6 (8/8) NA 0' Co 150 (19.9-315) 0.6[mies 2480 (19.9-315)

IC 15:0 130.5 (12112) RMSO.6MO 156.8 (8/8) NA

- (59.5-268) 0.6 miles 2480 (109-268) NA 0 1

4Cs. 150 . LLD <LLD NAO Fish-*,,,

(pCi/kg) y-spec '

130 <LLD <LLD NA 0

'Mn 130 <LLD <LLD NA. 0 bUCo.

<LLD <LLD NA 0 n 260 130- 159 (2/2) RFSO.6MO 159 (2/2)

(50.3-267) 0.6 miles 2480 (50.3-267) NA 0

. 1__

. s130 - -<LLD LLDNA Man-n ag ae*po eetbema only Fratio mesreetsa t specified

- ^ Mean and Range based pon detectable measuremens y. Fraction of detectaole measurements locatibns is indicated in parentheses. (f) .

for information on determining LLD values from Table E-2. See page E-8, "SENSITIVITY OF THE REMP MEASUREMENT PROCESS",

LLD and Minimum Detectable Activity (MDA).

13 2004 AREOR Rancho Seco Nuclear Station

TABLE 2

SUMMARY

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL 2510 Name of Facility Rancho Seco Nuclear Station Docket No. DPR-541.SNM Location of Facility Sacramento, California Reporting Period Januarv - December 2004 (County, State)

- . . - ~ . I , i~, 70*;;

.11 . l Number of Lower. - .. All Indicator Location with Highest-Annual Control locations Medium or ' ': , Type and Nonroutine Pathway - .Total . . !.imit of . -I.. .'Locations --" ar"':' Mean Mean (f) a Range Reported Sampled' Number of Detection Mean (f) Name' '  : Mean (fl a Measurements

- (Unit of -. I Analysis ,, (LLD) b Range Distance Range Measurement) Performned . .4 I~ ..

.& Direction' -

RWW0.8DO: 3.84 (3/4) 3.27 (3/4) 0 Well Water Gross 3 4. 3.84 (3/4)

(2.65-3.96)' 0.8 miles 67.50 (2.65-3.96) (2.81-4.36)

(pCi/L) ,(8)

<LID 0 Tntium 1000 -LLLDD

<LLD .

'y-spec ,

<LLD <LLD 0

._,___ Mn 15 <LLD

<LLD . <LLD 0.

.. Co _ 15 . <LLD

.<LLD <LLD <LLD 0 bn . - 30 '_._-_-____ -

0-

'Cs___ . '10 <LLD <LLD  ;<LD; LLD <LLD <LLD 0 Cs 10  ;

<LD NA 0 Runoff Water Tritium 2000 <LLD (pCi/L (31) _:  ; .

y-spec,

<LLD NA. 0 5 <LLD

<LLD . NA 0 i5 <LLD 0 30 <LLD- <LLD NA

. 1Zn 0

<LLD <LLD - NA

'Cs, 18  :

<LLD NA : 0

._._-_._Cs.,__ _____ 15 <LLD -

measurements at specified a Mean and Range based upon detectable measurements only. Fraction cf detectable locations is indicated in parentheses. (f)  ;  : :,

b MEASUREMENT PROCESS", for information on determining LLD values from Table E-2. See page E-8, "SENSITIVITY OF THE REMP LLD and Minimum Detectable Activity (MDA).

14 2004 AREOR Rancho Seco Nuclear Station

TABLE 2 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility Rancho Seco Nuclear Station Docket No. DPR-541 SNM 2510 Location of Facility Sac:amento, California Reporting Period' Januarv - December 2004 (County, State)

All Indicator Location with Highest Annual Control locations Number of Medium or Type and Lower Locations Mean - Mean a Nonroutine Pathway Total Limit of Mean ame Reported Sampled Number of Detection (LLD) Range Distance Range Measurements (Unit of 'Analysis' Measurement) Performed & Diieutqon

<LLD <LLD <LLD 0 Surface Water Tritium 2000.

_(pCi/L) t64) y-spec

= <LLD <LLD 0 4Mn 1

). <LLD -

- <LLD <LLD 0

- Go 15 <LLD i <LLD, <LLD -<LLD 0

_. b"Zn '30 0

18 - <LLD _ <LLD <LLD

. 3.74 (22/24)- RDW0.1GO 4.07 (11/12), 3.56 (11/12) 0 Drinking Water Gross ,B 4 .0 (2.58-5.1 1) ' 1 miles 135° (3.29-5.11) (2 35479) .

(pCi/L) (36) _

L LD <LLD 0 Tritium ' 1000 ' <LLD <

.- Spec1

^.(36)  :' -'

<LLD <LLD - <LLD 0 Mn '. 15

15 ' <LLD <LLD <LLD 0 bD

.'30-.

-' <LLO - - <LLD <LLD 0 Zn

<LLD' <LlD- '-' <LLD 0 1 J/Cs 10 -

4 a acs l 10 <LLD <LLD I <LLD 0 at specified Mean and Range based upon detectable measurements'only. Fraction of detectable measurements locations is indicated in parentheses. (f) for information on determining LLD values from Table E-2. See page E-8, 'SENSITIVITY OF THE REMP MEASUREMENT PROCESS',

LLD and Minimum Detectable Activity (MDA).

15 2004 AREOR Rancho Seco Nuclear Station

V. REFERENCES CFRa Code of Federal. Regulations, 2004, "National Primary Drinking Water Regulations," Title 40, Part 141.

CFRb Code of Federal Regulations, 2004, "Standards for Protection Against Radiation," Title 10,;p.art 20..

CFRc Code of Federal Regulations, 2004, "Domestic Licensing of Production and Utilization Facilities," Title 10, Part 50.

CFRd Code of Federal Regulations, 2004, "Environmental Radiation Protection Standards.for'Nuclear Power Operations," Title 40, Part 190.

CFRe  : Code of Federal Regulations, 2004, "Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High Lvel Radioactive Waste, and Reactor-Related Greater than Class C Waste," Title 10, Part72.  :

NRC74 United States Nuclear Regulatory Commission, 1974, "Permanently~

Defueled Technical Specifications for the Rancho Seco Nuclear Station," Appendix A toFacility License No. DPR-54. (as amended).

NRC 00 - United States Nuclear-Reguilatory-Commission,-2000, Rancho'Seco Nuclear Generating Station, "License for Independent Storage of Spent; Nuclear Fuel and High level Radioactive Waste," SNM-2510. (as amnded)  ;'. ' '

NRC77 United States Nuclear Regulatory Commission, 1977, "Calculation of

- . Annual Doses to Mari from Routine Releases of Reactor Effluents for the Purpose of Evaluating Cornpfiance with 10 CFR Part 50, Appendix I," Regulatory Guide 1.109, Revision 1.

NRC79a United States Nuclear Regulatory oCnmission, 1979, "An Acceptable Radiological Environmental Monitoring Program," Branch Technical

-Position, Revision.l. -

NRC79b United States Nuclear Regulatory Commission, 1979, 'Quality Assurance for Radiological Monitoring Programs (Normal Operations) -

- .Effluent Streams and the Environrhent," Regulatory Guide 4.15,

.: _ Revision 1. -

NRC92  :, United States Nuclear Regulatory Commission, "Air Sampling in the Workplace", Regulatory.Gu8ide 8.25, June 1992 NUREG79 United States Nuclear Regulatory Commission, 1979, "Radiological Effluent Technical Specifications for PWRs," NUREG-0472, Revision 2.

Rancho Seco Nuclear Station 16 2004 AREOR

jII L_

V. REFERENCES (continued)

NUREG80a United States Nuclear Regulatory Commission, 1980, "Methods for Demonstrating LWR Compliance with the EPA Uranium Fuel Cycle Standard (40 CFR Part 190)," NUREG-0543.

RS01 Rancho Seco Nuclear Station, 2004, "Annual Radioactive Effluent Release Report, January -December 2004," Sacramento Municipal Utility District report.

RS02 Rancho Seco Quality Control Manual, Appendix A Rancho Seco Nuclear Station 17 2004 AREOR

VI. APPENDICES Rancho Seco Nuclear Station 18 2004 AREOR

____________Ifu-APPENDIX A 200312004 LAND USE CENSUS RESULTS In compliance with the Rancho Seco Quality Manual [RS02] and the REMP Manual, section 4.0, "Land Use Census', a Iand use census was completed on March 16, 2005. The method of conducting the primary survey was to use ari aerial survey that was conducted during June 2004. Evaluating the aerial photographs continues to provide' an accurate Mliethod of determining locations and distances of the nearest residences. The aerial photos also provided a method to identify any changes in the sgricultural, commercial, residential, or industrial use of the land surrounding the site. The use of conservative dose factors for the purpose of projected dose calculations still requires that we evaluate the use of the area surrounding the site. The information that is presented is to verify this assumption and validate the process.

The land use census covered an area bounded by each of the sixteen meteorological sectors out to a two-mile radius from the Reactor Building.

The 2003/ 2004 Land LYse Census did not identify any changes 'n the use of the unrestricted areas that would require modifications in the Radiological Environmental Monitoring Program for evaluating doses to individuals from principal pathways of exposure. This evaluation and determination are in accordance with the requirements of 10 CFR Part 50, Appendix 1,section IV.B.3.

The Land Use Census is completed on a biennial schedule. Aerial surveys will be conducted during 2006 and the Galt Irrigation report covering 2005 and 2006 will be requested during the last quarter of 2006. This information will bc used to complete the 2005/ 2006 census, which is scheduled to be completed in 2007.

R.

Rancho Seco Nuclear Station A-I 2004 AREOR

A. RESIDENT EXPOSURE PATHWAY

SUMMARY

Inhalation, Ground Plane and Water Consumption The 2003/ 2004 census determined that seven of tlie 16 radial sectors have residences that are within the 2-mile (3219 meters)Land Use Ce'nsus radius. The closest residence in each of the seven sectors is identified below-Sector Dlsi't6e Ranking (Nearest to

. ___L____ - .Farthest)

A >3219 NA B -. 219 NA-C 42 3

., __-D -. _ 1 175' 1,

,E , 32i9 NA.

F -  ;. ,3219' NA G 2381 6

>3219. NA K 2320 5 L 1207 2 M 2028 4 N 3181 7 P >3219 NA Q >3219 NA R >3219 NA It is expected that all seven residences use well water for consumption and other domestic purposes.

Rancho Seco Nuclear Station A-2 2004 AREOR

ECle-B. DEPOSITION EXPOSURE PATHWAY

SUMMARY

Beef Consumption Based on conservative dose calculation parameters in use, the following is a summary for the 2003/ 2004 land use census of the potential deposition exposure pathways at the locations listed below:

Sector Distance (meters)

Consumption Ppthway I Comment A 433 Beef Unrestricted Area Boundary B 430 Beef Unrestricted Area Boundary C 531 Beef Unrestricted Area Boundary

. 451 Beef Unrestricted Area Boundary E 483 Beef Unrestricted Area Bout iday 4

499 Beef Unrestricted Area Boundary E 579 Beef Unrestricted Area Boundary H 798 Beef Unrestricted Area Boundary H 198 Beef Unrestricted Area Boundary J 195 Beef Unrestricted Area Boundary K 195 Beef Ara L 286 Beef Unrestricted Area Boundary N 514 Beef Unrestricted Area Boundary P 708 Beef Unrestricted Area Boundary Q 579 Beef Unrestricted Area Boundary R. 448 Beef Unrestricted Area Boundary Due to the revision of the ODCM, which eliminated the gaseous effluent pathway (August 26, 2002), the Deposition Exposure Pathway is not considered a credible evaluation with current plant conditions. Land Use Census use of this evaluation will be considered for revision in future surveillances.

Rancho Seco Nuclear Station A-3 2004 AREOR

C. IRRIGATED CROP EXPOSURE PATHWAY

SUMMARY

Laguna Creek Gait Irrigation District The Gait Irrigation District's 2003 Crop-Report stated 2651.4 acre-feet of Laguna Creek water was diverted for irrigation purposes during the 2003 crop production season. Crops irrigated were Oats, Corn, Clover, Pasture, Sudan, and Alfalfa over a tota! of 1021 acres.

The Galt Irrigation District's 2004 Crop Report stated 3019.499 acre-feet of Laguna Creek water was diverted for irrigation purposes during the.2002 crop production season. Crops irrigated were Oats, Corn, Ciover, Pasture, Sudan, and Alfalfa over a total of 1021 acres.

Rossini Farming Compan-In addition to the above, SMUD has contracted with Rossini Farming Co., the owners of the vineyards adjacent to, Rancho Seco Station,-to -supply irrigation water from Clay Creek on an as needed basis. - - -

The following information was reported by the SMUD Water and Power Group, which monitors the usage. For the years of -2003 -and -2004 it was reported that >500 Acre-feet of water was used from the effluerit creek for irrigating purposes for the vineyards.

.  :..t , ' , e Rach Sec Nula Stto --,- ,__. ._ . 200 AREOR_

. __' E L..

D. OTHER EXPOSURE PATHWAYS The 2003/2004 Land Use Census confirmed previous knowledge that the Clay/ Laguna Creeks are utilized by the general public for aquatic life consumption purposes. Based on direct observation cattle consume water from the Clay, Hadselville, and Laguna Creeks.

Past census evaluations have been unsuccessful in deferminingthe usagei occupancy factors for this consumption. Therefore, insufficient data existed to justify ODCM usage factor modification.

E. REMP EVALUATION An objective of the 2003/ 2004 Land Use Census was to compare census and current REMP Manual locations to ensure consistency exists between monitoring activities and actual land utilization. The following discussion is a summary of the comparison evaluation for each of the four exposure pathways.

Resident Exposure Pathwav Luxel dosimetry and air particulate sampling and analysis monitor the inhalation and ground plane exposure pathways, the principal-components of the Resident' Exposure Pathway, directly and indirectly. Well water was-monitored at three locations.

Since the existing REMP was more conservative with respect to Resident Exposure Pathway monitoring, no changes were required.

Deposition Exposure Pathway The Deposition Exposure Pathway is monitored directly within the Station Site Boundary through garden vegetation sampling and analysis. The potential for a deposition pathway has been evaluated by the ODCM and REMP programs and found to have little potential for the current plant status. Since the current REMP was representative and conservative with respect to Deposition Exposure Pathway monitoring, no changes were required.

Irrigated Crop Exposure Pathway The REMP was effective in monitoring the identified irrigated crop exposure pathways. This conclusion was because the REMP included irrigated vegetation sampling.

REMP surface water surveillance activities'monitor irrigation water radiological quality.

Current ODCM calculations are' conservative since dilution effects are not included when predicting potential dose delivered through downstream pathways.

Rancho Seco Nuclear Station A-5 2004 AREOR

E. REMP EVALUATION (continued)

Other Exposure Pathways Existing aquatic life, surface water and sediment sampling analysis practices are effective in monitoring potential observable effects associated with recreational activities occurring at the Clay Creek, Hadselville Creek, Lag'una Creek, Folsom South Canal and.Rancho Seco Lake.

With respect to availability and quantity of food sources, the other'identified consumption activities were considered inconsequential for'pathway monitoring purposes.

No REMP changes were required to monitor other exposure pathways..

F. ODCM EVALUATION Based on 2003/2004 Land Use Census findings, the following potential exposure pathways exist at the indicated locations:

LIQUID EFFLUENT Exposure PathaL -- . Location - Comment Freshwater Fish Clay Creek Recreation beyond the Site Boundary Swimming Clay Creek Recreatioh beybndtheSite Boundary Shoreline Deposits Clay Creek Recreation beyond the Site Boundary Irrigated vegetation. Clay Creek Commercial vineyards and potential

'-' residences beyond the site boundary Irrigated forage Clay Creek" Cattle grazing beyond the Site Boundary Drinking Water Clay Creek Cattle drinking water beyond the Site Boundary I . I . a . I. I I -

I .

, , f .I . - . I Rano N .c a ..So 2 Rancho Seco Nuclear Station A-6 2004 AREOR

-- IJUL.

F. ODCM EVALUATION (continued)

Specifying the Laguna Creek location also provides additional conservatism since the beneficial effects of downstream dilution are not considered when specifying effluent release restrictions.

As required by the 2003/ 2004 Land Use Census the above information for exposure pathways and locations was submitted'for incorporation in the 0DCM.

  • 1 Rancho Seco Nuclear Station A-7 2004 AREOR

APPENDIX B SAMPLE SITE DESCRIPTIONS AND MAPS This appendix provides descriptive information about the sampling locations and maps of all the locations for the Radiological Environmental Monitoring Program sites.

Table B-1 provides information on sample type, identification codes, and map location-references. The sample identification code is an alphanumeric string beginning with the prefix "R" (for Rancho Seco Nuclear Station) followed by two letters to identify the sample media:

AS Air MS Mud and Silt RW Runoff Water FS Fish SW

  • Surface Water LV Garden Vegetable DW Drinking Water TL Direct Gamma Radiation (Luxel)

'WW Well Water The numeric designations, which follow the letter designations, indicate the straight-line distance (in miles) from the center of the Reactor Building to the monitoring site.

The next letter designates the sector in which the monitoring location is located. The letters A through R are used for sector designators. The letters I and 0 are not used to prevent confusion with the numbers one and zero in the ID codes.

Sector Letter Degrees Azimuth Compass Point A 348.75 to 11.25 N B 11.25 to 33.75 NNE C 33.75 to 56.25 NE D 56.25 to 78.75 ENE E 78.75 to 101.25 E F 101.25 to 123.75 ESE G 123.75 to 146.25 SE H 146.25 to 168.75 SSE 168.75 to 191.25 S K 191.25 to 213.75 SSW L 213.75 to 236.25 SW M 236.25 to 258.75 WSW N 258.75 to 281.25 W P 281.25 to 303.75 WNW Q 303.75 to 326.25 NW R 326.25 to 348.75 NNW Rancho Seco Nuclear Station B-1 2004 AREOR

It E1L.

SAMPLE SITE DESCRIPTIONS AND MAPS (continued)

The final letter designation indicates if the location is part of the operational REMP program

("O") or post-operational REMP program ("P').

Table B-1 Lists each location referencing the sample t ype and the location ID code to the map site number on one of the four Radiological Environmental Monitoring Site Maps included in this-Appeiidix.

Figure B-1 Site Location Map: Shows the locations of the sample locations on' and/or near the Site (including Storm Drain locations).

Figure B-2 I Mile Radius map: Sampling locations within one mile o the Reactor Building centerline are sho'wun on this map.

Figure B-3 5 MPile Radius man: Sampling iocat~ons bletween one and five iriles from the Reactor Building centeiine arle shuwn on this map.

Figure B-4 25 Mile Radius map: Sampling !ocations between five to 25 miles from the Reactor Building centerline are shown on this map.

,I I

II Rancho Seco Nuclear Station B-2 2004 AREOR

f##21 3 b#) . 18 :- 17:. 21 '16:

\g'3=(#3j; (12) -(6) '0l1)

(.f8) (#5) MN Radiological Environmental Sam-piing Locations on and near the Site (Storm Drain location numbers are in pareinthesis)

B-3 2004 AREOR Rancho Seco Nuclear Station

S Figure B-2 Radiological Environmental Sampling Locations within I mile from the Reactor Building Rancho Seco Nuclear Station B-4 2004 AREOR

- - - BMW PAoPEKrY Figure B-3 Radiological Environmental Sampling Locations from I to 5 miles from the Reactor Building Rancho Seco Nuclear Station B-5 2004 AREOR

-- SUMC PROMMTY DOtDRY Figure B-4 Radiological Environmental Sampling Locations 5 to 25 miles from the Reactor Building I

Rancho Seco Nuc!ear Station B-6 2G04 AREOR

Table B-1 Radiological Environmental Monitoring Sites and Map Locations

.No.

Description. of Location Miles Sector Sample Type IDCode Class Map Location Collection Frequency On Site-PAP BLDG. 0.1 C IND. 1 ..Weekly AIR RASO.1C0 Meteorological Tow'r 0.7 E RASO.7EC CON 2 Weekly AIR Effluent Discharge E 0.3 M RASO.3MO IND. 3 Weekly AIR Site Boundary 0.6 M RRW0.6MO IND. 5 Biweekly RUNOFF WATER

.Water-Sump 0.7 N RSWO.7NO IND. 6 Monthly -K SURFACE WATER

,- Rancho Seco Reservoir 1.3 F RSW1.3FO CON 7 Monthly .

SURFACE WATER ISCO Composite Sampler at Folsom South Canal 3.7 N RSW3.7NO CON 8 Monthly Comrnosite SURFACE WATER ISCO Composite Sampler at Effluent Disaharge 0.3 M RSW0.3M0 IND. 3 Monthly Composite SURFACE WATER Confluence of Clav nd Hadselville Creeks 1.8 N RSW1.8NO IND. . 9 Monthly SURFACE WATER Rancho Seco Site 0.1 G RDW0.1GO IND. 10 Monthly DRINKING WATER F

- Rancho Seco Lake Well 1.8 RDW1.8FP CON 30 -Mcnth!y .

DRINKING WATER SAS Well - 0.2 P RDWO.2PP IND 65 Monthly DRINKING WATER Site Well 0.3 E RWWO.3EO IND. 1_1 Quarterly WELL WATER Marciel Ranch 0.8 D RWW0.8DO CON 12 Quarterly WELL WATER

-B-7 2004 AREOR Rancho Seco Nuclear Station

Table B-1 (Continued)

Radiological Environmental Monitoring Sites and Map Locations Description. of Location Miles Secto Sample Type ID Code Class Map location No. Collection Frequency Effluent Discharge 0.3 M MUD AND SILT RMS0.3MO IND. 3 Quarterly Site Boundary A__ _ 0.6 M MUD AND SILT RMS0.6MO IND. 5 Quarterdy Effluent Discharge 0.3 M FISH RFSO.3MO IND. 3 Semi-Annual Site Boundary 0.6 M FISH RFSO.6MO IND. . 5 Semi-Annual Water Sump 0.7 N FISH RFS0.7NO IND. 6 -Semi-Annual Rancho Seco Reservoir 1.5 F FISH RFS1.5FO CON 7 Semi-Annual Confluence of Clay and Hadselville Creeks 1.8 N FISH RFS1.8N0 IND. 9 - Semi-Annual Site Boundary Garden irrigated with No-Name Crc>k 0.6 M GARDEN RLV0.6MO IND. 5 Setoi-Atinual

_a . water VEGETABLES Truck Garden which provides local produce from the NA NA GARDEN RLVXX.XX CON NA - Semi-Annual local area -

VEGETABLES . .

B-8 2004 AREOR Rancho Seco Nuclear Station

Table B-1 (Continued)

Radiological Environmental Monitoring Sites and Map Locations Collection Description of Location Miles Sector Sample Type ID Code Class Map Location No.

,_ ,_ _Frequency

_ NNW Permeter Fence N/O Spray Ponds; #1 0.3 R LUXEL. RTLO.3RO IND. 31 Quarterly Quarterly NE Perimeter Fence/ parking lot NE comner; #2 0.3 C LUXEL RTL0.3C0 IND. 32 Quarterly W Perimeter Fence road/ pole/ top of hill; #3 0.3 N LUXEL RTL0.3NO IND. 17 Quarterly SW Perimeter Fence road near RS lake filters; #4 0.3 L LUXEL RTLO.3LO IND. 20 Quarterly Perimeter Fence/ S/O of Admin. Bldg.; #5 0.3 H LUXEL. RTLO.3H;0 IND. 33 Quarterly Photovoltaic Facility/ HcfthLFnc6 (NRC); # - 0.4 F LUXEL RTLO.4F0 IND. 34 Rt. 104 entrance to Rancho Seco #7" 0.5. C LUXEL RTLO.5CO IND. - 35Quarterly.

Quarterly Tokay Substation; #11 .I - 0.8 K LUXEL RTL6.6KO IND. 36 Quarterily 'In Clay atTfpling's Residence 11633 Clay Station Rd;- 2.1 M LUXEL RTL2.7MO IND. 14

. _ _ .-. .. .. . -#16

-- _Quartedy _ Elliott Cemetery NearAngelo Dairy; #17 .8.2 K LUXEL RTL8.2KO IND. -37 - -

Quarterly - Sam Jaber Residence/ 60i Carbondale Rd/ lone; #18 7.8 C LUXEL RTL7.8CO IND. 38 --

Quartdy Well pump fence @ reservoir; #43 1.7 G LUXEL RTLO.7GO IND. 30. .

Quartery . Clay East & Kirkwood (NRC); #20 1.5 M LUXEL RTL1.5MO IND. 40 SSW of Site on Borden Rd; #26 3.9 K LUXEL RTL3.9KO IND. 41 Quarterly - .

Quartedy . Herald Fire Station #87/ 12746 Ivie Rd; #30 7.4 M LUXEL RTL7.4MO IND. 42.

. -: , . - i I .

B-9 2004 AREOR Rancho Seco Nuclear Station

Table B-1 (Continued)

Radiological Environmental Monitoring Sites and Map Locations Collection Frequency Description of Location Miles Sector Sample Type ID Code Class Map Location No.

Quarterly Folsom South Canal near Hobday Rd; #31 3.7 N LUXEL RTL3 7NO IND. 43 Quarterly BLM entrance to Folsom South Canal Pumping Station; #33 3.8 M LUXEL . RTL3.8N10 IND. 44 _

Quarterly Hadselville Cr. & Clay Cr.; #35 1.9 N LUXEL RTL1.9NO IND. 9 Quarterly Rancho Seco Lake Maintenance Building #19 1.8 F LUXEL RTL1.8F0 IND. 45 Quarterly 0:9 Miles E/O Site on Twin Cities Road/ Rt. 104; #46 1.4 D LUXEL RTL1.4DO IND. 46 Quarterly Dillard School; #55 8.0 P LUXEL RTL8.OPO IND. 47 Quarterly Marciel Ranch; 14626 Twin Cities Rd; #63 0.8 D LUXEL RTLO.8DO !ND. 12 -

Quarterly . Site Boundary Irrigated Garden; #65. 0.6 M LUXEL- RTL0.6MO IND. 5 LUXEL RLO.4NO . IND. 29 Quarterly Depression @ Clay Creek; #66 0.4 N Quarterly Soil Pile @ Clay Creek; #67 0.4 N LUXEL RTLO.4N01 IND. 29 Quarterly West Fence; #68 0.3 P LUXEL RTLO.3PO IND. 48 Quarterly West Garden, #88 0.3 N LUXEL RTLO.3NP IND. 5_ --

Quarterly- Southwest ISFSI, #89 - 0.4 N LUXEL RTLO.4NP IND. 54 Quarterly Northwest ISFSI, #90 0.5 P LUXEL RrLO.5NP IND. 55 Quarier. Northeast ISFSI, #91 0.3 Q LUXEL RTLO.3QP IND. 56-

.Quartey Highway 104 at the rail spur on pole, #92 0.7 Q LUXEL RTLO.7QP !ND. 59 .

Quarterly Clay East Road on pole south of site boundary, #93 0.7 J

. LUXEL RTLO.7JP . IND. 61 Quarterly ISFSI ALARA fence north side, #94 0.4 P LUXEL.- RTLO.4PP IND. 62

. i- I I. i B-1 0 2004 AREOR Rancho Seco Nuclear Station

APPENDIX C QUALITY CONTROL SAMPLE ANALYSIS RESULTS QUALITY ASSURANCE AND CONTROL Implementation of the Radiological Enviropmental Monitoring Program (REMP) consists of a number of discrete steps including:

> Sample collection,,

=> Packaging,

> Shipment and receipt, -

' Measurements of radioactivity,

=> Data evaluation, and PnRsnrvnri These program elements are performed according to approved, %Writtenprocedures to 'assure the validity of REMP results. This section discusses the internal quality control measurements.

made by the analysis laboratory, Eberline Services, and the results of their participation in the Interlaboratory Compariso-Prrogram implemiented by the National Institute of Standards Testing (NIST). The Interlaboratory Comparison-Program and the analysis laboratories Quality Assurance Programs provide information on the validity (accuracy and precision) of the REMP implementation steps listed-above.

Because REMP measurement validity-is important for evaluating protection of the health and safety of the public, RSNS has established an Environmental Quality Assurance Program (EQAP) for radiological environmental measurements. The Environmental QA Program implements the guidance provided in Regufatory Guide 4.15, (NRC79a).

INTERLABORATORY COMPARISON PROGRAM Eberline Services participates in the Interlaboratory Comparison Program (ICP) sponsored by the DOE. -The ICP is a radiological analysis quality control program implemented by NIST and provided by vendor laboratories. Eberline Services participates in an ICP provided by Department of Energy (DOE) and Environmental Resources Associates (ERA). Participation in an ICP is a requirement of the Rancho Seco Quality. Manual (RS02), section 1.4.3.2. It provides for an independent check of the proficiency of the laboratory. It also provides information on the precision and accuracy of measurements of radioactive material in REMP samples by Eberline Services. The extent of Eberline Services participation in this program includes all of the environmental radioactivity determinations that are related to the analyses required by the REMP manual.

Rancho Seco Nuclear Station C-1 2004 AREOR

INTERLABORATORY COMPARISON PROGRAM (continued)

The Intercomparison Program consists of sample media spiked with known quantities of specific radioactive materials at ievels normally found in environmental samples. Most samples require long counting times to determine if any activity is present, and the results may have large deviations from the mean. When the samples are distributed, there is an implied precision requirement given in terms of the analysis requested to be performed. After the labs provide the results of their analyses, the DOE and ERA laboratories provides a statistical summary of all the results by the participating laboratory, This report includes the acceptance control limits, the mean of all laboratories and the standard d6viadion of the results by all labs, among other statistics.

If the results of a determination by Eberline'Ser'ices in the ICP is outside the specified control limits or do not pass the outliers test, Eberline Services must investigate and, if a problem is identified,' take corrective action to prevent problem recurrence.

During 2004, Eberline Services analyzed 54 ICP'§aimple analysis related to the current REMP program.

The Eberline Services measurement results are piresented inTable C-1 along with the acceptable values for each test.

INTRALABORATORY QUALITY ASSURANCE PROGRAM Eberline Services by contract also operate an Intralaboratory Comparison Program (Quality Assurance Program) to maintain an acceptable quality level on a routine basis.

As part of their Quality Assurance Program, the laboratory performs background counts, an analysis of spiked samples, and duplicate sample counts for every ten Rancho Seco REMP samples analyzed. These quality control procedures are performed for all analyses except gamma spectrometry, for which weekly energy and efficiency checks are performed.

Personnel not directly involved with the analysis prepare the spiked and duplicate samples.

Spiked samples, as well as the radioactive sources used for the gamma spectrometer checks, are traceable to the National Institute for Standards and Technology (NIST).

Rancho Seco Nuclear Station C-2 r 2004 AREOR

RANCHO SECO AUDIT AND SURVEILLANCE RESULTS The Rancho Seco Quality Program requires periodic audits of REMP activities, including Eberline Services. Contract laboratory performance is evaluated by the Rancho Seco QA Department.

CONCLUSIONS The Intraiaboratory and In'terlaboaoyrslspovide byEelin Services indicate that Eberline Services pe'rformance~was acceptable.

DIRECT RADIATION (Luxel) COMPARISON PROGRAM The monitoring badge. vendor, Landauer participates in-a comparison program provided by the Idaho National Environmental Laboratory (INEL). INEL did not conduct this comparison program in 2004; therefore no. results from thatpormaeaaal o thsrpt.Lnae also maintains NVLAP ceriiication wih N STAreiwoLandauer's NVLAP certification results indicates that Landauer has satisfactorily completed all of the required tests for the types of environmental radiation moni ored at RSNS and is certified through December 3.1, 2005.

This comparison program satisfies the requirement of the REMP manual section 6.0.

Rancho Seco Nuclear Station C-3 2004 AREOR

TABLE C-1 2004 INTERLABORATORY COMPARISON PROGRAM 1

I 1 Sample Type. Sample Date Assay Type lERA Result Eberline Result Control Limits (ERA RAD-56)

,- l 4/23/04 Sr-89 44.9 48.4 36.2-53.6 Water 4/23/04 Sr-90 11.6 10.5 2.94-20.3 Water 4/23/04 Ba-133 63.2 57.8 52.3-74.1 Water 4/23/04 Cs-134 75.8 78.7 67.1-84.5 Water 4/23/04 Cs-137 155 164 142-168 Water 4/23/04 Co-60 96.4 98.0 87.7-105 Water 4/23/04 Zn-65 102 109 84.4-120 Water 4/23/04 Gross Alpha 16.6 23.6 1.94-25.3 Water 4/23/04 Gross Beta *41.5 44.5 32.8-50.2 Water 4/23/04 TritiuI I 24900 24100 20600-29200 Water I__-_-_.,_ I _-_ _ _ _

C-4 2004 AREOR Rancho Seco Nuclear Station

TABLE C-1 (cont.)

2004 INTERLABORATORY COMPARISON PROGRAM Sample Type Sample Assay DOE Result Eberline Control Limits (DOE MAPEP-03-W11 Date Type Result Water 5/6/04 Cs-134 322.0 326.6 225.40-418.6 Water 5/6/04 Cs-137 124.0 121.5 86.80-161.20 Water 5/6/04 Co-60 121.8 123.1 i 85.26-158.34 Water 5/6/04 Tritium 379.0 X 390.7 265.30-492.70 Water 5/6/04 Mn-54 155.0 ' 155.9 108.50-201.50- -

Water. 5/6/04 Zri-65 - 320.0 L 341.5 224.00-416.00- - -

, , ~~~I  ; ' ' -'a'"'

. . . I .. . .

I. .. . ..

Rancho Seco Nuclear Station C-5 2004 AREOR

TABLE C-1 (cont.)

2004 INTERLABORATORY COMPARISON PROGRAM Sample Type Sample Assay Type EML Result Eberline Result Control (QAP .59) Date (reported) Limits (Reported/'

EML value)

Air Filter

  • 8/04 Co-60 35.4 +/- 0.85 35.5.+/- 0.33 (1.00) 0.80-1.26 Air Filter
  • 8/04 Cs-134 18.2 +/- 0.402 21.0 +/- 0.49 (1.15) 0.80-1.32 Air Filter
  • 8/04 Cs-'37 26.4I+ 0.86 27.5 +/- 0.25 (1.04) 0.80-1.32 Air Filter 8/04 Grcss Seta*' 2.85 +/- 0.28 2.73 +/- 0.035 (0.95) 0.76-1.36 Soil 8/04: Cs 1' 1323.0 +/- 66.17 1112.0 +/- 5.33 0.84) 0.80-1.25 Vegetation 8/04 Co--Go 14.47 +/- 0.64 :13.8 +/- 1.37 (0.95) 0.80-1.44 Vegetation 8/04 Cs- i37 584.67 +/- 29.23 477.0 +/- 3.71 (0.81) 0.80-1-.-31 Water 8/04_ Co-60 163.2 + 5.9 152.1 i 1.13 (0.93) 0.80:1.20 Water 8/04 Cs-1 37 51.95 22.7 49.4 +/- 0.67 (0.95) 0.80-1.22 Water 8/04 Gross Beta .1170.0 117.0 1177.0 +/- 23.5 (1.01) 0.61-1.43 Water 6/03 Tritium 186.6 +/- 3.3 252.0 +/- 19.0 (1.35) 0.78-2.45 C-6 2004 AREOR Rancho Seco Nuclear Station

TABLE C-1 (cont.)

2004 INTERLABORATORY COMPARISON PROGRAM Sample Type Sample Assay Type ERA Eberline l Control Limits (ERA RAD-58) Date Result Result l Water 4/23/04 Sr-89 20.0 21.7 11.3-28.7 Water ' 4123/04 Sr-90 136' 13.0 4.94-22.3 Water '4/23/04 Ba-133 32.1 31.4 '23.4-40.8 Water 4/23/04 Cs-1 34 '21'.6 22.3 .12.9-30.3' Water 4123/04 Cs-137 '193i, 202 .176-2.10 Water 4/23/04 Co-; O 24.0 25:1  : 15.3-32.7 Water '4123/04 -Zn-f65 '.143 .'- 156 - 118-168-

- A123/04 4ate- Gross'Alpha ;5 , >- 32.6, 32.37-81.7 -

Water *4/23/04, Gross Beta 20.0' 17.5 11.3-28.7 ,

Water .4/23/04 Tritium 5890 60 4870-6910 i I . . .

I .

_ " i . -.. I I _ . I I -

.. .- C-7 2004 AREOR Rancho Seco Nuclear Station

TABLE C-1 (cont.)

2004 INTERLABORATORY COMPARISON PROGRAM Sample Assay DOE Eberline Control.Limits Sample Type ll (DOE MAPEP-04-MaW12) Date Type Result Result 11/19/04 Cs-134 208 209.2 145.60-270.40 Water 11/19/04 Cs-137 250 253.3 175.00-325.00 Water 11/19/04 Co-60 163 171.3 114.10-211.90 Water Water 11/19/04 Tritium 82.9 84.55 58.10-107.90 11/19/04 Mn-54 267 281.6 186.90-347.10 Water Water 11/19:04 Zn-65 208 209.2 145.60-270.40 (DOE MAPEP-04-GrWI2.

11/19104 G-ross 4.07 4.35 2.05-6.15 Water

___ Beta - ____-_-__ --

-.. -l (DOE N!APEP-04-MaS12) _-

Soil 11/19/04 Cs-134 414 338.3 290.08-538.72

. -_ 11/19/04 Cs-137 836 643.5 585.34-1088 11/19/041 Co-60 518 416.6 362.60-673.40

. 11/19/04 1,Mn-54 '485 3a6.4, 339.29-630.11

_ 11/19/04 Zn-65 699 576.9 489.51-909.09

__ I '" - _

_ _ '---_ _ _ ' _ - -__ __ __ _'_ _'_ _. _ I C-8 2004 AREOR Rancho Seco Nuclear Station r

TABLE C-I (cont.)

2004 INTERLABORATORY COMPARISON PROGRAM Sample Type Samplp -Assay- DOE Eberline control Limits (DOE MAPEP-04-RdF12) Date Type A Resuit Resu!t Air Filter - 11/19/04 'Cs-134 2.9 3.50 2.03-3.77 Air Filter 11/9/04 Cs-137 1.96 2.07 1.40-2.60 Air Filter ___ __:_11/19104 Co-60 2.35 2.35 1.61-2.99 Ail Filter 11/19/04 Mn-54 3.03 3.27 2.10-3.90 Air Filter 11/19/04, Zn-66 l 4.11 4.84 2.80-5.20

_______,., ._______.l..--,:--:- ___,

2.' ..

. i ,  : .  : L .

.. , I , . If J

I Rancho Seco Nuclear Station2  ? C-9 2004 AREOR

____ ___I

___ i2 L.

APPENDIX D SAMPLE COLLECTION AND ANALYSIS METHODS For each of the sample media collected, the method of collection is documented in Rancho Seco Nuclear Station procedures. Detailed analysis methods are documented in procedures controlled by the contract laboratory, Eberline Services. A brief description of these collection and analysis methods is included in this Appendix.

Sample Media Collection/Analvsis Method AIR An air sampler continuously move's air through a filter paper designed to capture particulates by filter paper impaction. The air samplers are equipped with an elapsed time meter and flow gauge, which are used to calculate the volume of air that has passed through the filter paper.

The filter paper is exchanged weekly.. At least one day is allowed to elapse between samp5le collection and counting to reduce the interference of naturally occurring radon and thorium daughters on the sample analysis. The filter paper'is assayed for gross beta radioactivity by placing the filter on a stainless steel planchet and counted with an internal gas flow proportional counter.

The individual particulate filter papers are saved over a calendar quarter and the composite collection is assayed for gamma isotopic radioactivity by gamma spectroscopy.

DIRECT RADIATION Monitoring badges, (Luxels), are l6cated within a ten (10) mile radius of the site. The badges within a fiv'e (5) mile radius are considered indicator badges. Two (2) badges are placed at each monitoring location to assure adequate data recovery and to improve measurement statistics. The badge field exposure cycle is approximately ninety (90) days. At the end of the field exposure cycle, the badges are exchanged and returned to the contract laboratory for processing.

Rancho Seco Nuclear Station D-1 . 2004 APEOR

Sample Media CollectionlAnalysis Method SEDIMENT Samples of sediment are 'collected from the top three inches of the sampled material. Sediment samples are obtained approximately two feet from the shoreline. Each sample is assayed directly for gamma

-isotopic radioactivity' by ga~mma spectroscopy.,

GARDEN PRODUCE Samples of vegetables are collected semi-annually from a garden, which is maintained atihe Station Site Boundary. Control location samples.are collected from a local commercial vendor. The vegetables

-are assayed directly for gamma isotopic radioactivity by gamma spectroscopy. '

FISH Fish are collected semi-annually from the Clay Creek system. The dissected (edible) portion of each sample is assayed directly for gamma isotopic radioactivity by gamma spectroscopy.

WATER ' 1-liter grab samples of water frofr locations- in the liquid effluent pathway and groundwater are collected as follows:

  • Surface water and Drinking water are collected monthly
  • Runoff water is collected biweekly
  • Well water is collected 'quarterly.

At two locations, samples are obtained to provide a monthly composite sample. All samples are assayed for tritium by liquid scintillation

. . i- '. ,, ,I " -

counting and for gamma isotopic radioactivity by gamma zpectroscopy.

_1- I Drinking and Well water 'sarnples are analyzed for Gross Beta activity.
Drnkn an ,l . ar *an

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Rancho Seco Nuclear Station D-2 2 AREOR 2004

APPENDIX E ENVIRONMENTAL MONITORING PROGRAM DESIGN PROGRAM BASIS The Sacramento Municipal Utility District conducts a continuous Radiological Environmental Monitoring Program.(REMP) at the Rancho Seco Nuclear Station to assess the impact of Station operation on the surrounding environment. The current Post-Operational REMP is a continuation of a similar program initiated prior to and during operation of the Station. Samples of the surrounding environment are collected on a routine basis and analyzed to determine the amount of radiation and radioactive materials present in the exposure pathways.

During 2004 the program was directed and executed by the Radiation Protection/ Chemistry Superintendent. Decommissioning Chemistry/ Radiation Protection Technicians perform sample collection. The Radiological Health Supervisor performs data review and Program maintenance! oversight. The Program is operated with primary accountability and cognizance of the Manager, Plant Closure and Decommissioning.

The Program is designed consistent with Title 10, Code of Federal Regulations, Part 50, Appendix I - Section IV, B.2, 8.3 and C, and Appendix A, "General Design Criteria for Nuclear Power Plants," Criterion 64. The program also complies with Title .10, Code of Federal Regulations, Part 20, "Standards for. Protection Against Radiation," Section 1302. These federal requirements are cited in the Rancho Sepo Quality Manual, Appendix A,-and the REMP manual. REMP requirements are.implemented through the review, approval and routine use of several documents, namely the REMP Manual,, Offsite Dose Calculation Manual, Surveillance Procedures and Health Physics Implementing. Procedures.

The programmatic elements of the REMPlare based'on regulatory requirements and-associated guidelines. The objectives of the Program are to:

1. Provide the technological basis and the instruction for monitoring the environs for radioactivity sources. The radioactive sources, which contribute to detectable radioactivity in the local environs, are comprised of:

=> naturally occurring background,

=> releases during normal operations,

=> world-wide weapons testing, and

=, major global nuclear accidents Rancho Seco Nuclear Station E-1 2004 AREOR

PROGRAM BASIS (Continued)

2. Provide the means to verify the effectiveness of the Rancho Seco Nuclear Station Radiological Effluents Control Program.
3. Meet the minimum detectable limits for radioisotopes in environmental samples.
4. Provide quantitative measurements in thie gaseous (airbomenparticulate), liquid, and

'direct radiation exposure pathways for radionuclides.

5. 'Provide indications of the largest potential radiation exposure for individuals as a result of radionuclides in the principal exposure pathways.

The Program is deveioped and conducted using recognized standards and practices NRC79a, NRC79b, NUREG79, and NUREG8Oa.

REMP CHANGES The REMP manualwas not revised during'2004. Acdministratively controlled sampling was modified as'follows" - '

  • Soil, Rainwater, anid Algae sampling was disc6ntinued.
  • Garden samples from the 1ocal vineyards were discontinued.
  • The lback-up Control air sample locaioni at the Rancho Seco Lake Well Enclosure was

'discontinued. '

  • 2 Luxel badge locations were dis'con'tinued.
  • 3 of the 5 sediment sample locations were discontinued
  • 7 well water sample locations were discontinued These modifications were made as part of the REMP program downsizing of the Decommissioning Project and were reviewed by Plant Management prior to implementation.

EXPOSURE PATHWAYS ' '

The fundamental parameters, which have been defined prior to monitoring the environs, are:

1. Identification of the effluent release pathways
2. Identification of the human exposure pathways
3. Identification of the land use parameters by the population within a two-mile radius of the plant site.

Each of these three parameters is discussed below.

Rancho Seco Nuclear Station E-2 2004 AREOR

. - - .zjg&-

EXPOSURE PATHWAYS Effluent Release Pathways There are two principal 'pathwvays, which may result in human exposure to radiation and radioactive material originating from Station operation:

1. Liquid effluents and'
2. Direct radiation from these effluents and onsite sources.

Liquid Effluents' In the liquid exposure pathway, humans can ingest radioactive materials in surface waters directly or indirectly through the consumption of aquatic foods such as fish and she'Ifish.

Humans can consume vegetation, which is irrigated with Clay Creek water, which may contain radioactive material. Another exposure pathway from liquid effluents results from the consumption of animal products such as meat and milk from animals, which have fed upon irrigated vegetation and/ or consumed Clay Creek water.,

Direct Radiation In the direct radiation pathway, potential radiation exposure may occur from radioactive material storage areas, which are contained within the site boundary. People can potentially be exposed to direct radiation from ground deposition of par iculates deposited on the ground from liquid effluents. With the off-loeding of -D'ent fuelfto the ISFSI, the ISFSI has become part of the direct radiation pathway.

Rancho Seco Nuclear Station E-3 2004 AREOR

LAND USE CENSUS On a biennial basis, a.land use census is conducted within a two-mile radius to identify any changes in the human exposure pathways. The Land Use Census is used.to determine the changes needed for REMP monitoring activities. The results of the land use census conducted during 200312004 are presented in Appendix A 6f this Report. The next scheduled land use census will be conducted in 2005/ 2006 and reported in the 2006 AREOR. From data obtained from the Land Use Census, exposure pathways are analyzed through.a systematic process, which identifies a sample medium, or organism that is found to potentially contribute to an individual's radiation exposure. Usage'and bioaccumulation factors (NRC77) are then specified which represent the magnitude of radioactive material transfer through'the food chain to a receptor. The analysis of the effluent and exposure pathways enables monitoring sites'to be identified as "indicator' (for sites at which the potential effects of Station effluents would be readily detected) or "66ntrol" (for those sites which1 are not expected to be influenced by Station operation): The analysis results of samples obtained at indicator and control sites are routinely compared to identify potential exposures above background levels.

MONITORING LOCATION SELECTION:

The REMP maintains the monitoring sites required by the REMP manual, Table 6. This program is supplemented with additional samples to compensate for changes in the radiological environment surrounding Rancho Seco. The California Department of Health Services also selected sornr of (he monitoring sites as part of their monitoring programs.

Indicator sites~are placed in areaswhich would be most sensitive to the effects of Station effluents such as downwvirid, or dowrstrear 'areas near the Station. If radioactive material is detected abov6ebackgrbund at any of these indicator sites, observed potential exposure and

  • dose to humans can be estimated to verify the effectiveness of the Offsite Dose Calculation Manual in predicting potential exposures or doses. It is important to note that the detection of radioactive material in indicator samples does not necessarily mean that its presence can be attributed to Rancho Seco operations. Moreover, especially with liquid effluent pathway samples, the detection of radioactive material is difficult to interpret since it is unknown when the material was deposited. In many instances, the observed radioactive material could correctly be ascribed to historical (pre-2004) depositions.

Control locations provide data that should not be influenced by the operation of Rancho Seco.

These locations are selected based upon distance from the Station in the upwind or upstream direction of the effluent release pathways. -S'ahmples obtalined from control focation's should, upon analysis, reveal information about the presence and distribution of naturally occurring and man-made radioactive materials. Data from these'locations are used to aid in the discrimination between the effects of Rancho Seco releases and other natural phenomena or accidental releases, which may result in human exposure.

Rancho Seco NUclear Station E-4 2004 AREOR

MONITORING LOCATION SELECTION (continued)

Liquid radioactive effluents are discharge6 in batches from two onsite Retention Basins into "No Name" Creek located southwest of the Station. Dilution water, obtained from the Folsom South Canal, is discharged into "No- Name" Creek to give reasonable assurance of compliance with the 10CFR50, Appendix I dose guidelines. "No Name" Creek flows southerly into the Clay Creek. Without this dilution water flow, the Clay Creek would be in a dry state for most of the year.

Beyond the Site Boundary at a point north of Highway 104, the Clay Creek empties into the Hadselville Creek. Hadselville Creek then empties into the Laguna Creek at a point west of North Clay Station Road near the Folsom South Canal. Finally, Laguna Creek flows into the Cosumnes River at a point located approximately 20 straight-line miles west of Rancho Seco.

Since this stream system is the only routine release pathway for liquid radioactive and non-radioactive effluents from the Station, the liquid exposure pathway indicator sites are located along these creeks and nearby land.

The direct radiation pathway is monitored principally through a network of monitoring badges at sites distributed in sectors centered on the Station. -The badges are located primarily at the site, residential, and recreational areas around.'The Ranchlo Seob location. This design.

provides the capability to easily detect Station-induced direct radiation contributions to the observed terrestrial and cosmic direct radiation background.-

Some badges have been sited inspecial iocat!6ns to record.direct radiation resulting from, known depositions of radioactive material aind to provide-1-0 CFR Part 72 license req!Aired data for the Interim Spent Fuel Storage Installation (ISFSl): 7 Appendix B contains a detailed descriptioin and illustration o&the REMP sample and monitoring locations.

Rancho Seco Nuclear Station E-5 2004 AREOR

SAMPLE MEDIA Samples are collected from predetermined rnonitorfig sites at a specified frequency. The sample media chosen is a function of the type of mon toring desired and coincides with one of the following exposure pathways:

o Atmospheric o Direct radiation o Terrestrial o .,Aquatic life o ' later: . -

Atmospheric monitoring is accomplished by filtering a volume of air using a mechanical air pump to collect particulates with a particulate filter paper. Thre' air sampler locations are used to collect weekly air samples. One location (Meteorological Tower) is a control location and the remaining two locations are indicator locations-on the plant site.  ; - r Direct radiation monitoring is achieved by placing-monitoring badges at aboveground sites..-

The monitoring badges respond to, and record the amount of, gamma radiation exposure.. The source of this gamma radiation exosure is varied and includes potential Station effluents, naturally occurring terrestrial, anid csrhiogohic radionuclides.-.The monitoring badges are also influenced by seasonal and global (fallout) radiation sources.

There are -33 sites, which a~e'monit:red wmthin a .10-mile radius of the Station. The monitoring badges are placed at the Station Industrial Area Boundary, near the property boundary, locations of interest such as nearby residences, and at control locations located beyond five miles of the Station.

Terrestrial monitoring is accomplished by obtaining samples of sediment and garden vegetation to measure the quantity of radioactive material deposited from liquid effluents.

There are two mud and silt (sediment) and 2 garden vegetation locations.

Aquatic monitoring includes the sampling of fish. There are four fish sample locations.

Rancho Seco Nuclear Station E-6 2004 AREOR

SAMPLE MEDIA (continued)

Water monitoring includes samples of surface, runoff, drinking, and well sources from locations in the liquid effluent pathway and from area wells. The six surface water sampling locations monitor site supply 'water (Folsom South Canal), runoff waterand water discharged from the Station. Drinking water is sampled from two groundwater wells and three drinking water taps.

SAMPLE ANALYSIS & DATA HANDLING The laboratory, which provides radio-analytical services for the Program, is Eberline Services located in Richmond, California. Sample analysis results submitted by Eberline Services are reviewed for accuracy and completeness and then entered into a computerized database for evaluation.

Data comparisons are made between individual cobntrol and indicator sample sites to isolate potential Station influences on the measurement results. '

The summarized results of the 2004 Radiological Environmental Monitoring Program are presented in Table 2.

Individual (raw data) results are presented in Appendix F, Tables F-1 through F-9.

REGULATORY REPORTING LEVELS Sample analysis data is reviewed and evaluated by the Radiological Health Supervisor as the results are received. All sample analysis results are reviewed for correct sensitivity and anomalies.

The activity concentration values listed in Table E-1 are the environmental Fuel Cycle Dose quantities that, if exceeded, reqfuire a Speclal Report to be submitted to the USNRC. In accordance with the REMP Mahuial (Sectiohi 5, Fuel Cycle Dose), the'Special Report must include an evaluation of any release conditions,4'nvironmental factors or other aspects, which caused the reporting limits to be exceeded.

Rancho Seco Nuclear Station E-7 . 2004 AREOR

REGULATORY REPORTING LEVELS (continued)

In addition to the Fuel Cycle Dose reporting requirements, a Special Report is required to be submitted'to the USNRC wheri more than one of the radionuclides in Table E-1 are detected in the sampling medium' and the sumnmned ratio of detected activity concentration to the respective Reporting Level c6ncenhtration is greater thani,'or equal to, unity (1). When radionuclides other than those listed in Table E-1 are detected which are a result of Station effluents, a Special Report is required to be submitted if the potential annual dose commitment exceeds the 10 CFR 50, Appendix I guidelines.

No reports of the types described above were required to be submitted during 2004.

SENSITIVITY OF THE REMP MEASUREMENT PROCESS All Program measurements must be performed at a sensitivity, which meets USNRC requirements.' This sensitivity is determined "befoe'the fact" (aprion) for each radionuclide of interest and sample analysis type. Typical controllable sensitivity parameters include:

=> Sample volume or mass

=> Sampling efficiency

> Time from sample collection to measurement

= Instrument detection efficiency for the nuclides (energies) of interest

= Background radiation leve!s

=> Chemical recovery factors By adjusting and controlling each of these parameters to raximize measurement process efficiency, a maximum sensitivity level (activity concentration) can be specified for each nuclide of interest and analysis type while maintaining a;p economic measurement process. The maximum sensitivities in the REMP are specified by the USNRC in the REMP Manual approved for Rancho SeQo. These sensitivities are referred to as "LLD's", an acronym for "Lower Limit of Detectionr'. LLD's are specified on an "a prior? basis and apply to routine measurement process capabilities when no other interfering radioactivity is present. The word "routine" is emphasized since occasional circumstances, such as limited sample mass, elevated levels of background radiation and interfering nuclides can contribute to sensitivity degradation.

Such occurrences are normally noted and reported during the conduct of REMP activities.

Rancho Seco Nuclear Station E-8 2004 AREOR

MALL-SENSITIVITY OF THE REMP MEASUREMENT PROCESS (continued)

Meeting the LLD requirements is a quality control function shared by both REMP and the analytical laboratory personnel. Once the lab&otory establishes values for the controllable parameters for each analysis type, sample chain of custody controls ensure that these parameters are upheld: If all parameters are upheld, then compliance with the LLD requirements has been demonstrated. The specific LLD values for Program measurements are included in Table E-2.

Since most of the samples-analyzed result in the detection decision "activity not identified", a Minimum Detectabfe Activity (MDA) concentration value is calculated and reported. This value can be thought of as the LLD-at-the-time-of-counting since it is calculated'using an equation, which is similar to the one, used to establish LLD parameters. The biggest difference is ' hat actual (not "aprior?') parameters are used, including interference fronm natural radioactive material in the sample. It is important to note that MDA's are reported only for those measurements where the "activity not identified" decision has already been made.

MDA values are used primarily to identify changes in the measurement process arid to convey more information about the measurement itself. Without the use of the MDA concept, most Program measurements would be reported simply as "<LLD"'- With MDA used, Program measurements are reported as "< xxx "where "xxx' is the calculated MDA concentration.

I. - .. f I I

. , . . T, ,;;

Rancho Seco Nuclear Station E-9 2004 AREOR I . . - -I... I

TABLE E-1 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES.

Water- Airborne I d'h- :; F ;i Food A (pCi/L) Particulate or3 (pCilkg, wet) . -Products Analysis Gases (pCiIM ) .. (pCilkg, wet)

' H-3' tH-3 20000a':: \ . > -

Mn-54' .i' '30000 Co-60. 300 , - 10000 Zn-65 300 . 20000 ....

Cs-! 34 . .30 ,, 10 1000 1000 Cs-137 50 l20 20002000 Gross Beta 40 h2 C Notes: .For drinking water samples, this is a 40.CFR Part 141 value Gross Beta activity in water of ten times the yearly mean of the control samples is indicated as the level, that gamma isotopic analysis should be performed on the individual sample (NRC79a). Gamma isotopic analysis on each water sample is required by the REMP and therefore this requirement does not apply.

c Gross Beta activity is air of ten times the yearly mean of the control samples is indicated as the level that gamma isotopic analysis should be performed on the individual sample. The value indicated is Site specific.

nI - I N l Statio Rancho Seco Nuclear Station ..E-1 0 E1020 RO 2004 AREOR

TABLE E-2 MAXIMUM (REQUIRED) LLD VALUES.FOR ENVIRONMENTAL SAMPLES (NRC79A)

_ _= -

Airborne Fish Food Sediment Analysis Water Particulate (pCilkg, Products (pCilkg, dry)

(d) d)p (pCoIL) iL or Gases (pCi/M 3 )__

wet) (pCilkg, dry) _ _ _ _ _

Gross Beta 4 0.01 H-3 2000 (1000, )

Mn-54 15 130 Co-60 15 130 150e Zn-65 30 260 Cs-134 15 (10 ) d130 60 150 Cs-137 18 (10 b 0.01d 130 60 150 Notes:

(a) Analysis requirements are those recommended in the BTP [NRC79A] and RETS [NUREG79].

(b) LLD for water samples utilized for human consumption only [NUREG79].

(c) Other peaks, which are measurable and identifiable, together with the nuclides in Table E-2, shall be identified and reported.

(d) Composite analysis LLD is Shown; individual sample LLD is 0.05 pCi/i 3 (Site-specific value).

(e) LLD for Mud and Silt Co-60 is not required by RETS [NUREG79]. This value is consistent with the RETS required value for Cs-1 34 and Cs-1 37.

Ranch o Seco Nuclear Station E-1 1 2004 AREOR

APPENDIX F 2 .  ; A Y. R.A

- 2004 SAMPLE ANAW-sis -RAW DATA TABLES I i . : - . . . ._..  ; . !. , I . . I i .

i f

f . .

.I .; .. ..

. I

>1'.

Rancho Seco Nuclear Station F-1 .. 2004 AREOR

TABLE F-1 2004 WEEKL'Y AR SAMPLE

SUMMARY

Gross Beta Activity in Air Particulates (pCi/m3) 1/6/2004 0.015 0.001l 0.018 0.001 0.017 0.001 1113/2004 0.031 0.001 0.031 ;0.002 0.032 0.002 1/20/2004 0.047 0.002 .0.051 0.002 0.051 0.002 1/25/2004 0.025 0.001 0.024 0.001 0.026 0.001 1/27/2004 0.035 0.002 0.037 0.002 0.038 0.002 2/4/2004 0.013 0.001 0.014 0.001 0.014 0.001 2/10/2004 0.016 0.001 0.014 . 0.001 0.016 0.001 2/17/2004 0.026 0.001 0.028 0.001 0.029 0.001 2/24/2004 0.012 0.001 0.011 0.001 . - 0.011 0.001 3/2/2004 0.008 0.001 0.009 0.001 0.003 0.001 3/9/2004 0.016 0.001 0.020 0.001 0.017 0.001 3/16/2004 '-0.025 0.001 .0.027 0.001 0.027 0,001 3/23/2004 0.022 0.001 0.024 0.001 0.023 0.001 3130/2004 0.012 0.001 0.013 0.001 0.012 0.001 4/6/2004 0.014 0.001 0.013 0.001 0.014 0.001 4/13/2004 0.018 0.001 .015 -0.001 0.019 0.002 4/20/2004 0.009 0.001 0.010 0.001 -0.010 0.001 4/27/2004 0.018 0.001 0.017 - 0.001 0.019

. 0.001 5/4/2004 0.023 0.001 0.020 -`0.001 . 0.021 0.001 5/11/2004 0.010 0.001 -0.011 0.001 EO.O10

- 0.001 5/18/2004 0.012 0.001 '- 0.012 0.001 -0.013 0.001 5/25/2004 0.012: 0.001 0.01-3 1 0.001 . 0.012 0.001 6/1/2004 0.015 0.001 - 0.013 0.001 0.014 0.001 6/8/2004 0.015 0.001 0.014 - 0.001 0.014 0.001 6/15/2004 0.017 0.001 0.012 0.001 0.013 0.001 6/22/2004 0.017 0.001 0.015 0.001 0.017 0.002 6/29/2004 0.016 0.001 .0.015 0.001 0.014 0.001 Rancho Seco Nuclear Station F-2 2004 AREOR

TABLE F-1 2004 WEEKLY AIR SAMPLE

SUMMARY

(continued) .

Gross Beta Activity in Air Particulates

(

1ApCiirn 3) 7/C/2004 0.012 ':0.001 0.013 0.001 0.013 0.001 7/13/20D4 0.012 0001 0011 0001 0011 0.001 7/19/2004 0.014 0O.001 0.012 0.001 0.014 0.0011 7/27/2004 0.013 .0.001 0.013 0.001 0.013 0.001 8/3/2004 0.011 0.001 0.012 0.001 0.012 0.001

_8110/2004 0.014 ,0.001 10.014 0.002 0.013

. /17/2004 0.019 0.01 0.001 0.001 0.019 0.001 8/24/2004 0.014 . 0.001 .0.013 0.001 - 0.01 0.002 8/3112004 ,'0.015 0.002 . 0.013 0.001 ' 0.022 0.002 89/7/2004 0.023 0.001 0.022 !0.001 0.022 0.001 9/7/12004 '

9/14/2004 .003.-0.024 . 0.001 ;01 ' 022 0.020 .01 0.001 0.012 0.045

'/21/2004 0.013 0.001 0.012 0.001 0.00 0.004 0.012 0.002 9/2812004 0.024 0.001 0.048 0.002 0.058 0.003

.. 10/5/20041 10/5200  ! 01328 -', .i0.001 0.052 Q.02,0401-

-0.003 0.057 0.003 10111/2004 , 0.045 .52-.0005003 0.003 . 0.041 0.003 0.045 0.003 101912004 ;0.063 - 0.003 0.057 0.003 0.061 . 0.002

, 10126/2004 0.015 - 0O.001 0.015 0.001 0.018 0.001

.11/2/2004 - 0.043 0.002 0.038 0.002 , 0.043 0.002 11/912004 0.067 0.002 0.029  : 0.002 0.032 0.001 11(16/2004 0.068 0.003 0.029 . 0.006 0.064 0.003 11/23/2004 ,. 0.084 0.002  : 0.0351 0.002 0.2020.007 11/30/2004 0.038 0.002 . 0.035. 0.002 0.040 0.002 12/6/2004 ,0:044 0.002 0.046 0.002 0.045 0.002 12/14/2004 0.023 0.001 . 0.022 0.001 0.024 0.001 12/21/2004 0.036 .0.002 .. 0.031 0.001 0.037 0.002 12/28/2004 ' 0.043 '0.002 0.041 0.002 0.075 . 0.003 anh. Sn Rancho Seco Nuclear Station F-3 2004 AREOR

Table F-2 2004 Luxel Summary (Direct Radiation)

Quarterly (mRem)

I RTL0.3RO Site fence north of spray ponds. _ 16 19 20 20 2 RTLO.3CO NE corner of parking lot. I 17 21 19 21 3 RTLO.3NO Site fence west near south of rail spur I *22 30 25 24 4 RTLO.3LO Site fence south of canal pumps I 16 18 19 20 5 RTLO.3HO Site sduth of Admin. Bldg. :I 16 21 19 20 6 RTLO.4FO NE cornerof PV-1 I. 18 22 18 19 7 RTLO.5CO RS entrance sign I 17 23 19 19 11 RTL0.6KO Tokay substation I 17 17 17 19 16 RTL2.7MO Tippling's residence - I 18 15 15 17 17 RTL8.2KO Elliott Cemetery 25 C 22 21 22 18 RTL7.8CO Sam Jaber residence C 1_5 1 _9 1_7 1_7 19 RTL1.8FO RS Lake Maint. Bldg. I 18 16 14 16 20 RTL1.5MO Clay/ Kirkwood streets I 22 2_1 19 Missing 26 RTL3.9KO Borden Road 14 20 116 16 30 RTL7.4MO Herald Fire Staticnr C .16 21 21 19 31 RTL3.7NO Folsom South Cana! backentrance I 16 22 21 19 33 RTL3.8MO Folsom South Canal/ H'wyv 104 1 20 22 19 20 35 RTL1.9NO Hadselville/ Clay Creeks Ir 15 23 21 21 43 RTL1.7FO RS.Lake Well Encl. -I I 17. 15 18 17 46 RTL1.4DO Hwy-104 mile marker 13.15  : I 20 21 19 20 55 RTL8.OPO Dillard School ._ _C 16 18 _ 20 1_8 63 RTLO.8DO. Marciel Ranch: I 14 - 17 IS 17 65 RTLO.6MO Site Boundary'Garden. -1i 15 _17

_ 16 1_7 66 RTLO.4NO Soil depression area I: 26 35

-- 35 27 67 RTL0.4N01 Dredge pile ' 18 ' _21 20 20 68 RTLO.3PO Site fence west by ISOB _ 19 20_ 21 23 88 RTLO.3NP ISFSI south fence - .__2_'23 -_23 23 89 RTL0.4NP ISFSI south fence - 21 22 21 20 90 RTLO.5NP ISFSI west fence -_I_ 20 25 25 22 91 RTLO.3QP Site fence NW corner I 1_8 20 1_9 21 92 RTLO.7QP Railroad spur 16

_ 1_8 20 19 93 RTLO.7JP Clay Rd east south of site 1 _ 19

_8 _17 1_

9 94 RTLO.4PP ISFSI fence north - 20 25 23 23 I = Indicator Location / C = Control Location Rancho Seco Nuclear Station F-4 2004 AREOR

Table F-3 2004 Garden Vegetables Serni-anhual (pC0i/kg, wet)

RLV0.6MO 3/16/2004 <7.2 <8.0 <19 <8.2 <6.9 Cabbage RLVI8.OKO 3/16/2004 <2.7 <3.1 <7.5 <3.4 <2.3 Cabbage RLV18.OKO L9/29/2004 <3.69 <4.80 <11.1 <4.57 <3.20 Vegatables RLVO.6MO 9/2912004 <6.26 <6.50 <15.4 <7.40 <6.46 Tomato RLVO.6MO 9/29/2004 <8.51 <9.22 <20.2 <9.96 <8.23 Cucumber Table F-4 2004 SEDIMENT Quarterly -

,(pCi/kg)  :

I, RMSO.6MOQ: 1/27/2004 <4.6 141 <12: 1<5.8- 1143 16.0 RMSO.6MO 1/27/2004 <8.5 315 <21. <9.7 217- 11 RMSO.3MO.,' 1128/2004 <5.3 83.6 <14. <6.3 .177.2 6.5 RMSO.3MO: 4/26/2004 <4.5 46.0 .<14 <6.2 59.5 5.3 RMSO.6MOQ -4/2612004 <5.2 57.4 <14 <6.7 125 7.5 RMSO.6MO 4/26/2004 <5.7 114 <15 . <6.9 268 '10 RMSO.6MO 7/28/2004 <8.17- 128 <20.2 <10.2 121 7.5 RMSO.3MO 7/28/2004 <6.15 25.6 <14.3 <8.93 62.2 7.6 RMSO.6MOQ.. 7/28/2004

.578 <4.48 162 <12.4

<1.4 <5.78. 146 146 6.1 RMSO.3MO 10/21/2004 <8.56 21.7 <19.4 <9.877 113 6.1 RMSO.6MOQ 10/21/2004 <10.7 19.9 _<26.6. <13.2 125 11 RMS.6MO- 10/2112004 <6.02 27,8 <18.2 <8.03 109 7.3 Rancho Seco Nuclear Station F-5 2004 AREOR

TABLE F-5

. 2004 FISH Semi-Annual (pCi/kg, wet)

WIf W1 RFSO.6MOtl) 5 /17/20'i4 '58 -... 71 <1502 ~<76 267 X 61 RFSO.6MO(l) f 12/1/2004 <12.8 -113.7 <32.1 <1 5.7 51.2. 10 RFSO.6MO(1)Recount* 1 12/112004 <14.1 <15.0 <36.8, <15.7 49.4 11

  • Lab Initiated Note: (1)=Predator Snecies -

TABLE F-6 2004 WELL WATER Quarterly

-(pCiIL)

RWWO.8DO 2/17/200413 96 - 167 <4.15 <5.03 <

<5.65 <4.37 RWWO.3EO 2/17/200414.36 <174 <9.10 <10.3 <10.7 <9.51 RWWO.3EO 5/17/2004 2.81 <160. <7.6 <7.9 <16 <8.1 <7.5 RWWO.8DO 5/17/2004 3.2 - <160 <6.8 <8.1 <15 - <8.5 <7.0 RWWO.8D)0. 8/17/2004 <2.01 <187 '7.66. <7.50 <17.9 <8.23 <7.81 RWWO.3EO 8/17/2004 <1.80 <186 <4.13 <4.76 <9.86 <5.28 <4.17 RWWO.3EO 11/16/2004 4.35 <254 <7.01 '<7.87 <15.1 <8.46 <7.56 RWWO.8DO 11/16/2004 2.65 <253 <4.17 1<4.61 <8.33 1<5.41 <5.83

  • No Data Reported (> 10 half lives since Plant shut-down)

Rancho Seco Nuclear Station F-6 2004 0 AREOR

TABLE F-7 2004 RUNOFF WATER

' 'Biweekly (pCi/L)

RRWO.6MO 1/6/2004 <200 <8.7 <11 <23 <21 <9.G RRWO.6MO 1/20/2004 <180 <12 <12 <28 <15 <12 RRWO.6MO 2/4/2004 <180 <7.2 <7.8 <18, <8.3 <7.3 RRWO.6MQ 2/1712004 <160 <7.2 <6.6 <16 <8.1 <7.3 RRWO.6MO 2/24/2004 <160 <6.1 <7.1 <14 <7.5 <6.5 RRWO.6MO 3110/2004 <180 <3.8 <4.6 <8.4 <4.9 <3.8 RRWO.6MO 312312004 <170 <9.3 <10 <19 <12 <9.6 RRWO.6MOQ 4/6/2004 <160 <6.94 <8.33 <17.2 <8.24 -<7.18 RRWO.6MO 4/6/2004 <160 - ;<4.54 <4.22 <10.9 <5.53 <4.24 RRWO.6MO 4/20/2004 <150 <6.30 <6.71 <12.7 <8.10 <6.33 RRWO.6MO 5/4/2004 <170 -<6.5 <6.9 <16 <7.4 <6.4 RRWO.6MO 5/18/2004 <160 <4.3 <4.8 <8.9 <4.9 <4.1 RRWO.6MO 6/1/2004 .<160 . <6.3 <7.2 <13 <7.9 <6.2 RRWO.6MO 6/15/2004 c180; <4.0 <4.7 <8.4 <5.3 <4.2 RRWO.6MO 6/29/2004 <210 - <9.3 <9.3 <20 <12 <10 RRWO.6MOQQ 7!13/20Q4 -, ,<170 <8.99- ,10,2 <19.8 '<10.3 <8.67

'-RRWO.6MO 7/13/20G4 - <166 <8.67. <10.7 <21.1, <10.3 <9.77 RRWO.6MO ',7/27/2004- <164 <6.81 <7,03 <14.9 <8.11 <6.79 RRWO.6MO 8110/2004 <371 <7.72 <7.79 <16.6 <8.56 <6.94 RRWO.6MO 8124/2004 <188 <4.30 <4.81 <9.39 <5.75 <4.20 RRWO.6MO 9/7/2004 <184- <6.48 <10.8 '<20.6 <7.98 <7.59 RRWO.6MO 9/21/2004 <292 <9.00 <9.58 <18.1 <10.5' <9.48 RRWO0.610 1015/2004 <204 - <4.67 <4.90 <10.6 <5.32 <4.56 RRW0.6MCQ 1015/2004 <204 <7.80 <7.04 <17.5 <9.16 <7.40 RRW0.6M0 10/2112004. -.<166.- <7.60 <7.79"i <18.2 <8.46. <7.11 RRWO.6MO 11/2/2004 <158 <4.30 <4.82 <10.0 <5.47 <4.06 RRWO.6MO 11/15/2004 <255 <7.25 <7.65 <17.0 <8.64 <7.78 RRWO.6MO 11/30/2004 <249 <7.26. <7.60 <18.0 -.<8-79 <7.39 RRWO.6MO 12/14/2004 <258 <9.17 i <7.59 <21.4 1 <10.0 <8.60.

RRWO.6MQ 12/28/2004 <253 . <9.02 <9.27 <21 .6 <10.6 <8.26 RRW0.6MOQ 12/28/2004 <247 <8.03 <7.50 <20.2 <9.01 <8.14 Rancho Seco Nuclear Station F-7 2004 AREOR

ILE

. TABLE F-8 2004 SURFACE WATER Mo.n.hly Grab / Monthly Ccmposite

- (p !i/L), -

RSWO.3MO 1/27/2004 <160 <8.2 1<9.3 , <20 RSW3.7NO

<11 <9.5 1/27/2004 <160 <6.7c 7 <7.0 <16 <8.1 RSWO.7NO <7.0 1/28/2004 <160 <7.2 -<8.0 <17 <7.9 RSW1.8NO <7;1 1/28/2004 <160.- <4.5 <4.7 <9.1 <5.4 RSW..8NOQ <4.3 1/28/2004 <160. <2 <12 <28 <15 RSW1.3FO <13 1/28/2004 <160 - <6.7 -<70.0 <15 <7.1 RSW1.8NO <6.2 2124/2004 <160 <8.0 - <8.3 1<17 <8:9 RSWO.7NO c<80 2/24/2004 <160 <6.6 <7.0 <16 <7.7 RSWO.3MO <6-.8 2/24/2004 <160 <8.3 <8.3 <16 <9.4 RSW1.3FO: <7.9 21(412004 <160 <4.3 <4.7 <8.7 <5.2 .

RSW3.7NO <4.1 2/24/2004 <160 <10. <10 . <20 <1 1 -.

RSWO.7NO <9.5 3/30/2004 <170 <7.7 <7.9 - <17 <9.3 RSWN3;7NO <6.9 3/3012004 <160. - <7.5.. <8.0 <15 <9.0 RSW1.3FO <7.0 3/30/2004 <160 <12 _ <7.8. <18 <8.2 RSWO.3MO <6.7 3/30/2004 <160 <9.2. <9.1: <19. <9.&

'RSW1.8N0 <8,5

1. 3/30/20041<160 <9.9' 1<10 1<19 <11 . <9.1 RSWI.8NO I 4/28/2004 <170<' <44 1<4.9 <8.4 <5.3 <4.3 RSW1.8MOQ _ 4/2812004 <170 _<6.8 <7.1 <16 <7.& <6.9 RSWO.7NO . 4/28/2004 <17- <4 4: <4.2 RSW1.3FO

<9.9 <5.6. <4;2 4/2812004 <170 <4.1 <4.6 1<88.8 <5.2 RSWO.3MO <4.3 4/29/2004 <170 I <6.6 <7.S <15 <12, RSW3.7NO <6.7 4/29/2004 <170 <6.6 <7.7 * <14 <6.9 RSW1.3FO <6.7 5126/2004 <150 <7.3,- <8.3 <16 <9.2 RSW1.8NO <16.2 5/26/2004 <160 <6.6 <7.9 <15 <8.8 RSWO.7NO <7.1 5/26/2004 <160 <3.5 <3.6 <7. 8 _<49 _ <°.6 RSW3.7NO 5/26/2004 <160 1<54 <6.5.. <14 <6.5 <6.0 RSWO.3MO -'5/26/2004 <160. <5.8 <6.5 <13 <7.1 <5.6 RSWO.7NO 6129/2004 <210 <6.3- <7.6. <14 <7.9 '6.0 RSW0O.3MO 6129/2004 <200 <6:8 -8.0 <16 <9.3 <7.0 RSWI.3FO 6/29/2004 <200 <6.3 <6.6 <1 3 <72.3 <6.5 RSW1.8NO 6/2S(2004 <200 <3.7 <4.0 <7.4 <4.6 <3.8 RSW3.7NO j 6/29/2004 <210 <8.4 <9.0 <17 <:9.2 <8.8 Rancho Seco Nuclear Station F-8 . . 1 2004 AREOR

TABLE F-8 (continued, 2004 SURrACE YWATER Monthly Grab/.hMonthly Composite

~ ~; ~(Pr /)

  • '  ; '~~~~~~. . ,--.F1t;- 4 1 I 1 ffA= Fy RSW1.3FO 7/27/2004 <163 <9.06 c9.72 <17.1 9,66 <8.80 RSWV1.8NO 7/27/2004 <169 <8.33 <9.67 17.4 <11.0. <8.40 RSWO.7NO 7/27/2004 <170; <6.98 <8.16 <14.5 <9.13 <6.93 RSW1 i8NOQ 7127/2004 <164- <4.02 <4.25 " <9.02 <5.52 <3.98 RSW3.7NO 7/27/2004 <168 <3.95 <4.26 <8.71 <5.18 <3.88 RSWO.3MO> , 7/28/2004 <166 <7.02 <7.22 <16.5 <7.77 <6.94 RSW1.3FO 8/30/2034 <193 <6.12 <7.33 <14.0 <7.78 <6.03 RSWO.3MC0 8/30/2004 <186 - <6.55 <7.19 <15.8 <7.92 -<6.68 RSW1.8NO 8/30/2004 <191 <7.07 <7.43 <15.1 <8.88 <6.84 RSW3.7NO 8130/2004 <185 <7.31 <7.88 <15.5 <8.88 <6.62 RSWO.7NO' 8/30/2004 <188 <4.17 <4.67 <8.71 <5.14 <3.71 RSWI.3FO 9/28/2004 <204 <9.15 1<10.0 <20.1 <11.4 <8.70 RSWI.8NO 9i29/2004 <204 ' <4.72 <4.82 <9.84 '<5.64 -ic4.24 RSW3.7NO 9129/2004 <204'; <4.20 <4.92 <9.31 <5.40 <4.26 RSWO.7NO' 9/29/2004 <204 -, <7.58' -c7j48,- <17.4 <9.27 <7.15 RSW.3MO- - 9/30/2004 <204 - <7.36 <7.59 <16.4 <8.13 <7.71 IRSWO.7NO - 0/27/2004 <157' 1 <7.20 <7.70 <16.9 <8.43 <7.47 RSW1.8NOQ ', 1U/2712004 <154' <7.95 <7.42 '15.8 <8.00 <7.94 RSW1.8NO  :'10/27/2004 <158 <4.36: <4.70 <9.53 <5.25 '<3.69 RSW1.3F0 10/27/2004 <1 60 ' <4.82 <5.11 <11.6 <5.32 <4.66 IRSW3.7NO 10/27/2004 <157 <9.02' <10.2 1<21.9 <11.5 <9.29 RSW0.3MO, 10/27/2004 <1 58 <8.80 <8.00 <1 7.4 ' <9.50 <7.68 RSW3.7N  : 11/24i2004 <241 <9.71' <10C.0 <21.4 <10.8 <9.25 RSW1.3FQ -I '11/2412004 <242 <8.82 '1<9.01 <17.6 <10.2 <8.30 RSW1.8NO -11/24/2004 <243 <90.G0 - <8.00 <22.6 <11.3 <9.35 RSWO.7NO 11/ 2 4/ 2 004 <239 <6.24 <6.50 <14.8 <7.69 <6.66 RSWO.3MO '11/24/2004 <243 <3:9 <4.21 <34.3 <4.72 <3.69 RSW0.7NQ 12/20/2004 <255' <10.3 <9.58 <22.6 <11.2 - <9.50 RSWO.3MO 12/20/2004 <253:i <9.06 <8.69 <19.8 <10.4 <8.01 RSW3.7NO 12/20/2004 <250 <7.31 <8.12 <17.6 <8.31 <7.22 RSW1.3FO 12/20/2004 <254 <7.92 <7.73 <18.2 <9.10 <7.41 RSW1.8NO 12/20/2004 <250 <9.04 <8.88 <21.3 <10.5 <8.61 Rancho Seco Nuclear Station F-9 2004 AREOR

TABLE F-9 2004 Drinking Water Monthly (pCi/L)

RDWO.2PP 1/27/2004 3.84 <160 <6.6b <7.9 <16 <8.5 <7.5 RDWI.8FP 1/27/2004 4.02 <160 <14 <14 <35 <18 <15 RDW0.1GO 1/28/2004 4.34 <160 <12 <13 <28 <16 <13 RDWO.2PP 2/24/2004 3.64 <160 <9.7 <9.5 <20 <12 <10 RDWI.8FP 2/24/2004 4.37 <160 <4.8 - <4.3 <8.7 <3.3 <5.3 RDW0.1GO 2/26/2004 4.19 <160 <4.7 <5.4 <11 <5.7 <4.5 RDWO.1GO 3/30/2004 <1.9 <160 <4.8 <4.9 '10-- <6.0 <4.2 RDWO.2PP 3/30/2004 3,19 <160 <11 <11 <20 <13 <10 RDW1.8FP 3/30/2004 3.60 <160 <6.6. <6.9 * <14

- <8.3 <6.3 RVWI;.8FP 4/28/2004 2.78 <170 <6,7 <8.1 <16- <8.4' <7.0 RDW0.1GO 4/28/2004 4.89 <170 <9.1 <11 <21 - <12 <9.5 RDWO.2PP 4/28/2004 3.50 <170 <9.9 <9.4 <20. <11 <8.9 RDWO. 1GO 5/26/2004 3.40 . <160 <4.4 <4.4 <9.2 <5.3 <4.4 RDWO.2PP 5/26/2004 <3.2 <160"- <7.4 <7.3 <16 <8.2' <7.4 RDW1.8FP 5/26/2004 3.18 <160 <8.7 <9.6 <22 ' <12 <8.9 RDWO.2PP 6/29/2004 3.52 . <200 <4.2 <4.1 <8.6 <5.2 <4.2 DWO. 1GO _6/29/2004 3.48. .<210 <7.2 <7.7.. <15 ^ <8.7_ <'.6 RDW1.8FP 6/29/2004 4.79 <200 <7.2 <7.3 <16 <8.7 <6.6 RDW1.8FP 7/27/2004 3.64 <168 <9.58 <9.77 <17.6 <10.'6 1<8.75 RDW0.1GO 7/?8/2004 3.98 <161 <3.99 <5.1-. 58.66 <5.60 <4.16 RDWO.2PP 7/28/2004 2.58, <167 <7.46 <7.17 <15.7 <8.17 <7.94 RDW1.8FP 8/30/2004 2.93 <193 - <7.13 <8.32 <16.0. <9.30 <6.71 RDWO.2PP 8/30/2004 3.29 <188 <7.27 <7.89 <16.6 <8.00 <7.92 RDW0.1GO 8/30/2004 , 4.25, , <190 <7.58 <7.47 <17.3 <8.76 <7.53 RDW1.8FP 9/28/2004 3.31, <204 <3.69 <4.20 <8.43 <4.62 <3.48 RDW0.1GO 9/30/2004 5.11 <204 <7.67. <8.70 <18.0 <9.86 <7.42 RDWO.2PP 9t30/2z4 -2.59. .<204. <6.11 <6 t48. <122 <7.03 <6.35 RDWO.2PP 10/27/2004 3.90 <157 1<4.45 <4.58 <9.70 <5.13 <4.46 RDN0.1GO 10/27/2004 . 3.70- <158. <7.64 <8.64 <18.8 <9.25- <7.46 RDW1.8FP 10/27/2004 <1.78 <158. <7.10 <7.03 <16.3 <7.86 <7.09 RDWO.2PP 11/24/2004 3.46 <238 <7.81 <7.80 <16.5 <8.51 -<7.48 RDWO.IGO 11/24/2004 3.29 <241 <8.08 <7.43 <16.8; <8.34 <7.55.

RDWIVI.8FP 11/24/20041 3.22 <243 <7.71'. <7.12 <16.4 <8.50, <7.41 RDWO.2PP 12/2C/2004 3.95 <251 <6.84 <7,65 <16.0 <8.42 <6.85 lRDW0.1GO 12120/2004- 4.17 <248 <9.53 <9.90 <20.5 *15.2 1<8.19 LRDW1t.8FP 12/20/20041 2.35 <248 <7.53 1<7.95 <21.7 <10.6 <9.16 Rancho Seco Nuclear Station F-1 0 2004 AREOR

APPENDIX G 2004 MISSED SAMPLE REPORT In accordance with the requirements REMP manual section 3.1, the following samples are being reported as not being c6llectedfor tha, reasons indicated Uuring 2004. Corrective action as required by the REMP manuali as indicated. '

Air Sampler (Airborne Pathway)

RASO.7EO, Rancho Seco Meteorolcgical Tower (control)! - On March 3, 2004, the air sampler was not running for approximately 709,minutes due to a storm related power outage.

Air sampler volume did meet the minimum required.

RAS0.3MO, Plant Effluent (indicator) - On March 9, 2004 the air sampler was not running for approximately.33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br />, due to a plan~ned electrical outage. 'Air sampler volume did meet the minimum required. -

RAS0.3MO, Plant Effluent (indicator) - On March 2?, 2004 the air saMnpler was not running for approximately'J15 hours, due to a planned electrical outage. Air sampler volume did meet the minimuiim requimed., -'

RASO.ACO, PAP/ Security Bldg. (indicator)-ibn May 18, 2004 theair samplerwanot running for approximately 432 minutes due to a Site power failUre'. Sample volueme metthe required amount.-, -:

RASOi7EO, Rancho SecoMellteorological Tower (control)!- On:Gctober 19, 2004 the air sampler' was fou'nid runbing but the elapsedtifmer was not functioning. It was determined that the timer probie'rm was caused'by a.iow voltag e'condition at the sampler location. Air Sampler was replaced, but the same condition existed 'with th6ereplacement sampler. Work Order was initiated to investigate the voltage problem.'Air sampler volume did meet the minimum required using the Start and Stop tirmes to calculate the volume..

... . i., . -,

RASO.7EO, Rancho Secd'Meteor'ological'Tower (control)l- On October 26, 2004 the air sampler was found running -With the flow at' 2.1 cfm, but the elapsed timer was not functioning, presumed to be caused by the voltage problem identified the previous week.' Air sampler volume will be calculated using Start and Stop times.'

RASO.7EO, Rancho Seco Meteorological -Tower (control)/ - On November 23, 2004 the air sampler was found not running due to an electrical power problem. 'Total time lost from the sampling period was 2.79 days. The air sampler was restarted and ran normally.. Sample volume Was'greater than the required minimum.' Sample'results received from the analysis lab indicated a Gross Beta'result of 0.202 pCi/kgb A gamma scan was requested for this air filter.

Results from the gamma scan indicated no' detectable activity.

Rancho Seco Nuclear Station G-1 2004 AREOR

it SI.

APPENDIX G 2004 MISSED SAMPLE REPORT (continued)

Air Sampler (Airborne Pathway)

RASO.1CO, PAP/ Security Bldg. (indicator) -The second quarter composite sample gamma scan detected Cs-1 37 activity. A recount of the sample was requested from the analysis vendor (Eberlinre). The recount also showed detectable Cs-1 37 activity. The data sheets for the two counts were requested and a review of the data found that the analysis error for the two counts was 59% and 75% (1st and 2nd counts respectively). Based on the error of the analysis, the results will not be used.

Direct Monitoring Pathway (Luxel Badge))

RTL1.5MO, Clay/ Kirkwood Streets (indicator) - During the fourth quarter change-out of the monitoring badge at this location the badges were found missing. The area was searched and no badges were found. The badges were replaced at a more inconspicuous location. No data was reported for this location for the fourth quarter 2004.

Rancho Seco Nuclear Station G-2 .2004 AREOR