View source for SNRC-2185, Summarizes Results from Revised Exposure Pathway Analysis Using Corrected Dcf for External Exposure for Cs-137.Rev 1 to Analysis of Bulk Matl Reconcentration Potential & Possible Exposure Pathways Encl

{{Adams
| number = ML20073J279
| issue date = 10/04/1994
| title = Summarizes Results from Revised Exposure Pathway Analysis Using Corrected Dcf for External Exposure for Cs-137.Rev 1 to Analysis of Bulk Matl Reconcentration Potential & Possible Exposure Pathways Encl
| author name = Bortz A
| author affiliation = LONG ISLAND POWER AUTHORITY
| addressee name = 
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000322
| license number = 
| contact person = 
| document report number = LSNRC-2185, NUDOCS 9410060286
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 25
}}

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                                    -Long                             Shoreham Nuclear Power Station                                              I 1 .
                          .           Idand          "
P.O. Box 628                                                                ,
"Y                                  ' Power                           North Country Road                                                          l Authority                       Wading River, N.Y.11792 OCT        41994                                                                                              )
LSNRC-2185                   )
i U.S. Nuclear Regulatory Commission                                                                                            j Document Control Desk Washington, DC 20555                                                                                                         }
Shoreham Decommissioning Project                                                     {
Application of Soil Release Criteria to Other Bulk Material;                                           i Analysis of Reconcentration Potential and                                               :
Possible Exposure Pathways                                                       l Shoreham Nuclear Power Station . Unit 1                                                l Docket No. 50-322                                                       :
Ref:          (1)_      Long Island Power Authority _ letter LSNRC-2179, dated September 1,                                   I
_1994; subject: Same as Above                                                                          ;
(2)-      Telecon between C.L. Pittiglio and D. Fauver of USNRC and F.                                          .
Petschauer, M.S. Kumar, M. Tucker and S. Moss of LIPA on September                                    :
23,1994,                                                                                              i (3)       Telecon between D.'Fauver of USNRC and M.S. Kumar and S. Moss of                                      :
LIPA on September 27,1994 responding to questions and comments                                        i raised in Ref. 2.
7 i
Ladies and Gentlemen:                                                                                                         !
(
i The Long Island Power Authority (LIPA) performed an exposure pathway analysis to                                             1 evaluate thc-impact of radionuclides present in bulk materien at Shoreham. The                                                !
evaluation took into account the effect of potential reconcentration through mcycling
                 .or incineration. The results of the exposure pathway analysis were forwarded to the
               ' NRC via Reference 1.                                                                                                            l u'
D;7 i ng a telephone conversation on September 23,1994 (Reference 2), the NRC Staff sed y LIP                 i     Cs      7     d i e D F in           RC Dr t  UREG-150 o k g Dra t t
Regulatory Guide on Release Criteria for Decommissioning: NRC Staff's Draft for j
               ~ Comment".
kl QOO6o286.941co4                                                                   I        I w        ADOCK 0500o322' PDR                                                                  l

    =.
* LSNRC-2185                                                                                                      l
   ..  ($      , Page 2 of 2            .
The DCF's used in the LIPA analysis (Enclosure 1 of Reference 1) were taken directly from NUREG/CR-5512 (Final Report Vol.1). Upon additional review, however, it was noted that the DCF for external exposure by Cs-137 did not include the contribution
>                from the implicit daughter product (Ba-137m). For all other modes of exposure (Ingestion, Inhalation, Organ Specific, etc.), the DCF's in NUREG/CR-5512 include the contribution from the implicit daughter products within the DCF for the parent nuclide.
This'was discussed between LlPA arid NRC (Reference 3).
The exposure pathway analysis was revised using the corrected DCF for external exposure for Cs-137. LIPA also computed the Total Effective Dose Equivalent (TEDE) based on the average concentration of radionuclides in the specific bulk materials found at Shoreham in addition to revising the analysis based on the peak concentration. Enclosure 1 contains revised exposure pathway analysis. The revised and additional pages are marked " Revision 1", and change bars indicate the changes and additions.
The results from the revised exposure pathway analysis are summarized below:
Calculated (based on peak concentration) Calculated (based on average concentration)
Bulk Meterint            Total Effective Dose Eauivalent (TEDE)   Totat Effective Dose Eauivalent (TEDE)
Studge                             0.332 mrem /yr                           0.332 mrem /yr Concrete                            1.12 mrem /yr                           0.547 mrem /yr Charcoal                           4.63 mrem /yr                            1.36 mrem /yr Silt                               7.85 mrem /yr                            2.60 mrem /yr The details are presented in Table 1 of Enclosure 1. A tabulation of the weight, density, and volume of each bulk materialis included as Table 2 of Enclosure 1.
Please do not hesitate to contact me if you have any questions or require any additionalinformation in this matter.
Very u         yours,
                                                             ~
A. J.         z Resident Manager

==Enclosure:==
(1)     Analysis of Bulk Material Reconcentration Potential and Possible Exposure Pathways, Revision 1 cc:      D. Fauver C. L. Pittiglio T. T. Martin L-R. Nimitz

  .  *o     .      .
LSNRC -2185 ENCLOSURE 1 Analysis of Bulk Material Reconcentration Potential and Possible Exposure Pathways Revision 1 9
l 1

               ~'
Anclysis of Bulk Material Reconcentration Potential and Possible Exposure Pathways An analysis of the reconcentration potential and possible exposure pathways was performed for the bulk materials (other than soil) at the Shoreham site. The specific bulk materials were: (1) contaminated concrete rubble generated by removal of certain internal walls of the Radwaste Building; (2) contaminated charcoal which l
was utilized as part of the gaseous radwaste treatment system; (3) contaminated sewage sludge; and (4) contaminated sitt and/or biological material in the facility radwaste discharge tunnel. The suitability of allowing for the unrestricted release of l                 a site containing these materials is cddressed individually by conservative dose pathway analyses which are based on the peak activity concentration findings l                 reported in the applicable Termination Survey Unit Release Record. The survey unit i                 release records which report results for the above materials include:
SUO20, Sanitary Sewage (sewage sludge)
RWO59, Condensate Domineralizer Filters Corridor (concrete rubble)
RWO60, "A - H" Condensate Demineralizer Room (concrete rubble)
SUO44, Radwaste Offgas (contaminated charcoal)
SUO45, Circulating Water (silt and biological material)
The results of dose pathway analyses are provided in Attachments 1 through 4 and summarized in Table 1. The summary table also includes a comparison L the Draft NRC Criteria for Decommissioning, namely 15 mrem /yr. The pathway analyses presanted are all based on the residential use scenario developed for NUREG/CR-5512.
These analyses are highly conservative and include assumptions which envelope the effect of potential reconcentration of radionuclides within the materials. The major component exposure pathways analyzed for each material include direct external exposure to the volumetric source, inhalation of airborne material, and ingestion of contaminated foods. As shown in Table 1, the peak exposures from each of the additional materials are all less than the NRC Draft Guidance value of 15 mrem /yr, ranging from 0.332 mrem per year for sludge to 7.85 mrem per year due to silt in the j discharge tunnel.
The conservative nature of these exposure estimates, which use the generic l residential use scenario of NUREG/CR-5512, can be readily seen by comparison to dose assessments performed in a manner similar to the NRC-generated " Generic Dose Assessment For Disposal of incinerator Ash in a Landfill", dated January,1994. As listed in Table 1, the maximum public dose impact as determined by a RESRAD analysis for the combined four additional bulk materials are 0.68 mrem per year vs.
13.9 mrem /yr. (using peak concentration) and 4.8 mrem /yr. (using e ferage concentration) based on the NUREG/CR-5512 scenario.
Revision 1 Page 1 of 4

1 Analysis of Bulk Materials Reconcentration Potential and Possible Exposure Pathways c   .                          .
Each of the attachments (1 through 4) also provide an estimate of the reconcentration effects necessary to raise projected pathway peak doses to a value equivalent to the NRC Draft Guidance value of 15 mrem /yr. These reconcentration factors range from 1,91 to 45.2. Evaluation of the impact of reconcentration of these small amounts of radioactive material in the specific bulk materials listed above is based primarily upon a review of two NRC documents. The first is NUREG/CR-5814,
                                                 " Evaluation of Exposure Pathways to Man from Disposal of Radioactive Materials into Sanitary Sewer Systems", and the second document is the NRC-generated " Generic Dose Assessment For Disposal of incinerator Ash in a Landfill", dated January,1994.
The first reference states that a volume reduction of sewage sludge as a result of incineration is 95% or providing a reconcentration ratio of 20:1. The second                                                                             ,
reference assumes that for one generator, the dilution of incinerator ash by mixing with soil would provide a dilution ratio of 1:50. Thus, a disposal scenario for the bulk l
materials of concern which involves incineration and disposal of the ash by mixing with soil, as might be hypothesized for disposal of the sewage sludge, silt, or charcoal, would result in a net dilution ratio of 1:2.5, or a dilution facter of 0.4. By comparing this factor to the reconcentration factors for Shoreham specific materials, it is apparent that disposal of the bulk materials represents a minimal dose effect.                                                                    r Direct recycling of these materials (e.g., use of the sludge as fertilizer, use of the silt as fill or surface overlay, or reuse of the charcoali various products) without incineration would likely result in the dispersion of the radicouclides, or at least no reconcentration, as there are no other volume reduction processes which would typically be applied to the sludge, silt or charcoal. The concrete rubble must be regarded as at-least the equal of soil in terms of the lack of potential for reconcentration of contaminating radionuclides. Concrete rubble is rarely processed for volume reduction. It is much more credible to assume that the rubble would be used as fill material, where it would retain its essential volume and content except for minor surface wea during handling and placement. Thus in all probable disposal scenarios of these various materials, the dose estimate would be equal to or less than the doses provided in Table 1.
                                                                                            'As a further analysis, Section 8.1 of the generic dose assessment for the disposal of incinerator ash states that only certain radionuclides which are potentially in incinerator ash may represent significant radiological risks to the public and may approach the public dose limits of 10 CFR 20.301, based on the assumptions made in that generic assessment.                                                              The radionuclides found in the bulk materials at Shoreham, which are predominantly Co-60, but also include Cs-137, Zn-65, and Mn-54, are not among the suspect nuclides of the generic assessment. These suspect nuclides include C-14, Cl-36, TI-20A, Ag-208m, Al-26, Tc-99, Nb-94, H-3,1:129, P-32, S-35, Tc-99m, Fe-59, and Ca-45 depending upon disposal and exposure characteristics. The generic assessment recommends that for other than these suspect nuclides, disposal be based on meeting the concentrations given in 10 CFR Part 20, Appendix B, Table ll, Column 2 by converting Ci/mi to Ci/gm and assuming 1 ml of water is equivalent to 1 gm of ash. In applyinn the Appendix B values for Revision 1 Page 2 of 4
_ _ _ _ _ _ _ _ _ _ - _ _ _ . _ _ _ _                                                                      l

I l
l I' (.
        '*                                                                                              f
            ,   , ' An91ysis of Buh Materials Reconcentration Potential and Possible Exposure Pathways multiple nuclides, the sum of the fractions approach is suggested, with the sum to be lens than 100% Table 1 provides the results of such an analysis for each of the four bulk materials. The summation of the MPC fractions from all of the four materials gives 24.86% assuming peak concentration values, and 7.81 % using average material          :
concentration values. Similarly, the benchmark values of 8 pCi/gm of Co-60 in soil
,          represents an MPC fraction of 26.67% Therefore even by this method of analysis, the bulk materials are shown to be less than the benchmark and less than typically          1 accepted limits for disposal.
9 t
Page 3 of 4 i

REFERENCES
                   .                           (For Attachments 1 through 4)
: 1)   LIPA Memor.u.dum NLR 94-0146 dated July 13,1994; NRC Exit Meeting Record
: 2)    USNRC {{letter dated|date=July 18, 1994|text=letter dated July 18,1994}}; subject: Review of the Shoreham Decommissioning Project Termination Survey Plan, Revision,2, Section 3.1
: 3)    Shoreham Decommissioning Project Termination Survey Release Record Report for Survey Unit SUO20 - Sanitary Sewage; Termination Survey Final Report, Phase I                              ;
i
: 4)    Shoreham Decommissioning Project Termination Survey Release Record Report for Survey Unit      l SUO59 "A - H" Condensate Demineralizers Room; Termination Survey Final Report, Phase Ill
: 5)   Shoreham Decommissioning Project Termination Survey Release Record Report for Survey Unit SUO60 - Condensate Demineralizer Filters Corridor; Termination Survey Final Report, Phase til
: 6)   Shoreham Decommissioning Project Termination Survey Release Record Report for Survey Unit SUO44 - R=dwaste Off-Gas Synem: Termination Survey Final Report, Phase Ill
: 7)   Shoreham Decommissioning Project Termination Survey Release Record Report for Survey Unit SUO45 - Circulating Water System; Termination Survey Final Report, Phase IV
: 8)   NUREG/CR-5512, " Residual Radioactive Contamination From Decommissioning"; Pacific Northwest Laboratory - Final Report, October 1992 - Volume 1
: 9)   NUREG/CR-5512, " Residual Radioactive Contamination From Decommissioning"; Pacific Northwest Laboratory Draft Report, January 1990
: 10)  LILCO Calculation NO. CCI-039221, " Pathway and TEDE Doses for Shoreham Post-Decommissioning Dose Pathway Analysis", Rev. 0 - 3/6/92
: 11)  Shoreham Nuclear Power Station Post-Decommissioning Dose Pathway Analysis Report Draft Report, November 1991 USNRC Report " Generic Dose Assessment For Disposal of incinerator Ash in A Landfill", Draft 12)
Report, January 1994
: 13)  NUREG/CR-5814, " Evaluation of Exposure Pathways to Man From Disposal of Radioactive Materials into Sanitary Sewer Systems", Pacific Northwest Laboratory, May 1992 T
: 14)  Title 10 Code of Federal Regulations Part 20, Appendix B - Concentrations in Air and Water Above Natural Background, Table 11, Column 2
: 15)  LIPA Shoreham Decommissioning Project Termination Survey Plan, Revision 2
: 16)  LIPA Shoreham Ncclear Power Station Offsite Dose Calculation Manual, LIPA Rev. 2
: 17)  USNRC, " Radiological Criteria for Decommissioning of NRC-Licensed Facilities; Enhanced Participatory Rulemaking, Availability of the Staff's Draft of the Rule:, Federal Register, February 2, 1994, 4688 - 4869.
: 18)  USNRC, Draft Proposed Rule on Radiological Criteria for Decommissioning, SECY-94-150, May 31,1994 L
Page 4 of 4

TABLE 1 - BULK MATERIALS DOSE PATHWAY ANALYSIS RESULTS T.S.U. No.                    SUO20          RWO59/060           SUO44            SUO45 Bulk Material                   Sludge           Concrete       Charcoal                Silt Radionuclide                    Co-60               Co-60         Cs-137            Co-60 Concentration                  pCl/gm               pCi/gm         pCilgm           pCi/gm     ;
Peak                   6.52E-02            2.19E-01       3.85E+00         1.54 E+00
                         ' Average                 6.52E-02            1.07E-01       1.13E+00         5.10E-01    l ,
Activity                       uCi                  uCl           uCi              uCi    ,
Total                  6.17E-01            2.62E-01       2.79E+01         6.95E+01 Direct Exposure -             mrem /yr            mrem /yr       mrem /yr         mRemlyr       I Peak                   3.32E-01            1.12E+00       4.63E+00         7.85E+00 Average -             - 3.32E-01            5.47E-01       1.36E+00       ' 2.60E+00 inhalation Exposure               mrem /yr            mrem /yr       mrem /yr         mrem /yr Peak                   6.27E-06            2.11 E-05      5.41 E-05        1.48E-04      .
Average                y.27E-06             1.03E-05       1.59E-05         4.90E-05    l '
ingestion Exposure               mRemlyr             mrem /yr       mrem /yr         mrem /yr Peak                   3.25E-06            1.09E-05       2.13E-04         7.68 E-05
                        ' Average 3.25E-06            5.33E-06       6.25E-05         2.54E-05    l TEDE                    mrem /yr            mrem /yr       mRemlyr          mRemlyr Peak                   3.32E-01            1.12E+00       4.63E+00         7.85E+00      !
                        ! Average                - 3.32E-01            5.47E-01       1.36E+ 00        2.60E+00 TEDE-% of 15 mrem /yr Peak                       2.21 %                7.47 %      30.87 %           52.33 %   ,
Average                    12.21 %              - 3.65%         9.060'.         17.33 %
Percentage of MPC Peak                        0.22 %               0.73 %       19.25 %           4.66 %
Average                     0.22 %                0.36 %        5.65 %           1.58 %     ,
i 1.39E+01        i Sum of TEDEs (in mRemlyr) for peak bulk materials =
Sum of TEDEs (in mrem /yr) for average bulk materials =                                 4.84E+00 l
Sum of MPC fractions for bulk materials using peak concentration =                          24.86 %     1 Sum 'of MPC fractions for bulk materials using avg. concentration =                          7.81 %
Comparison with Generic Dose Assessment for Incinerator Ash                                             l RESRAD (Public)-                    3.75E-03            1.26E-02       5.74 E-01        8.86E-02 mrem /yr            mrem /yr       mrem /yr         mrem /yr IMPACTS (Max Ind)                   4.27E-02            1.44E-01       2.20E-01         1.01 E+00 mRemlyr             mrem /yr       mrem /yr         mrem /yr l Combined sum of RESRAD doses (in rnRemlyr) for materials                                6.79E-01 l      '
l Revision 1

e TABLE 2 - BULK MATERIALS PHYSICAL PARAMETERS - SNPS T.S.U. No.                   SUO20        RWO59/060                  SUO44               SUO45 BULK MATERIAL                   Sludge          Concrete              Charcoal                  Silt WEIGHT (gms)                   9.46E+06           2.44 E+06            2.47E+07            4.51 E+07 DENSITY (gm/cm'3)                       1.00              2.35                 0.57                 1.60 VOLUME (m'3)                        9.46                1.04               43.32               28.19 Density of charcoal determined from nominal weight of charcoal filling Waste Decay Tanks divided by internal volume of tanks. CRC Hdbk shows charcoal density (typical) @ 13.2 - 19.2 lbrdcu ft (0.21 - 0.30 gm/cm'3).
i Revision 1

ATTACHMENT 1                                       Page 1 of 4 Th'rmination Survey Un'it - SUO20: SANITARY SEWAGE - [ SLUDGE]
LOCATION             LOCATION            Co-60         Lc (LLD)*     >Lc          Lr +      >Lr         MASS      Co-60 NUMBER            DESCRIPTION          [pCi/gm]       [pCilgm]                 [pCi/gm]                [gms)      [uCi]
1             Ejec. Pump          < LLD        1.86E-02                         6 2            Sump Pump            < LLD        1.11 E-02                        6 3              Septic Tank         < LLD        1.64E-02                         6 4              Septic Tank         6.52E-02     4.12E-03         X               6              9.46E+06 6.17E-01 5             Leach Pool          < LLD        1.17E-02                         6 6             Leach Pool          < LLD        1.77E-02                         6 7             Leach Pool          <LLD         1.32E-02                         6 8             Leach Pool          < LLD        9.96E-03                         6 9             Leach Pool          < LLD        1.59E-02                         6 10             Septic Tank      Inaccessible        N/A                     N/A 11             Septic Tank         < LLD        1.37E-02                         6 12             Septic Tank         < LLD        1 59E-02                         6 13             Leach Pool          < LLD        1.86E-02                         6 14             Leach Pool       inaccessible        N/A                     N/A 9            QC Replicate         < LLD        1.32E-02                         6 P=k Activity Concentration Co-60            6.52E-02                                                     9.46E+06 6.17E-01 pCUgm                                                           gms         uCi
* Lc represents decay corrected LLD for identified isotope (s).
+ Lr represents 75% of the release limit (8 pCi/gm) for total activity in soil, sediment, and special samples.
Co-60 : Regulatory Limits / Commitments I
Co-60 Activity Concentration Values SOURCE        I        LIMIT                        REFERENCE                                                                ,
l 10CFR20 MPC           3E-05 uCi/ml     10 CFR Part 20, App.B. Table il Col.2                                                    l TERM SURVEY           BE-06 uOilgm      TSP Sec.5.2.3 (an NRC Criterion)
ODCM LLD            SE-07 uCi/ml     ODCM Table 4.11.1.1.1-1 REMP LLD           1.5E-08 uCl/ml    ODCM Table 4.12.1-1 VS.
SEWAGE        l 6.52E-08 uCilgm lSUO20 Term Survey Release Record Rpt.
MPC Fraction                   0.22% Peak & Avg.
For determining the suitability of using the soil free-release kmit of 8 pCilgm to other bulk material, the peak cctivity (6.52E-02 pCilgm) will be used. LILCO Calculation No. CCl-039221, " Pathway and TEDE Doses for Shoreham Post Decommissioning Dose Pathway Analysis" shows that of tne four scenarios, Building Renovation, Building Occupancy, Drinking VJ'ter and Residential Use; Residential Use results in the highest TEDE.
Furthermore, of the major component pathways for the residential use scenario, External Exposure is the most significant followed by ingestion and inhalation in that order, with groundwater not even being a credible pathway in the case of Shoreham. Average concentration doses will be scaled directly from calculated peak values.              l l Revision 1

             .                                               ATTACHMENT 1                                    Page 2 of 4
  +
Resideritial'Use Scenario L
Tha major component exposure pathways to be considered for this scenario include:
A) Direct External Exposure to Soil Volume Sources; B) inhalation of Airborne Materials;                                                                         ,
C) Ingestion of Contaminated Food.
Groundwater related exposure pathways are not credible at the Shoreham site for two reasons;
: 1) . This pathway is predicated on the presence of buried contaminated rubble left in place after decommissioning with the contamination allowed to teach into the groundwater where it would be picked up and transported to sources of domestic water supply. There is no buried contaminated rubble currently at the Shoreham site nor does the LIPA Decommissioning Plan allow for any                                ,
as part of the decommissioning process.
: 2) Groundwater drainage at the site is north to the Long Island Sound, the three onsite wells which are used for drinking water are located south of the actual                           ;
plant site and hence, no public or site drinking water supplies could be affected by any site activity.
i A) Direct External Exposure to Soil Volume Sources The fundamental relationship for calculating radiation dose rates to people from any radionuclide in an exposure pathway is given by:
R (1,p) = C (i p) X U (p) X D (i p)                                                          [Ref. 9]
Where R (i.p) =            The radiation dose (. p 'ent or committed radiation dose equivalent.                                     l from radionuclide i via exposure pathway p, in mremlyr; C (1,p) =            The concentration of radionuclide iin the media of exposure in pathway p, in pCilgm (Bg/gm) for volume contamination in buildings and soil;                                                                                                t
                        = 6.52E-02 pCi/gm                                                                                [Ref. 3]
U (p) =              The usage parameter (exposure rate) associated with exposure pathway p, in hrlyr for external exposure. For residential scenario, the equivalent number of direct (unshielded) exposure = 1800 hrs outdoors (actually                                     l 1700 hrs outdoors + 100 hrs gardening) + 4380 hrs indoors X 0.33 (Home Shielding Factor);                                                                            [Ref. 8,9]
                        = 3245 hrs D (i.p) =            The committed effective dose equivalent factor for radionuclide i and exposure pathway p, used to convert the concentration and usage parameters to the committed effective dose equivalent in mrem /hr per pCi/gm.
                        = 1.57E-03 mrem /hr per pCilgm for Co-60                                                         [Ref. 8]
Thtrefore, R (i,p) =             6.52E-02 pCl/gm X 3245 hrs X 1.57E-03 mrem /hr per pCi/gm
                                               =l 3.32E mrem /yr l Thiconcentration value used above is based on assumptions so conservative as to overwhelm any consideratior, of re-concentration within the bulk materialitself. This primarily refers to the assumption of essentially infinite extent at the maximum possible concentration.

            .                                                                     ATTACHMENT 1                                        Page 3 of 4 B)Inhalatio'n of Airborne Materials T'u general equation for estimating the committed effective dose rate equivalent by inhalation r:c*ived by individuals for radionuclide i is given by:
H (inh,i) = V X t X C (d) X C (w,i) X DF(inh,i)                                                                            [Ref. 9]
Where H (inh,1) =         The committed effective dose equivalent from a 1 year intake of radionuclide i                                                             ,
by inhalation, in mrem /yr;                                                                                                                !
V=                  The ventilation rate of the individual,in m"3/hr;
                    = 1.0                                                                                                                         [Ref. 8,9]
t=                  The duration of exposure for the individual, in br/yr;
                    = 4380 hrs Indoors + 1700 hrs Outdoors
* 100 hrs Gardening                                                                    [Ref. 8,9]
C(d)=               The concentration of respirable dust in air, in gm/m'3;
                    = Indoors = SE-05, Outdoors = 1E-04, Gardening = SE-04                                                                        [Ref. 8,9]
C (w,i) =           The concentration of radionuclide i in the contaminated material, in pCi/gm;
                    = 6.52E-02 pCi/gm                                                                                                             [Ref. 3]
DF (inh,I) =         The committed effective dose from inhalation of radionuclide I, in mrem /pCl.
                    = 2.19E-04 mrem /pCi for Co-60                                                                                                [Ref. 8]
Therefore, H (inh,1) =                             1 m'3/hr X (4380'5E-05+1700*1E-04+100*5E-04) hr-gm/yr-m'3 X 6.52E-02 pCi/gm X 2.19E-04 mrem / poi
                                           =l                              6.27E-06 mrem /yr l Th3 concentration value used above is based on assumptions so conservative as to overwhelm any consideration of re-concentration within the bulk materialitself. This primarily refers to the assumption of essentially infinite extent at the maximum possible concentration.
RESRAD incinerator Ash Dose (to the public)
Dose                = DSR(1,tmax)[ mrem /yr per pCi/gm] X Peak Concentration [pCilgm]                                                         [Ref.12]
                   = 5.75E-02 X 6.52E-02
                   =l             3.75E-03 mrem /yr                                l lMPACTS incinerator Ash Dose (to the max. individual)                                                                                         [Ref.12]
Dose               . = DSR(1,trans)[ mrem /yr per pCilgm] X Peak Concentration [pCi/gm]
                   = 6.554E-01 X 6.52E-02
                   =l            4.27E-02 mrem /yr                                 l e

  .g        y                                                ATTACHMENT 1                                     Page 4 of 4
   ,C)Inoeskion of Contaminated Food This pathway is based upon the assumption that a certain fraction of food consumed by site residents is grown in the soil _ onsite which contains residual activity concentrations. Assuming the same dietary commitments as NUREGICR-5512 (25% of total diet as defined in R.G.1.109) allows one to take the valu::s for specific nuclides directly from NUREGICR-5512, which are based on 1 pCl/gm concentrations nd multiply by the value to be used for soil volume concentrations.
P Th3 simplified form of the equation is given by:
.                         H (ing,1) = FD (ing,I) X C (i.p)                                                                [Ref. 9]
Where H (ing,i) =          The committed effective dose equivalent from a 1 year intake of radionuclide i by ingestion, in mrem /yr; FD (ing,1) =         The food ingestion effective dose equivalent factor for the most sensitive organ for radionuclide i, in mrem /pCl, assuming 1 pCilgm and the dietary input listed below:                   -
                                           ' a) 47.5 Kg/yr of vegetable produce, b) 27.5 IJyr of milk, c) 19.2 Kglyr of meat (beef, pork, poultry) d) 4.8 Kglyr of eggs.                                                        [Ref. 9]
I
                     = 4.99E-05 mrem /pCi for Co-60 for LLI wall. (@ 1 pCilgm soil activity)                              [Ref. 8]
C (1,p) =            The soll volume activity, for radionuclide i, in pCi/gm .
                   . = 6.52E-02 pCi/gm for Co-60                                                                          [Ref. 3]
Therefore, H (ing,i) =            4.99E-05 mrom/pCi per pCi/gm X 6.52E-02 pCi/gm
                                             =l      3.25E-06 mremlyr l                                                            >
The concentration value used above is based on assumptions so conservative as to overwhelm any consideration of re-concentration within the bulk materialitself. This primarily refers to the assumption of essentially infinite extent at the maximum possible concentration.
i R3sidential Use Scenario - Total Effective Dose Equivalent Direct Exposure + Inhalation Exposure + Fcod Ingestion Exposure 3.32E-01 mrem /yr + 6.27E-06 mrem /yr + 3.25E-06 mrem /yr
                      -l               TEDE =        3.32E-01 rnrem/yr l Reconcentration Factor required to raise projected pathway dose to Draft NRC Criteria Value =
l                RF=         4.52E+01 l

ATTACHMENT 2                                                          Page 1 of 4 Tcrmination Survey Unit - RWO59: "A-H" COND. DEMIN. RM. - [ CONCRETE]
Tcrmination Survey Unit - RWO60: COND. DEMIN. FLTRS COR. - [ CONCRETE]
SURVEY                   DRUM I.D.                      Co-60                CONCRETE                      Co-60 POINT                    NUMBER                       [pCilgm]                  [gm] *                     [uCi]
247/248                 93-DRM-142                 < 1. oE-02 251/252                 93-DRM-148                 < 1.36E-02 253/254                 93-DRM-150                 < 142E-02 255/256                 93-DRM-153                 < 1.30E-02 257/258                 93-DR M-154                < 1.13E-02 259/260                 93-DRM-162                 < 8.79E-03 261/262                 93-DRM-170                 < 1.19E-02 263/264                 93-DRM-171                 < 1.28E-02 265/266                 93-DRM-172                 < 1.15E-02 269/270                 93-DRM-174                 < 9.61 E-03 273/274                 93-DRM-139                       3.53 E-02              4.88E+05                 1.72E-02 347/348                 94-DRM-191                 < 1.45E-02                                                                    ]
353/354                 94-DRM-249                 < 1.03E-02 3S5/356                 94-DRM-235                       8.18E-02               4.88E+05                 4.00E-02 357/358                 94-DRM-234                       2.19E-01               4.88E+05                 1.07E-01 387/388                 94-DRM-248                 < 1.38E-02 391/392                      "A"                         1.07E-01               4.88E+05                 5.23E-02 393/394                 94-DRM-241                 < 1.39E-02 397/398                      "B"                   < 1.21 E-02 403/404                 94-DRM-189                       9.42E-02               4.88E+05                 4.60E-02                ,
405/406                      "C"                   < 1.50E-02                                                                    !
407/408                 94-DRM-261                 < 1.09E-02 411/412                      "D"                   < 6.02E-03 415/416                      "E"                    < 8.69E-03 PEAK            2.19E-01 pCi/gm             SUM                 2.62E-01 uCi
* Specific volumes not known, typically 65% - 85% full (55 gal. drum). Assume full. Density @ 2.35 gm/cm'3.
Co-60 : Regulatory Limits / Commitments Co-60 Activity Concentration Values SOURCE                      LIMIT                 l               REFERENCE 10CFR20 MPC               3E-05  uCi/mi            '10 CFR Part 20, App.B, Table ll Col.2 TERM SURVEY                8E-06 uCi/gm               TSP Sec.5.2.3 (an NRC Criterion)
ODCM LLD                   SE-07 uCl/mi               ODCM Table 4.11.1.1.1-1 REMP LLD                   1.5E-08 uCi/mi             ODCM Table 4.12.1-1 VS.
CONCRETE             Peak 2.19E-07 uCilgm             RWO59&O60 Term Survey Release Record Rpts.
Avg. 1.07E-07 uCi/gm MPC Fraction                   0.73%l      0.36 % Peak l Avg.
,   For determining the suitability of using the soil free-release limit of 8 pCi/gm to other bulk material, the peak concentration found (2.19E-01 pCi/gm of Co-60) represents the most conservative value and will be used in the dose pathway analysis. LILCO Calculation No. CCl-039221, " Pathway and TEDE Doses for Shoreham Post Decommissioning Dose Pathway Analysis" shows that of the four scenarios, Building Renovation, Building Occupancy, Drinking Water and Residential Use; Residential Use results in the highest TEDE.
   . Furthermore, of the major component pathways for the residential use scenario, Extemal Exposure is the most significant followed by ingestion and inhalation in that order, with groundwater not even being a credible path:tay in the case of Shoreham. Average concentration doses will be scaled directly from calculated peak values.              l Revision 1

ATTACHMENT 2                                         Page 2 of 4 Resideritial USe Scenario Th3 major component exposure pathways to be considered for this scenario include:
A) Direct External Exposure to Soil Volume Sources; B) Inhalation of Airborne Materials; C) Ingestion of Contaminated Food.
Groundwater related exposure pathways are not credible at the Shoreham site for two reasons;
: 1) This pathway is predicated on the presence of buried contaminated rubble left in place after decommissioning with the contamination allowed to teach into the groundwater where it would be picked up and transported to sources of domestic water supply. There is no buried contaminated rubble currently at the Shoreham site nor does the LIPA Decommissioning Plan allow for any as part of the decommissioning process.
: 2) Groundwater drainage at the site is north to the Long Island Sound. the three onsite wells which are used for drinking water are located south of the actual plant site and hence, no public or cite drinking water supplies could be affected by any site activity.
                                                                                                                                   ^
A) Direct External Exposure to Soil VoIume Sources The fundamental relationship for calculating radiation dose rates to people from any radionuclide in an exposure pathway is given by:
R (1,p) = C (i p) X U (p) X D (i,p)                                                                   [Ref. 9)
Where 9 (i.p) =      The radiation dose equivalent or committed radiation dose equivalent from radionuclide i via exposure pathway p, in miemlyr; C (i.p) =      The concentration of radionuclide i in the media of exposure in pathway p, in pCilgm (Bg/gm) for volume contamination in buildings and soil;
              = 2.19E-01 pCllgm                                                                                         [Ref. 4,5)   !
U (p) =       The usage parameter (exposure rate) associated with exposure pathway p, in br/yr for external exposure, For residential scenario, the equivalent                                           !
number of direct (ur. shielded) exposure = 1800 hrs outdoors (actually 1700 hrs outdoors + 100 hrs gardening) + 4380 hrs indoors X 0.33 (Home Shielding Factor);                                                                                    [Ref. 8,9]
              = 3245 hrs D (i p) =      The committed effective dose equivalent factor for radionuclide i and exposure pathway p, used to convert the concentration and usage parameters to the committed effective dose equivalent in mrem /hr per pCi/gm.
              = 1.57E-03 mrem /hr per pCi/gm for Co-60                                                                  [Ref. 8)
Therefore, R (1,p) =      2.19E-01 pCilgm X 3245 brs X 1.57E-03 mrem /hr per pCilgm
                              = l1.12E+00 mrem /yr l Th3 concentration value used above is based on assumptions so conservative as to overwhelm any consideration of re-coricentration within the bulk materialitself. This primarily refers to the assumption of assentially infinite extent at the maximum possible concentration.

ATTACHMENT 2                                     Page 3 of 4
     . B)Inhalatio'n of Airbome Materials Tho general equation for estimating the committed effective dose rate equivalent by inhalation r::c:ived by individuals for radionuclide i is given by:
H (inh,1) = V X t X C (d) X C (w.i) X DF(inh,i)                                                    [Ref. 9]
Wh:re H (inh,1) = The committed effective dose equivalent from a 1 year intake of radionuclide i by inhalation, in mrem /yr; V=             The ventilation rate of the individual,in m'3/hr;
                    = 1.0                                                                                                 [Ref. 8,9]
t=             The duration of exposure for the individual, in br/yr;
                    = 4380 hrs Indoors + 1700 hrs Outdoors + 100 hrs Gardening                                            [Ref. 8,9]
C (d) =        The concentration of respirable dust in air, in gm/m*3;
                    = Indoors = SE-05, Outdoors = 1E-04, Gardening = 5E-04                                                [Ref. 8,9]
C (w,1) =      The concentration of radionuclide i in the contarninated material, in pCi/gm;
                    = 2.19E-01 pCi/gm                                                                                     [Ref. 4,5)
DF (inh,1) = The cornmitted effective dose from inhalation of radionuclide i, in mrern/pCi.
                    = 2.19E-04 mrem /pCi for Co-60                                                                        [Ref. 8]
Therefore, H (inh,1) = 1 m'3/hr X (4380*5E-05+1700*1E-04+100*5E-04) hr-gm/yr-m'3 X 2.19E-01 pCilgm X 2.19E-04 mrem /pCl
                                  = l 2.11E-05 mremlyr l The concentration value used above is based on assumr+ ions so conservative as to overwhelm any consideration of re-concentration within the bulk materialitself. This primarily refers to the assumption 3      icisssantially infinite extent at the maxirnum possible concentration.
RESRAD incinerator Ash Dose (to the public)
Dose           = DSR(1,tmax)[ mrem /yr per pCilgm] X Peak Concentration [pCi/gm]                                  [Ref.12]
                    = 5.75E-02 X 2.19E-01
                    = l 1.2(,E-02 mrerEyr l l
IMPACTS Incinerator Ash Dose (to the max. individual)                                                             [Ref.12]   j
                       = D.SR(i trans)[ mrem /yr per pCilgm] X Peak Concentration [pCi/gm]
Dose
                    = 6.554E-01 X 2.19E-01
                    = l 1.44E-01 mremlyr l

i ATTACHMENT 2                                       Page 4 of 4 C)Inoestion of Conta,minated Food This pathway is based upon the assumption that a certain fraction of food consumed by site residents is grown in the soil onsite which contains residual acyivity concentrations. Assuming the same dietary commitments as NUREG/CR-5512 (25% of total diet as defined in R.G.1.109) allows one to take the vilues for specific nuclides directly from NUREG/CR-5512, which are based on 1 pCi/gm concentrations
   ;nd multiply by the value to be used for soil volume concentrations.
Tha simplified form of the equation is given by:
H (ing,i) = FD (ing,i) X C (i,p)                                                                    [Ref. 9]
Wh ro H (ing,1) = The committed effective dose equivalent from a 1 year intake of radionuclide i by ingestion, in mrem /yr;                                                                                      ;
FD (ing,i) = The food ingestion effective dose equivalent factor for the most sensitive organ for radionuclide i, in mrem /pCi, assuming 1 pCi/gm and the dietary input hsted below:               [Ref. 9) a) 47.5 Kglyr of vegetable produce,                                                                 I b) 27.5 L/yr of milk, c) 19.2 Kg/yr of meat (beef, poik, poultry) d) 4.8 Kglyr of eggs.                                                                               l l
               = 4.99E-05 mrem /pCi for Co-60 for LLI wall. (@ 1 pCi/gm soil activity)                                 [Ref. 8]
C (i.p) = -    .The soil volume activity, for radionuclide i, in pCilgm
               = 2.19E-01 pCl/gm for Co-60                                                                             [Ref. 4,5]
Th rcfore, H (ing,1) =    4.99E-05 mrem /pCl per pCilgm X 2.19E-01 pCilgm
                               = l1.09E-05 mrem /yr l The concentration value used above is based on assumptions so conservative as to overwhelm any consideration of re-concentration within the bulk material itself. This primarily refers to the assumption of cssentially infinite extent at the maximum possible concentration.
R::sidential Use Scenario - Total Effective Dose Equivalent Direct Exposure + Inhalation Exposure + Food Ingostion Exposure 1.12E+00 mremlyr + 2.11E-05 mrom/yr + 1.09E-05 mrem /yr
[ TEDE = 1.12E+00 mrem /yr l Reconcentration Factor required to raise projected pathway dose to Draft NRC Criteria Value =
l        RF= 1.34E+01 l

ATTACHMENT 3                                       Page 1 of 4 Termination Survey Unit - SUO44: RADWASTE OFFGAS - (CHARCOAL]
TANK     CHARCOAL           Co-60      Mn-54       Zn-65       Cs-134      Cs-137     Cs-137    CHARCOAL CHARCOAL NO.                [gms]  [pCl/gm]   [pCi/gm]    [pCi/gm]    [pCi/gm]    [pCi/gm]      [uCi]        [gms]         [lbs)
           -045A             5.10E+05   <0.015     <0.009      <0.026      <0.011        3.850         1.96    5.10E405           1,125
           -045B             5.10E+05   <0.014     <0.010      <0.026      <0.011        3.450         1.76    5.10E+05           1,125
           -047A            7.89E+06    <0.029     <0.019      <0.058      <0.019        2.550        20.13    7.89E+06          17,400
           -0478            7.89E+06    <0.031     <0.019      <0.053      <0.019        0.472         3.73    7.89E+06          17,400
           -047C            7.89E+06    <0.014     <0.008      <0.024      <0.009      <0.008
           -047D            7.89E+06    <0.019     <0.011      <0.034      <0.011      <0.011
           -047E            7.89E+06    <0.019     <0.010      <0.032      <0.012      <0.011
           -048A            7.89E+06    <0.018     <0.014      <0.049      <0.013        0.036         0.28    7.89E+06          17,400
           -048B            7.89E+06    <0.014     <0.008      <0.025      <0.009      <0.024
           -048C            7.89E+06    <0.016     <0.009      <0.004      <0.010      <0.009
          -048D             7.89E+06    <0.011     <0.007      <0.027      <0.007      <0.007
       , -048E              7.89E+06    <0.008     <0.007      <0.021      <0.005      <0.006 SUM          27.86     2.47E+07          54,450 Peak Conc. = 3.85 pCi/gm : Avg. Conc. = 1.13 pCi/gm CS-137 : Regulatory Limits / Commitments Cs-137 Activity Concentration Values SOURCE                          LIMIT                         REFERENCE 10CFR20 MPC                  2E-05 uCi/ml          10 CFR Part 20, App.B. Table ll Col.2 TERM SURVEY                  8E-06 uCi/gm         TSP Sec.5.2.3 (an NRC Criterion)
ODCM LLD                     SE-07 uCi/ml          ODCM Table 4.11.1.1.1-1 REMP LLD                     1.8E-08 uCi/mi        ODCM Table 4.12.1-1 VS.
CHARCOAL                     3.85E-06 uCi/gm       Peak - SUO44 Term Survey Release Record Rpt.
1.13E-06 uCi/gm      Avg. - SUO44 Teim Survey Release Record Rpt.
MPC Fraction                     19.25 %           Peak 5.65 %          Avg.
For determining the suitability of using the soil free-release limit of 8 pCilgm to other bulk material, the entire source term (27.86 uCi of Cs-137) will be considered and the Peak Conc. will be used for the dose pathway analysis. Use of the peak concen?ation (which was found in the smallest tank) will be extremely conservative for the dose pathway analysis. LILCO Calculation No. CCl-039221, " Pathway and TEDE Doses for Shoreham Post Decommissioning Dose Pathway Analysis" shows that of the four scenarios, Building Renovation, Building Occupancy, Drinking Water and Residential Use; Residential Use results in the highest TEDE.
Furthermore, of the major component pathways for the residential use scenario, External Exposure is the
}        most significant followed by ingestion and inhalation in that order, with groundwater not even being a credible pathway in the case of Shoreham. Average concentration doses will be scaled directly from calculated peak values.              l Revision 1

ATTACHMENT 3                                       Page 2 of 4 Resideritial Use Scenario The major component exposure pathways to be considered for this scenario include:
A) Direct External Exposure to Soil Volume Sources; B) Inhalation of Airborne Materials; C) Ingestion of Contaminated Food.
Groundwater related exposure pathways are not credible at the Shoreham site for two reasons;
: 1) This pathway is predicated on the presence of buried contaminated rubble left in place after decommissioning with the contamination allowed to teach into the groundwater where it would be picked up and transported to sources of domestic water supply. There is no buried contaminated rubt'!e currently at the Shoreham site nor does the LIPA Decommissioning Plan allow for any as part of the decommissioning process.                                                                        ;
: 2) Groundwater drainage at the site is north to the Long Island Sound. the three                                    l onsite wells which are used for drinking water are located south of the actual                                  j plant site and hence, no public or site drinking water supplies could be affected by any site activity.
A) Direct External Exposure to Soil Volume Sources The fundamental relationship for calculating radiation dose rates to people from any radionuclide in an exposure pathway is given by:
R (i p) = C (i,p) X U (p) X D (i.p)                                                               [Ref. 9]
Where R (i.p) = The radiation dose equivalent or committed radiation dose equivalent from radionuclide 1, via exposure pathway p, in mrem /yr; C (i.p) = The concentration of radionuclide iin the media of exposure in                                                   l pathway p, in pCl/gm (Bg/gm) for volume contamination in buildings and soil;
          = 3.85E+00 pCi/gm                                                                                     [Ref. 6)
U (p) = The usage parameter (exposure rate) associated with exposure pathway p, in hr/yr for external exposure. For residential scenario, the equivalent number of direct (unshielded) exposure = 1800 hrs outdoors (actually 1700 hrs outdoors + 100 hrs gardening) + 4380 hrs indoors X 0.33 (Home Shieldag Factor);                                                                                 [Ref. 8,9]
          = 3245 hrs D (i p) = The committed effective dose equivalent factor for radionuclide i and exposure pathway p, used to convert the concentration and usage parameters to the committed effective dose equivalent in mrem /hr per pCilgm.
          = 3.71E-04 mrem /hr per pCilgm for Cs-137                                                             [Ref. 8]
Therefore, R (i,p) =       3.85E+00 pCilgm X 3245 hrs X 3.71E-04 mrem /hr per pCi/gm
                           = l4.63E+00 mrem /yr l The concentration value used above is based on assurnptions so conservative as to overwhelm any consideration of re-concentration within the bulk materialitself. This primarily refers to the assumption of essentially infinite extent at the maximum possible concentration.
Revision 1

c                                                                                                                              -]
4 ATTACHMENT 3                                        Page 3 of 4 Bilobalation of Airt>orne Materials The general' equation for estimating the ^,ommitted effective dose rate equivalent by inhalation received by individuals for radionuclide i is given by:
               - H (inh,1) = V X t X C (d) X C (w,1) X DF (inh,1)                                                   [Ref. 9]
Wh:re H (inh,1) = The committed effective dose equivalent from a 1 year intake of radionuclide i byinhalation, in mrem /yr; Vw-        The ventilation rate of the individual, in m*3/hr;
            =    1.0                                                                                                [Ref. 8,9]
t=         The duration of exposure for the individual, in hrlyr;
            = 4380 hrs Indoors + 1700 hrs Outdoors + 100 hrs Gardening                                              [Ref. 8,9]
C(d)=      The concentratio1 of respirable dust in air, in gm/m*3;
            = Indoors = SE-05, Outdoors = 1E -04, Gardening = SE-04                                                 [Ref. 8,9]
C (w,1) = The concentration of radionuclide iin the contaminated material, in pCi/gm;
            = 3.85E+00 pC!/gm                                                                                       [Ref. 6]
DF (inh,1) The cornmitted effective dose from inhalation of radionuclide i, in mrem /pCi.
            = 3.20E-05 mrem /pCi for Cs-137                                                                         [Ref. 8]
Th:refore, H (inh,i) =     1 m'3/hr X (4380*5E-05+1700*1E-04+100*5E-04) hr-gm/yr-m'3 X                                     ,
3.85E+00 pCilgm X 3.20E-05 mrem /pCi
                             = l5.41E-05 mremlyr l                                                                               J The concentration value used above is based on assumptions so conservative as to overwhelm any                              ;
consideration of re-concentration within the bulk materialitself. This primarily refers to the assumption                   )
of cssentially infinite extent at the maximum possible concentration.
RESRAD incinerator Ash Dose (to the public)
Dose       = DSR(i,tmax)[ mrem /yr per pCilgm] X Peak Concentration [pCi/gm]                                   [Ref.12]
            = 1.49E-01 X 3.85E+00
            = L5.74E-01 mrem /yr j IMPACTS incinerator Ash Dose (to the max. Individual)                                                        -
[Ref.12]
Dose       = DSR(1,trans)[mremlyr per pCilgm] X Peak Concentration [pCi/gm]
            = 5.71E-02 X 3.85E+00
            =l 2.20E-01 mremlyr l                                                                                                 l

         .                                        ATTACHMENT 3                                          Page 4 of 4 C)looestion of Contaminated Food This pathway is based upon the assumption that a certain fraction of food consumed by site residents is grown in the soil onsite which contains residual activity concentrations. Assuming the same dietary commitments as NUREG/CR-5512 (25% of total diet as defined in R.G.1.109) allows one to take the valu:s for specific nuclides directly from NUREG/CR-5512, which are based on 1 pCilgm concentrations rnd multiply by the value to be used for soit volume concentrations.                                                             ,
The simplified form of the equation is given by:
H (ing,1) = FD (ing,i) X C (i.p)                                                                      [Ref. 9]
Wh:ro H (ing,i) = The committed effective dose equivalent from a 1 year intake of radionuclide i by ingestion, in mrem /yr; FD (ing,1) The food ingestion effective dose equivalent factor for the most sensitive organ for radionuclide I, in mrem /pCl, assuming 1 pCl/gm and the dietary input listed below:               [Ref. 9]
a) 47.5 Kglyr of vegetable produce, b) 27.5 Uyr of milk, c) 19.2 Kg/yr of meat (beef, pork, poultry) d) 4.8 Kglyr of eggs.
           = 5.54E-05 mrom/pCi for Cs-137 for Adrenals. (@ 1 pCilgm soil activity)                                  [Ref. 8) i C (i,p) = The soll volume activity, for radionuclide i, in pCi/gm                                                                  i
           = 3.85E+00 pCilgm for Cs-137                                                                             [Ref. 6)
Th:refore, H (ing.i) =     5.54E-05 mrem /pCi per pCilgm X 3.85E+00 pCl/gm
                            = l2.13E-04 mrem /yr l Th3 concentration value used above is based on assumptions so conservative as to overwhelrn any cor' sideration of re-concentration within the bulk materk?!itself. This primarily refers to the assumption of essentially infinite oxtent at the maximum possible concentration.
R sidential Use Scenario - Total Effective Dose Equivalent Direct Exposure + Inhalation Exposure + Food ingestion Exposure 4.63E+00 mrem /yr + 5.41E-05 mrem /yr + 2.13E-04 mrem /yr                                                                     l l     TEDE = 4.63E+C'O mrem /yr l Reconcentration Factor required to raise projected pathway dose to Draft NRC Criteria Value =
RF= 3.24E+00 Revision 1

I                                                          ATTACHMENT 4                                           Page 1 of 4 Termination Survey Unit - SUO45: CIRCULATING WATER - [ SILT]
LOCATION        LOCATION          Co-60        Cs-137       Mn-54        Zn-65 NUMBER DESCRIPTION              [pCi/gm]     [pCilgm]     [pCilgm]     [pCilgm]
Sitt Volume = 1000 cu.ft.
1           Upstream        1.79E-01 <1.18E-02 1.68E-02 <2.85E-02                         Sitt Density = 1.6 gm/cm*3 Top of Weir                                                                     Silt Activity = Mass X A.C.
Mass =         4.51E+07 gms 2         Downstream        1.26E-01 <1.24 E-02 <1.20E-02 <2.81 E-02                      A.C. =          1.54E+00 pCilgm Top of Weir                             _
l Silt Activity =             6.95E+01 l        UCi 3         Downstredr;t      1.10E-01 <1.05E-02 <1.18E-02 <2.10 E-02 Wati _
4           Upstream        1.29E+00 2.82E-02 3.30E-02 1.86E-01 incline Wall                                                                                                               i Peak activity concentrations as given for Location #4.                  SUM = 1.54E+00 pCi/gm               l Co-60 / Cs-137 / Mn-54 / Zn-65 : Regulatory Limits / Commitments Co-60 / Cs-137 / Mn-54 / Zn-65 Activity Concentration Values SOURCE                                       LIMIT                                 REFERENCE MPC                    Co-60              3E-05 uCi/ml                 10 CFR Part 20, App.B. Table 11 Col.2 Cs-137              2E-05 uCi/ml Mn-54              1E-04 uCi/ml Zn-65              1E-04 uCi/ml TERM SURVEY .                            8E-06 uCi/gm                  TSP Sec.5.2.3 (an NRC Criterion)
ODCM LLD                                  SE-07 uCi/mi                 ODCM Table 4.11.1.1.1-1                                           .l REMP LLD '             Co-60            1.5E-08 uCl/mi                 ODCM Table 4.12.1-1                                                  l Cs-137-           1.8E-08 uCi/ml                                                                                     1 Mn-54            1.5E-08 uCi/ml Zn-65            3.0E-08 uCi/ml VS.                                                                                       1 Peak Conc Ava Conc SILT                   Co-60     1.29E-06 4.26E-07 uCi/gm              SUO45 Term Survey Release Record Rpt.
Cs-137. 2.82E-08 1.57E-08 uCilgm                                                                                      1 Mn-54 3.30E-08 1.84E-08 uCl/gm Zn-65     1.86E-07 6.59E-08 uCilgm
    % of MPC               Co-60          4.30 %       1.42%
Cs-137          0.14 %       0.08 %
Mn-54          0.03 %       0.02 %
Zn-65          0.19 %       0.07 %
SUM          4.66 %       1.58 %
For determining the suitability of using the soil free-release limit of 8 pCilgm to other bulk material,11 o combined peak source activity (1.54E+00 pCilgm) wa be considered as Co-60. This is not only conservative but also will simplify the dose pathway analysis. LILCO Calculation No. CCl-039221, " Pathway and TEDE Doses for Shoreham Post Decommissioning Dose Pathway Analysis" shows that of the four scenarios, Building Renovation.
Building Occupancy, Drinking Water and Residential Use; Residential Use results in the highest TEDE.
Furthermore, of the major component pathways for the residential use scenario, External Exposure is the most significant followed by ingestion and inhalation in that order, with groundwater not even being a credible path:!ay in the case of Shoreham. Average concentration doses will be scaled directly from calculated peak values.                     l Revision 1

ATTACHMENT 4                                   Page 2 of 4 Residential Use Scenario Th3 major component exposure pathways to be considered for this scenario include:
A) Direct External Exposure to Soil Volume Sources; B) Inhalation of Airborne Materials; C) Ingestion of Contaminated Food.
Groundwater related exposure pathways are not credible at the Shoreham site for two reasons;
             .1) This pathway is predicated on the presence of buried contaminated rubble left in place after decommissioning with the contamination allowed to leach into the groundwater where it would be picked up and transported to sources of domestic water supply. There is no buried contaminated rubble currently at the Shoreham site nor does the LIPA Decommissioning Plan allow for any as part of the decommissioning process.
: 2) Groundwater drainage at the site is north to the Long Island Sound. the three p                 .onsite wells which are used for drinking water are located south of the actual plant site and hence, no public or site drinking water supplies could be affected by any site activity.
A) Direct External Exposure to Soil Volume Sources The fundamental relationship for calculating radiation dose rates to people from any radionuclide in an exposure pathway is given by:
R (i.p) = C (i.p) X U (p) X D (i.p)                                                                [Ref. 9]
Where '
R (1,p) =     . The radiation dose equivalent or committed radiation dose equivalent from radionuclide i via exposure pathway p, in mrem /yr; C (1,p) =       The concentration of radionuclide iin the media of exposure in pathway p, in pCi/gm (Bg/gm) for volume contamination in buildings and soil; -
               = 1.54E+00 pCl/gm                                                                                      [Ref. 7)
U (p) =         The usage parameter (exposure rate) associated with exposure pathway p, in hrlyr for external exposure. For residential scenario, the equivalent number of direct (unshielded) exposure = 1800 hrs outdoors (actually 1700 hrs outdoors + 100 hrs gardening) + 4380 hrs indoors X 0.33 (Home                                          j Shielding Factor);                                                                                 [Ref. 8,9]
               = 3245 hrs D (i,p) =       The committed effective dose equivalant factor for radionuclide i and exposure pathway p, used to convert the concentration and usage parameters to the committed effective dose equivalent in mrem /hr per pCi/gm.
1.57E-03 mrem /hr per pCilgm for Co-60                                                            [Ref. 8]
R (1,p) =          1.54E+00 pCi/gm .X 3245 hrs X 1.57E-03 mrem /hr per pCilgm
                                   = l 7.85E+00 mremlyr l The concentration value used above is based on assumptions so conservative as to overwhelm any consideration of re-concentration within the bulk material itself. This primarily refers to the assumption of cssentially infinite extent at the maximum possible concentration.

ATTACHMENT 4                                    Page 3 of 4 Bilnhalation of Airborne Materials Th3 general equation for estimating the committed effective dose rate equivalent by inhalation r:c;lved by individuals for radionuclide i is given by:
H (inh,1) = V X t X C (d) X C (w i) X DF (inh,i)                                                     [Ref. 9]
Wh:ra H (inh.1) = The committed effective dose equivalent from a 1 year intake of radionuclide i by inhalation, in mrem /yr; V=            The ventilation rate of the individual, in m*3/hr;
               = 1.0                                                                                                    [Ref. 8,9]
t=            The duration of exposure for the individual, in hrlyr;
               = 4380 hrs Indoors + 1700 hrs Outdoors + 100 hrs Gardening                                               [Ref. 8,9]
C (d) =       The concentration of respirable dust in air, in gm/m'3;
               = indoors = SE-05, Outdoors = 1E-04, Gardening = 5E-04                                                   [Ref. 8,9]
C (w,1) =     The concentration of radionuclide i in the contaminated material, in pCi/gm;
               = 1.54E+00 pCi/gm                                                                                        (Ref. 7)
DF (inh,1) = The committed effective dose from inhalation of radionuclide i, in rnrem/pCl.
               = 2.19E-04 mrem /pCi for Co-60                                                                           [Ref. 8]
Therefore, H (inh,i) =        1 m'3/hr X (4380*5E-05+1700*1E-04+100*5E-04) hr-gm/yr-m'3 X 1.54E+00 pCi/gm X 2.19E-04 mrem /pCi
                                  = l 1.48E-04 mrem /yr l The concentration value used above is based on assumptions so conservative as to overwhelm any consideration of re-concentration within the bulk materialitself. This primarily refers to the assumption of essentially infinite extent at the maximum possible concentration.
RE8 RAD incinerator Ash Dose (to the public)
Dose          = DSR(1,tmax)[ mrem /yr per pCi/gm] X Peak Concentration [pCilgm]                                    [Ref.12]
               = 5.75E-02 X 1.54E400
               =l        8.86E-02 mrem /yr        l IMPACTS Incinerator Ash Dose (to the max. Individual)                                                              [Ref.12]
Dose          = DSR(Urans)[mremlyr per pCilgm] X Peak Concentration [pCilgm]
                = 6.554E-01 X 1.54E+00
                =I 1.01E+00 mremlyr               l

ATTACHMENT 4                                    Page 4 of 4
  ]C1100esfion of Contaminated Food This pathway is based upon the assumption that a certain fraction of food consumed by site residents is grown in the soil onsite which contains residual acyivity concentrations. Assuming the same dietary commitments as NUREG/CR-5512 (25% of total diet as defined in R.G.1.109) allows one to take the vilu:s for specific nuclides directly from NUREGICR-5512, which are based on 1 pCi/gm concentrations and multiply by the value to be used for soil volume concentrations.
Th3 simplified form of the equation is given by:
H (ing,1) = FD (ing,1) X C (i.p)                                                                    [Ref. 9]
Where H (ing,1) =     The committed effective dose equivalent from a 1 year intake of radionuclide i by ingestion, in mrem /yr; FD (ing,1) = The food ingestion effective dose equivalent factor for the most sensitive organ for radionuclide i, in mrem /pCl, assuming 1 pCi/gm and the dietary input listed below:             [Ref. 9) a) 47.5 Kglyr of vegetable produce, b) 27.5 Uyr of milk, c) 19.2 Kglyr of meat (beef, pork, poultry) d) 4.8 Kg/yr of eggs.
                = 4.99E-05 mrem /pCi for Co-60 for LLI wall. (@ 1 pCilgm soil activity)                                 [Ref. 8]
C (i.p) =       The soit volume activity, for radionuclide i, in pCilgm
                = 1.54E+00 pCilgm for Co-60                                                                             [Ref. 7]
Therefore,
,                   H (ing,1) =       4.99E-05 mrem /pCi per pCi/gm X 1.54E+00 pCi/gm
                                   = l 7.68E-05 mrem /yr l Tha concentration value used above is based on assumptions so conservative as to overwhelm any consideration of re-concentration within the bulk materialitself. This primarily refers to the assumption of essentially infinite extent at the maximum possible concentration.                                                        j R sidential Use Scenario - Total Effective Dose Equivalent l
Direct Exposure + Inhalation Exposure + Food Ingestion Exposure 7.85E+00 mrom/yr + 1.48E-04 mrem /yr + 7.68E-05 mrom/yr l        TEDE =        7.85E+00 mremlyr l Reconcentration Factor required to raise projected pathway dose to Draft NRC Criteria Value =
                 'l             RF =     1.91E+00 l}}