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{{Adams
#REDIRECT [[RBG-26000, Addendum to Semiannual Radioactive Effluent Release Rept, Jul-Dec 1986]]
| number = ML20214P838
| issue date = 12/31/1986
| title = Addendum to Semiannual Radioactive Effluent Release Rept, Jul-Dec 1986
| author name = Booker J
| author affiliation = GULF STATES UTILITIES CO.
| addressee name =
| addressee affiliation = NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
| docket = 05000458
| license number =
| contact person =
| document report number = RBG-26000, NUDOCS 8706040097
| document type = ENVIRONMENTAL MONITORING REPORTS(&RADIOLOGICAL)-PERIODIC, TEXT-ENVIRONMENTAL REPORTS
| page count = 7
}}
 
=Text=
{{#Wiki_filter:*
SDEUNGUAL RADIORCTIVE EFFIENT RELEASE REEMP MOEMXM FACILITY:            River Bend Station - Unit I LICENSEE:            Gulf States Utilities Ccmpany REPORT PERICD:        July 1,1986 through Decenber 31, 1986
          ~
                  '1his addendtzn is sutraitted under. River Bend Station (RBS)    License Nurter NPF-47 and          provides information that was not available or finalized when the quarter 3/4 1986 RBS Semiannual Radioactive- Release, report was being compiled.
Specifically this addendum piovides an update for the following:
: 1. Abnormal Gaseous Release, page 9 of original sutmittal.
                  ?. Radiological Impact on Man, page 11.
: 3. Tables 4 & 5 Sr-89 and Sr-90 4th quarter Ccunposite Results, pages 19 and 22.
: 4. Table 6 Sr-89,      Sr-90 and Fe-55 4th quarter Ccarposite Results, pages 26 and 27.
: 5. Table 7, page 28, note-1st and 2nd quarter of 1986 results were inadvertently sutraitted, the values in this update reflect the volunes and                    ,
curies associated with spent resins, filter sludges etc. for the 3rd and 4th quarter of 1986.
It should be noted that an entry of "0.00 + 00" Ci in the following tables does not represent the absence of a radionuclide; but, rather indicates that the concentration of'a particular radionuclide was below the IcWer Limit of Detection (LID) .
8706040097 861231 PDR R
ADOCK 05000458 PDR
                                                                                  #h g
 
F. Abnoural Release
        -2. Gaseous 3rd Quarter 1986
: a. Nunter of Releases: 1
: b. Total Activity Peleased: 7.09 E-05 Ci VI. Radiological Lupact on Man The total body, skin, tnyroid and other organ dose (s) to a marber of the public frtxn the uranium fuel cycle  (40CFR190 ompliance) calculated in accordance with the GX24 was <1 mPan. .
 
TAB [E 4 ADDENXM t
Effluent and Waste Disposal Seniannual Report 1986 Year Gaseous Effluents - Conditionally Elevated Releases 3/4 Quarters
                                                  ~
Continuous Mode                Batch Mode Nuclides Released    Unit  Quarter 3    Ouarter 4      Quarter 3    Quarter 4
: 3. Particulates              -
Strontiun-89          C1        (3)        3.21 E-07        (3)      3.09 E-09    -
Strontiun-90          Ci        (3)        0.00 E 00        (3)        0.00 E 00(2)
Total for Period      Ci        (3)        5.67 E-06    3.06E-08      3.09 E-09 (2)    Quarterly cmposite particulate filter analysis indicates a Minimum Detectable Activity (MDA) concentration of <7.0 E-16 uCi/cc for the Main Plant Exhaust Duct. This value is less
                                                                      -11 than the Iower Limit of Detection (LID) of 1 x 10          uCi/ml as          .
specified    in  table    4.11.2.1.2-1      of    RBS    Technical Specifications.
(3)    Value was reported in original subnittal.
 
taste 5 ADDEMIM Effluent and Waste Disposal SanianrAlal Report 1986 Year Gaseous Effluents - Ground Ievel Releases 3/4 Quarters Continuous Mode            Batch Mode Nuclides Released    Unit  Quarter 3    Ouarter 4  Ouarter 3    Quarter 4
: 3. Particulates Strontium-89          Ci      (3)      1.20 E-07      (3)      0.00 E 00 _
Strontitzn-90          Ci      (3)      0.00 E 00(2)    (3)      0.00 E 00 Total for Period      C1      (3)      1.20 E-07      (3)    0.00 E 00 (2)    Quarterly emposite particulate filter analysis indicates a MinimJn_ Detectable Activity (FDA)      concentration of <5 E-16 uCi/cc for the Fuel Building Exhaust Vent and the Radwaste Building Exhaust Vent. This value is less than the Imer Limit
                                        ~I1 of Detection (LID) of 1 x 10      uCi/ml as specified in table 4.11.2.1.2-1 of RBS Technical Specifications.
(3)    Value was reported in original subnittal.
 
                                                'mBLE 6 NIEE@tM Effluent and Waste Disposal Seniannual Report 1986 Year G. Liquid Effluents 3/4 Quarters Continuous                        Batch Nuclides Released      Unit            Quarter 3    Quarter 4  Quarter 3        Quarter 4 Strontium-89            Ci                N/A          N/A            (3)        2.49 E-06 Strontiun-90            Ci                N/A          N/A              (3)      0.00 E 00(2)
Iron-55                -Ci                N/A          N/A            (3)        1.62 E-04 Total for Period        Ci                N/A          N/A              (3        6.51 E-01 (2)    Analysis of quarterly emposite indicates a Minin= Detectable Activity 00A) concentration of <9.0 E-11 uCi/rc.l. 'Ihis value is
                                                                                        -8 less than the Lower Limit of Detection (LID) of 5 x 10 uCi/ml as specified    in            Table  4.11.1.1.1-1    of  RBS        Technical Specifications.
(3)    Value was reported in original subnittal.
 
    'n l
l l
B B[E 7                                            i l
Effluent and Maste Di==al Smiannual Report 1986 Year Solid Maste and Trrarliated Ibel mi%
Reporting Period 07/01/86 to 12/31/86 Otr 3/4 A. Solid Waste Shipped for Burial or Disposal (Not irradiated fuel) 6-Month      Waste  Est. Total
: 1. Type of waste                            Unit Period      Class    Error, %
3
: a. Spent resins, filter sludges        m    2.57 E 02      A evaporator bottams, etc.            Ci  7.79 E 01            2.24E+01
 
  ~      ,      ,
    .c
      ).
i bS GULF STATES                    UTILITIES COMPANY POSTOFFICEBOX 220 .          ST. FRANCiSViLLE. LOUlS1ANA 70775 AREACoDE 504 635 3237            387-4257 May 26, 1987 RBG- 26000.
File Nos. G9.5, G9.25.1.5 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C.      20555 Gentlemen:
River Bend Station - Unit ~ 1 Docket No. 50-458
                                            ~
Enclosed' 's i    the Addendum to the Semiannual Radioactive-Effluent Release Report for.the period of July 1 to December 31,               1986 submitted to you previously (ref. RBG-25416 dated February 27, 1987). This Addendum provides. information which            was  not available -at      the time that the Semiannual Radioactive Effluent Release Report was being compiled.              This Addendum is being submitted in accordance with Technical Specification 6.9.1.8 of Appendix A to River Bend Station (RBS) License Number NPF-47.
Sincerely,
                                                        . [.
J.:E. Booker Manager-River Bend Oversight River Bend Nuclear Group JEB R          /CLF/ehs Enclosure.
cc:    U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 NRC Resident Inspector P. O. Box 1051 St. Francisville, LA 70775 ff' J,
                                                                        . --              -}}

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