ML20214P838

From kanterella
Revision as of 23:09, 18 January 2021 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Addendum to Semiannual Radioactive Effluent Release Rept, Jul-Dec 1986
ML20214P838
Person / Time
Site: River Bend Entergy icon.png
Issue date: 12/31/1986
From: Booker J
GULF STATES UTILITIES CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
RBG-26000, NUDOCS 8706040097
Download: ML20214P838 (7)


Text

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

  1. 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,

. -- -