ML20215C192
| ML20215C192 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 08/25/1986 |
| From: | MISSISSIPPI POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20215C166 | List: |
| References | |
| PROC-860825, NUDOCS 8610100145 | |
| Download: ML20215C192 (33) | |
Text
{{#Wiki_filter:* l l ATTACHMENT II ODCH, REVISION 8 8610100145 860926 PDR ADOCK 05000416 P PDR GRAND GULF, UNIT 1 Rev. 8 - 08/86 J200DCM86090205 - 3
4 GRAND GULF NUCLEAR STATION ODCM INSTRUCTIONS FOR ENTRY OF REVISION ODCM Revision No. 8 Attached are revised pages of the GGNS ODCM. Please remove and insert as directed below: REMOVE INSERT s Cover Page, Rev. 7 Cover Page, Rev. 8 Page i, Rev. 7 Page i, Rev. 8 -s Page iii, Rev. 2 Page iii, Rev. 8 Page iv, Rev. 2 Page iv, Rev. 8 . ,, Page vii, Rev. 7 Page vii, Rev. 8 - Page 1.0-8, Rev. 6 Page 1.0-8, Rev. 8 Page 1.0-15, Rev. 4 Page 1.0-15, Rev. 8 Page 1.0-16, Rev. 8 Page 2.0-10a, Rev. 5 Page Page 2.0-10a, Rev. 8 Page 2.0-35, Rev. 6 Page 2.0-35, Rev. 8 Page 2.0-35a, Rev. 8 Page 2.0-36, Rev. 5 Page 2.0-36, Rev. 8 Page 2.0-37, Rev. 8 Please sign and date the Transmittal and Acknowledgement Form and return, as ? indicated, as soon as possible. s s GRAND GULF, UNIT 1 Rev. 8 - 08/86
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1 l l J l 0FFSITE DOSE CALCULATION MANUAL GRAND GULF NUCLEAR STATION r GRAND GULF, UNIT 1 Rev. 8 - 08/86 J36PMI86052201 - 3
p . Revision No. 8 Date 08/86 GRAND GULF NUCLEAR STATION OFFSITE DOSE CALCULATION MANUAL SAFETY RELATED EVALUATION APPLICABILITY SAFETY EVALUATION ENVIRONMENTAL EVALUATION [X] APPLICABLE [X] APPLICABLE [ ] NOT APPLICABLE [ ] NOT APPLICABLE Reviewed / Approved: . Ob.s h 8-DO-D Supervisor, Envignmental Serv' ices /Date Reviewed / Approved: M Supervisor, Radiological Services /Date
. hM h A./ . /7e// M/f/TTa Reviewed / Approved: 20M Manager,Radiolopcal&EnvironmentalServices/Date Reviewed / Approved: k /
Director, Nuc apupp)rt/Date Reviewed / Approved: 3_ h ) i w, / i 7- 7 Cha i rifia rr, 'P1'e tiDSa fe t,y ' Revi W Oommi tte e1Da te I i GRAND GULF, UNIT 1 i Rev. 8 - 08/86 J36PMI86052201 - 1
ODCM TABLE OF CONTENTS _ Page MANUAL APPROVAL SKEET .......................................... i INTRODUCTION ................................................... ii TABLE OF CONTENTS .............................................. iii LIST OF FIGURES ................................................ iv LIST OF TABLES ................................................. v LIST OF REFERENCES ............................................. vi LIST OF EFFECTIVE PAGES ........................................ vii 1.0 LIQUID EFFLUENTS 1.1 Liquid Effluent Monitor Setpoints 1.1.1 Liquid Radwaste Effluent Line Monitors .......... 1.0-1 1.2 Dose Calculations for Liquid Effluents 1.2.1 Maximum Exposed Individual Model ............... 1.0-7 1.2.2 Do s e P roj e ct i on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 0-8 8 1.3 Liquid Radwaste Treatment System .......................... 1.0-15 '
?
2.0 GASEOUS EFFLUENTS 2.1 Gaseous Effluent Monitor Setpoints 2.1.1 Continuous Ventilation Monitors ................ 2.0-1 2.1.2 Text Deleted ................................... 2.0-3 2.2 Gaseous Effluent Dose Calculations 2.2.1 Unrestricted Area Boundary Dose ................ 2.0-7 2.2.2 Unrestricted Area Dose to Individual ........... 2.0-8 2.2.3 Dose Projection ................................ 2.0-10a 8 2.3 Meteorological Model 2.3.1 Atmospheric Dispersion ......................... 2.0-24 2.3.2 Deposition ..................................... 2.0-25 2.4 Definitions of Gaseous Effluents Parameters .............. 2.0-27 2.5 Gaseous Radwaste Treatment System ........................ 2.0-35 2.6 Annual Dose Commitment .................................... 2.0-36 2.6.1 Direct Radiation Dose Measurement ............... 2.0-36 8 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 3.1 Sampling Locations ....................................... 3.0-1 GRAND GULF, UNIT 1 iii Rev. 8 - 08/86 J36PMIB6052201 - 5 l
ODCM LIST OF FIGURES Flaure Title Page 1.0-1 Calibration Curve for Liquid Effluent Monitor................... 1.0-6 1.3-1 Liquid Radwaste Treatment System................................ 1.0-16 8 2.3-1 Plume Depletion Effect for Ground Level Releases................ 2.0-31 2.3-2 Vertical Standard Deviation of Material in a Plume. . . . . . . . . . . . . . 2.0-32 2.3-3 Relative Deposition of Ground-Level Releases.................... 2.0-33 2.3-4 Open Terrain Recirculation Factor............................... 2.0-34 2.5-1 Gaseous Radwaste Treatment System............................... 2.0-35a 8 3.0-1 Collection Site Locations, 0-5 Mile Area Map.................... 3.0-7 3.0-2 oJ Collection Site Locations, General Area Map..................... 3.0-8 3.b-3 Collection Site Locations, 0-10 Mile Area Map................... 3.0-9 3.0-4 Deleted......................................................... 3.0-10
?
GRAND GULF, UNIT 1 iv Rev. 8 - 08/86 J36PMI86052201 - 5
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ODCM LIST OF EFFECTIVE PAGES , PAGE REV. PAGE REV. NO. NO. NO. NO. i 8 2.0-22 1 11 2 2.0-23 7 iii 8 2.0-24 6 iv 8 2.0-25 0 v 6 2.0-26 7 vi 2 2.0-27 3 vii 8 2.0-28 5 2.0-29 3 1.0-1 0 2.0-30 3 1.0-2 2 2.0-31 0 1.0-3 2 2.0-32 0 1.0-4 1 2.0-33 0 1.0-5 6 2.0-34 0 1.0-6 1 2.0-35 8 1.0-7 5 2.0-35a 8 1.0-8 8 2.0-36 8 1.0-9 2 2.0-37 8 1.0-10 0 1.0-11 0 3.0-1 6 1.0-12 0 2.0-2 6 1.0-13 2 3.0-3 7 1.0-14 1 3.0-3a 7 1.0-15 8 3.0-3b 6 1.0-16 8 3.0-4 6 3.0-5 5 .? 2.0-1 5 3.0-6 5 2.0-2 5 3.0-6a 5 2.0-3 2 3.0-6b 5 2.0-4 6 3.0-6c 6 2.0-5 6 3.0-7 3 2.0-6 0 3.0-8 1 2.0-7 5 3.0-9 3 2.0-8 6 3.0-10 5 2.0-9 6 3.0-11 5 2.0-10 5 2.0-10a 8 2.0-11 1 2.0-12 1 2.0-13 2 2.0-14 1 2.0-15 2 2.0-16 2 2.0-17 1 2.0-18 2 2.0-19 1 2.0-20 1 2.0-21 2 GRAND GULF, UNIT 1 vii Rev. 8 - 08/86 J36PMI86052201 - 2
- t F
1
= near field average dilution factor for Ciduring any liquid effluent release. Defined as the ratio of the average undiluted liquid waste flow during release to the product of the average flow from the site discharge structure to unrestric receiving waters times the applicable factor of 2
= average undiluted liquid waste flow average flow from site discharge x 2 K, =
units conversion factor 1.14 x 10 5 x 10 3m
= 6 10 + 8766 U
F
= adult fish consumption (21 kg/yr) ( }.
BF f
=
Bioaccumulation factor for each nuclide, i, in fish, in pCi/kg per pCi/l from Table 1.2-1 (taken from Reference 3, Table A-1). DF g = Dose conversion factor for each nuclide, i, for adults in preselected organ, Tau, in mrem /pCi, from Table 1.2-2 (taken from Reference 3, Table E-11). Calculated values of A g, for radionuclides which might be observed in liquid effluents are given in Table 1.2-3. 1.2.2 Doses from liquid effluents to UNRESTRICTED AREAS are projected at least 8 every 31 days as required by GGNS Technical Specification 4.11.1.3.1. These projections are made by averaging the doses (DTau) fr m Previous operating history (normally the previous six months) which is indicative of expected future operations. GRAND GULF, UNIT 1 1.0-8 Rev. 8 - 08/86 J36PMI86052201 - 6
1.3 Liquid Radwaste Treatmegt System The essential compop'.nts of the liquid radwaste treatment system are indicated on the following page by an asterisk (*). NOTES for Figure 1.3-1 8 (1) The essential components outlined on the following page are those necessary to collect, process and sample liquid radwaste prior to discharge to the environment. (2) Only one of the following is required in order to process liquid waste.
- a. Equipment drain filter
- b. Floor drain filter
- c. Equipment drain demineralizer -
- d. Floor drain demineralizer (3) 'One of the Waste Surge Tanks may be used to replace the Floor Drain Waste Collection Tank.
i l i l GRAND GULF, UNIT 1 1.0-15 Rev. 8 - 08/86 J36PMI86052201 - 7
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Qg = cumulative release of radionuclide i of toble gas, tritium, I-131, I-133, or material it; particulate form over the period of interest (uCi) 2.2.2.c For the purpose of implementing Specification 6.9.1, of the RETS, dose calculations will be performed using the above equations or with the substitution of average meteorological parameters (most limiting parameters will be used) which prevailed for the period of the report. 2.2.3 Doses from gaseous effluents to UNRESTRICTED AREAS are projected at least every 31 days as required by GGNS Technical Specifica-tion 4.11.2.5.1. These projections are made by averaging the doses (D , Dp , D ) from previous operating history (normally 8 the previous six months) which is indicative of future expected operations. 7 GRAND GULF, UNIT 1 2.0-10a Rev. 8 - 08/86 J36PMI86052201 - 9
2.5 Gaseous Radwaste Treatment System The instruments required to be checked by RETS 3/4.11.2.4 to ensure that the GASEOUS RADWASTE TREATMENT (Offgas) SYSTEM is functioning are:
- 1. Absorber train bypass switch (IN64-HS-M611)
- 2. Bypass valve indication (IN64-F045)
When the absorber train bypass switch is in the TREAT position and the bypass valve indicates closed, the GASEOUS RADWASTE TREATMENT (Offgas) SYSTEM is functioning. NOTES for Figure 2.5-1 A flow diagram for the Gaseous Radwaste Treatment System is provided 8 on the following page. Notes for the diagram are listed below. (1) The charcoal beds are bypassed during startup until an adequate dewpoint is obtained in the process stream. 7 (2) This pathway may be utilized for power levels 5 5%. 8 (3) Standby Gas Treatment System not normally operated. l GRAND GULF, UNIT 1 2.0-35 Rev. 8 - 08/86 J36PMI86052201 - 10
I Figure 2.5-1
. GASEOUS RADWASTE TREATMENT SYSTEM To ATuos,,eg
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2.0-35a REV. 8 - 08/86
2.6 Annual Dose Commitment-For the purpose of implementing Technical Specification 3.11.4, the annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC will be calculated by summing the folinwing doses for the calendar year:
- Direct radiation dose Liquid effluent dose (DTau)
- Noble gas dose (D , Dg)
- Particulate dose (D ) g These calculations are required only if the liquid or gaseous effluents exceed twice the limits of Technical Specifications 3.11.1.2.a, 3.11.1.2.b, 3.11.2.2.a, 3.11.2.2.b, 3.11.2.3.a, or 3.11.2.3.b.
2.6.1 Direct Radiation Dose Measurement ? Technical Specification 3.11.4 requires the determination of cumulative dose contributions to a MEMBER OF THE PUBLIC , from direct radiation from the reactor units and from radwaste storage tanks. This requirement is applicable only under conditions set forth in Specification 3.11.4 Action a. This determination is made by the utilization of direct radiation measurements from thermoluminescent dosimeters (TLDs) M-61 through M-84 located at equidistant intervals on the Unit I protected area fence. Exact GRAND GULF, UNIT 1 2.0-36 Rev. 8 - 08/86 J36PMI86052201 - 12
i
=
i locations are defined in Table 3.0-3. Measurements from these TLDs represent the direct radiation generated by the facility plus normal background radiation. Control TLD's are also utilized to differentiate between background radiation and direct radiation from the facility. The following seven TLDs are designated as controls based on the criterion that they are located ten miles or greater from the facility. Exact locations are identified in Table 3.0-3. M-06 M-12 M-14 M-39 M-11 H-13 M-33 The difference between the averaged quarterly radiation measurements of the protected area TLDs and the control TLDs represents the direct radiation dose to a MEMBER OF THE PUBLIC from the operating facility. -' GRAND GULF, UNIT 1 2.0-37 Rev. 8 - 08/86 J36PMI86052201 - 37
ATTACHMENT III 4 JUSTIFICATION / DETAILED OUTLINE ODCM, REVISION 8 GRAND GULF, UNIT 1 Rev. 8 - 08/86 J200DCM86090205 - 4
IV. OFFSITE DOSE CALCULATION MANUAL / PROCESS CONTROL PROGRAM REVISIONS A. Offsite Dose Calculation Manual (ODCM) Revision 8 Revision 8 to the ODCM was reviewed and approved by the Plant Safety Review Committee on August 25, 1986. The changes within this revision can be characterized as administrative revisions. The changes do not reduce the accuracy nor the reliability of the dose calculations or setpoint determinations. The intent of Revision 8 was to incorporate changes requested by the Nuclear Regulatory Commission in correspondence dated April 2, 1986 (MAEC-86/0094). The requested changes involved the following three areas:
- Projected dose
- Annual dose commitment
- Diagrams for Liquid & Gaseous Radwaste Treatment Systems.
Subject:
Grand Gulf Nuclear Station Offsite Dose Calculation Manual (ODCM), Revision 8, August 25, 1986.
- Page iii
*Affected Lines: 16, 25, 31 and 32 Revision / Justification: Lines 16, 25, 31 and 32 were added to make the Table of Contents consistent with the ODCM text.
- Line numbers reflect revision location in the ODCM, Revision 8.
GRAND GULF, UNIT 1 Rev. 8 - 08/86 J200DCM86090205 - 5
- Page iv Affected Lines: 5 and 10 Revision / Justification: Drawings for the Liquid and Gaseous Radwaste Treatment Systems have been identified with Figure numbers and the List of Figures revised accordingly.
- Page 1.0-8 Affected Lines: 21 and 23 Revision: The numbers 1.2.2 were added at the beginning of line 21.
The letters "au" in Tau were made lower case on line 23. Justification: .Line 21 was preceded with a section number to delineate the method for projecting liquid effluent dose as required by GGNS Technical Specification 4.11.1.3.1. This change was made in response to NRC correspondence dated April 2, 1986 (MAEC-86/0094). Lower case letters were used to be consistent with other usage of Tau in the ODCM.
- Page 1.0-15 Affected Lines: 3, 4, 5, 16 and the Liquid Radwaste Treatment System (LRTS) flow diagram.
Revision: The LRTS flow diagram was enlarged, identified as Figure 1.3-1, and placed on an additional page (1.0-16). The phrase "on the following page" replaces the words "below" and "above" on page 1.0-15 lines 3 and 5, respectively, to indicate the new location of the LRTS flow diagram. The phase "for Figure 1.3-1" was added following the word NOTES on line 4 to identify the LRTS flow diagram. Since the flow diagram was moved to the next page, the notes were respaced to 9 improve readability. Line 16 was deleted. Justification: The LRTS flow diagram was enlarged to make it more legible. Improvement of flow diagram legibility was requested by the NRC in correspondence dated April 2, 1986 (MAEC-86/0094). Line 16 was deleted because there is only one operating unit at GGNS. GRAND GULF, UNIT 1 Rev. 8 - 08/86 J200DCM86090205 - 6
- Page 1.0-16 Affected Lines: All (New Page).
Revision: Added enlarged LRTS flow diagram and identified as Figure 1.3-1. Made the word " tanks" singular in " condensate storage tanks". Made the word " tank" plural in " sample tank" for low purity waste. Justification: The LRTS flow diagram was enlarged and placed on a separate page to make it more legible. Improvement of flow diagram legibility was requested by the NRC in correspondence dated April 2, 1986 (MAEC-86/0094). The word " tanks" in " condensate storage tanks" was made singular because there in only one tank at GGNS. The word " tank" in " sample tank" for low purity waste was made plural to correct a typographical error.
- Page 2.0-10a Affected Lines: 10 through 15 Revision: Added paragraph 2.2.3 on gaseous effluent dose projection.
Justification: Paragraph 2.2.3 was added to describe the method for projecting gaseous effluent dose as required by GGNS Technical Specification 4.11.2.5.1. This addition was requested by the NRC in correspondence dated April 2, 1986 (MAEC-86/0094).
- Page 2.0-35 Affected Lines: 10, 11, 12 and the Gaseous Radwaste Treatment System (GRTS) flow diagram.
Revision: The GRTS flow diagram was enlarged, identified as Figure 2.5-1, and placed on an additional page (2.0-35a). Lines 10, 11, and 12 were added to identify the locations of the GRTS flow diagram and associated notes. Since the flow diagram was removed from the bottom of page 2.0-35, the notes were respaced to improve readability. Note Number 3 was deleted, and Note Number 4 was changed to Number 3. Justification: The GRTS flow diagram was enlarged to make it more legible. Improvement of flow diagram legibility was requested by the NRC in correspondence dated April 2, 1986 (MAEC-86/0094). GRAND GULF, UNIT 1 Rev. 8 - 08/86 J200DCM86090205 - 7
Note Number 3 was deleted because these units have been installed and are being used.
- Page 2.0-35a Affected Lines: All (New Page).
Revision: Added enlarged GRTS flow diagram and identified as Figure 2.5-1. The reference to Note "(3)" for the Turbine Building was deleted. This change necessitated changing Note "(4)" for Standby Gas Treatment to Note "(3)". Justification: The GRTS flow diagram was enlarged to make it more legible. Improvement of flow diagram legibility was requested by the NRC in correspondence dated April 2, 1986 (MAEC-86/0094). Note "(3)" was no longer applicable. See justification for Page 2.0-35.
- Page 2.0-36 Affected Lines: 1 through 14 Revision: Section 2.6 was retitled and a paragraph (lines 1 through
- 13) inserted on annual dose commitment. Direct Radiation Dose Measurement is now identified on line 14 as 2.6.1 instead of 2.6.
Justification: The method for calculating annual dose commitment was added to address GGNS Technical Specification 3.11.4. This necessitated renumbering the paragraph on direct radiation dose measurement as 2.6.1. This change was requested by the NRC in correspondence dated April 2, 1986 (MAEC-86/0094). GRAND GULF, UNIT 1 Rev. 8 - 08/86 J200DCM86090205 - 8
Significant Hazards Consideration Revision 8 to the ODCM involves no changes to the safety-related equipment at GGNS. It does not introduce a significant reduction in the margin of safety and does not involve a significant increase in the probability or consequences of Jua accident previously evaluated. It does not create the possibility of a new or different kind of accident from any accident previously evaluated nor does it reduce the accuracy or reliability of dose calculations or setpoint determinations. Thus there are no significant hazards involved. GRAND GULF, UNIT 1 Rev. 8 - 08/86 J200DCM86090205 - 9 l
ATTACHMENT IV MARKUP ODCM, REVISION 8 GRAND GULF, UNIT 1 Rev. 8 - 08/86 J200DCM86090205 - 10
y
's
- n. TABLE T CCNTDfTS Page 99NUAL APPRCVAL SHEET. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . i INTRCDUCTICN. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ii TABLE T CXNIDfrS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . iii LIST T FIGURES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . iv LIST T TABIZS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V LIST T REEDENCES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Vi LIST T H TECTIVE PAGES.................................... vii 1.0 LIQUID EETIUDfIS 1 1
1.1 Liquid Effluent Monitor Setpoints 1.1.1 Liquid Radwaste Effluent Line Monitors........ 1.0-1 1.2 Dose Calculations for Liquid Effluents 1.2.1 Maxinum Exposed Individual Model. . . . . . . . . . . . . . 1. 0-7 1.3 Liquid Radwaste Treatment Systan. . . . . . . . . . . . . . . . . . . . . 1. 0-15 s 2.0 GASDJUS EFTIDDfIS 2.1 Gaseous Effluent Monitor Setpoints y 2.1.1 Continucus ventilation Monitors. . . . . . . . . . . . . . . 2.0-1 2.1.2 'next Deleted. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 0-3 l2 2.2 Gaseous Effluent Dose Calculations i 2.2.1 Unrestricted Area Boundary Dose. . . . . . . . . . . . . . . 2.0-7 2.2.2 Unrestricted Area Dose to Individual.......... 2.0-8 2.3 Meteorological Model 2.3.1 Atnospheric Dispersicm. . . . . . . . . . . . . . . . . . . . . . . . 2.0-24 i 2.3.2 Deposition.................................... 2.0-25 l l 2.4 Definitions of Gaseous Effluents Paraneters.......... 2.0-27 l 2.5 Gaseous Radwaste Treatment Syntan. . . . . . . . . . . . . . . . . . . . 2.0-35 3.0 RADICWGICAL DNIBCIMENIAL MCETIUtING I 3.1 Sanpling locations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 0-1 psy -s-1.2.2 . Dos e Proj e ction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 0-8 l 2.2.3 Dose Projection ................................ 2.0-10a lii l 2.6 Annual Dose Commitment .................................... 2.0-36 j 2.6.1 Direct Radiation Dose Measurement . . . . . . . . . . . . . . . 2.0-36 j l i -- - _ _ - - _ -pt __ - - GRAND GUIE, INIT 1 Rev. 2 - 5/84
CocM
..,.x, LIST or FIGURES Fiaure Title Page
'1.0-1 Calibration Curve for Liquid Effluent Monitor........ 1.0-6 2.3-1 Plune Depletion Effect for Grourd Invel Releases..... 2.0-31 2.3-2 vertical Standard Deviation of Material in a Pitune... 2.b-32 2.3-3 Relative Deposition of Ground-Invel Releases......... 2.0-33 2.3-4 Open Terrain Recirculation Factor. . . . . . . . . . . . . . . . . . . . 2. 0-34 3.0-1 Collection Site Iccations, 0-5 Mile Area Map......... 3.0-7 2 3.0-2 Collection Site locations , General Area Map. . . . . . . . . . 3. 0-8 3.0-3 Collection Site Iccations, 0-10 Mile Area Map........ 3.0-9 l2 3.0-4 Deleted.............................................. 3.0-10 2 gg7T 1.3-1 Liquid Radwaste Treatment System..... . . . . . . . . . . . . . ............. 1.0-16 2.5-1 Gaseous Radwaste Treatment System..... . . . . . . . . . . . . . ............ 2.0-35a l
i l l 1 iv GRMO GUIE, UNIT 1 Rev. 2 -5/84
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y,_, , , , , ,
, ~ T 3
= near field average dilution factor for C gduring any liquid effluent release. Defined as the ratio of the average undiluted liquid waste flow during release to the product of the average flow from the site discharge structure to unrestricted receiving waters times the applicable factor of 2(5) ,
= average undiluted liquid waste flow average flow from site discharge x 2 K, = units conversion factor 1.14 x 10 5
= 6 3 10 p x 10 a1 + 8766 hr uCi Kg yr Up = adult fish consumption (21 kg/yr) (3) ,
BF g = Bioaccumulation factor for each nuclide, i, in fish, in y pCi/kg per pCi/1 from Table 1.2-1 (taken from Reference 3, Table A-1). DF g = Dose conversion factor for each nuclide, i, for adults
~
in preselected organ, Tau, in arem/pCi, from Table 1.2-2 1.2.2 (taken from Reference 3, Table E-11). ( ' Calculated values of A iTau f r radionuclides which might be observed in liquid effluents are given in Table 1.2-3. Doses from liquid effluents to UNRESTRICTED AREAS are projected at least every 31 days as required by GGNS Technical Specification 4.11.1.3.1. These projections are made by averaging the doses from previous 6 operating history (normally the previous six months) which is indicative of expected' future operations. ~
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(DTau} GRAND GULF, UNIT 1 1.0-8 Rev. 6 - 9/85 J200DCM850829
- ~
~U 1.3 Liquid Radwaste Tremtrnent systm N
'1he essential wwents of the liquid radwaste treatznent systs are 4
indicated by an astarisk (*) . A sums. (, , : M hM m "e a. l, '."*"g o , 0
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T'M_, g aaru .=. su ==
. , = , .w.
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on the following page , ! NOTES h ( 1. The essential omponents outlinedgare those necessary to collect, I process and sanple liquid radwaste prior to discharge to the environment.
- 2. Only one of the following is required in order to process liquid waste.
- a. Equipnent drain filter
- b. Floor drain filter l
- c. Equipnent drain demineralizer
- d. Floor drain demineralizer
- 3. Ole of the Waste Surge Tanks way be used to replace the Floor Drain Waste Collection Tank.
T** """ M * " .'. "". "r ".'SMJ ^ '
GRAND GUIE, UNIT 1 1.0-15 Fev. 4 - 8/84
Og = cumulative release of radionuclide i of noble gas, tritium, 1-131, 1-133, or material in particulate form over the period of interest (uC1) 2.2.2.c For the purpose of implementing Specification 6.9.1, of the RETS, dose calculations will be performed using the above equations or with the substitution of average meteorological parameters (most limiting parameters will 5 be used) which prevailed for the period of the report. f$b
)
2.2.3 Doses from gaseous effluents to UNRESTRICTED AREAS are projected at least every 31 days as required by GGNS Technical Specifica-tion 4.11.2.5.1. These projections are made by averaging the doses (D , Dp , Dp ) from previous operating history (normally h
- the previous six months) which is indicative of future expected j operations.
l i 1 GRAND GULF, UNIT 1 2.0-10a Rev. 5 - 1/85
2.5 Caseous Rad =aste Treatment System
~
The instruments required to be checked by RETS 3/4.11.2.4 to ensure that the CASEOUS RADWASTE TREATMENT (Offgas) $YSTEM is functioning are:
- 1. Absorber train bypass switch (IN64-HS-M611)
- 2. Sypass valve indication (IN64-F045)
When the absorber train bypass switch is in the TREAT position and the bypass valve indicates closed, the CASEOUS RADWASTE TREATMENT (Offges) System is functioning. W - 1 ,
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o A flew diagram for the Geseous Redoeste Treatmast System is provided "j gg 4: en the following page. Notes for the diagram are listed below. __ = _ - - _ _ - - __ _ _ _ -y _
- 1. The charcoal beds are bypassed during startup until an adequate dowpoint is obtained in the process stream.
- 2. This pathway may be utill ed for power levels 6 5%.
T
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. n e _ _ ' _--- , _",':,g '. :::' ?t: : _2
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[ standby Cas Treatment system not norme11y operated. 1 GRAND GULF, UNIT 1 2.0-35 Rev. 6 - 9/85
.1200DCM8508.~ 9
Z#SE77 2.t , Direct Radiation Dose Measurement Technical Specification 3.11.4 requires the determination of cumu-lative dose contributions to a MEMBER OF THE PUBLIC from direct radiation from the reactor units and from radwaste storage tanks. This requirement is applicable only under conditions set forth in Specification 3.11.4 Action a. This determination is made by the utilization of direct radiation measurements from thermoluminescent dosimeters (TLDs) M-61 through M-84 located at equidistant intervals on the Unit I protected area fence. Exact locations are defined in Table 3.0-3. Measurements from these TLDs represent the direct radiation generated by the facility plus normal background radiation. 5 Control TLD's are also utilized to differentiate between background
) radiation and direct radiation from the facility. The following seven TLDs are designated as controls based on the criterion that they are located ten miles or greater from the facility. Exact locations are identified in Table 3.0-3.
M-06 M-12 M-14 M-39 M-11 M-13 M-33 The difference between the averaged quarterly radiation measure-ments of the protected area TLDs and the control TLDs represents the direct radiation dose to a MEMBER OF THE PUBLIC from the operating facility. GRAND GULF, UNIT 1 2.0-36 Rev. 5 - 1/85
-g -
1 ENSERT z- __ 2.6 Annual Dose Commitment l s For the purpose of implementing Technical Specification 3.11.4, the ' annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC will be calculated by summing the following doses for the h{ - calendar year: (fi () Direct radiation dose i f
- f Liquid effluent dose (DTau) *
- Noble gas dose (D , Dg ) I l
I Particulate dose (Dp ) These calculations are required only if the liquid or gaseous , effluents exceed twice the limits of Technical Specifications
- 1) J 1
3 3.11.1.2.a. 3.11.1.2.b, 3.11.2.2.a, 3.11.2.2.b, 3.11.2.3.a, or 3.11.2.3.b. 1 i j
e
- ATTACHMENT V ENLARGEMENTS OF REVISED DIAGRAMS FOR ODCM, REVISION 8 i
l l I l l GRAND GULF, UNIT 1 Rev. 8 - 08/86 J200DCM86090205 - 11 l l l l
Figure 1.3-1 LIGUID RADWASTE TREATMENT l REACTOR l 1 Z J L I f FROM CONDENSATE SURGE LE TAE DEMINERALIZER i f HIGH PURITY WASIE
- 1. EQUIPMENT DRAINS A. CONTAINENT G DRYWELL BLDG B. AUXILLARY BLDG ,
EQUIPMENT DRAINSLt . j TUNIE BLDS WASTE -. " C. FILTER DEMIERJ D. RADWASTE BLD6 COLLECTION TAE j k J ( l 2. EVAPORATOR DISTILLATE
- 3. C0tOENSATE DEMINERALIZER RINSE ] f
- 4. RWCU DECANT FILTER CAKE TO SOLID WASTE
_ LOW PURITY WASTE FLOOR DRAINS ] f
%.1 f l
- 1. FLOOR DRAIN SUMPS m
" ^
A. CONTAI M G DRYWELL BLDG COLLECTION T g FILTER DEMIEW l B. AUXILLARY BLDG C. TUMINE BLD6 D. RADWASTE BLD6 E RESIN ESEERATION REGEERATION ESIN REGEERATION CHEMICALS U SOLUTION COLLECTION 3 SOLUTION TAE EUTRALIZER TAE j(
.81sca.Lammis_xaaIE _.
MISCELLANFN?.' 3 CEMICAL DRAINS U CEMICAL hASTt 7 1FE ._ GRAND GULF, UNIT i 1.0-16 1
= .
SYSTEM Z TUFBINE C CONDENSER _, i f COWENSATE l STORAGE Tale ( 1f Jk COOLING TOWER BED E m SAMPLEU LIZER
- TANKS j( RADIATION J NONITOR I f JL
= )
EER ? TE" 8 7 EVAPORMOR i f DISTILATE TO HI PUAITY WMTE TO SOLID WASTE JL 3' EVAPORATOR TO SOLID WASTE TI APERTURE CMtD STATION 2 BLONDOWN DISCHARGE Ah AveMle on Aperture Car.1 MISSISSIPPI RIVER REV. 8 - 08/86 glotooM3 -Of
4 l I (. Figure 2.5-1 _ GASEOUS _RADWASTE TREATMENT SYSTEM To Arnospuens
,-s s ,-s, i POST \ / \
8 RADIATION: lTEA %
\ MONITOR, 40 scfa 10 MIN BYPASS LIE (1) (MONITOR /
OFF GAS - now UP - ,
'< ' d'"
FHON MAIN ] PIPE EPA CHARCOAL EPA ComEN9ER 2 STA6ti H022 (ColeEN9ER) ' FILTER-- BEDS FILTER C, AIR - CATALYTIC I EJECTOR EC00EINEF OEPESENTATIVE RADI0 ACTIVE OF i PFf LNIT) I
\
/
OFF GAS TEATENT I SYSTEM i 1 s ECH. VAC. Ptw (2) 1 I PM [ ' RADWASTE EPA CHAF N 1 EPA ! FILTER FILTER BEDS FILTER ,__ i I I I I I FILTER F
-> FILTER w ER I
I I I TO I ATM09 PERE l n i PE EPA CHARCOAL- EPA I FILTER BUILDIM FILTER FILTER- BEDS FILTER
," {s s IR BUILDING i s VENTILATION cRADIATION: ___ __ m________ _ _ _
s nunuunj s ' m- ,-s, _- TO ATN09 PERE [RADIATI0di t MONITOR,'
% /
OUTSIDE m p AUXILARY N C AIR I I TO ATN09PEM r-----
#AN PRE I EPA CHARCOAL EPA M FILTER- BEDS I FILTER
? FILTER FILTER _
i DRYMELL f { 's
- - 5 RADIATION:
tMONITOR/ l ' I I I TO ATNOSPEE I h l STAM BY SAS l EPA i PE EPA CHARCOAL TREATENT (3) FILTER FILTER FILTER 6 BEDS
/
',b's SYSTEN (REPESENTATIVE
[ RADIATION: OF 2 PER LMIT) t MONITOR 8 NOTES ON PREVIOUS PAGE
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GRAND GULF, UNIT i 2.0-35a REV. 8 - 08/86
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