ML20212P733
| ML20212P733 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 12/31/1986 |
| From: | Fitzpatrick E, Peacock B COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| (4266Z), EEF-87-27, NUDOCS 8703160226 | |
| Download: ML20212P733 (74) | |
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BRAIDWOOD NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-456 LICENSE NO. NPP-59 J
- T4'228884 884881.
R PDR
- m. . ,
eo
I. Monthly Report for Braidwood Unit 1 A. Summary of Operating Experience for Unit 1 The unit remained in Mode 5 throughout the month of December,1986.
Pre-operational testing continued.
(42662)
. a B. OPERATING DATA _ REPORT DOCKET NO.: 50-456 UNIT: Braidwood 1 DATE: 01/05/87 CCMPILED BY: B. M. Peacock TELEFIIONE: (815)458-2801 ext. 2480 OPERATING STATUS
- 1. Reporting Period: Deceeber 1986 Gross Hours: 744
- 2. Currently Authorized Power Level (MWt): 0 Design Electrical Rating (MWe-gross): 1175 Design Electrical Rating (MWe-net): 1120 Max Dependable Capacity (MWe-net): 0
- 3. Power level to which restricted (If Any): 0 (MWe-gross)
- 4. Reasons for restriction (If Any): Low power testing license has not been received yet.
Ti!IS MONTil YR TO DATE CUMULATIVE
- 5. Report period !!ours: 744 1800 1800
- 6. Ifours Reactor Critical: 0 0 0
- 7. RX Reserve Shutdown llours: O O O
- 8. Ilours Generator on Line: 0 0 ,_
0 _
- 9. Unit Raserve Shutdown !!oure: 0 0 0
- 10. Gross Thermal Energy (MWil): 0 0 0
- 11. Gross Elec. Energy (MWil): 0 0 0
- 12. Net Elec. Energy (MW11): 0 0 O_ _
- 13. Reactor Service Factor: 0 0 0 _ __
- 14. Reactor Availability Factor: 0 0 0
- 15. Unit Service Factor: 0 0 0
- 16. Unit Availability Factor: 0 0 0
- 17. Unit Capacity Factor (MDC net): 0 _
0 0
- 18. Unit Capacity Factor (DER net): 0 0 0
- 19. Unit Forced Outage !!ours: 0 0 0
- 20. Unit Forced Outage Rate: 0 0 0
- 21. Shutdowns Scheduled Over Next 6 Months: N/A N/A N/A
- 22. If Shutdcwn at End of Report Period, Estimated Date of Startup: 03/13/87 N/A N/A
- 23. Units in Test Status (Frior to Commercial Operation):
FORECAST ACilIEVED Initial Criticality 03/13/87 Initial Electricity 04/20/87 Commercial Operation 07/19/87 (4266z)
[ . ,
l l C. AVERAGE DAILY UNIT NET POWER LEVEL LOG DOCKET NO.: 50-456 l UNIT: Braidwood 1 DATE: 01/05/87 COMPILED BY: B. M. Peacock TELEPHONE: (815)458-2801 ext. 2480 MONTH: December, 1986
- 1. 0 17. 0
- 2. 0 18. 0
- 3. 0 19. 0
- 4. O __ 20. 0
- 5. 0 21. 0
- 6. 0 22. _
0
- 7. 0 23. 0
- 8. 0 24. 0
- 9. 0 25. 0
- 10. 0 26. 0
- 11. O _
- 27. 0
- 12. 0 28. 0
- 13. 0 29. 0
- 14. 0 30, 0
- 15. 0 31. 0
- 16. O INSTRUCTIONS On this form list the average daily unit power level in MWE-Net for each day in the reporting month. Compute to the nearest whole megawatt.
These figures will be used to plot a graph for each reporting month.
Note that when maximum dependable capacity is used for the net electrical rating of the unit there may be occasions when the daily average power level exceeds the 100>. line (or the restricted power level line). In such cases the average daily unit power output sheet should be footnoted to explain the apparent anomaly.
(4266z)
s D. UNIT SHUTDOWNS / REDUCTIONS DOCKET NO.: 50-456 UNIT: Braidwood 1 DATE: 01/05/87 COMPILED BY: B. M. Peacock
- TELEPHONE: (815)458-2801 ext. 2480 REPORT PERIOD: December 1986 -
No DATE TYPE HOURS REASON METHOD LER NUMBER SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO PREVENT RECURRENCE N/A PRECRITICAL PERIOD coceaeeeeeeeeeeem
SUMMARY
eeeee ***********
TYPE REASON METHOD SYSTEM & COMPONENT F-Forced A-Equipment Failure Maint or Test 1 - Method Exhibit F & H S-Scheduled C-Refueling 2 - Manual Scram Instructions for Preparation of D-Regulatory Restriction 3 - Auto Scram Data Entry Sheet E-Operator Training & License Examination 4 - Continued Licensee Event Report F-Administration 5 - Reduced Load (LER) File (NUREG-0161)
G-Oper Error 9 - Other H-Other (4266z) .
. o E. UNIQUE REPORTING REQUIREMDJTS
- 1. Safety / Relief valve operations for Unit 1.
VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED ACTUATION CONDITION OF EVENT None
- 2. Licensee generated changes to ODCM.
The following changes have been made to Braidwood Station's Offsite Dose Calculation Manual (ODCM):
Section 7.2, Revision 11 Section 8.0, Revision 11 Pursuant to Technical Specification 6.14.2.a, the following information is provided:
- 1) These revisions were made to make the ODCM consistent with the Station's Technical Specifications. These revisions reflect current information for site specific monitor setpoints, ODCM calculation pa ramete rs , and the environmental radiological monitoring program.
The specific changes are listed in Attachment 1. The changed pages are enclosed as Attachment 2.
- 2) The accuracy and reliability of dose calculations and setpoint determinations has not been diminished.
- 3) These revisions were distributed for use on December 11, 1986 after receiving the necessary review and acceptance by the Onsite Review and Investigative Function.
l (4266z) l
. i F. LICENSEE EVENT REPOR_TS The following is a tabular surrary of all Licensee Event Reports for Braidwood Nuclear Power Station, Unit 3, submitted during the reporting period, December 1 through December 31, 1986. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CFR50.73.
Licensee Event Report Number Date Title of Occurrence 86-002-00 12/05/86 All Action Requirements of Tech Specs Not Met While Both Source Range Channels Were Inoperable 86-003-00 12/15/86 Inoperable Hard Rubber Fire Hoses Due to Couplings Separating from the Hoses 86-004-00 12/23/86 Steam Generator Low-Low Level Results in Reactor Trip due to Misadjusted Valve 86-005-00 12/23/86 Containment Purge Isolation From a Voltage Transient Caused by Construction Activity 86-006-00 12/23/86 Failure to Follow Action Statement 3.3.3.10 On Failure of 1RT-PR028 (Auxiliary Building Effluent Radiation Monitor) 86-007-00 12/23/86 Temporary Procedure Change not reviewed within 14 days due to unclear steps in procedure (4266z)
. i ATTACHMENT 1 Braidwood Station ODCM Revision 11 Section 7.2 and 8.0 Changes
- 1. All Pages -
Date and number of revision changed.
- 2. Page 7.2-1 -
Remove extraneous asterisk for t units.
Corrected default value for t in footnote.
- 3. Page 7.2-4 -
Update ranges for nearest resident and dairies.
- 4. Page 8-i -
Revised Table of Content.
- 5. Page 8-11 -
Updated List of Tables.
- 6. Page 8-iii - Updated List of Figures.
- 7. Section 8.1 - Updated monitor and set point information.
Added Figure 8.1-1.
- 8. Section 8.2 - Updated monitor and set point information.
Added Figure 8.2-1.
- 9. Section 8.4 - Modified format of tables and added specific information for all current sampling locations.
Removed Reporting Levels to separate table.
Removed "Postoperation Monitoring Program".
Removed " Table 8.4-4, Sampling Codes".
Updated Figure 8.1-1.
- Added Figures 8.4-2 and 8.4-3.
- 10. Page 8.4-1 -
Updated description of figure and tables,
- 11. Page 8.4-7 - Corrected values to correspond to Tech Specs.
- 12. Page 8.4-8 -
Corrected values to correspond to Tech Specs.
(42662)
h,et.*@ D h e 1ce @ M S B RAICWOOD REVISION 11
("'N, AUGUST 1986
.\ /
LIST OF TABLES FOR SECTION 7.2.
NUMBER TITLE PAGE 7.2-1 Acuatic Environmental Dose Parameters 7.2-1 7.2-2 Annual Design Objectives Set By 10 CFR 50, Appendix I, for Each Reactor 7.2-2 7.2-3 Station Characteristics 7.2-3 7.2-4 Critical Ranges 7.2-4 7.2-5 Terrain Correction Factors (h t) 7.2-5 7.2-6 X/Q and D/O Maxima at or Beyond the Unrestricted Area Boundary 7.2-6 7.2-7 D/Q at the Nearest Milk Cow and Meat Animal Locations Within 5 Miles 7.2-8 7.2-8 Maximum Offsite Finite Plume Gamma Dose Factors for Selected Nuclides 7.2-9 7.2-1 l
l 1
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_ - _ - _ - - _ . _ . _ _ . . . -J
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he. D e? @ G BRAIDWOOD REVISION 11 AUGUST 1986 LIST OF FIGURES FOR SECTION 7.2 NUMBER TITLE 7.2-1 Unrestricted Area Boundary O
O 7.2-11
e e bx%mecA kt 3 o? @ bS BRAIDWOOD REVISION 1]
,y AUGUST 1986
)
'V TABLE 7.2-1 .
AQUATIC ENVIRONMENT DOSE PARAMETERS PARAMETERS BRAIDWOOD j U", water usage, liters /hr 0.042 U I , fish consumption, kg/hr 2.4 x 10~3 1/M", 1/M I 1 F", ft /sec 3
1.37 x 10 4 F I , ft 3 /sec 3.9 x 10 3
I t , hr* 24 t", hr** 120 l I
E g Regulatory Guide 1.109, Revision 1, October 1977, Table A-1, Column 2 for freshwater fish. See Table 7.1-12.
F t , ft 3 /sec 5 w
Fo, ft 3/sec IIN o Not Applicable. No outdoor tanks without overflow pipes connected ,
t"o' he to other storage tanks. !
V t , 9,1 t , hr o
s !
i f
- t (hr) = 24 hr (all stations) for the fish ingestion pathway
- t" (hr) = 120 hr (distance to Peoria is 120 river milear flow rate of 1 mph assumed) ;
q 7.2-1 l
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i k 07 h M BRAIDWOCJ REVISION 11 l ( m ,)
'y AUGUST 1986 l
l TABLE 7.2-2 ANNUAL DESIGN OBJECTIVES SET BY 10 CFR 50, APPENDIX I, FOR EACH REACTOR TYPE OF DOSE ANNUAL LIMIT Airborne Releases Gamma Air Dose 10 mrad
< Beta Air Dose 20 mrad l
Whole Body Dose 5 mrem Skin Dose 15 mrem Inf ant Thyroid Dose 15 mrem Liquid Releases Whole Body Dose 3 mrem Thyroid Dose 10 mrem Bone Dose 10 mrem Skin Dose 10 mrem l
O 7.2-2 l
l
%%mA he % @%is BRAIDWOOD REVISION 11 .
/'~'N AUGUST 1986 e
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TABLE 7.2-3 ,
STATION CHARACTERISTICS -
- <- . a STATION: Braidwood ,
LOCATION: Braceville, Illinois ,
CHARACTERISTICS OF ELEVATED RELEASE POINT
- 1) Release Height = NA m 2) Diameter = NA m ~f. ,
-1 KCal s
- 3) Exit Speed = NA ms 4) Heat Content NA ,
'/
, jt
. /-
~,
CHARACTERISTICS OF VENT STACK RELEASE POINT l
- 1) Release Height = 60.96 m 2) Diameyer = 2.8 m
- 3) Exit Speed = 15.34 ms"I -
i n ,
l CHARACTERISTICS OF GROUND LEVEL RELEASE
- 1) Release Height a O m j
j
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7
- 2) Building Factor (D) = 60.6 m ,
METEOROLOGICAL DATA ,
[ , ,
A 320 ft Tower it. Lor.ated 573 m NE of vont st.ac' release point Tower Data Used in Calculations Wind Speed and Differential Release Point Direction Tempersture Elevated (NA) (NA)
Vent 203 ft 199 - 30 ft Ground 34 ft 199 - 30 ft 7.2-3
jl Darwh j Q N b? La LC 1
, , BRAIDWOOD REVISION 11 0 ,
,g AUGUST 1986
, TABLE 7. 2-4
~ ,
CRITICAL RANGES
,+
SITE NEAREST NEAREST DAIRY FARM BOUNDARY
- RESIDENT ** RANGE ***
DIRECTION ' '
(m) (m) (m)
N 610 805 ----
NNE 914 1126 ----
NE 792 1931 ----
4 ENE 701 1770 ----
n i E 1036 1126 3540 i .*
i ,
ESE 2713 3540 ----
l
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j' j' DE 3414 4506 ----
e SSE 3444 5150 ----
j ., S 4633 6276 ----
) SSW 975 1448 ----
J
! SW 625 1126 ----
ik WSW 533 644 ----
l l W 518 518 ----
l WNW 503 644 ----
- ~ '
NW 495 495 7723 l l
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j",,, '
j NNW 510 644 ----
[j*. ,/
j
- Environmental Report Table 2.1-1.
l j ** Nearest 7:esident Census 1985, Teledyne Isotopes.
[ ***Within 5 miles, Milch Animal Census 1985, Teledyne Isotopes.
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BRAIDWOOD REVISION 11 i Le <
AUGUST 1986 2
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- i TABLE 7.2-5 ,
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s ih TERRAIN CORRECTION FACTORS (h g )*
M 'y (ht = 0 to, Stated Range, Then h t = Given Value) r.
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E y
RANGE t DIRECTION (miles) (meters)
N ---
0.0 j NNE ---
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+ NE ---
0.0 4
m , s i
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0.0 ESE, ---
0.0
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0.0 +
- (
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0.0 SW ---
0.0 4 JWSW ---
0.0 4
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0.0 NW ---
0.0 i NNW ---
0.0 l *Within 10 mffdi~""""
7.2-5
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- V V TABLE 7.2-6 X/O AND D/O max!MA AT OR BEYONO THE UNRESTRICTED AREA BOUNDARY DOWNWINO ELEVATED (STACK) RELEASE MIXED MODE (VENT) RELEASE GROUND LEVEL RELEASE DIRECTION RADIUS X/O RADIUS D/O RA01US X/Q D/O RADIUS A/O D/0 (METERS) (SEC/M**3) (METERS) (t/M**2) (METERS) (SEC/M**3) (1/M**2) (METERS) (SEC/M**3) (t/M**2)
N 2600. 4.135-08 690. 1.704-09 610. 8.466-07 8.946-09 610. 5.379-06 3.189-08 NNE 2600. 4.915-08 914 1.509-09 914 4.964-07 5.138-09 914. 3.163-06 1.735-08 Os
-J NE 2414.
2200.
4.159-08 3.378-08 792.
701.
f.638-09 1.564-09 792.
701.
4.082-07 4.912-07 4.091-09 3.680-09 792.
701.
2.759-06 3.308-06 1.475-08 1.508-08 g
ENE
[3 E 2414. 3.826-08 1036. 1.082-09 1036. 2.264-07 2.022-09 1036. f.683-06 7.303-09 (j g ESE 2713. 4.041-08 2713. 5.635-10 2713. 8.574-08 7.347-10 2713. 4.138-07 1.633-09 sq 04 SE 3414. 3.701-08 3414. 4.399-10 3414 6.476-08 5.011-10 3414, 2.985-07 1.026-09 O SSE 3444. 3.365-08 3444 3.785-10 3444. 5.683-08 4.527-10 3444, 2.333-07 9.046-10 E) 1.683-10 4633. 3.427-08 2.064-10 4633, 1.425-07 4.831-10 U S 4633. 2.256-08 4633.
SSW 2414. 2.892-08 975. 8.258-10 975. 1.428-07 1.631-09 975. 1.306-06 6.640 09 SW 2200. 3.283-08 625. 1.165-09 625. 2.793-07 2.756-09 625. 2.912-06 1.353-08 WSW 2600. 2.740-08 533. 7.904-10 533. 6.313-07 2.410-09 533. 5.595-06 f.647-08 4
W 2800. 2.502-08 518. 8.004-10 518. 1.191-06 2.934-09 518. 7.215-06 1.644-08 WNW 503. 2.126-08 503. 8.989-10 503. 1.084-06 3.224-09 503. 6.729-06 1.646-08 NW 495. 2.805-08 500. 1.420-09 495. 7.774-07 4.250-09 495. 6.804-06 2.426 08 NNW 2600. 2.798-08 510. 9.909-10 510. 6.755-07 5.129-09 510. 5.762-06 2.654-08 BRAIDWOOD SITE METEOROLOGICAL DATA t/74 - 12/76
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n W %m6th Mi, of M 46 BRAIDWOOD REVISION 11 AUGUST 1986 TABLE 7.2-6 (Cont'd)
BRAIDWOOD 1&2 AVERAGE WIND SPEEDS FOR EACH RELEASE MODE DOWNWIND AVERAGE WIND SPEED ~ (m/sec)
DIRECTION ELEVATED MIXED MODE GROUND LEVEL N 7.2 6.7 5.0 NNE 7.5 6.9 4.8 NE 6.9 6.5 4.3 ENE 6.4 5.9 3.9 E 6.1 5.7 3.9 ESE 6.4 5.9 4.1 SE 6.3 5.7 3.9 SSE 6.0 5.6 4.0 S 5.7 5.3 3.9 SSW 5.7 5.5 4.0 SW 5.7 5.3 3.6 WSW 4.8 4.4 2.4 W 4.9 4.4 2.0 WNW 5.8 5.1 2.4 NW 6.1 5.5 3.1 NNW 6.4 5.9 3.9 O
7.2-7
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TABLE 7.2-8 BRAIDWOOO 182 MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR MR 83M DOWNWIND RESTRICTED ELEVATED (STACK) RELEASE MINED MODE (VENT) RELEASE GROUND LEVEL RELEASE DIRECTION AREA BOUND RADIUS S SBAR RADIUS V VBAR RADIUS G GBAR (METERS) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UC1/SEC) (METERS) (MRAD /YR)/(UCI/SEC)
N 610. 610. 5.545-06 5.007-07 610. 9.808-05 8.857-06 610. 5.949-04 5.372-05 D3
,3 NNE 914. 914 6.023-06 5.439-07 914. 5.775-05 5.215-06 914 3.492-04 3.153-05 g3
. NE 792. 792. 5.479-06 4.948-07 792 4.710-05 4.253-06 792. 3.077-04 2.778-05 g, bJ ENE 701. 701. 4.667-06 4.214-07 701. 5.319-05 4.803-06 70t. 3.572-04 3.225-05 ty 8 E 1036. 1036. 4.534-06 4.094-07 1036, 2.606-05 2.353-06 8036. f.829-04 1.651-05 sg NO 2713. 4.096-06 3.699-07 2713. 8.457-06 7.636-07 2713. 3.873-05 3.497-06 C)
ESE 2713.
SE 3414. 3414, 3.645-06 3.299-07 3414. 6.068-06 5.479-07 3414 2.545-05 2.298-06 C) 3444. 3444. 3.274-06 2.957-07 3444. 5.352-06 4.833-07 3444 2.038-05 1.840-06 U
SSE S 4633. 4633. 2.154-06 1.945-07 4633. 3.132-06 2.828-07 4633. 1.130-05 1.028-06 SSW 975. 975. 3.180-06 2.872-07 975. 1.716-05 1.550-06 975. 1.435-04 1.296-05 SW 625. 625. 3.989-06 3.602-07 625. 3.339-05 3.015-06 625. 3.253-04 2.937-05 WSW 533. 533. 3.379-06 3.052-07 533. 6.705-05 6.055-06 533. 6.140-04 5.544-05 W 518, 518. 3.506-06 3.166-07 518. 1.163-04 1.050-05 518. 7.414-04 6.695-05 WNW 503. 503. 3.698-06 3.339-07 503. 1.044-04 9.424-06 503, 6.777-04 6.120-05 NW 495. 495. 4.847-06 4.377-07 495. 7.981-05 7.206-06 495. 7.036-04 6.353-05 NNW 510. 510. 3.993-06 3.606-07 510. 7.439-05 6.717-06 510. 6.206-04 5.604-05 BRAIDWOOD SITE METEOROLOGICAL DATA 1/74 - 12/76 38 W C: to O<
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TABLE 7.2-8 (Cont'd)
BRAIDWOOD 182 MAXIMUM OFFSITE FINITE Pt.UME GAMMA DOSE FACTORS FOR KR 85M DOWNWINO RESTRICTED ELEVATED (STACK) RELEASE MIXED MODE (VENT) RELEASE GROUND LEVEL RELEASE DIRECTION AREA BOUND RADIUS S SBAR RADIUS V VBAR RADIUS G GBAR (METERS) (METERS) (MRAD /YR)/(UCl/SEC) (METERS) (MRAD /VR)/(UCl/SEC) (METERS) (MRAD /YR)/(UCI/SEC) 2.865-03 1.465-03 U2 N 610. 610. 3.301-04 1.760-04 610. 7.270-04 3.778-04 610.
-J NNE 914 914 2.626-04 1.398-04 1.385-04 914 792.
4.993-04 4.436-04 2.605-04 2.319-04 914 792.
f.P49-03 1.616-03 9.486-04 8.289-04 ff pq
. NE 792. 792. 2.599-04 bJ ENE 701. 701. 2.400-04 1.279-04 700 4.471-04 2.331-04 701. l.784-03 9.130-04 t3 1036, 2.855-04 1.497-04 1036. 1.032-03 5.309-04 3C 8
1036. 1036. 1.876-04 9.986-05 E
ESE 2713, 2713. 7.469-05 3.948-05 2713. 1.021-04 5.359-05 2713. 3.000-04 1.556-04 fj SE 3414, 3414. 6.323-05 3.340-05 3414 7.965-05 4.186-05 3414 2.161-04 1.122-04 ty SSE 3444, 3444 5.453-05 2.879-05 3444 6.997-05 3.678-05 3444 f.732-04 9.000-05 5 4633. 4633. 3.242-05 1.708-05 4633. 4,068-05 2.137-05 4633. 1.069-04 5.523-05 SSW 975. 975, f.406-04 7.487-05 975. 2.115-04 1.112-04 975. 8.406-04 4.329-04 SW 625. 625, 2.249-04 1.199-04 625. 3.625-04 1.901-04 C25. 1.681-03 8.620-04 WSW 533. 533. 2.449-04 1.307-04 533. 5.289-04 2.752-04 533. 2.963-03 1.514-03' W 518, 518, 2.617-04 1.396-04 5fB. 7.388-04 3.818-04 518. 3.409-03 1.738-03 WNW 503. 503. 2.318-04 1.236-04 503. 6.420-04 3.315-04 503. 3.046-03 1.551-03 NW 495. 495. 2.833-04 1.510-04 495. 5.916-04 3.074-04 495. 3.232-03 1.648-03 NNW 510. 510. 2.765-04 1.475-04 510. 5.686-04 2.957-04 510, 2.896-03 1.478-03 BRAIDWOOD SITE METEOROLOGICAL DATA 1/74 - 12/76 ((,
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BRAIDWOOO 182 MAXIMUM OFFSITE FINITE PLUME CAMMA OOSE FACTORS FOR KR 85 00WNWIND RESTRICTED ELEVATED (STACK) RELEASE MIXED MODE (VENT ) RELE ASE GROUND LEVEL RELEASE DIRECTION AREA BOUNO RADIUS S SBAR RADIUS V VBAR RADIUS G GBAR (METERS) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /vR)/(UCI/SEC)
N 610. 610. 4.122-06 2.551-OG 610. 8.328-06 5.855-06 610. 3.107-05 1.923-05 00 NNE 914, 914. 3.260-06 2.018-06 914 5.784-06 3,581-06 914. 2.028-05 1.255-05 DO
. NE 792. 792. 3.231-06 2.000-0G 792. 5.193-06 3.215-06 792. 1.772-05 1.097-05 fl h3 ENE 701. 701. 3.000-06 f.857-06 701. 5.220-06 3.231-06 701. 1.950-05 f.207-05 ty I E 1036. 1036. 2.349-06 f.454-06 1036 3.405-06 2.108-06 1016. 1.147-05 7.097-06 3C
>" ESE 2713. 2713. 9.427-07 5.836-07 2713. 1.263-06 7.815-07 2713. 3.581-06 2.217-06 O
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SE 3414 3414 8.094-07 5.0f0-07 3414 1.010-06 6.253-07 3414. 2.669-06 1.652-06 3
4 SSE 3444, 3444 6.972-07 4.316-07 3444 8.836-07 5.469-07 3444. 2.119-06 1.312-06 S 4633. 4G33. 4.281-07 2.650-07 4633. 5.313-07 3.289-07 4633. 1.359-06 8.414-07 SSW 975. 975. 1.773-06 1.097-06 975. 2.539-06 f.572-06 975. 9.316-06 5.767-06 SW 625. 625. 2.832-06 1.753-06 625. 4.310-06 2.668-06 625. 1.839-05 1.f38-05 WSW 533. 533, 3.104-06 1.921-06 533. 6.1R6-06 3.829-06 533. 3.230-05 1.999-05 W 518. 518. 3.319-06 2.055-06 518, 8.503-06 5.263-06 518. 3.717-05 2.301-05 WNW 503. 503. 2.926-06 1.811-06 503. 7.355-06 4.553-06 503. 3.315-05 2.052-05 NW 495. 495. 3.563-06 2.205-06 495. 6.855-06 4.243-06 495. 3.507-05 2.171-05 NNW 510. 510. 3.483-06 2.156-06 510, 6.581-06 4.074-06 510. 3.135-05 1.941-05 t
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BRAIDWOOD 152 MAXIMUM OFFSITE FINITE PLUME CAMMA DOSE FACTORS FOR NR 89 DOWNWIND RESTRICTED ELEVATED (STACK) RELEASE MINED MODE (VENT) RELEASE GQDUND L E VE L RE L E AS E DIRECTION AREA BOUND RADIUS S SRAR RADIUS V VBAR RADIUS G GBAR (MFTERS) (METERS) (MRAD /vR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCf/SEC) (METERS) ( MRAD /YR )/(UC f /SEC )
I N 610. 610. f.801-03 1.324-03 610. 3.030-03 2.216-03 610. 7.629-03 5.553-03 up ha NNE 914. 914 1.213-03 8.917-04 914. 1.711-03 1.252-03 914. 3.483-03 2.536-03 I NE 792. 792. 1.248-03 9.172-04 792. 1.602-03 1.173-03. 792. 3.173-03 2.310-03
$[ ENE 701. 701. 1.165-03 8.569-04 701. 1.522-03 1.115-03 709. 3.532-03 2.571-03 hj E 1036. 1036. 6.776-04 4.981-04 1036. 7.553-04 5.538-04 1036. 1.240-03 9.032-04 3C ESE 2713. 2713. 9.987-05 7.327-05 2713. 9.816-05 7.238-05 2713. 9.245-05 6.746-05 C)
SE 3414. 3414 5.285-05 3.877-05 3414. 4.369-05 3.423-05 3414. 3.535-05 2.581-05 C)
C3 SSE 3444. 3444. 4.156-05 3.049-05 3444 4.117-05 3.018-05 3444. 3.131-05 2.286 05 5 4633. 4633. 1.169-05 8.572-06 4633. 1.134-05 8.311-06 4633. 8.376-06 6.119-06 SSW 975. 975. 4.856-04 3.570-04 975. 6.015-04 4.410-04 975. 1.163-03 8.472-04 SW 625. 625. 1.045-03 7.687-04 625. 1.325-03 9.717-04 625. 3.091-03 2.250-03 WSW 533. 533. 1.232-03 9.071-04 533. 1.613-03 1.183-03 533. 4.318-03 3.143-03 W 518. 518, 1.310-03 9.646-04 518. 1.793-03 1.315-03 518. 4.449-03 3.238-03 WNW 503. 503. 1.224-03 9.006-04 503. 1.782-03 f.306-03 503, 4.731-03 3.443-03 NW 495. 495. 1.594-03 1.172-03 495. 2.281-03 1.671-03 495. 6.909-03 5.029-03 NNW 510. 510. 1.514-03 1.114-03 510. 2.328-03 1.705-03 510. 7.172-03 5.220-03 BRAIDWOOD SITE METEDROLOGICAL DATA 1/74 - 12/76 3 l
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TABLE 7.2-8 (Cont'd) 8RAIDWOOD 182 MAxlMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR XE13tM DOWNWIND RESTRIC7ED ELEVATED (STACK) RELEASE MIXED MODE (VENT) RELEASE GROUND LEVEL RELEASE OIRECTION AREA 8OUND RADIUS S SBAR RADIUS V VBAR RADIUS G GBAR (METERS) (METERS) (MRAD /VR)/(UC1/SEC) (METERS) (MRAD /YR)/(UCI/SEC) (METER $) (MRAD /YR)/(UCI/SEC)
N 610. 610. 1.136-05 4.142-06 610. 9.314-05 1.508-05 610. 5.377-04 7.448-05 05 NNE 914 914 1.036-05 3.418-06 914. 5.708-05 9.779-06 914. 3.254-04 4.633-05
'3 NE 792. 792. 9.857-06 3.347-06 792. 4.733-05 8.391-06 792. 2.850-04 4.051-05 ENE 701. 701. 8.783-06 3.062-06 701, 5.248-05 8.878-06 709, 3.281-04 4.587-05 k$
[a E 1036. 1036. 7.631-06 2.471-06 1036. 2.765-05 5.177-06 1036. 1.759-04 2.546-05 3 2713. 5.030-06 1.172-06 2713. 9.785-06 1.871-06 2713. 4.387-05 6.925-06 C)
Ed ESE 2713. O C' SE 3414. 3414. 4.501-06 1.024-06 3414 7.387-06 1.454-06 3414. 3.137-05 5.038-06 SSE 3444 3444 4.001-06 8.923-07 3444, 6.420-06 1.266-06 3444, 2.449-05 3.961-06 S 4633. 4633. 2.653-06 S.605-07 4633. 3.875-06 7.563-07 4633. 1.494-05 2.463-06 SSW 975. 975. 5.540-06 1.838-06 975, 1.849-05 3.657-06 975. 1.378-04 2.024-05 SW 625. 625. 7.941-06 2.847-06 625, 3.455-05 6.496-06 625. 3.008-04 4.252-05 WSW 533. 533. 7.877-06 3.029-06 533. 6.583-05 f.084-05 533. 5.637-04 7.788-05 W 518. 518. 8.334-06 3.230-06 518. 1.107-04 1.680-05 518, 6.788-04 9.220-05 WNW 503. 503, 7.841-06 2.891-06 503. 9.831-05 1.476-05 503. 6.154-04 8.316-05 NW 495. 495. 9.813-06 3.559-06 495. 7.632-05 1.233-05 495. 6.350-04 8.656-05 NNW 510. 510. 9.018-06 3.427-06 510. 7.112-05 1.165-05 510, 5.587-04 7.661-05 BRAIDWOOD SITE METEOROLOGICAL DATA 1/74 - 12/76 ff o <:
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BRAIDWOOD 142 MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR net 33M DOWNWIND RESTRICTED ELEVATED (STACK) RELEASE MIXED MOOE(VENT) RELEASE- GROUND LEVEL RELEASE DIRECTION AREA BOUND RADIUS S SBAR RADIUS V VBAR RADIUS G GBAR (METERS) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) ( MR AD/YR )/(UC I / SF C )
N 610. 610, 5.117-05 2.536-05 610. 1.811-04 6.075-05 610. 8.861-04 2.525-04 03 NNE 914 914. 4.212-05 2.032-05 914. 1.177-04 4.140-05 914. 5.517-04 1.624 S4 y
%J NE 792. 792. 4.128-05 2.00R-05 792. 1.012-04 3.652-05 792. 4.824-04 1.418-04 7 ha ENE 701. 701. 3.778-05 1.851-05 700. 1.068-04 3.717-05 701, 5.458-04 1.573-04 (j t E 1036. 1036. 3.042-05 1.460-05 1036. 6.253-05 2.347-05 1036. 3.032-04 9.102-05 s; Fd ESE 2713 2713. 1.427-05 6.056-06 2713. 2.257-05 8.593-06 2713, 8.258-05 2.707-05 Q
'3 SE 3414. 3414. 1.244-05 5.220-06 3414. 1.754-05 6.799-06 3414. 6.000-05 1.999-05 'U 1.583-05 C3 SSE 3444, 3444 1.084-05 4.502-06 3444. 1.528-05 5.933-06 3444. 4.723-05 S 4633. 4633. 6.783-06 2.739-06 4633. 9.113-06 3.513-06 4633. 2.931-05 9.992-06 SSW 975. 975. 2.264-05 1.094-05 975. 4.428-05 1.721-05 975. 2.413-04 7.358-05 SW 625, 625. 3.514-05 1.734-05 625. 7.853-05 2.956-05 625. 5.062-04 f.478-04 WSW 533. 533. 3.745-05 1.880-05 533. 1.301-04 4.429-05 533. 9.259-04 2.630-04 W 518. 518. 3.994-05 2.009-05 518. 2.008-04 6.333-05 518. 1.095-03 3.048-04 WNW 503. 503. 3.582-05 1.7R2-05 503. 1.764-04 5.508-05 503. 9.874-04 2.726-04 NW 495. 495 4.396-05 2.176-05 495. 1.480-04 4.953-05 495. 1.029-03 2.872-04 NNW 510. 510, 4.237-05 2.122-05 510. 1.399-04 4.741-05 510. 9.108-04 2.562-04 BRAIDWOOD SITE METEOROLOGICAL DATA 1/74 - 12/76 3' W c: M ,-
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BRAIDWOOD 1&2 MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR XE133 DOWNWIND RESTRICTED ELEVATED (STACK) RELEASE MIXEG MODE (VENT) RELEASE GROUND LEVEL RELEASE DIRECTION AREA BOUND RADIUS 5 SBAR RADIUS V VBAR RADIUS G GBAR (METERS) (METERS) (MRAD /VR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) 1.976-04 5.995-05 610. 9.703-04 2.684-04 DD
-J N 610. 610. 5.550-05 2.163-05 610.
NNE 914. 914 4.624-05 1.771-05 914 1.298-04 4.063-05 914 6.100-04 1.726-04
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g NE 792. 792. 4.495-05 1.730-05 792. 1.109-04 3.529-05 792. 5.336-04 1.508-04 pq Fa ENE 701. 701. 4.076-05 1.575-05 701. 1.160-04 3.594-05 701. 5.998-04 1.672-04 ty 03 E 1036. 1036. 3.279-05 1.249-05 1036. 6.847-05 2.226-05 1036. 3.378-04 9.689-05 3C ESE 2713. 2713. 1.542-05 5.409-06 2713. 2.495-05 8.197-06 2713. 9.390-05 2.849-05
[]
SE 3414. 3414. 1.344-05 4.678-06 3414 1.934-05 6.424-06 3414. 6.847-05 2.098-05 ty SSE 3444 3444. 1.173-05 4.058-06 3444. 1.685-05' 5.600-06 3444 5.388-05 1.656-05 5 4633. 4633. 7.438-06 2.532-06 4633. 1.011-05 3.352-06 4633. 3.353-05 1.041-05 SSW 975. 975. 2.425-05 9.277-06 975. 4.840-05 1.608-05 975. 2.700-04 7.829-05 SW 625. 625. 3.756-05 f.458-05 625. 8.548-05 2.780-05 625. 5.590-04 1.574-04 WSW 533. 533. 3.978-05 1.563-05 533. 1.403-04 4.276-05 533. 1.013-03 2.794-04 W 518. 518, 4.240-05 1.668-05 518. 2.154-04 6.256-05 518. 1.189-03 3.230-04 WNW 503. 503. 3.840-05 1.499-05 503. 1.892-04 5.461-05 503. 1.068-03 2.886-04 NW 495. 495. 4.728-05 f.840-05 495. 1.595-04 4.812-05 495. 1.117-03 3.041-04 NNW 510. 510. 4.555-05 1.787-05 510. 1.514-04 4.607-05 510. 9.919-04 2.717-04 BRAIDWOOD SITE METEOROLOGICAL DATA t/74 - 12/76 j h!
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T TABLE 7.2-8 (Cont'd) 8RAIOwo00 182 MAXIMUM OFFSITE FINITE PLUME GAsesA DOSE FACTORS FDR XE135M DOWNWIND RESTRICTED ELEVATED (ST ACM) RELE ASE MIXED MODE (VENT) RELEASE GROUND LEVEL RELEASE DIRECTIDN AREA SOUND RADIUS 5 584R RADIUS V V8AR RADIUS G GBAR (METERS) (WETERS) (MRAD /VR)/(UC1/SEC) (METERS) (MRAD /VR)/(UCl/SEC) (METERS) ( MR AD/YR )/( UCl /SE C )
N 610. 610, 6.991-04 4.322-04 610. 1.375-03 8.423-04 610. 4.701-03 2.861-03 g3
,a NNE 914 914. 5.287-04 3.267-04 914. 8.919-04 5.474-04 914. 2.712-03 1.653-03 y 792. 5.287-04 3.268-04 792. 8.073-04 4.960-04 792. 2.431-03 1.482-03 7 NE 792.
hJ ENE 701. 701. 4.931-04 3.048-04 701, 7.997-04 4.908-04 701. 2.713-03 f.653-03 (j l E 1036. 1036, 3.534-04 2.184-04 1036. 4.708-04 2.896-04 1036. 1.311-03 7.998-04 g (y ESE 2713. 27t3. 1.086-Os 6.697-05 2713, 1.251-04 7.700-05 2713. 2.234-04 1.369-04 C) 4*14, 3414 7.782-05 4.794-05 3414 8.197-05 5.044-05 3414. 1.220-04 7.477-05 C)
SE C2 SSE 3444 3444 6.701 05 4.128-05 3444 7.543-05 4.642-05 3444 1.099-04 6.736-05 5 4633. 4633. 3.299 05 2.032-05 4633. 3.665-05 2.255-05 4633. 5.143-05 3.154-05 SSW 975. 975. 2.610-04 f.613-04 975. 3.605-04 2.218-04 975. 1.107-03 6.756-04 Sw 625. 625, 4.560-04 2.819-04 625. 6.672-04 4.103-04 625. 2.504-03 1.526-03 WSW 533. 533. 5.140-04 3.178-04 533. 9.205-04 5.649 533. 4.294-03 2.614-03 w 518. 518. 5.471-04 3.383-04 518. 1.207-03 7.386-04 518. 4.872-03 2.963-03 WNW 503. 503. 4.890-04 3.024-04 503. 1.084-03 6.634-04 503. 4.506-03 2.739-03 NW 495. 495. 6.088-04 3,764-04 495. 1.103-03 6.761-04 495. 5.907-03 3.806-03 NNW 510. 510. 5.887-04 3.640-04 510. 1,078-03 6.607-04 510. 4.711-03 2.866-03 BRAIDWOOO SITE METEOROLOGICAL DATA t/74 - 17/76 lO -
o <:
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TABLE 7.2-8 (Cont'd)
BRAIDWOOO 162 MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR XE135 DOWNWIND RESTRICTED ELEVATED (STACK) RELEASE MIXED MODE (VENT) RELEASE GRDUND LEVEL RELEASE DIRECTION AREA BOUND PADIUS S SBAR RADIUS V VBAR RADIUS G GBAR '
(METERS) (METERS) iMRAD/VR)/(UCt/SEC) (METERS) (MRAD /VR)/(UCl/SEC) (METERS) (MRAD /YR)/(UCI/SEC)
N 610. 610. 4.612-04 2.494-04 610, 9.884-04 5.313-04 610. 3.836-03 2.054-03 05 NNE 914. 914 3.668-04 1.983-04 994. 6.831-04 3.675-04 914. 2.494-03 1.337-03 g3
-J 2.178-03 f.167-03
. NE 792. 792. 3.632-04 f.963-04 792. 6.083-04 3.275 04 792. p4 kJ ENE 701. 701. 3.355-04 1.814-04 701. 6.117-04 3.291-04 701. 2.397-03 1.284-03 ty I E 1036. 1036. 2.627-04 1.420-04 1036, 3.944-04 2.125-04 1036, t.403-03 7.520-04 3C ESE 2713. 2713. 1.050-04 5.665-05 27t3. 1.433-04 7.723-05 2713. 4.225-04 2.269-04.
{}
$$ 3414 8.954-05 4.832-05 3414 1.131-04 6.097-05 3414 3.096-04 f.664-04 SE 3414. E#
SSE 3444. 3444 7.791-05 4.161-05 3444. 9.905-05 5.338-05 3444. 2.469-04 1.327-04 S 4633. 4633. 4.625-05 2.495-05 4633, 5.816-05 3.135-05 4633. 1.544-04 8.300-05 SSW 975. 975. 1.972-04 1.066-04 975. 2.926-04 f.577-04 975. 1.142-03 6.126-04 SW 625. 625, 3.148-04 f.702-04 625. 4.990-04 2.688-04 625. 2.264-03 1.213-03 WSW 533. 533. 3.430-04 1.855-04 533. 7.231-04 3.888-04 533. 3.979-03 2.130-03 W 518. 518. 3.666-04 1.983-04 518. 1.004-03 5.391-04 518. 4.570-03 2.446-03 WNW 503. 503. 3.243-04 f.754-04 503 8.707-04 4.674-04 503. 4.076-03 2.188-03 NW 495. 495. 3.959-04 2.141-04 495. 8.055-04 4.330-04 495. 4.322-03 2.313-03 NNW 510. 510. 3.868 04 2.092-04 510. 7.744-04 4.164-04 510. 3.871-03 2.072-03 BRAIDWOOO SITE METEOROLOGICAL DATA 1/74 - 12/76 ff O< -
c: M MM 63 H c O (It HZ e
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TABLE 7.2-8 (Cont'd)
BRAIDWODO 182 MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR net 37 DOWNWIND RESTRICTED ELEVATED (STACK) RELEASE MIXED MODE (VENT) RELEASE GROUND LEVEL RELEASE SBAR RADIUS V VBAR RADIUS G GBAR DIRECTIDN AREA BOUND RADIUS S (METERS) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCl/SEC) (METERS) (MRAD /YR)/(UCI/SEC)
N 610. 610. 2.454-04 1.586-04 610. 4.396-04 2.833-04 610. 1.206-03 7.751-04 03 NNE 914, 914. 1.697-04 1.097-04 914 2.538-04 1.636-04 914 792.
5.728-04 5.215-04 3.682-04 3.352-04 g
J NE 792. 792. 1.729-04 1.118-04 792. 2.341-04 1.510-04 p4 7 2.235-04 1.442-04 701, 5.811-04 3.735-04 og ENE 701. 701, t.612-04 1.043-04 701. ty i E 1036, 1036. 9.786-05 6.326-05 1036. 1.138-04 7.345-05 1036, 2.131-04 f.370-04 2C 2713. 1.736-05 f.120-05 2713. 1.852-05 f.192-05 C)
NJ ESE 2713. 2713. 1.704-05 1.100-05 C)
F" SE 3414. 3414. 9.528-06 6.150-06 3414 8.G95-06 5.610-06 3414, 7.554-06 4.864-06 SSE 3444, 3444. 7.620-06 4.919-06 3444. 7.743-06 4.996-06 3444. 6.720-06 4.326-06 S 4633. 4633. 2.393-06 1.545-06 4633, 2.380-06 f.535-06 4633. 1.977-06 f.274-06 SSW 975. 975. 7.017-05 4.537-05 975. 9.021-05 5.822-05 975. 1.957-04 1.258-04 SW 625. 625. 1.445-04 9.346-05 625. 1.916-04 1.237-04 625. 5.100-04 3.278-04 WSW 533. 533. 1.688-04 1.092-04 533. 2.367-04 1.528-04 533. 7.486-04 4.811-04 W 518. 518. 1.794-04 1.161-04 518. 2.718-04 1.754-04 518. 7.895-04 5.074-04 WNW 503. 503. 1.665-04 1.077-04 503. 2.674-04 1.724-04 503. 8.557-04 5.242-04 NW 495. 495. 2.156-04 1.394-04 495. 3.305-04 2.132-04 495. f.133-03 7.283-04 NNW 510. 510. 2.052-04 1.327-04 510. 3.364-04 2.169-04 510. 1.149-03 7.386-04
>n p BRAIDWOOD SITE METEOROLOGICAL DATA t/74 - 12/76 C: M ,"
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he M@@bS BRAIDWOOD REVISION 11 AUGUST 1986 ODCM TABLE OF CONTENTS FOR BRAIDWOOD SECTION 8.0 l PAGE 8.0 RADIOACTIVE EFFLUENT TREATMENT SYSTEMS, MODELS FOR SETTING GASEOUS AND LIQUID EFFLUENT MONITOR ALARM AND TRIP SETPOINTS, AND ENVIRONMENTAL RADIOLOGICAL MONITORING 8.1-1 8.1 GASEOUS RELEASES 8.1-1 8.1.1 System Design 8.1-1 8.1.1.1 Gaseous Radwaste Treatment System 8.1-1 8.2.1.2 Ventilation Exhaust Treatment System 8.1-1 4 8.1.2 Alarm and Trip Setpoints 8.1-1 8.1.3 Station Vent Stack Monitors 8.1-3 8.1.4 Containment Purge Effluent Monitors 8.1-4 8.1.5 Gas Decay Tank Monitors 8.1-5 8.1.6 Allocation of Effluents from Common Release Points 8.1-6 8.1.7 Symbols Used in Section 8.1 8.1-7
)
8.1.8 Constants Used in Section 8.1 8.1-8 8.2 LIQUID RELEASES 8.2.1 System Design 8.2-1 8.2.2' Alarm Setpoints 8.2-1 8.2-3 Liquid Radwaste Effluent Monitor 8.2-3 8.2-4 Station Blowdown Monitor 8.2-4 8.2-5 Reactor Containment Fan Cooler (RCFC) and Essential Service Water Outlet Line Monitors 8.2-5 l 8.2-6 Administrative and Procedural Controls for Radwaste Discharges 8.2-6 8.2-7 Determination of Initial Dilution Stream Flow Rates 8.2-6 8.2.8 Allocation of Effluents from Common Release Points 8.2-7 8.2.9 Symbols Used in Section 8.2 8.2-7 8.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM 8.3-1 s 8.4 ENVIRONMENTAL RADIOLOGICAL MONITORING 8.4-1 O
8-i
o k ES BRAIDWOOD REVISION 11 AUGUST 1986 O ODCM LIST OF TABLES FOR BRAIDWOOD SECTION 8.0 l NUMBER TITLE PAGE 8.4-1 Environmental Radiological Monitoring Program 8.4-2 8.4-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 8.4-8 8.4-3 Detection Capabilities for Environmental Sample Analysis 8.4-9 O
l i
O 8-li i
N%uGCt A
& @h5LES BRAIDWOOD REVISION 11 AUGUST 1986 b
i ODCM LIST OF FIGURES FOR BRAIDWOOD SECTION 8.0 l l
NUMBER TITLE i
8.1-1 Simplified HVAC and Gaseous Effluent Flow Diagram 8.2-1 Simplified Liquid Radwaste Processing Diagram 8.2-2 Simplified Liquid Effluent Flow Diagram 8.3-1 Simplified Solid Radwaste Processing Diagram 8.4-1 Fixed Air Sampling Sites and Outer Ring TLD Locations 8.4-2 Inner Ring TLD Locations 8.4-3 Ingestion and Waterborne Exposure Pathway Sample Locations l
- O i
4 J
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M CA Qk E D of b RS BRAIDWOOD REVISION 11 AUGUST 1986 V
8.0 RADIOACTIVE EFFLUENT TREATMENT SYSTEMS, MODELS FOR SETTING GASEOUS AND LIQUID EFFLUENT MONITOR ALARM AND TRIP SETPOINTS, AND ENVIRONMENTAL RADIOLOGICAL MONITORING 8.1 GASEOUS RELEASES 8.1.1 System Design 8.1.1.1 Gaseous Radwaste Treatment System A gaseous radwaste treatment system shall be any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system off gases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the g-~) environment. Refer to Figure 8.1-1 for a simplified system flow
(_) path diagram.
8.1.1.2 Ventilation Exhaust Treatment System A ventilation exhaust treatment system shall be any system designed and installed to reduce gaseous radiciodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents). Engineered Safety Feature (ESP) atmospheric cleanup systems are not considered to be ventilation exhaust treatment system components.
8.1.2 Alarm and Trip Setpoints Alarm and trip setpoints of gaseous effluent monitors at the
() principal points of release of ventilation exhaust air containing 8.1-1
I. .
%tt<xs h Of b ES BRAIDWOOD REVISION 11 AUGUST 1986
,s V radioactivity are established to ensure that the release limits of 10 CFR 20 are not exceeded. The setpoints are found by solving Equations 2.6 and 2.7 for each class of releases. l For this equation, the radioactivity mixture in the exhaust air is assumed to have the composition of gases listed in Table 3.5-7 of the Environmental Report Operating License Stage. According to Subsection 3.5.3.4 of the report, releases of radionuclides in gaseous effluents were calculated using the PWR-GALE computer program and the parameters listed in Table 3.5-5.
Equation 2.6 is rewritten using the fractional composition of l each nuclide, f 1 , and a total release rate, Ot , f r station vent stack releases (the principal point of release of ventilation exhaust air containing radioactivity):
1.11 Qtv( i
- i) 00 mrem /yr (8.1)
O f i
Fractional Radionuclide Composition The release rate of radionuclide i divided by the total release of all radionuclides.
Total Release Rate, Vent Release (pCi/sec)
Qv t The release rate for all radionuclides due to a station vent stack release.
Oly =O tv f i
(8.2)
Equation 8.1 can be solved for Qt for release limit determinations. Similarly, Equation 2.7 can be rewritten: l j (x/Q)y Q tv fi **P (~ Ai R/3600 uy ) +
1.u v, o,, <c m 00 mrem /yr (8.3) 8.1-2
-
- s bWek BRAIDWOOD
% REVISION 32os11elbs AUGUST 1986 O
V-Equation 8.3 can be solved for Qtv and a corresponding release limit can be determined. The most conservative release limit from Equations 8.1 and 8.3 will be used in selecting the appropriate alarm and trip setpoints for a vent release.
The exact settings will be selected to ensure that 10 CFR 20 limits are not exceeded.
Surveillance frequencies for gaseous effluent monitors will be as stated in Table 4.3-9 of the Technical Specifications. l Calibration methods will be consistent with the definitions found in Section 1.0 of the Technical Specifications.
8.1.3 Station Vent Stack Monitors Detectors 1RE-PR028A, B, C, D and E (particulate, low gas, iodine, high gas and background subtraction channels, respectively) and 2RE-PR028A, B, C, D and E monitor station vent stack effluent from the auxiliary building vent stacks.
The particulate detector utilizes a beta scintillator and has a range of 10-11 to 10-5 uCi/cc . The low and high gas detectors utilize beta scintillators and have ranges of 10-6 to
-2 2 10 pCi/cc and 10 to 10 Ci/cc, respectively. The iodine detector utilizes a NaI(Tl) scintillator and has a range of 10-11 to 10-5 uCi/cc .
Both vent stack effluent monitors feature automatic isokinetic sampling, automatic gaseous composite grab sampling, and tritium sampling.
f The monitor skids with associated pumps, detectors, and local j controls are located in the auxiliary building on the 477 foot elevation.
!O Each monitor system has a microprocessor (RM-80) which utilizes I digital processing techniques to analyze data and control monitor i
i 8.1-3 i
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BRAIDWOOD REVISION 11 4' AUGUST 1966 ..
(3 4 .. o V. L
?
functions. Monitor data, including current radiation levels, high radiation, alarms, and monitor operational status, are ,
displayed on a CR[ display (RM-ll) in the main control room. '
Apowersupplyunitfurnishesthepositiveandnegativevoltag(s ~
for the circuits, relays, and alarm lights and provides the high d(,
voltage for the detector. The power. supply unit is located on the monitor skids. The monitors are pove~ced by local 120-Vac instrumentation buses. x -
0
. / /
Alarm setpoint determination is addressed in Subsection.8.r.5. '
The release limits (pC1/sec) cbtained from Equ'ations 8.1 and 8.3 (r il are divided by the normal auxiliary building vent' stack # flow ,
l rates (cc/sec) to obtain the pC1/cc alaru setpiint values.
Readouts for the vent stack monitorn are in pC1/cc. The cpm' to pC1/cc conversion is accomplished by use of conversion factors Q in the radiation monitoring system software. -
(
8.1.4 Containment Purge Effluent Monitors ,
o fy Detectors 1RE-PR001A,D,andC(particulate,\gasandiodine di "
channels, respectively) and 2RE-PR001A, B, and C monitor containment purge effluent discharge to the auxiliary building vent stacks for Units 1 and 2, respectively. '
. . ~ i The particulate detector utilizes a beta scintillator and has A p , .. -l range of 10-11 to 10-5 pC1/cc. The gas detector utilizes a beta
~
scintillator and has a range of 10-6 to 10-2 uti/cc. The iodine detector utilizes a NaI(Tl) scintillator and has a range of 10-11 to 10-5 pCi/cc.
The monitor skids with associated pumps, (Ctectors, and local -
- controls are located in the auxiliary building on the 475 foot I elevation.
O 8.1-4 l i
r
- - - - - . . - . - . - _ _ , _- - , - - - _ - . _ . , _ . , . , . . - - - --_---.,,--.,____.,.,_,_--.,_.__--,m e,-,.-------,,-,- , _ _ -- y -- . _ ... . , . - - -
. - .' ' i hNtbNk
" A. s / t.Y OF h AMS BRAIDWOOD REVISION 11
,b
./ f- ( AUGUST 1986 p[f
,e Each monitor has a micrcprocessor (RM-80) which utilizes digital processing techniques to analyze data and control monitor
- functions. Monitor data, including current radiation levels, high radiation alarms, and monitor operational status, are displayed on a CRT display'(RM-11) in the main control room.
l ~
A power supply unit furnishes the positive and negative voltages for the circuits, relsys, and alarm lights and provides the high voltag'e for the detectors. The power supply unit is located on the monitor' skids. The monitors are powered by local 120-Vac
~ instrumentation buses.
'l ,
V' A containment atmosphere sample is obtained and analyzed prior to each containment purge 1elease. The isotopic analysis results of this sample are used to determine the maximum allowed containment
. purge fl'ow rate. This isotopic analysis or the containment
- b atmospheic' monitor 1(2)RE-PR0ll readings are utilized as the I [' , basis for determining the containment purge effluent monitor setpoints.
{
8.1.5 Gas Decay Tank Monitors Detectors ORE-PR002A and B (low range gas and high range gas,
.respectively) monitor the radiation level of the gas decay tank i discharge to the auxiliary building vent stacks. Detectors g i'
,' ORE-PR002A and B are interlocked with valve OGWO14.
Automatically, on a high radiation and/or instrument failure signal from the detectors, vent valve 0GW014 closes to isolate the gas dgcay tank discharge line.
. ,an-8.1-5
- t 6
s BRAIDWOOD REVISION 11 AUGUST 1986
- (-
'wJ 2 , Both the low and high range gas detectors utilize beta scintil.lators And h' ave ranges of 10-6 to 10-2 uCi/cc and 10-2 to 102 . uC1/cc, respectively.
'The monitor skid'with as'sociated pump, detectors, and local controls is located in the auxiliary building o., the 346 foot i- elevation. g Y I The monitor has a microprocessor (RM-80) which utilizes digital processing techniques'to analyze data and: control monitor functions. Monitoi data, including current radiation levels, Aigh radiation alarms, add monitor operational status, are displayed on a CRT display (RM-ll) in the main control room.
f ;
'A powerJsupply unit' furnishes the positive and negative voltages for the? circuits, relays, and alarn lights and provides the high 1
s j voltage'for theidetectors. The power supply unit is located on
' }' the monitor skid. The monitor is powered by local 120-Vac instrumentation buses, a 'i A grab.' sample,from the gas decay tank to be released is obtained and analyzed prior to each' gas decay tank discharge. The isotopic analysis results of this sample are used to determine
- the maximum allowed gas decay tank discharge line flow rate and as a basis for determining the gas decay tank monitor interlock i and high' alarm setpoints.
y '
8.1.6 Allocation of Effluents from Common Release Points l f
Radioactive gaseous effluents released from the auxiliary building, miscellaneous ventilation system, and the gas decay tanks'are comprised of contributions from both units. Under normal operating conditions, it is difficult to apportion the radioactivity between the units. Consequently, allocation will
, /~') normally be made evenly between units. l rJ
\
'8.1-6 l,
s
g g hh eab BRAIDWOOD REVISION 11 AUGUST 1986
)
,1 8.1.7 Symbols Used in Section 8.1 l SYMBOLS NAME UNIT Total Release Rate, Vent Release (uCi/sec)
Qv t Vj Gamma Whole Body Dose Constant, Vent Release (mrad /yr per pCi/sec) f i
Fractional Radionuclide Composition Ej Beta Skin Dose Constant (mrem /yr per uCi/m3)
(X/Q)y Relative Effluent Concentration, Vent Release (sec/m3 ) l 1
9 Radiological Decay Constant (hr-1)
R Downward Range (m) uy Average Wind Speed, Vent Release (m/sec)
Qy i Release Rate, Vent Release (uCi/sec) l Vi Gamma Dose Constant, Vent Release (mrad /yr per uCi/sec) l
- 8.1-7
,- . . - - . - _ . - - _ - - - - - - - - ~ . - - . . - _ _ , _ _ _ - . - . - - . . -
3
'l '
kAChME7 k i
%1h S%s '
BRAIDWOOD REVISION 11 AUGUST 1986 V
8.1.8 Constants Used in Section 8.1 l NUMERICAL VALUE NAME UNIT 1.11 Conversion Constant (mrem / mrad) 3600 Conversion Constant (sec/hr)
- o L
1 l
t O
8.1-8
W EED
@.3% 09 h Q3 REVISION 13 AUGUST 1986' Ooe One
%' y y [. y e e: :
I ' - Elev. 200 00 Z w 2 m above grade l
Containtnent Unit 1 " . ,
2RE.PR028 (Typical) '
E Ve n eoo 1RE.PR028 H Mini purge H C ...
. . . , . . . . .g. . .. qy,-e g ; g HCH Post LOCA purge ,
4, * ,, !. . . _- W} 1RE-PR001 N 0 1RE-PRG11 Containment Unit 2 F 43.900 2RE PR001 Stack 1 Stack 2 H
Fuel handimg 136.080 21.000 3 _g
____i___ l{}{ol H CH Auxiliary , g 125.490 buildmg E
Access areas y g 125.680
P----H t M E
Nonaccess areas
- CH 2
20 (only during Gas discharge) decay ORE-PR002 136.080 Nonfiltered p ,,,,____,,_____ ,
suulliary building tank vents H C H I
Fittered h auulliary building tank vents I
g 9.230 13,030 Sample rooms '
E i and leboratories H 3,800 Laundry b E d p {
t l
l BRAIDWOOD STATION FIGURE 8.1-1
'\ SIMPLIFIED HVAC AND GASE0US EFFLUENT FLOW DIAGRAM (SHEET 1 0F 2 )
CS43-1 08 359
w & tR L REVISION 11 AUGUST 1986 c neer 2.500 (During Unit 1 startup)
Q hoggir,g , ump
]
4 v-Gland steam 1400' N 1.432 condenser l F 0 l
.--- Q - -
- YI I'
Steam iet air ejector 32 l;HCCH g,,,,,,g,,,,,,,
i! TurtHne building i
i_..aceneral erea l (Elevation 451 ft)
Unit 2 2.500 (During condenser l
Unit 2 stgup) ;
hogging pump l l Stack 1 Stock 2 l
Gland steam r.,1.4001 e N 1.432 condenser V U F 0
% 32 Steam let eir elector f H
Solid redweste ,
Drumming ,, p station 3.100 Volume reduction G HC C H Legend Notes Normal or frequent flow path 1. Used intermittently to vent containment dunng normal
Occasional flow path operation.
- 2. Used only during postaccident operation.
A Containment atmosphere radiation 3. Filter untt operates only when high radiation is detected in monitor offges system effluent.
C Charcoal filter 4. All flow rates are design flow rates in cubic feet per minute.
F Refueling G Noble ses radiation monitor (ofiline)
H HEPA filter M Three-channel radiation monitor for particulate, lodine, and noble gas (offline)
N Normal operation P Porticulate monitor (offline)
R Hydrogen recombiner S Normal range eteck radiation monitor (particulate, lod 6ne, and noble gas)
W Wide-range stack noble gas radiation monitor BRAIDWOOD STATION FIGURE 8.1-1 SIMPLIFIED HVAC AND GASE0US EFFLUENT FLOW DIAGRAM (SHEET 2 0F 2 )
2 6543 2 06
.. - ~ ,-86-359
+
- bChtWE::rCtk E kD OF h g BRAIDWOOD REVISION 11 AUGUST 1986 (O
V ,
8.2 LIQUID RELEASES 8.2.1 System Design A liquid radwaste treatment system shall be a system designed and [
installed to reduce. radioactive liquid effluents by collecting the liquids, providing for retention or holdup, and providing for g treatment by demineralizer or a concentrator for the purpose of reducing the total radioactivity prior to release to the environment. Refer to Figures 8.2-1 and 8.2-2 for simplified liquid radwaste and liquid effluent flow path diagrams.
8.2.2 Alarm Setpoints Alarm setpoints of liquid effluent monitors at the principal release points are established to ensure that the limits of 10 CFR 20 are not exceeded in the unrestricted area. Prior to each 0_-
s batch release, a grab sample from the release tank is obtained and analyzed. Equation 8.4 is evaluated for the radionuclide mix identified in the grab sample isotopic analysis results to determine the maximum allowable flow rate in the liquid radwaste discharge line.
pd t
F,"a , *K (8.4)
{
i MPC
- i.
F ,rax Maximum Permissible Flow Rate, Radwaste Discharge (gpm)
The maximum flow rate permitted in liquid radwaste discharge line that meets 10 CFR 20 limits.
O V
8.2-1
WCumCQ IAg k\<>f h h 6 BRAIDWOOD REVISION 11 AUGUST 1986
% 1 Actual Flow Rate, Initial Dilution Fht Stream (gpm)
The actual flow rate of the initial dilution stream which carries the radionuclides to the unrestricted area boundary.
MPC i Maximum Permissible Concentration of Radionuclide i in the Unrestricted Area (10 CFR 20, Appendix B, Table II, Column 2) (uCi/ml)
Ci Concentration of Radionuclide i in the Release Tank (uCi/ml)
K Conservatism Constant Determined by Station Procedures for Liquid Release; K > l.0. Division by K allows station management to provide a l
margin of conservatism for liquid batch releases.
Af ter determining F[ax fr m Equation 8.4, 10 CFR 20 compliance is verified using Equations 8.5 and 8.6.
pr a max C =C 9 g (8.5) max
+F act C" = Concentration of Radionuclide i in the Unrestricted Area. (uCi/ml) 8.2-2 l
l l
.._ .- hw@ k h e D w (A h ES BRAIDWOOD REVISION 11 AUGUST 1986
- w a
)) C
<1 (8.6) i MPC 4 The alarm setpoints_for the liquid radwaste effluent monitor (ORE-PR001) are determined prior to each release and.are based on the isotopic analysis results of the release tank grab sample.
The alarm setpoints are set so that any unexpected deviations from the isotopic analysis results will result in the automatic termination of the release. Readouts for the liquid effluent monitor are in uCi/ml. The cpm to pCi/ml conversion is accomplished by use of conversion factors in the radiation monitoring system software.
4 8.2.3 Liquid Radwaste Effluent Monitor Radiation monitor ORE-PR001 monitors liquid radwaste effluent and
() is interlocked with release tank discharge valves 0WX-353 and 0WX-896, which are both interlocked with circulating waterflow valve 0FIS-CWO92.
On high radiation in the liquid radwaste effluent, the release tank discharge valve is closed automatically.
Each release tank (0WX0lT and 0WX26T) holds 30,000 gallons. Both are located in the turbine building on the 401 foot elevation.
l The monitor utilizes a NaI(Tl) detector with a range for gamma i radiation of 10-8 pCi/mi to 10-2 pCi/ml. The monitor skid and i associated features are located in the turbine building on the 401 foot elevation.
The monitor has a microprocessor (RM-80) which utilizes digital processing techniques to analyze data and control monitor
! functions. Monitor data, including current radiation levels, high radiation alarms, and monitor operational status are displayed on a CRT display (RM-ll) in the main control room.
8.2-3
PGmomEC NE D of @ MS BRAIDWOOD REVISION 11 AUGUST 1986
/]
's_/
A power supply unit furnishes the positive and negative voltages for the circuits, relays, and alarm lights and provides the high voltage for the detector. The power supply is located on the monitor skid. The monitor is powered by local 120-Vac instrumentation buses.
A discussion of alarm setpoints for ORE-PR001 is included in Subsection 8.2.2.
8.2.4 Station Blowdown Monitor
. Radiation monitor ORE-PR010 continuously monitors the circulating water blowdown for radioactivity. The monitor utilizes a NaI(Tl) detector with a range for gamma radiation of 10-8 pC1/mi to 10-2 pC1/ml.
The monitor skid and associated features are located in the turbine building on the 357 foot elevation.
O
(/ The monitor has a microprocessor (RM-80) which utilizes digital processing techniques to analyze data and control monitor functions. Monitor data, including current radiation levels, high radiation alarms, and monitor operational status are displayed on a CRT display (RM-11) in the main control room.
A power supply unit furnishes the positive and negative voltages for the circuits, relays, and alarm lights and provides high voltage for the detector. The power supply is located on the monitor skid. The monitor is powered from local 120-Vac instrumentation buses.
The alarm setpoints for the station blowdown monitor are determined prior to each release and are based on the isotopic analysis results of the release tank grab sample and the actual dilution flow rates. The alarm setpoints are set so that unexpected deviations from the isotopic analysis results or from
() the specified dilution flow rate will result in an alarm from the 8.2-4
+
- k M ktA A kAR M of b %%S BRAIDWOOD REVISION 11 AUGUST 1986
(
% ./
monitor. Between batch releases, the station blowdown monitor alert and high alarm setpoints are established at levels specified by station procedures.
8.2.5 Reactor Containment Fan Cooler (RCFC) and Essential Service Water Outlet Line Monitors Radiation monitors 1RE-PR002, 2RE-PR002, 1RE-PR003, and 2RE-PR003 monitor the RCFC and essential service water outlet lines for radioactivity. .The monitor utilizes a.NaI(Tl) detector with a range for gamma radiation of 10-8 uCi/ml to 10-2 uC1/ml. The monitor skid and associated features are located in the auxiliary building on the 401 foot elevation.
The monitor has a microprocessor (RM-80) which utilizes digital processing techniques to analyze data and control monitor
,( functions. Monitor data, including current radiation levels, high radiation alarms, and monitor operational status, are displayed on a CRT display (RM-ll) in the main control room.
A power supply unit furnishes the positive and negative voltages for the circuits, relays, and alarm lights and provides high voltage for the detector. The power supply is located on the monitor skid. The monitor is powered from local 120-Vac instrumentation buses.
Unit 1 radiation monitor high alarm setpoints are based on detector response to a mix of several radionuclides - those listed on Table 11.2-4 of FSAR which are capable of being detected by the monitor's NaI(Tl) detector. Each nuclide in the mix is at a concentration which is 10% of the MPC value given in 10 CFR 20 Appendix B, Table 2, Column 2.
O v
8.2-5
h%cwEtk E k 09 b 6 BRAIDWOOD REVISION 11 AUGUST 1986 O
8.2.6 Administrative and Procedural Controls for Radwaste l Discharges Administrative and procedural controls have been designed to ensure proper control of radioactive liquid radwaste discharge in order to preclude a release in excess of 10 CFR 20 limits. The discharge rate for each batch is calculated by radiation chemistry personnel (Equation 8.4) and then provided to operating staff personnel. All liquid radwaste discharges will be from either release tank OWX0lT or release tank OWX26T. On high radiation in the liquid radwaste effluent, the release tank discharge valve 0WX353 is closed automatically.
The proper valve lineup is performed by the operator prior to each batch discharge, per station procedures. The actual discharge is authorized by the shift engineer.
The effluent monitoring instrumentation system is equipped with alarm / trip setpoints which, if exceeded, initiate automatic valve closure on the release tank discharge line to prevent exceeding 10 CFR 20 liquid release limits.
8.2.7 Determination of Initial Dilution Stream Flow Rates l For those release paths which have installed flow monitoring instrumentation, that instrumentation will be used to determine the flow rate of the initial dilution stream. This instrumentation will be operated and maintained as prescribed by the Technical Specifications. For those release paths which do not have installed flow monitoring instrumentation, flow rates will be determined by use of appropriate engineering data such as pump curves, differential pressures, or valve position indication.
8.2-6
D CA @ k
%E kof N ES BRAIDWOOD REVISION 11 AUGUST 1986 v
8.2.8 Allocation of Effluents from Common Release Points Radioactive liquid effluents released from either release tank (OWXOlT or OWX26T) are comprised of contributions from both units. Under normal operating conditions, it is difficult to apportion the radioactivity between the units. Consequently, allocation will normally be made evenly between units.
8.2.9 Symbols Used in Section 8.2 SYMBOL NAME UNIT 8
C Concentration of Radionuclide i in the (uCi/ml)
Unrestricted Area Ci Concentration of Radionuclide i in the (uCi/ml)
Release Tank t
k_
MPCi Maximum Permissible Concentration of (uCi/ml)
Radionuclide i in the Unrestricted Area
- Maximum Permissible Flow Rate, (gpm)
F max Radwaste Discharge d Actual Flow Rate, Initial Dilution (gpm)
F act Stream K Conservatism Constant Determined by Station Procedures for Liquid Releases; K > 1.0 1
O 8.2-7
r Unli i blC400WN PRE-F ILTERS U"II '. UNii l UN:
ggp jT EN 2 2 2 OLO C30EN5ER DEWINEP gm 1 1
- l. =
1 1
1 UNIT 2 I 8 LOWDOWN 1 PRE-FILTERS ,
UNIT 2 I ';
UNIT 2 UN STE# AM A OI" BLOWOOWN : r BLOWDOWN DEWINEP g CONDENSER l i
i l
1 I
TUR8.BLOG. EQUIP, ORAIN FILTER I 1
1 tuRS.8 LOG. EQUIP. '
l ORAIN TANKS 1 I
o l TUR8.8 LOG.FLOM - -
3 DRAIN FILTER ,6 g l
TUR8.BL OG. FLOOR _
' l DRAIN TANK $ g i
1 i
l I
CHEW! CAL l ORAIN FILTER I I
CNEWICAL _
1 DRAIN TANK 1 l
i REEERAfim -
WASTE DRAIN FILTER If REEMRATION WASTE -
ORAIN TANKS Aut.8 LOG. EQUIP.
ORAIN FILTER 1P AUI.8 LOG.ECEIP. w P57 7
ORAIN TMS DEWINER d
I i Aux.8 LOG.FL0m DRAIN FILTER AUI.8 LOG.FLCID 7 ORAIN TMS RA05ASTE if _ RADWASTI
~
,g EVAPWATORS BE0 DEWlh L AUNDRY ORAIN =
FIL TE R LAUNDRT _
_, LauM)RT WASTE
$TWAE TMS DRAIN TA*
w c. nes
%%hN h41 ee (Abs ESU "9 OEu!NER ALINR AFTER FILTER
'1 TO uh!T 2 KIED-BE0 = 2 CONDENSATE LIJtts . U STORAGE TAht d
a0 x.
J1Rs - -.
""rs"A'"R F n
" ~
&0.=0
\, =~ = ass'A Ll2ERS STORAGE TAht i TO RAceASTE
f
l_ a g;g <sE!'li"fr-
= ENT. = 'os 7dg' JOE"
=
TI APERTURE CARD Also Avauable On Aperture Card LEGEND H dL - w+- FLEX 18tt HOSE RLE MAIN PROCESS PATH KINE SECONDARY PROCESS PATH U ---- INTERTIE (OCCAil@AL USEl RA09ASTE DE WihER AllHR AFTER FILTER
~T"l:0 ' _ _
"'O'#ITI BRAIDWOOD STATION
~ ~
~-
utnR ?AM7 FIGURE 8.2-1 SIMPLIFIED LIQUID RADWASTE PROCESSING DIAGRAM
$70 3l 6 6 AM9 / -
. . INTTN".W h M.
OMg " ggDE REVISION 11 AUGUST 1986 l
-- ),1*J Ab [ [ E'\{; .
Ovm . De
- 17!c, 4;**] 1 *%
O #87% P 'l c
- 1vi8 5:RE t h N3,$!
~
j A 0 ,
Baal:qar p30 ;
E55th11a; COOL th0 P0hc
- 4 l 4 i tate SCREIh Klust ;
?
i i t i l i i l
Ohlt 1 Uh:t t Lpi!T 2 Uhlt 2
,, i ,
ESSEN'lai 155Eht ia. [55t hil&L 155ENilai SERvlCE ta1E8 SERvlCE tatED SERolCE TATER SEPv!CE TATER Uhlt I Uhli 2 3 3 g i O E55[ hila; O -E55Ehtia, { { { {
5tRtlCE WaT[R SEPylC[ WaTEP Uhlt i Uh!T I Unit 2 Unit 2
- l RU C A&C R0FC SC R7CAA0 RUC SC a CMILLt# CHILLER CHILLIA CHILt[p CDCEN5l# COO (NSIp CDO[N5(A C30045[S Pe W'- h .'t O EA 8 8 EL-J EE3 gE3
%E3 E]s?
? ? E E E
- -
I o o e o
,e ,as1t o 5ch,2 ex, C ,
,,5,, m ,5, , _
~
Uh!1 i Uhli 2 (fRW flG.8.2 Il l
BR AIDWOOD ST ATION l LEGEND AN: NDIES I
fr Q "tloulC l* pa:latim.
FIGURE 8.2-2 u ,:rC.ata o Catai=w t rah C00tra O th (4:= Uhtt. Dr.1 TMt at: OF 8 0 CM!LLED E Ca.:th5tes or crtentih5 at a.t tiw. SIMPLIFIED LIQUID
- s. EFFLUENT FLOW DIAGRAM E
l a
?r_T_____ _ _ . _ _ _ _ - _ - . . - _ _ _ - . - . , _ . , _ _ _.__ - ,__. . , _ _ - - - . _ _ - , _ - . .___. _.
MckstCtk ME. h oc- h 6G BRAIDWOOD REVISION 11 AUGUST 1986 8.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM i The process control program (PCP) shall contain the sampling, analysis, and formulation determination by which solidification of radioactive wastes from liquid systems is ensured. Figure 8.3-1 is a simplified diagram of solid radwaste processing.
J d
J l
t O
1 j
!O l
l 8.3-1
(
- - ~ - - . _ _ . _ _ - . _ _ _ _ _ _ _ _ . _ . _ . _ _ _ , _ . . _ , . _ _ . _ . _ _ _ _ _ , _ _ _ . . . , _ _ _ , , , _ _ _ , , _ _ , _ _ _ _ _ _ _ , , , , , _ . . _ . . _ . - . - . _ _ _ _ _ _ _ , _ , _ .
wwkw%
S h e h e 4,4 h s REVISION 11 AUGUST 1986
~
f g
es weekly @
wS Lo mei
'] {')
\j.
% V .
TABLE 8.4-1 (Con t ' d )
TYPE AND EXPOSURE PATHWAY SAMPLING OR FREQUENCY AND/OR SAMPLE SAMPLING OR MONITORING LOCATION COLLECTION FREQUENCY OF ANALYSIS
- 2. Direct a. At Air Sampler Sites a Quarterly Gamma dose Radiation quarterly Same locations as fixed air sampling locations in Item 1.
- b. Inner Ring d Quarterly Gamma dose 101- 1, 0.6 mi N 101-2, 0.6 mi N 102-1, 1. 2 mi NNE 102-2, 1.1 mi NNE 104-1, 0.7 mi ENE 104-2, 0.7 mi ENE y 105-1, 1.5 mi E g 105-2, 1.5 mi E s 106-1, 1.7 mi ESE y a 106-2, 1.7 mi ESE O O 107-1, 2.0 mi SE O 107-2, 2.0 mi SE 108-1, 2.0 mi SSE 108-2, 2.0 mi SSE 109-1, 2.5 mi S 110-1, 1.8 mi SSW 110- 2, 1.8 mi SSW 111a-1, 1.4 mi SW 111a-2, 1.4 mi SW 111b-1, 1.1 mi SW 111b-2, 1.1 mi SW 112-1, 0.7 mi WSW 112-2, 0.7 mi WSW >N c
113a-1, 0.5 mi W ON 113a-2, 113b-1, 0.5 0.4 mi mi W
W $$O $
113b-2, 0.4 mi W $*
114-1, 0.4 mi WNW $[
114-2, 116-1, 0.4 0.4 mi mi WNW NNW p
116-2, 0.5 mi NNW
O O O .
TABLE 8.4-1 (Cont ' d)
TYPE AND EXPOSURE PATHWAY SAMPLING OR FREQUENCY AND/OR SAMPLE SAMPLING OR MONITORING LOCATION COLLECTION FREQUENCY OF ANALYSIS
208-1, 4.5 mi SSE g
. s
, 208-2, 4.5 mi SSE y i 209-1, 4.8 mt S o 210-1, 4.9 mi SSW @
210- 2, 4.9 mi SSW 211-1, 4.8 mi SW 212-1, 4.7 mi WSW 212-2, 4.7 mi WSW 213-1, 4.5 mi W 213-2, 4.5 mi W 214-1, 4.3 mi WNW 214-2, 4.3 mi WNW 215-1, 4.5 mi NW 216-1, 4.4 mi NNW 216-2, 4.4 mi NNW EE -
85 3*om
" t: f .
_ _ _ _ . _ _ _ _ _ _ _ __ .._ _ _ m _ ,4 .
O O O .
TABLE 8.4-1 (Cont' d)
TYPE AND EXPOSURE PATHWAY SAMPLING OR FREQUENCY AND/OR SAMPLE SAMPLING OR MONITORING LOCATION COLLECTION FREQUENCY OF ANALYSIS d
- 3. Waterborne
- a. Surface BD-07, Kankakee River upstream Weekly Gross beta of discharge, 5.4 mi E analysis weekly.
BD-10, Kankakee River downstream Gamma isotopic of discharge, 5.0 mi ENE on monthly composite.
Composite quarterly for tritium and Sr-89, 90 analysis.
- b. Cooling BD-08, Intake pipe at Kankakee Weekly Gross beta Water River , 5.0 mi E analysis weekly. W BD-09, Blowdown pipe at Kankakee Tritium, gamma $
m River, 5.0 mi E isotopic and y
. Sr-89, 90 analysis g e on monthly o composite. O
- c. Ground BD-13, Braidwood well, 1.7 mi NNE Weekly Gamma isotopic, gross beta, tritium and Sr-89, 90 analysis on quarterly composite,
- d. Sediment BD-07, Kankakee River upstream of Three times a year Gamma isotopic and [
from discharge, 5.4 mi E gross beta analysis M Shoreline BD-10, Kankakee River downstream of each sample. $$ d}
discharge, 5.0 mi ENE O $ LU mmo
- e. Aquatic Plants BD-07, Kankakee River discharge, 5.4 upstream of mi E Three times a year Gamma isotopic and gross beta analysis d51 g z 6'N BD-10, Kankakee River downstream of on each sample, es discharge, 5.0 mi ENE *H-k 3
TABLE 8.4-1 (Cont'd)
TYPE AND EXPOSURE PATHWAY SAMPLING OR FREQUENCY AND/OR SAMPLE SAMPLING OR MONITORING LOCATION COLLECTION FREQUENCY OF ANALYSIS
- f. Precipita- BD-11, Morris Farm, 2.4 mi E Monthly Gross beta analysis tion BD-12, Goodwin Farm, 7.7 mi ENE monthly. Composite BD-17, Trotter's Dairy, 4.8 mi NW for gamma isotopic, BD-18, Biros Farm, 10.5 mi WNW tritium and Sr-89, 90 analysis quarterly.
- 4. Ingestion d
- a. Milk BD-11, Morris Farm, 2.4 mi E Weekly: May to Gamma isotopic BD-12, Goodwin Farm, 7.7 mi ENE October and I-131 BD-17, Trotter's Dairy, 4.8 mi NW Monthly: November analysis on BD-18, Biros Farm, 10.5 mi WNW to April each sample. g
. Sr-89, 90 analysis o
?
Fish monthly.
f O
- b. BD-07, Kankakee River upstream of Three times a year Gross beta, gamma discharge, 5.4 mi E isotopic and BD-10, Kankakee River downstream of Sr-89, 90 analysis discharge, 5.0 mi ENE on each sample, edible portions only.
- c. Cattle- BD-11, Morris Farm, 2.4 mi E Ouarterly Gross beta, gamma feed and BD-12, Goodwin Farm, 7.7 mi ENE isotopic and Grass BD-17, Trotter's Dairy, 4.8 mi NW Sr-89, 90 analysis BD-18, Biros Farm, 10.5 mi WNW quarterly, as e- $
w bN GP S
n
~ - _ _ - _ _ _ _ _ . . - _ . .. _ . . . - - _ - - - - . _ - . -
O O O :
TABLE 8.4-1 (Cont ' d)
TYPE AND EXPOSURE PATHWAY SAMPLING OR FREQUENCY AND/OR SAMPLE SAMPLING OR MONITORING LOCATION COLLECTION FREQUENCY OF ANALYSIS
- d. Vegetables BD-14, Pinnick Farm, 1.8 mi N Annually Gross beta, gamma BD-15, Girot Farm, 1.4 mi N isotopic and BD-16, Clark Farm, 3.3 mi ENE Sr-89, 90 analysis annually. I-131 analysis on leafy vegetables,
- a. See Figure 8.4-1.
- b. Perform qamma isotopic analysis on each sample when gross beta activity is greater than (>) 10 times the yearly mean of control samples. W
- c. See Figure 8.4-2. 5 s
. d. See Figure 8.4-3.
u a
ss>n -
==.
- 3 }
e
,{ l
o o o :
TABLE 8.4-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONDENTAL SAMPLES REPORTING LEVELS IdATER FISH MILK FOOD PRODUCTS ANALYSIS (pCi/t) AIRBORNE OR CASES PARTICUlp)TE (pCi/m (pCi/kg, wet) (pCi/t) (pCi/kg, wet)
H-3 20,000*
Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 to m h
, Zn-65 300 20,000 g a
z Z r-Nb-95 400 @
O I-131 2 0.9 3 100 Cs-134 30 10 I,000 60 I,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300
- For drinking water samples. This is 40 CFR Part 141 value. If no drinking water pathway exists, y a value of 30,000 pCi/1 may be used.
tn N
- 8=Q.
20 P (./y Y
h,I W
O O O :
TABLE 8.4-3 DETECTION CAPABILITIES FOR ENVIRONENTAL SAMPLE ANALYSIS *
-LOWER LIMIT OF DETECTION (LLD)b,c WATER FISH MILK FOOD PRODUCTS SEDIENT ANALYSIS (pCi/1) AIRBORNE PARTICp) TE(pCi/kg, OR CAS (pCi/m wet) (pCi/t) (pCi/ka, wet) (pCi/kg, dry)
Cross Beta 4 0.01 H-3 2000*
Mn-54 15 130 Fe-59 30 260 Co-58,60 15 130 m
, Zn-65 30 260 $
s I
Ba-La-140 15 15
- If no drinking water pathway exists, a value of 3000 pCi/t may be used. ness
@y bP
BRAIDWOOD
%.% A% % l ;
AUGUST 1986 /
/m
~ TABLE.8.4-3 (Cent'd)
(v)
- This list does not mean that only these nuclides are to be considered, . l .
Other peaks that are identifiable, together with those of the above noc11 des, shall also be analyzed and reported in the Annual Radiological Environmental ,
" "' s Operating Report. - a Required detection capabilities for thermoluminiscent dosimeters used for environmental measurements are given is Regulatory Guide 4.13.
- The LLD is defined, for purposes of these specificatiens, as the smallest.
concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95 percent probability with only 5 percent probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system, which may incinie radiochemical separation 4.66 s b E
- V
- 2. 2 2 . Y . e x p ( - A t.t )
wheret O LLD = the "a priori" lower limit of detection (picoCuries per unic V mass or volume), -
= the standard deviation of the background counting rate or of '
s b
the counting rate of a blank sample as appt'opriate (hunts per minute), o E = the counting efficiency (counts per disintegrat i on),
V = the sample size (units of mass or volume), ,
2.22 = the number of disintegrations per minute pu picocurie, Y = the fractional radiochemical yield, when applicable, A
= the y dioactive decay constant for the parti d lar radionuclide, (see ), and ,
At = the elapsed time between sample collection, or end of the sample collection period, and time of counting (sec).
Typical values of E, V, Y, and A t should be used in the calculation.
It should be recognized that the LLD is defined ai en a priori (before the fact) limit representing the capability of a swasurement system and not as an a posteriori (af ter the fact) limit for a particular -
measurement. Analyser shall be performed in such a manner that the stated LLDs will be achieved under routine conditiors. Cecasionally G
s 8.4-10 -
L
DMWth BRAIDWOOD W
REVISION 11 i
AUGUST 1986 TABLE 8.4-3 (Cont'd) hackground fluctuations, unavoidable small' sample sizes, the presence
. of interfering nuclides, or other uncontrollable circumstances may I
render these LLDs unachievable. In such cases, the contributing factors e, shall be identified and described in the Annual Radiological Environmental Operating Repo.-t, LLD for drinking water samples. If no drinking water pathway exists, an t.LD of 60 pCi/1 may be used.
~
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Scale
!_ _. . f ! f 0 1 2 4 8 8 10 Kilometers t I i t i I f
4 BR AIDWOOD STATION FIGURE 8.4-1 l C FIXED AIR SAMPLING SITES i
' AND OUTER RING TLD LOCATIONS UIlii'395 l
3 .* - hh@
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REVISION 11 AUGUST 1986 O
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106-2 cv
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1;o 2,o m.* FIGURE 8.4-2
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o j 2 3 4 xuom.ier. INNER RING TLD LOCATIONS UIls#- 39s i
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Location is,
- --10.5 miles e Braidwood irom .ianon f
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Station 6
'4 in L T vN g Braceville g N w
& yO County Line Rd.
s Gardner Essex l [ Rice Rd. l South Wilmington
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l BR AIDWOOD STATION FIGURE 8.4-3 INGESTION AND WATERBORNE l (m i
EXPOSURE PATHWAY SAMPLE LOCATIONS OIle'-395
y-g .
[N Commonwealth Edison WN P.
/ --
2 Braidwood Nuclear Power Station Route C1, Box 84
- \ '"' Braceville, Illinob 60407
( Telephone 815/458-2801 EEF/87-27 File: AGNC-14 January 9, 1987 Director, Office of Resource Management United States Nuclear Regulatory Commission Washington, D.C. 20555 ATTN: Document Control Desk Gentlemen:
Enclosed for your information is the Monthly Performance Report covering Braidwood Nuclear Power Station for the period December 1 through December 31, 1986.
Very truly yours, E. E. Fit atrick Station Manager Braidwood Nuclear Power Station EEF/HDP/mjv (4266z)
Attachments cc: J. G. Keppler, NRC, Region III NRC Resident Inspector Braidwood Gary Wright, Ill. Dept. of Nuclear Safety D. P. Galle T. J. Maiman l
D. L. Farrar Nuclear Fuel Services, PWR Plant Support i L. Anastasia, Station Nuclear Engineering INPO Records Center Performance Monitoring Group, Tech Staff Braidwood Station j Nuclear Group, Tech Staff Braidwood Station i J. Stevens - USNRC 4 f P. L. Barnes d
/*
I i H. D. Pontious \
., _ - . _- . . . . _ . . _ _ . _ . . - - . .___ . _ . . __ . _ . _ _ _ _ _ - _ _ . . _ - _ .