Text

Monthly Operating Repts for Jul 1986.Rev 11 to Site-Specific Sections 7.2 & 8.0 of Offsite Dose Calculation Manual & Encl
	ML20203K940
Person / Time
Site:	Quad Cities
Issue date:	07/31/1986
From:	Kronich C, Robey R; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
	RAR-86-23, NUDOCS 8608220271
	Download: ML20203K940 (93)
	v • d • e

{{#Wiki_filter:. QUAD-CITIES NLCLEAR P0HER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT JULY, 1986 COMMONWEALTH EDISON COMPANY AND IONA-ILLIN0IS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 8605220271 0'>0731 PDR ADOCK 0 D 0002 3 ',+ P 'c'n R J (,'f 0027H/0061Z

TABLE OF CONTENTS I. Introduction II. Summary of Operating Expe-tence A. Unit One B. Unit Two III. Plant or Procedure Changes, Tests, Experiments, and Safety Related Maintenance A. Amendments to Facility License or Technical Specifications B. Facility or Procedure Changes Requiring NRC Approval C. Tests and Experiments Requiring NRC Approval D. Corrective Maintenance of Safety Related Equipment IV. Licensee Event Reports V. Data Tabulations A. Operating Data Report B. Average Daily Unit Power Level C. Unit Shutdowns and Power Reductions VI. Unique Reporting Requirements A. Main Steam Relief Valve Operations B. Control Rod Drive Scram Timing Data VII. Refueling Information VIII. Glossary 0027H/0061Z

I. INTRODUCTION Quad-Cities Nuclear Power station is composed of two Boiling Water Reactors, each with a Maximum Dependable Capacity of 769 MWe Net, located in Cordova, Illinois. The Station is jointly owned by Commonwealth Edison Company and Iowa-Illinois Gas & Electric Company. The Nuclear Steam Supply Systems are General Electric Company Bolling H2.ter Reactors. The Architect / Engineer was Sargent & Lundy, Incorporated, and the primary construction contractor was United Engineers & Constructors. The Mississippi River is the condenser cooling water source. The plant is subject to license numbers DPR-29 and DPR-30, issued October 1, 1971, and March 21, 1972, respectively; pursuant to Docket Numbers 50-254 and 50-265. The date of initial Reactor criticalities for Units One and 'wo, respectively were October 18, 1971, and April 26, 1972. Commercial generation of power began on February 18, 1973 for Unit One and March 10, 1973 lor Unit Two. This report was compiled by Becky Brown and Carol Kronich, telephone number 309-654-2241, extensions 2240 and 2157. 0027H/0061Z l

II.

SUMMARY

OF OPERATING EXPEPLENCE A. Unit One July 1-13 Unit One began the month of July holding load near full power. At 0920 hours, on July 1, the unit was placed on Economic Generation Control (EGC). The unit was taken out of EGC operation on July 4 at 0046 hours, and returned at 0215 hours. On July 5, at 0315 hours, the unit was taken off of EGC, and load was dropped to 700 MWe for Turbine surveil-lances. Load was increased to 750 MWe and the unit returned to EGC operation at 0410 hours. At 0953 hours the unit was taken off of EGC, and load was increased to full power. On July 6, at 0308 hours, the unit returned to EGC. T On July 7, at 0915 hours, the unit was taken off of EGC, and load was increased to full power. At 2030 hours load began a drop at 200 MWe/ hour for a unit shutdown due to high conductivity -- condenser tube leak. The unit was taken off line on July 8, at 0045 hours, and at 0100 hours the unit was manually scrammed. On July 9, at 1538 hours, unit startup commenced. At 1844 hours the Reactor went critical. The unit was placed on line on July 10 at 0615 hours. Full power was reached on July 12 at 0100 hours after a normal load increase. Full load was held until July 13, at 0420 hours, when the unit was placed on EGC. The unit was taken off of EGC at 1715 hours and returned at 1755 hours. July 14-31 On July 14, at 1020 hours, the unit was taken off of EGC for rod maneuvers. At 1522 hours load was increased to full power. Load was held near full power until July 19, at 2210 hours, when load was dropped to 705 MWe to reverse condenser flow. At 2330 hours load began an increase to full power. On July 20, at 1750 hours, the unit was placed on EGC. EGC was tripped on July 21, at 0757 hours, and load was increased to full power. The unit returned to EGC operation at 2353 hours. At 0659 hours, on July 22, the unit was taken off of EGC, and load was in-creased to full power. At 2205 hours the unit was returned to EGC operation until 2225 hours, when load was dropped to 700 MWe as per Load Dispatcher. At 2345 hours load was increased within ECC limits and the unit returned to EGC operation at 0030 hours, on July 23. At 0520 hours the unit was taken off of EGC, and load was increased to full power. i 1 0027H/0061Z ,,,7 -.g-,

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i A. Unit One (cont.) t On July 25, at 0045 hours, load was dropped to 775 MWe to reverse condenser flow. At 0150 hours load was being held at full power. On July 26, at 0100 hours, load was dropped to 700 MWe for Turbine surveil-lances. At 0250 hours load began an increase to full power. At 1230 hours load was being held at 810 MWe. At 1700 hours the unit was returned to EGC operation. On July 28, at 0600 hours, the unit was taken off of EGC and load was increased to full power. On July 30, at 1615 hours, the unit was placed on EGC. At 1210 hours, on July 31, the unit was taken off of EGC, and load was increased to full power. The unit remained in EGC operation for the remainder of July, j i B. Unit Two July 1-17 i Unit Two began the month of July on Economic Generation Control (EGC). On July 2, at 1455 hours, the unit was taken off of EGC, and later returned at 1545 hours. On July 4, at 2390 hours, the unit was taken off of EGC to perform surveillances. On July 5, at 0200 hours, the unit returned to EGC operation. At 0855 hours the unit was taken off of EGC and load was dropped to 740 MWe due to high 2A Condensate Demineralizer i Post Strainer differential pressure. At 1035 hours the unit returned to EGC. At 1100 hours the unit was taken off of EGC, and load dropped to 765 MWe due to high 2G Condensate Demineralizer Post Strainer differential pressure. At 1240 hours load was dropped to 650 MWe to remove the 2G Condensate Demineralizer from service. At 2035 hours load began a normal increase to full power. On July 6, at 1020 hours, the unit reached 801 MWe and held steady until 1630 hours when the unit was placed on EGC. On July 7, at 1000 hours, the unit was taken off of EGC and load was increased to full power. The unit returned to EGC operation at 0410 hours on July 8. At 0829 hours EGC was tripped and load was increased to full power. Load was held near full power until 0210 hours, on July 10, when the unit was placed on EGC. The unit was taken off of EGC at 0840 hours, on July 12, for surveillances. i EGC operation was returned to at 1000 hours. On July 13, at 0015 hours, the unit was taken off of EGC, and load was dropped to 650 MWe for control rod maneuvers. At 0405 hours load began an increase to full power. At 1230 hours, on July 14, load was dropped to approximately 420 MWe due to Recirculation Motor-Generator Set 1' problems. At 1530 hours load began an increase towards full power. Full power was held until July 17, at 2045 hours, when load was dropped to 715 1 MWe to remove the 2A Circulation Water Pump from service. I I

B. Unit Two (cont.) July 18-31 On July 18, at 0500 hours, load began an increase to full power. At 2320 hours, on July 19, load was dropped to 600 MWe to change over Reactor Feed Pumps. Load began an increase to full power at 2205 hours on July 20. On July 22, at 2215 hours, load began a drop to 700 MWe at the Load Dispatcher's request. On July 23, at 0045 hours, load began an increase to approximately full power. Lcad was held until 0135 hours, on July 21, when load was dropped to 715 MWe to remove the 2E Condensate Demineralizer from service. At 0505 hours load began an increase to 800 MWe. On July 25, at 1020 hours, the unit was placed in EGC operation. EGC was tripped and load dropped to 735 MWe, on July 26, at 0055 hours, to perform Turbine surveillances. At 0253 hours the unit was returned to EGC. The unit continued in EGC operation until July 30, at 0030 hours, when EGC was tripped and the load was increased to near full load where it remained for the remainder of July. 1 4 9

III. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE A. Amendments to Facility License or Technical Specifications On June 10, 1986, the NRC issued Amendments 94 and 90 to Facility Operating License Nos. DPR-29 and DPR-30, respectively. These Amendments add limiting conditions for operation and surveillance requirements to the Technical Specifications for certain plant modifications required by TMI Action Plan Items covered by Generic Letter 83-36. The Technical Specifications were approved for Post Accident Sampling, Sampling and Analysis of Plant Effluents, Containment High Range Radiation Monitor, Containment Pressure Monitor, Containment Water Level Monitor, and Containment Hydrogen Monitor. B. Facility or Procedure Changes Requiring NRC Approval In accordance with Technical Specification Section 6.7.B. changes to the Offsite Dose Calculation Manual (0DCM), Revision 11, information to support the change, and documenta-tion that the change has been On-Site and Off-Site review approved are enclosed for submittal. C. Tests and Experiments Requiring NRC Approval There were no Tests or Experiments requiring NRC approval for the reporting period. D. Corrective Maintenance of Safety Related Equipment The following represents a tabular summary of the major safety related maintenance performed on Units 1 and 2 during the reporting period. This summary includes the following: Work Request Numbers, Licensee Event Report Numbers, l Components, Cause of Malfunctions, Results and Effects on f Safe Operation, and Action Taken to Prevent Repetition. l

UNIT 1 MAINTENANCE SUWARY CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NLAEER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q43084 1-595-134 See Work Request Q42800 - Unit 2 Standby Gas Trectment Initiation Relay 0027H/0061Z v

UNIT 2 MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q42800 2-595-134 The relay armature The 'B' Standby Gas The relay was replaced Standby Gas hung-up when it de-Treatment would not auto-like-for-like, and was Treatment energized, which start, but could be tested satisfactorily. Initiation prevented the relay started manually. The Relay contacts from 'A' Standby Gas Treat-closing when the ment System was fully relay was de-energized operable. while testing the auto-start function of Standby Gas Treatment System. Q49865 2-756 Incorrectly coded LPRM The 'C' and 'D' signals All other LPRM cables were 41 LPRM cables allowed the 'C' were bypassed when the checked, and the affected and 'D' cables to be signals were noticed to cables were corrected reversed. be reversed.'A TIP was during the next shutdown of used on the affected sufficient duration. LPRM to assure operability. 0021H/0061Z s

O IV. LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for Quad-Cities Units One and Two occurring during the reporting period, pursuant to the reportable occtrrence reporting requirements as set forth in sections 6.6.B.1. and 6.6.B.2. of the Technical Specifications. UNIT 1 Licensee Event Report Number Date Title of Occurrence There were no Licensee Event Reports for Unit 1 for the reporting period. UNIT 2 Licensee Event Report Number Date Title of Occurrence There were no Licensee Event Reports for Unit 2 for the reporting period. l ( 0027H/00612

V. DATA TABULATIONS The following data tabulations are presented in this report: A. Operating Data Report B. Average Daily Unit Power Level C. Unit Shutdowns and Power Reductions l 0027H/0061Z

OPERATING DATA REPORT DOCKET NO. 50-254 UNIT ONE DATEAUGUST 4 1986 COMPLETED BYCAROL L KRONICH TELEPHONE (309) 654-2241 OPERATING STATUS 0000 070186

1. Reporting period:2400 073186 Gross hours in reporting period:

744

2. Currently authorized power level (MWt): 2511 Max. Depend capacity (MWe-Net): 769* Design electrical rating (MWe-Net): 789

3. Power level to which restricted (if any)(MWe-Net): NA 4.

Reasons for restriction (if any): This Month Yr.to Date Cumulative

5. Number of hours reactor was critical 702.3 2858.6 99520.0

6. Reactor reserve shutdown hours 0.0 0.0 3421.9

7. Hours ge.nerator on line 690.5 2800.5 96080.0

8. Unit reserve shutdown hours.

0.0 0.0 909.2 9. Gross thernal energy generated (MWH) 1668413 6629226 201594383

10. Gross electrical energy generated (MWH) 539577 2151347 65270718 ii. Net electrical energy generated (MWH) 515725 2040352 61074885

12. Reactor service factor 94.4 56.2 79.8

13. Reactor avo11ob111ty factor 94.4 56.2 82.6

14. Unit service factor 92.8 55.1 77.i

15. Unit avo11obility factor 92.8 55.1 77.8

16. Unit copocity factor (Using MDC) 90.1 52.4 63.7

17. Unit capacity factor (Using Des.MWe) 87.9 51.0 62.i_

18. Unit forced outoge rate 7.2 2.0 5.8

19. Shutdowns scheduled over next 6 months (Type,Date,and Duration of each):

20. If shutdown at end of report period, estimated date of startup NA i

l MMOFFICIAL ColfANY NUleERS ARE USED IN THIS REPORT l l i

1 9 OPERATING DATA REPORT DOCKET NO. 50-265 UNIT TWO DATEAUGUST 4 1986 COMPLETED BYCAROL L KRONICH TELEPHONE (309) 654-2241 OPERATING STATUS 0000 070186 Reporting period:2400 073186 Gross hours in reporting period: 744 l 1.

2. Currently authorized power level (MWt): 2511 Max. Depend capacity (MWe-Net): 769* Design electrical roting (MWe-Net): 789 l

3. Power level to which restricted (if any)(MWe-Net): NA f

4. Reasons for restriction (if any): This Month Yr.to Date Cunulative

5. Number of hours reactor was critical 744.0 4757.7 96025.4

6. Reactor reserve shutdown hours 0.0 0.0 2985.8

7. Hours generator on line 744.0 4715.3 93012.9

8. Unit reserve shutdown hours.

0.0 0.0 702.9 l 9. Gross thermal energy generated (MWH) 1805766 11234663 197343686 i

10. Gross electrical energy generated (MWH) 571627 3655476 63072258 l

I ii. Het electrical energy generated (MWH) 546418 3498990 59373249

12. Reactor service factor 100.0 93.5 77.6

13. Reactor availability factor 100.0 93.5 80.0

14. Unit service factor 100.0 92.7 75.2

15. Unit avo11obility factor 100.0 92.7 75.7

16. Unit copocity factor (Using MDC) 95.5 89.4 62.4

17. Unit capacity factor (Using Des.MWe) 93.1 87.2 60.8

18. Unit forced outage rate 0.0

.5 7.8

19. Shutdowns scheduled over next 6 months (Type,Date,and Duration of each):

NA

20. If shutdown at end of report period,estinated date of startup

$ UNOFFICIAL COMPANY NUMBERS ARE USED IN THIS REPORT

l APPENDIX B AVERAGE DAILY UNIT POWER LEVEL ^ DOCKET NO. 50-254 UNIT ONE l DATEAUGUST 4 1986 COMPLETED BYCAROL L KRONICH TELEPHONE (309) 654-2241 l MONTH Julv 1986 i DAY AVERAGE DAILY POWER' LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (HWe-Net) I i. 764.0 17, 770.7 f 2. 752.8 18. 761.0 3. 753.8 19. 775.9 4. 751.7 20. 753.7 5. 758.4 21. 752.7 6. 750.9 22. 781.3 ) 7. 708.0 23, 731.4 8. -8,3 24. 779.6 9. -11.2 25, 763.3 I 10, 322.0 26, 757.0 l ii. 696.5 27. 740.2 12. 784.0 28, 775.3 13. 750.3 29. 769.8 l 14. 748.0 30. 770.6 15. 767.8 31. 745.0 i 16, 775.5 INSTRUCTIONS i On this forn, list the everage daily soit pour level la tule-Ilet for each det in the reporting nenth. Compete to the neerest dele neenwtt. l These figures will be esed to plot a graph for each reporting month, liete that uhen noxinen dependable cepecity is l esed for the net electrical rating of the enit there ney be occasions den the daily seerage pour level exceeds the lIII line (or the restricted powr leoel line),.In such cases,the overage daily snit powr setput sheet sheeld be feetnoted to explain the opperent enently . -. ~

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-265 UNIT TWO DATEAUGUST 4 1986 COMPLETED BYCAROL L KRONICH ] TELEPHONE (309) 654-2241 MONTH July 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1. 741.6 47 736.0 2. 741.8 18. 717.9 3. 741.0 19, 753.0 4. 740.0 20, 699.5 5. 685.5 21, 747.7 6. 741.4 22, 764.8 7. 746.6 23, 721.6 8. 754.3 24, 755.9 9. 771.7 25. 742.4 10, 742.8 26. 779.6 ii. 737.i 27, 674.5 12. 753.1 28, 742,0 13, 697.0 29, 721.0 14. 631.3 30. 751.4 15, 731.7 31. 738.4 16, 754.6 I INSTRUCTIONS On this forn, list the overage daily snit power level in IWe-Net for each day in the reporting nenth.Conpete to the nearest uhele negewett. These figeres will be esed to plot a graph for each reporting nenth. Netz that when notinen dependeble copocitt is esed for the net electrical rating of the snit there.ecy be occasions when the daily overage power level exceeds the 1901 line (or the restricted power level line),In sech cases,the overage daily enit power setpet sheet sheeld be q.feetpeted to explain the apparent onenely

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M M M M M M M M M. M M M P"1 M y i ID/5A APPENDIX D QTP 300-S13 UNIT SIIUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO. _050-265 August 1982 UNIT NAME Quad-Cities Unit 1 COMPLETED BY C. Kronich DATE August 13, 1986 REPORT HONTil JULY 1986 TELEP110NE 309-654-2241 H N j$ ed u m z $m O o M LICENSEE mo mo go g DURATION d EVENT g w u REPORT NO. CORRECTIVE ACTIONS / COMMENTS NO. DATE (110URS) o Q 86-22 860705 S 0.0 B 5 HH DEMINX Reduced load to 650 MWe -- Condensate Demineralizer maintenance 86-23 860713 S 0.0 H 5 RC CONROD Reduced load to 650 MWe for a control rod pattern adjustment 86-24 860714 F 0.0 H 5 CB MOTORX Reduced load to 420 MWe due to Recirculation Motor-Generator Set problems 86-25 860717 S 0.0 H 5 HF PUMPXX Reduced load to 715 MWe to take 2A Circulation Water Pump out of service 86-26 860719 S 0.0 B 5 CH PUMPXX Reduced load to 600 MWe to change over Reactor feed pumps 86-27 860722 S 0.0 H 5 .ZZ ZZZZZZ Reduced load to 700 MWe as per Load Dispatcher 86-28 860724 S 0.0 B 5 HH DEMINX Reduced load to 715 MWe to remove 2E Condensate Demineralizer from service 86-29 860726 S 0.0 B 5 HA TURBIN Reduced load to 735 MWe APPROVED for Turbine surveillances AUG 101982 .__ (final) ,ygg3g

VII. REFUELING INFORMATION The following information about future reloads at Quad-Cities Station was requested in a January 26, 1978, licensing memorandum (78-24) from D. E. O'Brien to C. Reed, et al., titled "Dresden, Quad-Cities, and Zion Station--NRC Request for Refueling Information", dated January 18, 1978. 1 1 t 0027H/0061Z

QTP 300-S32 Revision 1 QUAD-CITIES REFUELING March 1978 INFORMATION REQUEST 1. Unit: Q1 Ralcad: 8 Cycle: 9 2. Scheduled date for next refueling shutdown: 9-14-87 3 Scheduled date for restart following refueling: 12-21-87 4. Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment: NOT AS YET DETERMINED. 5 Scheduled date(s) for submitting proposed licensing action and supporting information: AUGUST 21, 1987 6. Important licensing considerations associated with refueling, k.g., new or 'different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures: NONE PLANNED AT PRESENT TIME. [ l 7 The number of fuel assemblies. a. Number of assemblies in core: 724 b. Number of assemblies in spent fuel pool: 1896 8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned in number of fuel assemblies: a. Licensed storage capaelty for spent fuel: 3657 0 l b. Planned increase in licensed storage: 9 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: 2003 l XPPROVED APR 2 01978 C). c:. c). s. Ft.

QTP 300-S32 Revision 1 QUAD-CITIES REFUELING March 1978 INFORMATION REQUEST 1. Unit: 02 Reload: 7 Cycle: 8 2. Scheduled date for next refueling shutdown: 10-13-86 3. Scheduled date for restart following refueling: 1-19-87 4. Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment: TECHNICAL SPECIFICATION CHANGES WILL BE REQUIRED FOR NEW FUEL TYPES (MAPLHGR CURVES), MCPR OPERATING LIMIT, AND A LICENSE AMENDMENT TO MOVE SINGLE LOOP OPERATION INTO TECHNICAL SPECUICMIONS. 5 Scheduled date(s) for submitting proposed licensing action and supporting information: SEPTEMBER 19, 1986, IF REQUIRED. 6. Important licensing considerations associated with refueling, e.g., new or

different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

NONE PLANNED AT PRESENT TIME. l 7 The number of fuel assembiles. a. Number of assemblies in core: 724 b. Number of assemblies in spent fuel pool: 836 8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned in number of fuel assemblies: a. Licensed storage capacity for spent fuel: 3897 b. Planned increase in licensed storage: 0 1 9 The projected date of the last refueling that can be discharged to the l spent fuel pool assuming the present licensed capacity: 2003 4PPROVED APR 2 01978 Q.C.O.S.R. /

VIII. GLOSSARY The follcwing abbreviations which may have been used in the Monthly Report, j are defined below: ACAD/ CAM - Atmospheric Containment Atmospheric Dilution / Containment Atmospheric Monitoring ANSI American National Standards Institute APRM Average Power Range Monitor ATHS Anticipated Transient Without Scram BWR Bolling Water Reactor CR0 Control Rod Drive EHC Electro-Hydraulic Control System EOF Emergency Operations Facility GSEP Generating Stations Emergency Plan HEPA High-Efficiency Particulate Filter HPCI High Pressure Coolant Injection System HRSS High Radiation Sampling System IPCLRT Integrated Primary Containment Leak Rate Test IRM Intermediate Range Monitor ISI Inservice Inspection LER Licensee Event Report LLRT Local Leak Rate Test LPCI Low Pressure Coolant Injection Mode of RHRS LPRM Local Power Range Monitor 4 MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MFLCPR Maximum Fraction Limiting Critical Power Ratio MPC Maximum Permissible Concentration MSIV Main Steam Isolation Valve NIOSH National Institute for Occupational Safety and Health PCI Primary Containment Isolation PCIOMR Preconditioning Interim Operating Management Recommendations RBCCW Reactor Building Closed Coo' ling Water System RBM Rod Block Monitor RCIC Reactor Core Isolation Cooling System RHRS Residual Heat Removal System RPS Reactor Protection System RWM Rod Worth Minimizer Standby Gas Treatment System SBGTS SBLC Standby Liquid Control SDC Shutdown Cooling Mode of RHRS I SDV Scram Discharge Volume SRM Source Range Monitor TBCCW Turbine Building Closed Cooling Water System TIP Traversing Incore Probe TSC Technical Support Center i 0027H/0061Z \\ -.-n. -, -

July 15, 1986 To: R. L. Bax j;pc 2}'86 Station Manager Quad Cities Station ROUTE: A (Asst. Suot.)

Subject:

Inclusion of the Quad Cities Station offsite 8 Dose Calculation Manual, site Specific c ain n nce) Sections ~7.2&8.0, Revision 11,intheJulyOperatin[depor[ D Admin. & Tectb F7 E Personnel. Per Technical Specifications, revisions to the Offsite Dose Calculation Manual (ODCM) are to be included in the Station's Monthlyinitia M Operating Report for submittal to the NRC. The enclosed Quad Cities ODCM, Site Specific Sections 7.2 & 8.0, Revision 11, has completed the necessary onsite and offsite reviews, and appropriate comments incorporated. Please include this ODCM in the July Operating Report. oQ If you have any questions regarding this request, please feel free 1 to call D. M. Kenealy of my staff at G.O. Extension 3271. g dl .t. Sincerely, A / 0)' 2 J. C. Golden Supervisor of Emergency Planning Nuclear Services Technical Enclosure cc: J. E.Sirovy J. J. Kopacz EPG-04-RE-ODCMll DMK/Imk/6306E/48

QUAD-CITIES REVISION 11 DECEMBER 1985 = ODCM LIST OF TABLES FOR QUAD-CITIES SECTION 7.2 NUMBER TITLE PAGE 7.2-1 Aquatic Environment 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 ) 7.2-5 t 7.2-6 X/Q and D/Q 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 l l l 7.2-i

7 QUAD-CITIES REVISION 11 DECEMBER 1985 l ^ ODCM LIST OF FIGURES FOR QUAD-CITIES SECTION 7.2 NUMBER TITLE 7.2-1 Unrestricted Area Boundary i 1 i 7.2-11 l

QUAD-CITIES REVISION 11 DECEMBER 1985 TABLE 7.2-1 AQUATIC ENVIRONMENT DOSE PARAMETERS i PARAMETER QUAD CITIES U", water usage, liters /hr 0.083 f -3 U fish consumption, kg/hr 2.4 x 10 1/M" 1 f 1/M 1 W F ft /sec 4.7 x 1(4 f 3 F ft /sec 4.7 x 10 t hr* 24 t", hr** 7.5 B. - Regulatory Guide 1.109, Revision 1, October 1977, Table A-1, 1 Column 2 for freshwater fish. See Table 7.1-12. t F ft /sec F ft /sec J/M" Not applicable. No outdoor tanks without overflow pipes' connected y T hr to other storage pipes. g, D V, gal t hr o, s f

t (hr) = 24 hr (all stations) for the fish ingestion pathway
- t" (hr) = 7.5 hr (Distance to Davenport is 15 miles; flow rate of 2 m.p.h.)

7.2-1

i QUAD-CITIES REVISIO24 11 DECEMBER 1985 s TABLE 7.2-2 ANNUAL DESIGN OBJECTIVES SET BY 10 CFR 50, APPENDIX I FOR EACH REACTOR TYPE OF DOSE ANNUAL DESIGN OBJECTIVES Airborne Releases Gamma Air Dose 10 mrad Beta Air Dose 20 mrad Whole Body Dose 5 mrem Skin Dose 15 mrem Infant Thyroid Dose 15 mrem Liquid Releases Whole Body Dose 3 mrem Thyroid Dose 10 mrem Bone Dose 10 mrem Skin Dose 10 mrem 7.2-2

QUAD-CITIES REVISION 11 DECEMBER 1985 s TABLE 7.2-3 ~~ STATION: Quad-Cities Nuclear Power Station LOCATION: Cordova, Illinois CHARACTERISTICS OF ELEVATED RELEASE POINT

1) Release Height =

95 m

2) Diameter 3.35 m

= ~1 -1 20.3 ms

4) Heat Content =

4.lE3 KCal s

3) Exit Speed

= CHARACTERISTICS OF VENT STACK RELEASE POINT

1) Release Height =

48 m

2) Diameter =

2.74 m -1

3) Exit Speed 15.3 ms

= CHARACTERISTICS OF GROUND LEVEL RELEASE

1) Release Height = 0m 36 m

2) Building Factor (D)

= METEOROLOGICAL DATA A 296 ft. Tower is Located 1623 m SSE of Elevated Release Point Tower Data Used in Calculations Release Point Wind Speed Differential And Direction Temperature Elevated 296 ft. 296-33 ft. Vent 196 ft. 196-33 ft. Ground 33 ft. 196-33 ft. I

7. 2-3

REVISION 11 QUAD-CITIES DECEMBER 1985 TABLE 7.2-4 ~ CRITICAL RANGES PRACTICAL SITE NEAREST NEAREST DAIRY FARM BOUNDARY

RESIDENT **

RANGE *** DIRECTION (m) (m) (m) N 864 966 NNE 1029 1600 NE 1212 2100 ENE 1367 4600 E 1170 3700 ESE 1170 3219 SE 1189 1600 SSE 1422 1800 I S 1198 1300 SSW 2140 4800 l SW 1372 4600 WSW 823 3219 W 713 .4000 WNW 713 4000 NW 823 3219 NNW 1481 3200

Nearest land in unrestricted area i
- Estimate range
  - Within 5 miles 7.2-4

TABLE 7*2-5 .pgggAIN CORRECTION FACTORS (h.) - ggAD-CITigs bTAT M x 3 s i e 1 x. i; is- ~ j Jv I ,e ri n

t. t su 7

Gi 16 i c5 f ok-u o C I! ? y a /ol e Y ,36 Shaded area has h =30m; un-b t p y,,,. shaded area has h =0, y t , {3 H 6 's> V'. M 37 (Each increment is 4 mi) m in ,I-Point 145 is the site. 1s3 f7i ,1o8d r$1 d>I U n< nr 237 MH Es L ac mo 02 ass yn HH @H ) g 3'f. 6 03 2D = 4 9

l TABLE 7.2-6 X/Q AND D/Q MAXIMA AT OR BEYOND THE UNRESTRICTED AREA BOUNDARY l DOWNwlND ELEVATEDISTACM D gtEASE mixed MODE (VENT) RELEASL_ GROUND LEVEL RELEASE DIRECTIDN RADIUS X/Q + RADIUS D/QA RADIUS X/Q + O/Q A RADIUS X/Q + D/Q A (WETERS) (SEC/M**3) (METERS) (1/M**2) (METERS) ISEC/M**3) (1/M**2) (METERS) (SEC/M**3) (1/M**2) h N 064. 3.359-08 864. 1.627-09 864. 1.569-06 1.050-08 864 3.785-06 2.085-08 NNE 1029. 4.304-08 1029 1.869-09 1029. 5.723-07 4.333-09 1029. 1.151-06 6.452-09 ltv NE 2000. 3.649-08 1212. 1.419-09 1212. 7.858-07 3.502-09 1212. 1.299-06 4.967-09 Oy ENE 2000. 2.203-08 1367. 6.363-10 1367. 5.866-07 2.572-09 1367. 1.003-06 4.418-09 4 E 3219. 2.288-08 1170. 8.769-10 1170. 4.843-07 3.550-09 1170. 1.010-06 6.056-09 y ESE 2000. 3.026-08 1170. 1.317-09 1170. 7.185-07 4.754-09 1170. 1.228-06 7.493-09 8 SE 2000 3.906-08 11851. 1.428-09 1189. 9.715-07 5.298-09 1189. 1.681-06 9.041-09 H M k SSE 2000. 3.067-08 1422. 8.104-10 1422. 5.276-07 2.488-09 1422. 1.108-06 4.828-09 5 3000 2.526-08 1198. 7.757-10 1198. 3.412-07 2.253-09 1198. 1.261-06 5.022-09 SSW 3219. 2.194-08 1024. 7.054-10 1024. 2.913-07 2.639-09 1024. 1.002-06 5.535-09 Sw 654. 3.439-08 654. 9.739-10 654. 6.155-07 4.495-09 654. 2.794-06 1.168-08 WSW 494 7.298-08 500. 1.672-09 494. 1.039-06 6.518-09 494. 3.338-06 1.697-08 w 451 6.637-08 500. 1.729-09 451. 2.657-06 1.238-08

451, 5.717-06 2.636-08 WNw 451.

7.002-08 500. 1.800-09 451. 5.104-06 1.824-08 451. 9.660-06 3.163-08 Nw 485. 7.614-08 500. 1.698-09 485. 5.043-06 1.490-08 485. 1.218-05 2.980-08 NNw

640, 3.829-08 640.

1.335-09 640. 2.773-06 1.048-08 640. 5.197-06 1.810-08 QUAD-CITIES 142 SITE METEOROLOGICAL DATA 1/74 - 12/75 ON O< H un H MO + Beta air, beta skin, and inhalation dose pathways.

o z A

Produce and leafy vegetable pathways. (( co U1 or 9

QUAD-CITIES REVISION 11 DECEMBER 1985 TABLE 7.2-6 (Cont'd) QUAD-CITIES 1&2 AVERAGE WIND SPEEDS FOR EACH RELEASE MODE DOWNWIND AVERAGE WIND SPEED (m/sec) DIRECTION ELEVATED MIXED MODE GROUND LEVEL N 6.5 4.4 4.0 NNE 5.7 3.9 3.4 NE 5.8 3.7 2.9 ENE 5.8 3.9 3.5 E 6.4 4.6 4.4 ESE 6.7 4.7 4.4 SE 6.2 4.1 3.8 SSE 5.2 3.7 3.2 S 5.2 3.7 3.3 SSW 5.3 4.2 4.1 SW 5.4 4.0 3.7 WSW 4.5 3.5 3.3 i W 5.7 4.0 3.7 WNW 6.1 3.7 3.4 NW 5.9 3.4 2.8 i ) NNW 6.2 3.8 3.5 I E 7.2-7 i - -., - ~ _ - -, - -,

TABLE 7.2-7 D/O AT THE NEAREST MILK COW AND MEAT ANIMAL LOCATIONS WITHIN 5 MILES NEAREST MEAT ANIMAL D/Q(1/M**2) _D[Q[1[M312)DUND DOWNWIND NEAREST MILK COW MIXED GR RADIUS ELEVATED MIXED GROUND DIRECTION RADIUS ELEVATED (METERS) RELEASE RELEAS_E RELEASE (METERS) RELEASE RELEASE RELEASE N 8047. 1.119-10 2.564-10 4.415-10 8047. 1.119-10 2.564-10 4.415-10 NNE 8047. 1.345-10 1.613-10 1.810-10 8047. 1.345-10 1.613-10 1.810-10 g) NE 8047. 1.2RG-10 1.659-10 1.842-10 4828. 2.817-10 3.938-10 4.552-10 c ENE 8047. 7.134-11 1.362-10 2.011-10 8047. 7.134-11 1.362-10 2.011-10 -J E 3219. 3.212-10 7.066-10 1.055-09 3219. 3.212-10 7.066-10 1.055-09 C3 ESE 8047. 1.34G-10 1.977-10 2.616-10 8047. 1.346-10 1.977-10 2.616-10 h h3 SE 8047. 1.46G-10 2.312-10 3.245-10 3219. 5.375-10 1.088-09 1.619-09 H $3 SSE 0047. 9.765-11 1.516-10 2.350-10 8047. 9.765-11 1.516-10 2.350-10 H S 1694. 5.681-10 1.348-09 2.783-09 3219. 2.886-10 5.040-10 9.112-10 y SSW 8047. 6.654-11 9.673-11 1.540-10 8047. 6.654-11 9.673-11 1.540-10 m SW 8047. 6.086-11 8.692-11 1.586-10 8047. 6.006-11 8.692-11 1.586-10 WSW 8047. 7.959-11 1.008-10 1.478-10 8047. 7.959-11 1.008-10 1.478-10 W 8047. 8.643-11 1.384-10 1.999-10 8047.. 8.643-11 1.384-10 1.999-10 WNW 8047. 8.184-11 1.738-10 2.400-10 8047. 8.184-11 1.738-10 2.400-10 NW 8047. 7.265-11 1.572-10 2.523-10 8047. 7.265-11 1.572-10 2.523-10 NNW 8047. 7.920-11 1.683-10 2.376-10 8047. 7.920-11 1.683-10 2.376-10 QUAD-CITIES 142 SITE METEOROLOGICAL DATA.1/74 - 12/75 OM 19 M O< tn H T in fri H MO WZ HH @H G) U1 A 9

TABLE 7.2-8 OUAD-CITIES 1&2 MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR KR 83M DOWNWIND RESTRICTED J1EV ATED LST ACK ) RElGSE, _ mixed MODE 1YENT) RELEASE _ GROUND LEVEL RELEASE DIRECTIDN AREA BOUND RADIUS S 58AR RADIUS V VBAR RADIUS G G8AR (METERS) (METERS) (MRAD /fR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) K) C h N 864 864 4.43G-06 4.006-07 864. 1.726-04 1.559-05 864. 4.081-04 3.685-05 'J NNE 1029. 1029. 5.563-06 5.024-07 1029. 6.291-05 5.681-06 1029. 1.210-04 1.092-05 NE 1212. 1212. 4.239-06 3.828-07 1212. 8.139-05 7.350-06 1212. 1.336-04 1.206-05 O )# ENE 1367. 1367. 2.259-06 2.040-07 1367. 5.986-05 5.406-06 1367. 1.019-04 9.203-06 H us E 1170. 1170. 2.396-06 2.164-07 1170. 5.173-05 4.671-06 1170. 1.048-04 9.461-06 d ESE 1170. 1170. 3.347-06 3.022-07 1970. 7.541-05 6.810-06 1170. 1.272-04 1.149-05 m SE 1189. 1189. 4.093-06 3.696-07 1189. 1.019-04 9.200-06 1189. 1.737-04 1.568-05 m SSE 1422. 1422. 3.156-06 2.850-07 1422. 5.367-05 4.847-06 1422. 1.114-04 1.006-05 S 1198. 1198. 2.567-06 2.318-07 1190. 3.656-05 3.301-06 1198. 1.298-04 1.172-05 SSW

1024, 1024, 2.294-06 2.071-07 1024.

3.283-D5 2.965-06 1024. 1.050-04 9.481-06 SW 654 654. 4.231-06 3.820-07 654. 7.185-05 6.488-06

654, 2.932-04 2.648-05 WSW 494 494.

8.240-06 7.441-07 494. 1.164-04 1.051-05 494. 3.653-04 3.298-05 W 451. 451. 7.616-06 6.877-07 451. 2.770-04 2.501-05 451. 5.883-04 5.313-05 WNW 451. 451. 7.837-06 7.077-07 451. 5.155-04 4.655-05 451. 9.168-04 8.279-05 NW 485. 485. 8.367-06 7.556-07 485. 4.985-04 4.508-05 485. 1.109-03 1.002-04 NNW 640. 640. 4.750-06 4.289-07 640. 2.900-04 2.619-05 640. 5.238-04 4.730-05 OUAD-CITIES 142 SITE METEDROLOGIC AL DAT A 1/74 - 12/75 g n< MH J: En tD H MO

0 '2.

HH @H CD Ut s 8 i

i TABLE 7.2-8 (Cont'd) OUAD-CITIES 1&2 MAXIMUM _ OFFS!_TE FINITE PLUME GAMMA DOSE FACTORS FOR KR 85M DOWNWIND RESTRICTED ELEVATED (STACK) RELEASE MINED MODE (VENT) RELEASE GRDUND LEVEL RELEASE DIRECTION AREA 8OUND RADIUS S SBAR RADIUS V V8AR RADIUS G GBAR (METERS), (METERS) (MRAD /YR)/(UCI/SEC) JMETERS) _(MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCl/SEC) () C3 %J N 864. 864 2.001-04 1.066-04 864. 1.192-03 6.175-04 864. 2.252-03 1.158-03 f hJ NNE 1029. 1029. 2.401-04 1.278-04 1029. 6.266-04 3.278-04 1029. 7.455-04 3.847-04 1 NE 1212. 1212. 1.692-04 9.001-05 1212. 6.397-04 3.325-04 1212. 8.024-04 4.134-04 o ENE 1367. 1367. 9.329-05 4.965-05 1367. 4.656-04 2.419-04 1367. 6.447-04 3.327-04 H E 1170.

1170, 1.134-04 6.037-05 1170.

4.396-04 2.291-04 1170. 6.585-04 3.400-04 8 ESE 1170.

1170, 1.416-04 7.539-05 1170.

5.858-04 3.045-04 1170. 7.905-04 4.080-04 [ SE 1189. 1189. 1.772-04 9.431-05 1189. 7.843-04 4.075-04 1189. 1.097-03 5.662-04 m SSE 1422. 1422. 1.212-04 6.446-05 1422. 4.612-04 2.403-04 1422. 7.236-04 3.738-04 5 1190. 1198. 1.232-04 6.559-05 1198. 3.642-04 1.905-04 1198. 7.618-04 3.922-04 SSw 1024 1024 1.326-04 7.066-05 1024. 3.430-04 1.797-04

1024, 6.186-04 3.187-04 SW

654, 654 1.973-04 1.051-04 654.

6.135-04 3.199-04 654. 1.439-03 7.360-04 WSw 494 494. 3.307-04 1.760-04 494. 9.683-04 5.047-04 494. 1.800-03 9.210-04 w 451. 451. 3.395-04 1.808-04 451. 1.668-03 8.605-04 451. 2.739-03 1.398-03 WNw 451. 451. 3.176-04 1.690-04 451. 2.666-03 1.367-03 451. 3.988-03 2.028-03 Nw 485. 485. 3.193-04 1.699-04 485. 2.597-03 1.332-03 485. 4.722-03 2.399-03 NNw 640. 640. 2.252-04 1.199-04 640. 1.659-03 8.538-04 640. 2.466-03 1.259-03 QUAD. CITIES 182 SITE METEOROLOGICAL DATA 1/74 - 12/75 NN o< H (/) H O OZ HH @H 00 U1 n 1

TATILE 7. 2-8 (Cont'd) OUAD-CITI ES -1& 2 l MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR KR 85 DOWNWIND RESTRICTED ELEVATED (STACM) RELEASE MIXED MODE (VENT) RELEASE GROUND LEVEL RELEASE -DIRECTION AREA BOUND #151b5-' S 58AR RADIUS V VBAR RADIUS G GBAR (METERS) (METERS) (MRAD /VR)/(UCI/SEC) (METERS) (MRAD /VR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) () C -J N 864 864. 2.596-06 1.607-06 H64. 1.350-05 8.354-06 864. 2.484-05 1.538-05 T NNE

1029, 1029.

3.135-0G 1.941-06 1029. 7.378-06 4.567-06 1029. 8.309-06 5.143-06 )# NE 1212. 1212. 2.200-06 1.367-06 1212. 7.455-06 4.614-06 1212. 9.040-06 5.596-06 c) F4 ENE 1367 1367. 1.224-06 7.576-07 1367. 5.424-06 3.357-06 1367. 7.313-06 4.526-06 H i F' E 1170 1170. 1.475-0G 9.133-07 1170. 5.086-06 3.148-06 1170. 7.362-06 4.557-06 8 ESE 1170. 1170. 1.839-06 1.138-06 1170. 6.750-06 4.178-06 1970. 8.840-06 5.472-06 hj SE 1189. 1189. 2.309-06 1.429-06 1189. 9.048-06 5.601-06 1189. 1.229-05 7.606-06 u) SSE 1422. 1422. 1.595-06 9.874-07 1422. 5.427-06 3.360-06 1422. 8.222-06 5.090-06 S 1196. 1198. 1.616-06 1.000-06 1190. 4.296-06 2.660-06 1198. 8.551-06 5.293-06 SSw 1024.

1024, 1.740-06 1.077-06 1024.

4.033-06 2.497-06 1024. 6.861-06 4.247-06 Sw 654 654 2.564-06 1.587-06 654. 7.098-06 4.394-06 654. 1.575-05 9.750-06 WSW 494 494. 4.303-06 2.664-06 494. 1.124-05 6.955-06 4 94. 1.960-05 1.213-05 w 451. 451. 4.446-06 2.752-06 451. 1.880-05 1.164-05 451. 2.973-05 1.841-05 i WNW 451. 451. 4.163-06 2.577-06 451. 2.961-05 1.833-05 451. 4.328-05 2.679-05 Nw 485. 485. 4.160-06 2.575-06 485. 2.891-05 1.790-05 485. 5.130-05 3.175-05 i NNW 640. 640. 2.919-06 1.807-06 640. 1.860-05 1.151-05 640. 2.697-05 1.669-05 QUAD-CITIES 142 SITE METEOROLOGICAL DATA 1/74 - 12/75 ON MM i () <0 H U) H MO i 23 Z HH @H CD LD a t e

1 TABLE 7.2-8 (Cont'd) OUAD-CITIES 1&2 MAXIMUM _OFFSITE FINI_TE PLU,ME_ GAMMA _ DOSE FACTORS FOR KR 87 I DOWNWINO RESTRICTED ELEVATED (STACK) RELEASE. MINED MODE (VENT) RELEASE GROUND LEVEL RELEASE DIRECTION AREA BOUND RADIUS S 58AR RADIUS V VBAR RADIUS G GBAR i l (METERS) (METERS) (MRAD /VR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC), (METERS) (MRAD /YR)/(UCI/SEC) g) C 4 N 864. 864. 8.531-04 6.236-04 864. 3.746-03 2.710-03 864. 6.768-03 4.887-03 NNE 1029. 1029. 9.989-04 7.301-04

1029, 2.060-03 1.494-03 1029.

2.224-03 1.606-03 0 Y NE 1212. 1212. 6.913-04 5.051-04 1212. 1.967-03 1.424-03 1212. 2.324-03 1.678-03 b H ENE 1367. 1367. 3.785-04 2.765-04 1367. 1.397-03 1.011-03 1367. 1.863-03 1.345-03 H PJ E 1170. 1170. 4.711-04 3.443-04 1170. 1.388-03 1.005-03 1170. 1.957-03 1.413-03

3 ESE 1170.

1170. 5.879-04 4.296-04 1170. 1.823-03 1.320-03 1170. 2.349-03 1.696-03 y SE 1189. 1189. 7.291-04 5.328-04 1189. 2.418-03 1.750-03 1189. 3.246-03 2.344-03 m SSE 1422. 1422. 4.850-04 3.549-04 1422. 1.408-03 1.020-03 1422. 2.089-03 1.509-03 I S 1198. 1198. 5.031-04 3.677-04 1198. 1.172-03 8.500-04 1198. 2.214-03 1.598-03 SSw 1024. 1024. 5.522-04 4.037-04 1024. 1.138-03 8.257-04 1024. 1.842-03 1.330-03 Sw 654. 654. 8.411-04 L.148-04 654. 2.054-03 1.488-03 654. 4.334-03 3.129-03 WSw 494 494. 1.428-03 1.044-03 494. 3.322-03 2.409-03 4s4 5.520-03 3.985-03 w 451. 451. 1.487-03 1.087-03 451. 5.442-03 3.938-03 451. 8.387-03 6.054-03 WNw 451. 451. 1.390-03 1.016-03 451. 8.411-03 6.080-03 4 51. 1.212-02 8.749-03 NW 485. 485. 1.389-03 1.015-03 485. 8.166-01 5.903-03 485. 1.423-02 1.027-02 j NNW 640. 640. 9.672-04 7.071-04 640. 5.180-03 3.745-03 640. 7.397-03 5.339-03 4 QUAD-CITIES 142 StTE METEOROLOGICAL DATA 1/74 - 12/75 Oatr MN I O< MH 3 lE to WH MO ltf Z HH @H CD ) 4 s

i i TABLE 7.2-8 (Cont'd) QUAD-C ITI ES 1&2 i MAXIMUM OFFSITE FINITE PLU_ME GAMMA _DQSE FACTORS FOR KR 88 i l DOWNWIND RESTRICTED ELEVATED (STACK) RELEASE MINED MODE (VENT) RELEASE GROUND LEVEL RELEASE DIRECTIDN AREA BOUND RADIUS S SBAR RADIUS V V8AR RADIUS G G8AR (METERS) (METERS) (MRAD /YR)/(UCI/SEC).. (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) () C i q N 864 864. 2.135-03 1.647-03 864. 9.137-03 6.971-03 864 1.636-02 1.244-02 f M NNE 1029. 1029. 2.535-03 1.956-03 1029. 5.143-03 3.930-03 1029. 5.449-03 4.149-03 NE 1212. 1212. 1.764-03 1.361-03 1212. 4.977-03 3.802-03 1212. 5.803-03 4.416-04 o ENE 1367. 1367. 9.697-04 7.478-04 1367. 3.550-03 2.710-03 1367. 4.669-03 3.555-03 H w E 1170. 1170. 1.193-03 9.200-04 1170. 3.454-03 2.640-03 1170. 4.797-03 3.652-03 d ESE 1170. 1170. 1.4R4-03 1.145-03 1170. 4.541-03 3.468-03 1170. 5.762-03 4.387-03 m SE 1989. 1189. 1.852-03 1.428-03 1189. 6.050-03 4.619-03 1189. 7.984-03 6.079-03 m SSE 1422. 1422. 1.252-03 9.654-04 1422. 3.598-03 2.750-03 1422. 5.247-03 3.996-03 l 5 1198. 1998. 1.290-03 9.947-04 1198. 2.952-03 2.260-03 1198. 5,496-03 4.182-03 SSw 1024 1024 1.407-03 1.086-03 1024. 2.825-03 2.163-03 1024. 4.488-03 3.415-03 Sw 654. 654. 2.101-03 1.622-03 654. 4.995-03 3.821-03 654. 1.040-02 7.900-03 WSW 494. 494. 3.543-03 2.738-03 494. 8.043-03 6.154-03 494. 1.311-02 9.965-03 w 451. 451. 3.672-03 2.833-03 451. 1.304-02 9.942-03 451. 1.986-02 1.508-02 WNw 451. 451. 3.433-03 2.648-03 451. 2.012-02 1.531-02 451. 2.878-02 2.184-02 NW 485. 485. 3.442-03 2.656-03 485. 1.963-02 1.494-02 485. 3.396-02 2.576-02 NNW 640. 640. 2.407-03 1.857-03 640. 1.256-02 9.568-03 640. 1.777-02 1.349-02 QUAD-CITIES 182 SITE METEOROLOGICAL DATA 1/74 - 12/75 ty y i MM o <: i MH m ) H j MO mz 1 HH 1 03 1,11 1 I I dt 1 e

TABLE 7.2-8 (Cont'd) QUAD -CITI ES 1&2 MAXIMUM OFFSI_TE F_INI_TE__PLU_ME. GAMMA DOSE FACTORS FOR KR 89 DOWNWIND RESTRICTED _E LEVATED_(ST ACK ).RELE A_SE MIXED 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), (MRADfvR)/(UCI/SEC) (METERS) iMRADfYR)/(UCI/SEC) h N 864. 864. 8.056-04 5.943-04 864. 2.160-03 1.576-03 864. 3.780-03 2.753-03 h) NNE 1029. 1029. 6.806-04 5.020-04 1029. 8.818-04 6.449-04 1029. 8.991-04 6.552-04 1 1 NE 1212. 1212. 4.236-04 3.124-04 1212. 5.550-04 4.057-04 1212. 5.668-04 4.130-04 O ENE 1367. 1367. 2.140-04 1.578-04 1367. 3.773-04 2.755-04 1367. 4.751-04 3.462-04 y E 1170. 1170. 3.4R6-04 2.571-04 1170. 6.405-04 4.677-04 1170. 8.439-04 6.148-04 s ESE 1170. 1170. 4.631-04 3.415-04 1170. 8.0;5-04 5.882-04 1170. 1.025-03 7.409-04 M SE 1189. 1189. 5.015-04 3.698-04 1189. 9.158-04 6.687-04 1189. 1.259-03 9.173-04 W SSE 1422. 1422. 2.346-04 1.729-04 1422. 3.697-04 2.702-04 1422. 5.091-04 3.709-04 S 1190. 1198. 2.75H-04 2.034-04 1198. 4.251-04 3.107-04 1198. 6.592-04 4.802-04 SSw 1024 1024. 3.404-04 2.511-04 1024. 5.820-04 4.253-04 1024. 8.797-04 6.408-04 Sw 654 654. 7.494-04 5.528-04 654. 1.365-03 9.976-04 654. 2.595-03 1.890-03 WSW 494 494. 1.414-03 1.043-03 494. 2.503-03 1.830-03 494. 4.276-03 3.114-03 W 451. 451. 1.745-03 1.287-03 451. 4.334-03 3.164-03 451. 6.959-03 5.067-33 i wNw 451. 451. 1.630-03 1.202-03 451. 5.883-03 4.291-03 451. 8.959-03 6.523-03 Nw 485. 485. 1.535-03 1.132-03 485. 4.917-03 3.588-03 485. 8.718-03 6.347-03 NNw 640. 640. 9.993-04 7.372-04 640. 2.760-03 2.014-03 640. 4.153-03 3.024-03 QUAD-CITIES 142 SITE METEOROLOGICAL DATA 1/74 - 12/75 g MM O< MH M (n WH 19 O lc Z HH @H CD U1 se e

TABLE 7.2-8 (Co n t 'd ) OUAD-CITIES 1&2 MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR KR 90 DOWNWIND 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)/(UCI/SEC) (METERS) (MRAD /VR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCl/SEC) g-) C q N 864 864. 1.015-04 7.277-05 864. 1.480-04 1.047-04 864. 1.835-04 1.295-04 M NNE 1029. 1029. 5.079-05 3.641-05 1029. 3.336-05 2.365-05 1029. 2.365-05 1.669-05 U h NE 1212. 1212. 2.263-05 1.622-05 1212. 1.122-05 7.957-06 1212. 5.414-06 3.823-06 b ui ENE 1367. 1367. 8.713-06 6.242-06 1367. 7.049-06 4.989-06 1367. 6.174-06 4.360-06 H E 1170. 1170. 2.397-05 1.718-05 1170. 2.571-05 1.819-05 1970. 2.491-05 1.759-05 4 ESE 1170. 1170. 3.671-05 2.630-05 1170. 3.368-05 2.383-05 1170. 3.320-05 2.343-05 y SE 1189. 1189. 3.286-05 2.354-05 1189. 2.564-05 1.015-05 1169. 2.389-05 1.687-05 cn SSE 1422. 1422. 6.624-06 4.744-06 1422. 4.173-06 2.957-06 1422. 3.379-06 2.387-06 S 1190. 1198. 1.289-05 9.233-06 1198. 9.167-06 6.494-06 1198. 8.062-06 5.692-06 SSw 1024. 1024. 2.230-05 1.598-05 1024. 2.678-05 1.895-05 1024. 3.068-05 2.166-05 SW 654. 654. 1.085-04 7.776-05 654. 1.430-04 1.012-04 654. 1.925-04 1 358-04 WSW 494 494. 2.325-04 1.666-04 494. 3.155-04 2.237-04 494 4.241-04 2.992-04 w 451. 451 4.430-04 3.175-04 451. 7.115-04 5.036-04 451. 8.888-04 6 270-04 WNw 451. 451. 4.456-04 3.194-04 451. 7.985-04 5.648-04 451. 9.518-04 6 715-04 Nw 485. 485. 3.687-04 2.644-04 485. 5.259-04 3.722-04 485. 6.338-04 4.470-04 NNW 640. 640. 1.869-04 1.340-04 640. 2.602-04 1.841-04 640. 2.887-04 2.036-04 O QUAD-CITIES 142 SITE METEOROLOGICA1. DATA 1/74 - 12/75 M OMH

K(n WH MO A3 Z PH u) H CD U1 e

?

s TABLE 7.2-8 (Cont'd) QUAD-CITIES 1&2 MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTDRS FOR XE131M_ DOWNWIND RESTRICTED ELEVATED (STACK) RELEASE MIXED MODE (VENT) RELEASE GROUND LEVEL RELEASE DIRECTIDN AREA POUND RADIUS S SBAR RADIUS V VBAR RADIUS G G8AR (METERS) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /fR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) g) C 'J N 864. 864. 7.85G-06 2.614-06 864. 1.679-04 2.624-05 864. 3.832-04 5.531-05 [3 NNE 1029. 1029. 9.733-06 3.179-06 1029. 6.641-05 1.193-05 1029. 1.168-04 1.748-05 ? g HE 1212. 1212. 7.163-06 2.273-06 1212. 8.439-05 1.369-05 1212. 1.318-04 1.943-05 o F' ENE 1367. 1367. 3.90.1-06 1.252-06

1367, 6.241-05 1.007-05 1367.

1.018-04 1.527-05 H 04 E 1170. 1970. 4.399-06 1.483-06 1170. 5.307-05 8.942-06 1970. 1.018-04 1.533-05 "3 ESE 1170. 1970. 5.762-06 1.874-06 1170. 7.659-05 1.244-05 1970. 1.236-04 1.852-05 SE 1189. 1989. 7.180-06 2.348-06 1189. 1.039-04 1.679-05 1989. 1.695-04 2.554-05 m SSE 1422. 1422. 5.280-06 s.649-06 1422. 5.711-05 9.571-06 1422. 1.120-04 1.695-05 S 1190. 1190. 4.792-06 1.620-06 1198. 3.897-05 6.984-06 1198. 1.270-04 1.859-05 SSW 1024 1024. 4.744-06 1.703-06 1024. 3.457-05 6.363-06 1024. 1.004-04 1.480-05 Sw 654. 654. 7.621-06 2.564-06 654. 7.147-05 1.217-05 654. 2.691-04 3.740-05 WSW 494. 494. 1.360-05 4.359-06 494. 1.144-04 1.930-05 4 94. 3.309-04 4.619-05 w 451. 451. 1.325-05 4.404-06

451, 2.578-04 3.854-05 451.

5.281-04 7.239-05 WNw 451. 451. 1.295-05 4.169-06 451. 4.716-04 6.683-05 451. 8.198-04 1.099-04 Nw 485. 485. 1.344-05 4.232-06 485. 4.588-04 6.511-05 485. 9.954-04 1.324-04 NNw 640. 640. 8.598-06 2.912-06 640. 2.731-04 3.992-05 640. 4.793-04 6.570-05 OUAD-CITIES 182 SITE METEOROLOGICAL DATA 1/74 - 12/75 k h! n< MH 1 yw wH MO Af Z F* w @H CD U1 A e

TABLE 7.2-8 (Cont'd) OUAD-CITIES 1&2 MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR XE133M DOWNWIND RESTRICTED ELEVATED (STACK) RELEASE MIMED MODE (VENT) RELEASE GROUNO LEVEL RELEASE DIRECTION AREA BOUND RADIUS S SBAR RADIUS V VBAR RADIUS G GBAR (METERS) (METERS) (MRAD /vR)/(UCt/SEC) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) O h 'J N 864. 864 3.220-05 1.557-05 864 3.141-04 1.020-04 864. 6.591-04 1.972-04 NNE 1029. 1029. 3.913-05 1.883-05 1029. 1.437-04 5.239-05 1029. 2.087-04 6.491-05 ty I# NE 1212. 1212. 2.794-05 1.333-05 1212. 1.640-04 5.514-05 1212. 2.315-04 7.088-05 i Fa ENE 1367. 1367. 1.539-05 7.367-06 1367. 1.206-04 4.034-05 1367. 1.821-04 5.677-05 O 'J E 1970. 1170. 1.826-05 8.866-06 1170. 1.074-04 3.726-05 1170. 1.831-04 5.730-05 y ESE 1170. 1170. 2.307-05 1.109-05 1170. 1.490-04 5.013-05 1170. 2.211-04 6.889-05 s SE 1189. 1189. 2.889-05 1.390-05 1989. 2.011-04 6.735-05 1189. 3.049-04 9.554-05 M SSE 1422. 1422. 2.025-05 9.614-06 1422. 1.148-04 3.966-05 1422. 2.022-04 6.362-05 M S 1198. 1198. 1.995-05 9.692-06 1198. 8.410-05 3.061-05 1198. 2.214-04 6.729-05 SSW 1024. 1024. 2.100-05 1.037-05 1024. 7.677-05 2.847-05 1024. 1.765-04 5.402-05 SW 654 654. 3.160-05 1.533-05 654. 1.463-04 5.121-05 654. 4.449-04 1.273-04 wsw 494. 494. 5.367-05 2.568-05 494. 2.321-04 8.067-05 494. 5.497-04 1.581-04 w 451. 451. 5.428-05 2.625-05 451. 4.605-04 1.431-04 451. 8.607-04 2.421-04 WNw 451 451. 5.134-05 2.460-05 451. 7.960-04 2.332-04 451. 1.305-03 3.564-04 NW 485. 485. 5.208-05 2.479-05 485. 7.754-04 2.275-04 485. 1.571-03 4.246-04 NNW 640. 640. 3.590-05 1.745-05 640. 4.761-04 1.444-04 640. 7.807-04 2.196-04 QUAD-CITIES 142 $1TE METEOROLOGICAL DATA 1/74 - 12/75 k$ O< H U) H MO 0Z >* H @H ED U1 e 1

TABLE 7.2-8 (Cont'd) QUAD-CITIES 1&2 MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR XE133 DOWNWIND RESTRICTED ELEVATED (STACK) RELEASE MIXED MODE (VENT) RELEASE GROUND LEVEL RELEASE DIRECTION AREA BOUND RADIU5 S SBAR RADIUS y VBAR RADIUS G GBAR (METERS) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) O N 864 864. 3.323-05 1.26R-05 864. 3.515-04 1.056-04 864. 7.318-04 2.092-04 C .'d ba NNE 1029. 1029. 4.043-05 1.538-05 1029. 1.619-04 5.209-05 1029. 2.347-04 6.892-05 8 NE 1212. 1212. 2.900-05 1.100-05 1212. 1.840-04 5.641-05 1212. 2.597-04 7.550-05 ENE 1367. 1367. 1.609-05 6.101-06 1367. 1.361-04 4.167-05 1367. 2.053-04 6.041-05 b E 1170. 1970. 1.882-05 7.204-06 1170. 1.214-04 3.800-05 1170. 2.069-04 6.110-05 H [ ESE 1970. 1170. 2.390-05 9.085-06 1170. 1.677-04 5.149-05 1170. 2.494-04 7.343-05 SE 1189. 1169. 2.995-05 1.140-05 1189. 2.263-04 6.928-05 1189. 3.447-04 1.018-04 m SSE 1422. 1422. 2.128-05 8.026-06 1422. 1.294-04 4.035-05 1422. 2.285-04 6.766-05 U) 5 1198. 1198. 2.059-05 7.887-06 1198. 9.490-05 3.053-05 1198. 2.481-04 7.179-05 SSw 1024 1024 2.148-05 8.319-06 1024. 8.670-05 2.821-05 1024 1.977-04 5.746-05 SW 654 654. 3.23H-05 1.238-05 654. 1.635-04 5.127-05 654. 4.873-04 1.351-04 WSW 494. 494. 5.596-05 2.121-05 494. 2.566-04 7.985-05 4 94. 6.018-04 1.673-04 w 451. 451. 5.613-05 2.143-05 451. 5.031-04 1.460-04 451. 9.354-04 2.559-04 WNw 451. 451. 5.329-05 2.022-05 451. 8.636-04 2.415-04 451. 1.403-03 3.755-04 Nw 485. 485. 5.444-05 2.056-05 485. 8.414-04 2.355-04 485. 1.683-03 4.469-04 NNw 640.

640, 3.675-05 1.407-05 640.

5.222-04 1.497-04 640. 8.494-04 2.325-04 QUAD-CITIES 142 SITE METEOROLOGICAL DATA 1/74 - 12/75 o <: MH g tn wH MO % 'Z ww @w CO U' d i e

TABLE 7.2-8 (Cont'd) OUAD-CITTES 1&2 MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR XE135M DOWNWIND RESTRICTED ELEVATED (STACM) RELEASE MINED MODE (VENT) RELEASE _ GROUND iEVEL RELEASE DIRECTION AREA 8OUND RADIUS S SBAR RADIUS V VBAR RADIUS G GBAR (METERS) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) K)C h N 864 864. 3.872-04 2.393-04 864. 1.720-03 1.052-03 864 3.220-03 1.964-03 h3 NNE 1029. 1029. 4.150-04 2.564-04 1029. 8.409-04 5.166-04 1029. 9.696-04 5.923-04 a 1 NE 1212. 1212. 2.783-04 1.720-04 1212. 7.184-04 4.404-04 1212. 8.897-04 5.432-04 O ENE 1367 1367. 1.488-04 9.193-05 1367. 4.963-04 3.041-04

367.

7.041-04 4.302-04 H F' E 1170. 1170. 2.000-04 1.236-04 1170. 5.748-04 3.525-O' 1170. 8.513-04 5.202-04 d ESE 1970 1170. 2.540-04 1.570-04 1t70. 7.447-04 4.56?-04 1170. 1.021-03 6.237-04 m SE 1189. 1189. 3.027-04 1.871-04 1189. 9.546-04 5.650-04 1189. 1.382-03 8.442-04 m SSE 1422. 1422. 1.838-04 1.136-04 1422. 4.911-04 3.013-04 1422. 7.799-04 4.767-04 5 1198. 1198. 1.966-04 1.215-04 1198. 4.539-04 2.788-04 1198. 8.818-04 5.383-04 SSW 1024. 1024 2.234-04 1.381-04 1024. 4.870-04 2.992-04 1024. 8.318-04 5.078-04 Sw 654 654. 3.810-04 2.355-04 654. 9.794-04 6.000-04 654. 2.151-03 1.310-03 wSw 494. 494. 6.701-04 4.141-04 494. 1.647-03 1.010-03 4 94. 2.933-03 1.786-03 w 451. 451. 7.248-04 4.480-04 451. 2.815-03 1.721-03 451. 4.546-03 2.766-03 WNw 451. 451. 6.778-04 4.188-04 451. 4.326-03 2.638-03 451. 6.456-03 3.923-03 NW 485. 485. 6.649-04 4.109-04 485. 4.068-03 2.481-03 485. 7.321-03 4.448-03 NNw 640. 640. 4.526-04 2.797-04 640. 2.440-03 1.490-03 640. 3.837-03 2.213-03 QUAD-CITIES 182 SITE METEOROLOGICAL DATA 1/74 - 12/75 @y C <: H (A H MO

D Z HH

@H CD Un d e

i TABLE 7.2-8 (Cont'd) QUAD-CITIES 1&2 l MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR XE135 DOWNWIND RESTRICTED ELEVATE 0(STACK) RELEASE MIXED MODE (VENT) tLEASE GROUND LEVEL RELE ASE DIRECTION AREA BOUND RADIUS S SBAR RADIUS V VBAR RADIUS G GBAR (METERS) (METERS) (MP4t'/YR)/(UCI/SEC) (METERS) (MRAD /YR)/.VCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) g) C 7 N 864 864 J.814-04 1.522-04 864. 1.627-03 8.738-04 864. 3.046-03 1.633-03 f FJ NNE 1029. 1029. 1.387-04 1.831-04 1029. 8.676-04 4.670-04 1029. 1.015-03 5.448-04 8 NE 1212. 1212. 2.389-04 1.291-04 1212. 8.843-04 4.753-04 1212. 1.097-03 5.886-04 o FJ ENE 1367 1367. i.320-04 7.135-05 1367. 6.446-04 3 464-04 1367. 8.844-04 4.746-04 H E 1170. 1170. 1.5911-04 8.643-05 1170. 6.063-04 3.260-04 1170. 8.982-04 4.820-04 8 C' ESE 1170. 1170. 1.995-04 1.078-04 1170. 8.064-04 4.334-04 1170. 1.078-03 5.784-04 SE 1189. 1189. 2.499-04 1.351-04 1189. 1.081-03 5.R07-04 1189. 1.497-03 8.034-04 v3 SSE 1422. 1422. 1.717-04 9.281-05 1422. 6.407-04 3.445-04 1422. 9.941-04 5.335-04 S 1198. 1198. 1.743-04 9.424-05 1198. 5.054-04 2.720-04 1198. 1.040-03 5.576-04 SSW 1024 1024. 1.874-04 1.014-04 1024. 4.747-04 2.556-04 1024. 8.404-04 4.507-04 Sw 654 654. 2.773-04 1.499-04 654. 8.413-04 4.525-04 654. 1.934-03 1.036-03 wSW 494 494. 4.638-04 2.508-04 494. 1.325-03 7.127-04 4 94. 2.413-03 1.292-03 w 451. 451. 4.760-04 2.575-04 451. 2.257-03 1.211-03 451. 3.660-03 1.959-03 wNw 451. 451. 4.452-04 2.408-04 451. 3.587-03 1.922-03 451. 5.318-03 2.844-03 Nw 485. 485. 4.475-04 2.420-04 485. 3.499-03 1.875-03 485. 6.296-03 3.367-03 NNw 640. 640. 3.161-04 4.709-04 640. 2.247-03 1.205-03 640. 3.309-03 1.771-03 l 0N MM CUAD-CITIES 142 SITE METE 040 LOGICAL DATA 1/74 - 12/75 o< i H u) tD H MO NZ HH @H I OD U1 1 a

TABLE 7.2-8 (Cont'd) QUAD-CITIES 1&2 MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR XE137 DOWNWIND RESTRICTED ELEVATED (STACH) RELEASE MIXED MODE (VENT) RELEASE GROUND LEVEL RELEASE DIRECTIDN AREA B3OND RADIUS S SBAR RADIUS V VBAR RADIU5 G GUAR (METERS) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) OC h Q N 864. 864. 1.103-04 7.148-05 864. 3.450-04 2.226-04 864. 6.269-04 4.031-04 NNE 1029. 1029. 9.70G-05 6.286-05 1029. 1.429-04 9.211-05 1029. 1.551-04 9.976-05 g N NE 1212. 1212. 6.142-05 3.977-05 1212. 9.384-05 6.046-05 1212. 1.041-04 6.693-05 O b ENE 1367. 1367. 3.14G-05 2.037-05 1367. 6.455-05 4.156-05 1367. 8.642-05 5.557-05 y e E 1170. 1170. 4.952-05 3.206-05 1170. 1.038-04 6.686-05 1170. 1.438-04 9.247-05 g ESE 1170. 1170. 6.53H-05 4.233-05 1170. 1.306-04 8.411-05 1170. 1.739-04 1.119-04 m SE 1189. 1189. 7.175-05 4.646-05 1189. 1.515-04 9.758-05 1189. 2.184-04 1.404-04 m SSE 1422. 1422. 3.533-05 2.287-05 1422. 6.340-05 4.084-05 1422. 9.355-05 6.016-05 5 1998. 1198. 4.051-05 2.623-05 1198. 7.053-05 4.545-05 1196. 1.176-04 7.561-05 SSw 1024. 1024. 4.912-05 3.181-05 1024. 9.325-05 6.007-05 1054. 1.483-04 9.534-05 SW 654 654. 1.039-04 6.723-05 654. 2.145-04 1.382-04 F54. 4.306-04 2.768-04 wSW 494 494. 1.944-04 1.259-04 494. 3.884-04 2.503-04 494. 6.907-04 4.441-04 w 451. 451. 2.344-04 1.518-04 451. 6.798-04 4.377-04

451, 1.116-03 7.175-04 WNw 451.

451. 2.191-04 1.419-04 451. 9.533-04 6.133-04 451. 1.467-03 9.426-04 Nw 485. 485. 2.071-04 1.341-04 485. 8.128-04 5.230-04 485. 1.471-03 9.457-04 NNw 640. 640. 1.355-04 8.779-05 640. 4.535-03 2.918-04 640. 6.963-04 4.476-04 QUAD-CITIES 182 SITE METEOROLOGICAL DATA 1/74 - 12/75 gy MM O< MH g tn WH MO WZ HH W>* CD U1 e t

1 TABLE 7.2-8 (Cont'd) QUAD-CITIES 1&2 i MAXIMUM OFFSITE TINITE PLUME GAMMA DOSE FACTORS FOR XE138 DOWNWIND RESTRICTED ELEVATED (STACK) RELEASE MIXED MODE (VENT) RELEASE GROUND LEVEL RELEASE DIRECTION AREA BOUND RADIUS S SBAR RADIUS V VBAR RADIUS G GBAR (METERS 1, (METERS) (MRAD /YR)/fuCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) () C -J N 864 864. 9.510-04 6.932-04 864. 3.639-03 2.610-03 864. 6.657-03 4.761-03 E7 NNE 1029. 1029. 1.00R-03 7.337-04 1029. 1.823-03 1.392-03 1029. 2.003-03 1.434-03 [3 NE 1212. 1212. 6.713-04 4.886-04 1212. 1.515-03 1.088-03 1212. 1.812-03 1.296-03 ha ENE 1367. 1367. 3.575-04 2.602-04 1367. 1.034-03 7.422-04 1367. 1.433-03 1.025-03 H hJ E 1170. 1870. 4.060-04 3.538-04 1170. 1.225-03 8.001-04 1970. 1.755-03 1.256-03 8 hj ESE 1170. 8170. 6.158-04 4.482-04 1970. 1.578-03 1.133-03 1170. 2.106-03 1.507-03 SE 1189. 1889. 7.310-04 5.326-04 1189. 2.013-03 1.445-03 1189. 2.842-03 2.034-03 ui SSE 1422. 1422. 4.384-04 3.190-04 1422. 1.034-03 7.430-04 1422. 1.588-03 1.137-03 S 1190. 1998. 4.737-04 3.440-04 1998. 9.751-04 7.017-04 1198. 1.798-03 1.286-03 SSw 1024. 1024. 5.420-04 3.953-04 1024. 1.057-03 7.607-04 1024. 1.716-03 1.227-03 Sw 654 654. 9.326-04 6.792-04 654. 2.127-03 1.530-03 654. 4.441-03 3.174-03 wSW 494 494. 1.643-03 1.19G-03 494. 3.619-03 2.605-03 494. 6.111-03 4.369-03 w 459. 451 1.778-03 1.295-03 451. 6.032-03 4.329-03 451. 9.453-03 6.756-03 WNw 451. 451. 1.660-03 1.209-03 451. 9.114-C3 6.529-03 451. 1.336-02 9.542-03 Nw 485. 485. 1.633-03 1.190-03 485. 8.565-03 6.137-03 485. 1.500-02 1.077-02 NNW 640. 640. 1.113-03 8.103-04 640. 5.133-03 3.679-03 640. 7.487-03 5.350-03 OM QUAD-CITIES 182 SITE METEOROLOGICAL DATA t/74 - 12/75 MM o< H U3 H MO AZ HH @H CD SP e 9

TABLE 7.2-8 (Cont'd) OUAD-CITIER 1&2 MAXIMUM OFFSITE FINITE PLUME GAMMA DOSE FACTORS FOR AR 41 DOWNw!ND R13TRICTED ELEVATED (STACK) RELEASE MIXED MODE (VENT) RELEASE GROUND LEVEL RELEASE DIRECT IDN AREA BOUND RADIUS S SBAR RADIUS V VBAR RADIU5 G GUAR (METERS) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /YR)/(UCI/SEC) (METERS) (MRAD /VR)/(UCI/SEC) g) Cg N 864. 864. 1.279-03 9.016-04 864. 5.819-03 4.102-03 864. 1.057-02 7.449-03 ,3 NNE 1029. 1029. 1.507-03 1.062-03 1029. 3.201-03 2.256-03 1029. 3.492-03 2.462-03 hJ NE 1212. 1212. 1.044-03 7.361-04 1212. 3.109-03 2.192-03 1212. 3.698-03 2.607-03 b I ENE 1367. 1367. 5.741-04 4.040-04 1367. 2.218-03 1.564-03 1367. 2.965-03 2.090-03 H E 1170. 1170. 7.079-04 4.991-04 1170. 2.172-03 1.531-03 1170. 3.084-03 2.175-03 63 h# ESE 1170. 1170. 0.827-04 6.223-04 1870. 2.062-03 2.018-03 1170. 3.703-03 2.611-03 SE 1189. 1189. 1.090-03 7.742-04 1189. 3.808-03 2.685-03 1189. 5.128-03 3.615-03 v3 t SSE 1422. 1422. 7.391-04 5.211-04 1422. 2.233-03 1.574-03 1422. 3.329-03 2.347-03 S 1198. 1198. 7.689-04 5.371-04 1198. 1.836-03 1.294-03 1198. 3.517-C3 2.480-03 SSW 1024. 1024. 8.349-04 5.886-04 1024. 1.764-03 1.244-03 1024. 2.891-03 2.038-03 SW 654 654. 1.258-03 8.072-04 654. 3.150-03 2.221-03 654. 6.756-03 4.763-03 wSW 494. 494. 2.140-03 1.509-03 494. 5.085-03 3.585-03 494. 8.554-03 6.031-03 W 451. 451. 2.219-03 1.564-03 451. 8.373-03 5.903-03 451. 1.300-02 9.168-03 WNw 451. 451. 2.074-03 1.462-03 451. 1.302-02 9.179-03 451. 1.885-02 1.329-02 Nw 485. 485. 2.07G-03 1.463-03 485. 1.266-02 8.926-03 485. 2.219-02 1.565-02 NNw 640. 640. 1.443-03 1.017-03 640. 8.046-03 5.673-03 640. 1.156-02 8.142-03 QUAD-CITIES 182 SITE METEOROLOGICAL DAT A 1/74 - 12/75 t, E Mo< H I/3 H MO WZ VH @H 00 (P e 9

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QUAD-CITIES REVISION 11 DECEMBER 1985 8.0 RADIOACTIVE EFFLUENT TREATMENT SYSTEMS, MODELS FOR SETTING GASEOUS AND LIQUID EFFLUENT MONITOR ALARM AND TRIP SETPOINTS, AND ENVIRONMENTAL RADIOLOGICAL MONITORING TABLE OF CONTENTS PAGE 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 l 8.1.2 Alarm and Trip Setpoints 8.1-1 8.1.3 Main Chimney Releases 8.1-3 8.1.3.1 Chimney Noble Gas Monitors 8.1-3 8.1.3.2 SJAE Off-Gas Monitors 8.1-5 I 8.1.3.3 Allocation of Effluents from Common Release Points 8.1-6 l 8.1.4 Reactor Building Ventilation Stack Releases 8.1-7 8.1.4.1 Ventilation Stack Monitors 8.1-7 8.1.4.2 Allocation of Effluents from Common Release Points 8.1-8 8.1.5 Symbols Used in Section 8.1 8.1-9 t 8.1.6 Constants Used in Section 8.1 8.1-11 8.2 LIQUID RELEASES 8.2.1 8.2.1

System Design

8.2-1 8.2.2 Alarm Setpoints 8.2-1 8.2.3 Radwaste Discharge Line Releases 8.2-2 8.2.3.1 Radwaste Discharge Monitor 8.2-2 l 8.2.3.2 Allocation of Effluents from Common l Release Points 8.2-3 l 3.2.3.3 Administrative and Procedural Controls l for Radwaste Discharges 8.2-4 8.2.4 Service Water Header Releases 8.2-5 8.2.4.1 Service Water Effluent Monitors 8.2-5 8.2.5 Determination of Initial Dilution Stream l Flow Rates 8.2-6 8.2.6 Symbols Used in Section 8.2 8.2-7 l 8.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM 8.3-1 8.4 ENVIRONMENTAL RADIOLOGICAL MONITORING 8.4-1 8-i

QUAD-CITIES REVISION 11 DECEMBER 1985 l ODCM LIST OF TABLES FOR QUAD-CITIES SECTION 8.0 NUMBER TITLE PAGE 8.4-1 Radiological Monitoring Program 8.4-2 8.4-2 Reporting Levels For Radioactivity Concentrations In Environmental Samples 8.4-6 8.4-3 Maximum Values For The Lower Limits of Detection (LLD) 8.4-7 4 8-ii

QUAD-CITIES REVISION 11 DECEMBER 1985 ODCM LIST OF FIGURES FOR QUAD-CITIES SECTION 8.0 d NUMBER TITLE 8.1-1 Simplified Gaseous Radwaste 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 Milk, Fish, Water and Sediment Sample Locations l l l 8-iii i t

f QUAD-CITIES REVISION 11 DECEMBER 1985 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

A simplified gaseous radwaste and gaseous effluent flow diagram is provided in Figure 8.1-1. 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 pro-viding for delay or holdup for the purpose of redacing the total radioactivity prior to release to the environment. 8.1.2 Alarm and Trip Setpoints Alarm and trip setpoints of gaseous effluent monttors at the principal points of release of ventilation exhaust air containing radioactivity are established to ensure that the release limits l of 10 CFR 20 are not exceeded. The setpoints are found by solving Equaticns 2.6 and 2.7 for each class of release. l l For this evaluation the radioactivity mixture in the exhaust air is assumed to have the composition of gases listed in Table 3-3 from " Technical Derivation of BWR 1971 Design Basis Radioactive Material Source Terms", NEDO-10871, March 1973, General Electric Company. This mixture of radioactive gases is representative of the activity found at the point of release from the fuel with no radioactive decay accounted for. 8.1-1

QUAD-CITIES REVISION 11 DECEMBER 1985 Equation 2.6 is rewritten using the fractional composition of l each nuclide, f, and a total release rate, Q, f r each class: i t 1.11 O I8i*f) +O I i*f) <500 " ts i tv i (8.1) f Fractional Radionuclide Composition g The release rate of radionuclide i divided by the total release of all radionuclides. Q Total Release Rate, Stack Release (pCi/sec) ts The release rate for all radionuclides due to a stack release'. Q Total Release Rate, Vent Release (pCi/sec) tv The release rate for all radionuclides due to a vent release. Equation 8.1 can be solved for Q for each class of release t for release limit determinations. Sinilarly, Equation 2.7 can be rewritten: l Ei, (X/Q) s O tv i **PI-A R/3600u ) ts i **PI-A R/3600u ) (X/Q)y Q f f + i y i s + 1.11 "S Qg ts i + v Qitvifx3000 f f (8. 2) .) Equation 8.2 can be solved for Q for each class of release and t a corresponding release limit be determined. The most conservative release limit determined from Equations 8.1 and 8.2 will be used in selecting the appropriate alarm and trip setpoints for each class of release. The exact settings will be selected to ensure that 10 CFR 20 limits are not exceeded. 8.1-2

QUAD-CITIES REVISION 11 DECEMBER 1985 Surveillance frequencies for gaseous effluent monitors will be as stated in Table 4.2-4 of the Technical Specifications. Calibration methods will be consistent with the definitions found in Section 1 0 of the Technical Specifications. 8.1.3 Main chimney Releases 8.1.3.1 Chimney Noble Gas Monitors Releases of radioactive noble gases from the main chimney release point are continuously monitored by a General Electric (GE) off-line monitoring system consisting of two instrument channels, each of which uses a scintillation detector as its sensing element. Samples of the effluent stream are taken high in the chimney, where good mixing is ensured, and drawn through a constant flow-and-pump network, past the detectors. The detector equipment part numbers are RE 1/2-1731A and RE 1/2-1731B. Each monitoring channel consists of a 2-inch by 2-inch sodium iodide thallium activated scintillation detector, shielded l sample chamber, pulse preamplifier, and process radiation (log count) monitor with integral power supply for providing high voltage to the detector. The channels share a common recorder and common trip auxiliaries unit whose output initiate high radiation alarm annunciations. The recorder, alarms, 1 and remote control switches for the chimney gas monitoring system are located in the main control room. The monitor display has a logarithmic scale with a range of -1 6 10 to 10 counts per second. 8.1-3

QUAD-CITIES REVISION 11 DECEMBER 1985 = In addition to the GE noble gas monitors, the gas sample is routed through a filter paper on which particulates are deposited, through a charcoal cartridge which traps the iodines, and through Eberline low and medium range noble gas detectors. Under accident conditions, the above pathway can be bypassed and the sample routed through an Eberline/Victoreen system which has an Eberline high range noble gas monitor and a Victoreen postaccident particulate and iodine sampler. The Eberline low and medium range noble gas detectors view 'the same volume, while the Eberline high range noble gas detector views externally a section of one inch stainless steel tubing as its sample volume. The low range is monitored by a beta scintillation detector (Eberline Model RDA-3A), while both the medium and high range measurements are performed l by an energy-compensated GM detector. Background subtraction is provided for all three ranges. Sample flow is provided by a stainless steel diaphragm vacuum pump and an air flow regulator. Sample flow is set to insure isokinetic sampling l monitored by a solid-state flow sensor. The three Eberline noble gas detectors are part of a microprocessor-controlled gaseous effluent monitoring system (Eberline SPING-4). The monitoring system's control terminal, strip chart recorder panel 912-1 and annunciating panel 912-4 are located in the control room on Panel 912-1. The control terminal provides immediate access to current detector activity, operating parameo rs, and history files for any detector. Changes in detector operational status are automatically printed and audibly acknowledged. The SPING-4 microprocessor's memory has battery backup to maintain all operating parameters and history files for any detector in the event of a system power loss. l 8.1-4 l

\\ QUAD-CITIES REVISION 11 DECEMBER 1985 s For all of the above monitors, the sample pumps and detectors, with local controls, are located in the chimney sample house at the base of the chimney. Power is supplied to the process radiation' monitors from the station 48/24-Vdc battery systems. The main chimney noble gas monitor alarm setpoints will be selected to ensure that the combined release rate of the main chimney and the reactor building vent stack does not exceed the most conservative release limit determined from Equations 8.1 and 8.2. 8.1.3.2 SJAE Off-Gas Monitors ~ The major source of radioactive noble gases is from each unit's off-gas system. Each unit's off-gas system has its own radia-tion detection instrumentation capable of isolating the off-gas release pathway. Off-gas from the main condenser is monitored for gross gamma activity downstream of the steam jet air eject 6rs (SJAE) and prior to release to the main chimney. Continuous radiation monitoring is maintained on the off-gas hold-up pipe. The off gas mca-itoring system for each unit is performed in two channels, each of which includes a gamma sensitive ion-chamber detector, and a logarithmic radiation monitor with integral power supply. The two channels share a common two pen recorder and a trip auxiliaries unit whose output feeds an interval timer. System controls, alarm annunciators, recorder, and displays are located on panels in the main control room. The ion-chamber detectors are mounted adjacent to and at the beginning of the off-gas hold-up pipe, a 36-inch diameter header whose function is to contain the off-gas for a period of time dependent on off-gas flow and allow for radioactive decay prior to release to the chimney. 8.1-5

QUAD-CITIES REVISION 11 DECEMBER 1985 = A high radiation condition in the hold-up pipe will initiate an interval timer with a variable setting of 0 to 15 minutes. When the preselected time interval has elapsed, an isolation valve at the inlet to the chimney from the off-gas system will automatically close, preventing release of radioactive gases from the affected off-gas system. Power is supplied to the off-gas process radiation monitors from the station's 48/24-Vdc battery systems. Power to the interval timer is from the 120-Vac essential service bus. The timer provides the signal to the solenoid-operated valves which control the air supply to the air-operated isolation valve (equipment part number A0 1(2)-5406). The monitor display 6 is a logarithmic scale and has a range of 1 to 10 units (mR/hr ). The detectors equipment part numbers are RE 1(2)-1733A and RE 1(2)-1733B. The SJAE monitor alarm setpoints will be selected to ensure that the combined release rate of the main chimney and station vent stack does not exceed the most conservative release limit determined from Equations 8.1 and 8.2. 8.1.3.3 Allocation of Effluents from Common Release Points Radioactive gaseous effluents released from the main chimney are comprised of contributions from both units. Under normal operating conditions, it is difficult to allocate the radio-activity between units due to fuel performance, in-plant leakage, power history, and other variables. Consequently, allocation will normally be made evenly between the units. During extended unit shutdowns or periods of known differences, the apportionment will be adjusted accordingly. The allocation of the effluents will be made on a monthly basis. 8.1-6

QUAD-CITIES REVISION 11 DECEMBER 1985 = 8.1.4 Reactor Building Ventilation Stack Releases 8.1.4.1 Ventilation Stack Monitors Releases of radioactive noble gases from each reactor building's ventilation system are monitored prior to introduction to the ventilation stack. Two sensor and converter (detector) units are located in each unit's reactor building exhaust duct, and provide continuous gamma radiation monitoring. The sensor is a Geiger-Mueller tube, polarized by high voltage from the power supply. The output signal from each sensor converter is applied to an indicator and trip unit, where it is amplified and used to drive a meter. This unit also provides trip functions for upscale and downscale alarms through auxiliary units. A downscale trip in either channel annunciates a low radiation (malfunction) alarm. An upscale trip in either l channel initiates a reactor building ventilation system high-high radiation alarm. Control logic is such that one channel high level trip or two channel low level trips will shut down and isolate the reactor building ventilation system for both units and initiate the standby gas treatment system. The exhaust duct monitors provide a signal to a two pen recorder which will annunciate a high radiation condition in the exhaust duct. This is an alarm only, and does not initiate corrective action. The recorder, controls, indicator and trip units, alarms, and annunciators are located on panels in the main control room. The power supply to each sensor channel is supplied from a different power source. The A channel is fed from the 120-Vac. A reactor protection system and the B channel are fed from the 120-Vac B reactor protection system. 8.1-7 l

QUAD-CITIES REVZSION 11 DECEMBER 1985 The indicating meters have a logarithmic scale with a range of 0.01 to 100 mR/hr. The sensor and converter units have equipment part numbers RE 1(2)-1735A and RE 1(2)-1735B. Each reactor building's ventilation system is isolated by closure of two air-operated butterfly valves (A0 1(2)A-5741 and A0 1(2)B-5741) located in series downstream of the reactor building ventilation supply fans, and by closure of two air-operated butterfly valves (A0 1(2) A-5742 and A0 1(2)B-5742) located in series downstream of the radiation sensors and up-stream of the exhaust fans. Air supplies to these valves are controlled by solenoid valves powered from the 125-Vdc station battery systems. The control logic relays which operate these solenoids are powered by the 120-Vac essential service bus. The reactor building ventilation stack monitor alarm setpoint will be 2 mR/hr above background. Using an empirical relationship of mR/hr and U/Ci/sec at design flowrates, the calculated reactor building ventilation stack release rate will be etaployed in Equation 8.1 and 8.2 to select the most conservative main chimney monitor alarm setpoints. 8.1.4.2 Allocation of Effluents from Common Release Points Radioactive gaseous effluents released from the reactor building vent stack are comprised of contributions from both units. Estimates of noble gas contributions from each unit will be made by analyzing grab samples from the individual units. Allocations of radiciodine and radioactive particulate releases will be made by analyzing samples taken from continuous samples on each unit. The allocation of the effluents will be made on a monthly basis. 8.1-8

l QUAD-CITIES REVISION 11 DECEMBER 1985 8.1.5 Symbols Used in Section 8.1 SYMBOL NAME UNIT O Total Release Rate, Stack Release (pCi/sec) ts 5 Gamma Whole Body Dose Constant, Stack (arad/yr per g Release pCi/sec) f Fractional Radionuclide Composition g Q Total Release Rate, Vent Release (pCi/sec) tv V Gamma Whole Body Dose Constant, (mrad /yr per Vent Release pCi/sec)) O Release Rate of Nuclide i, Stack Release (pCi/sec) is O Release Rate of Nuclide i, Vent Release (pCi/sec) gy L Beta Skin Dose Constant (mrem /yr per g UCi/m ) l 3 (x/Q) s Relative Effluent Concentration, (sec/m ) Vent Stack Release A Radiological Decay Constant (hr-1) g R Downwind Range (m) u Average Wind Speed, Stack Release (m/sec) s 8.1-9

QUAD-CITIES REVISION 11 DECEMBER 1985 s SYMBOL NAME UNIT 3 ()(/Q) y Relative Effluent Concentration, Vent sec/m ) Release u Average Wind Speed, Vent Release (m/sec) y S Gamma Dose Constant, Stack Release (mrad /yr per i pCi/sec) V Gamma Dose Constant, Stack Release (mrad /yr per g pCi/sec) i l 8.1-10

QUAD-CITIES REVISION 11 DECEMBER 1985 8.1.6 Constants Used In Section 8.1 NUMERICAL VALUE NAME UNIT 1.11 Conversion Constant (mrem / mrad) 3600 Conversion Constant (sec/hr) I l I l 8.1-11

- ~ _ - .. ~ - - - 34 1 FFNISION I1 er g e gg - *i ra ge:F ICa':% -g- - - - - -, yg g, [ - ~ ry'r 'ca7 ] DECf:MBI:R 19M _]. f S2'X'O C8_. _ _ _ _.. _.1 -+me : - -m W j q cy g g g eg ._*?_ l an' ruR9: m oc. ' 77:* a = t'~ _h ^ esavin v Rf CVClf 6000 Ciu "' N E-1-If b a l ' (P' f) u%1 T I 5:E g, c, , f 7. i rg pg, Rf Cow:4 A BiDC. l 173,9 l b- [,gg ""2 f /?-1](4B RE Pgg r.Jd ?- wr en smo Cr. Tupelw 9t Dc. I F??00 CT u y _, I rj. i rega, t;ht i 2 28 ' I,@h[- P .mx C,. , j f el fleu [, 15'"" "1 Rar,er g[l' a x. j ~ ' ~ ~ - ~ g_ p 411800 CFM H lp 5,- 7 -"d@}'8'1k

f vt =7 tt atich 4E - 78 M

[CG ll CHI'" ' = e 9 Oraw nR 159* A8tovt RADE EEE r-~ q ig g g,.tnc' r----- I f fI 1 Wp, f ++ + eDue l i W* W Hilt 0 uP l-- s e ups.eef N f -[l RFCraelg R IN fg' g--- J DRyte f-= CHARC0at 4050RAF R Y-al# (JE CTCIR i I'- f'h ~}, i __. lhil. 2 _.. IfuR914 BIOC.l ; aw; tnt are l,- g%i f f Ri ACTOR Butt 01% -M- ,...d_... A M 5', - g R a oc, e scis wt ut it at t ah '=' 'M-y

J setsat sie I

'...w. . 1 A. lTupstw stoc.] Rf I-24 en w{]; h}W Rf f { 74 t RB y e out s 2 Rf ACTOR ~ e E E h] ',,g l @L U[i-~ 3 ' o*W C!". ' '.I,l,',' 8?' p suit or=0 1 1 Pt a%f GRADE "3 l> 3 3 unit 2 '04500 cru j ,-g-{/ a90vt ust tnit i J l j r 7 Rt -i 2e oc Rf I-24'80 l Davu t t Puwct 0{

-E p U-

/ (,<p,'> v n. LECf ND AND NOTES "W - g - ws.Pa s it le $ PaRitcut ait saett U[ Reatm osnCm' t QUAD-CITIES STATION -h-CeaRtcat -@~ 10014 saett ' t,09,P rH Q q g ),y NoRunt t y Comtlues Units 1 & 2 g -{tI!H tt's THRtRJGM RADlaf10h WINIT@: F P4aarf cut an -,i - acasimat rtes Paru g gg $N w-t::. W osuu a

ton -J-fies Ettu 47 GASE0t's EFFLUENT FLOW DIAGRAM MIIE 3 All IL O'rt s'. NOT atit,A, 8 II5 I DISIC" RANCE ME E Cas Ft03 pa

o QUAD-CITIES REVISION 11 DECEMBER 1985 8.2 . LIQUID RELEASES = e 8.2.1

System Design

Simplified liquid radwaste and liquid effluent flow diagrams are provided in Figures 8.2-1 and 8.2-2. A liquid radwaste treatment system shall be a system designed and installed to treat radioactive liquid effluents by collecting the liquids, providing for retention or holdup, and providing for treatment by demineralization to reduce the total radioactivity prior to the release of liquids to the environment. 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. The concentration limit (Cyg,) in the discharge line prior to dilution in the initial dilution stream is: - d pave + Fmax C = MPC lim r (6.3) p max C Limiting Concentration (u Ci/ml) yg in Discharge Line The maximum concentration in the dis-I charge line permitted to be discharged to the initial dilution stream. MPC Weighted Maximum Permissible (uCi/ml) Concentration n n [Cf g A MPC = l U# C. n A (8.4) MPC g g y M C; 8.2-1

\\ QUAD-CITIES REVISION 11 DECEMBER 1985 t where: C = u Ci/ml of nuclide i; i MPC i = maximum permissible concentration pCi/ml of nuclide 1; and A = pCi of nuclide i released in time t. 1 3 Fr Maximum Flow Rate, Radwaste Discharge (ft /sec) max The maximum flow rate of radwaste from the discharge tank to the initial dilution stream. F Average Flow Rate, (ft /sec) yg Initial Dilution Stream The average flow rate of the initial dilution stream which carries the radionuclides to the unrestricted area boundary. Surveillance frequencies for liquid effluent monitors will be as stated in Table 4.2-3 of the Technical Specifications. Calibration methods will be consistent with the definitions found in Section 1.0 of the Technical Specifications. 8.2.3 Radwaste Discharge Line Releases 8.2.3.1 Radwaste Discharge Monitor l The radwaste releases are currently monitored for radioactivity using two grab samples and a composite sample. These samples t are analyzed for alpha, beta, and gamma radiation. MPC calculations are done to determine discharge rate and dilution volume. 8.2-2

) QUAD-CITIES REVISION 11 DECEMBER 1985 s Installation of a new continuous monitor for the radwaste discharge line is in progress. It is an offline monitoring system which uses a 2-inch by 2-inch sodium iodine thallium actuated scintillation detector in a lead-shielded housing. The sample container is bowl shaped to minimize crud buildup. A GM tube is used to determine the background radiation level. The radwaste discharge monitor provides a signal to a recorder and an Eberline CT-2 control terminal. A high radiation alarm will be activated by the control terminal. The process radiation monitor, control terminal, alarm, and annunciator are located on panels in the main control room. i The process liquid monitor has a logarithmic scale with -1 6 a range of 10 to 10 counts /sec. The monitor is powered by 120-Vac. The radwaste discharge line detector (RE 1/2-1799-01) is mounted adjacent to the radwaste control room. The flow is routed there after the flow control valves and prior to the selection of several alternate discharge routes. The alarm setpoint for the radwaste discharge monitor is established at or below the maximum concentration determined by Equation 8.3. The concentration is converted to an alarm l setpoint using an efficiency curve developed for the monitor through use of a Cs-137/Ba-137m liquid calibration sources. 8.2.3.2 Allocation of Effluents From Common Release Points Radioactive liquid effluents released from the radwaste j treatment system are comprised of contributions from both units. Determination of the allocation of waste is achieved by comparing I 8.2-3

) QUAD-CITIES REVISION 11 DECEMBER 1985 the pump timer totals for each unit's floor drain and equipment drain pumps to the amount of waste sent to the river discharge tank from the floor drain and waste collector storage tanks. Liquid effluents from laundry and chemical waste are allocated evenly between units. During extended unit shutdown or periodt I of significant plant input differences, the apportionment will be adjusted accordingly. The allocation of the effluents will be made on a monthly basis. 8.2.3.3 Administrative and Procedural Controls for Radwaste Discharges Administrative and procedural controls have been implemented to ensure proper control of radioactive liquid radwaste discharges, to preclude a release in excess of 10 CFR 20 limits. The dis-charge rate for each batch is calculated by a technician and then independently verified by two operating staff personnel. A single river discharge tank has been designated and modified from which all radwaste discharges will normally be released. This tank has manual inlet and discharge valves which can be locked. The inlet valve is locked closed during recirculation of the tank prior to sampling and during the discharge to preclude an accidental addition to the tank which could change its activity. The discharge valve is locked closed at all times except during the discharge. All other lines, which tie-in with the discharge line, are locked closed. The high and low flow control valves are selected by a key-lock switch which allows the use of only one of the two flow control valves at any one time. The key to this switch and the locked valves is under the administrative control of the radwaste foreman. 8.2-4 i

QUAD-CITIES REVISION 11 DECEMBER 1985 s A documented valve checklist is prepared for each batch discharge. The proper valve lineup is checked by the operator and the radwaste foreman, prior to release. If any sudden significant increase of the radiation monitor occurs during the discharge, the release is terminated. These controls are documented in Station Operating and Administrative Procedures. 8.2.4 Service Water Header Releases 8.2.4.1 Service Water Effluent Monitors Each unit's main service water effluent header is monitored for radioactivity by taking grab samples every twelve hours and analyzing for gross beta activity. I Installation of a new continuous monitor for both service water headers is in progress. It is an offline continuous monitoring system. The process liquid monitor uses a 2-inch i by 2-inch sodium iodine thallium-activated scintillation detector in a lead shielded housing. The samp,le container is bowl shaped to minimize crud buildup. A GM tube is used to determine background radiation levels. The service water effluent monitor on each unit provides a signal to a recorder and to an Eberline CT-2 control terminal, l which initiates a high radiation alarm. The process radiation monitor, recorder, alarm and annuciator are located on the panels in the main control room. i l The process liquid monitors have logarithmic scales with a ~1 6 range of 10 to 10 counts per second. The monitors are l powered from 120 Vac. I 8.2-5

QUAD-CITIE REVISION 11 DECEMBER 1985 s ~ The service water system detectors (RE 1(2)-1799-01) are located adjacent to the main service water effluent header on each unit prior to release to the discharge bay. The alarm setpoints for the service water effluent monitors are established at or below the maximum concentration determined by Equation 8.3. 8.2.5 Determination of Initial Dilution Stream Flow Rates 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 instrumenta-tion will be operated and maintained as prescribed by the Tech-nical 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

'l QUAD-CITIES REVISION 11 DECEMBER 1985 8.2.6 Symbols Used In Section 8.2 SYMBOL NAME UNIT C lim Liquid Release Limit (pCi/ml) MPC Weighted Maximum Permissible (pCi/ml) Concentration C Nuclide Concentration (pCi/ml) g MPC Maximum Permissible g Concentration (pCi/ml) A Nuclide Quantity Released (pCi) g F[,, Maximum Flow Rate, Radwaste (f t /sec) Discharge d F Average Flow Rate, Initial (f t /sec) ave Dilution Stream i l 8.2-7

t' e i 4 OUw I ~85 REVISION 11 E s'$ DECEMBER 1985 w8Ba _t i 4 I l I l g a y n iIs-i i m ': zJ a = E's I j E EU g?w ab: -25 l t = n n I I l l l I i t I it l' = !l RE E l!

., l me,

a-em i i_,, s-- = 5b5 .[EE ik El 3 l l c:$ lil l a( l s n j l =, o t I i =,- = i I i I g l l l I I I ! l l l !-l ll -l l l 5 llE5-i!N ' sf ' 6 Ei j i !! l l EE y:5 c5 I l ta 7- '... l i. 1 l 1 C. i l i i h i. ^ l i i i i l u sl i l !l =s l w p l l3j~' VE!' i EE!' ~ EE! -EI!' lE*~j i!5~{ l'5~j l"'~, l j I l l 1 l QUAD-CITIES STATION Units 1 & 2 i FIGURE 8.2-1 l SIMPLIFIED LIQUID RADWASTE l PROCESSING DIAGRAM 1 l l

i A REVISION ll , cr a 1 DECEMBER 1985 l i * .I i l E li I' y j r e; E 5 i el $ I O L~ l e ls ( i _ Ej l 2 i A I ~ i 8 t l l 1 l e.=~ =i !E!i l I = + = 3 l -A E y a l ^4, s' i I s 9 E y. l r w vs 9 3 3a a l - gess os= xr 9 Ei n ; ls 3

s : :

i ! 8! ' Il hd! l Jg;;:l O tu 1 ) E! i 15'SEl* L_i Is! i a i E5l j l ~ / . 5 Eli-! ( = gi-i i i i l f Vl l i [ l i i. = i i, t ( le l i I i in E:. = / ,/ E ', I 5 +' l! H _ m - s - j e / - E! T 2 V,' - r g: EFbM -eII != 1 QU AD-CITIES STATION Units 1 4. 2 FIGURE 8.2-2 SIMPLIFIED LIQUID EFFLUENT FLOW DIAGRAM

) QUAD-CITIES REVISION 11 DECEMBER 1985 = 8.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM 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. l r t 8.3-1

i REVISION 11 DECEMBER 1985 = i l t r n I l / i NN m I .I n + g e 0 0 i oo j m i l l "I a. i =- l a l 6 u., E E i I s\\ l 5 i l i i i i a il sI eg E5 ! i Ep! ust "It

t KE-Ex-El5l

_35;E 1 53 sc l l

3El I

4 1

33 Eav EE!i t,

QUAD-CITIES STATION Units 1 6. 2 FIGURE 8.3-1 i SIMPLIFIED SOLID RADWASTE PROCESSING DIAGRAM

l ~ QUAD-CITIES REVISION 11 DECEMBER 1985 8.4 ENVIRONMENTAL RADIOLOGICAL MONITORING The environmental radiological monitoring program to be performed in the environs around Quad-Cities Station is given in Table 8.4-1. Figure 8.4-1 shows the 16 fixed air sampling sites and TLD locations; also shown are the " outer ring" (approximately 5 miles distant) TLD locations. Figure 8.4-2 shows the " inner ring" TLD locations. The TLD's are code numbered as follows: XYY-N, l where: X= J means inner ring, X= 2 means outer ring, and YY-N is an identification code. Figure 8.4-3 shows the milk, fish, water, and sediment sample locations. The reporting levels for radioactivity concentrations in envi-ronmental samples are given in Table 8.4-2. The p(hetical lower limits of detection for this program are given in Table 8.4-3. 8.4-1

TABLE 8.4-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM EXPOSURE PATHWAY SAMPLING OR TYPE AND FREQUENCY AND/OR SAMPLE SAMPLING OR MONITORING !.OCATIONS COLLECTION FREQUENCY OF ANALYSIS 1. Airborne a. Onsite or Near Field

Particulate Sampler:

Q-01 Onsite Station 1 0.5 mi N Continuous sampler Gross beta analysis b Q-02 Onsite Station 2 0.5 mi ENE operation with partic-following filter change Q-G3 Onsite Station 3 0.6 mi S ulate filter collec-Q-04 Nitrin 1.5 mi NE tion weekly and Radiciodine Canister: Q-05 Saddle Club Dairy 1.8 mi SSE radiolodine canister Farm collection bi-weekly I-131 analysis bi-weekly Q-06 Hanson's Boat 1.8 mi NNW Landing Sampling Train: Test and maintenance weekly b. Far Field" Q-07 Clinton 9.0 mi NE Continuous sampler Particulate Sampler: Q-08 Sikkema Fara 7.0 mi ENE operation with partic-Q-09 Erie 13.0 mi ESE ulate filter exchange Gross beta when o b,c Q-10 Hillsdale 10.0 mi SE weekly and radiolodine analyses are made Q-ll Port Byron 8.0 mi S canister exchange U Q-12 Bettendorf 13.0 mi SW bi-weekly Radiciodine Canister; o S Q-13 Princeton 4.8 mi SW y Q-14 Utica Ridge Road 11.0 mi ESE I-131 whgn analyses y Q-15 DeWitt 13.0 mi WNW are made m Q-16 Low Moor 6.0 mi NNW Sampling Train: Test and maintenance weekly N$ R5 5"

e d

e 4 s

TABLE 8.4-1 (Cont'd) EXPOSURE PATHWAY SAMPLING OR TYPE AND FF.EQUENCY AND/OR SAMPLE SAMPLING OR MONITORING LOCATIONS COLLECTION FREQUENCY OF ANALYSIS 2. Direct Radiation a. At Air Sampling Sites

Quarterly Camma dose quarterly Same locations as fixed air sampling locations in Item 1.

d b. Inner Rine Quarterly Gamma dose quarterly 101-1 0.7 mi N 101-2 0.8 mi N 102-1 1.7 mi NNE 102-2 1.7 al NNE 103-1 1.2 mi NE 104-1 1.1 mi ENE 104-2 0.95 at ENE 104-3 0.63 mi ENE 105-1 0.75 mi E 106-1 0.71 mi ESE O 106-2 0.71 pi ESE e. 107-1 0.73 mi SE 7 107-2 0.78 al SE C 'w 107-3 0.86 mi SE 108-1 0.96 mi SSE

j m

108-2 0.89 mi SSE 109-1 0.87 mi S 109-2 0.98 mi S 111-1 2.6 mi SW 111-2 2.6 mi SW 112-1 2.5 mi WSW 112-2 2.2 mi WSW 113-1 2.6 mi W 113-2 2.5 mi W 114-1 2.6 mi WNW 114-2 2.5 mi WNW 115-1 2.6 mi NW 115-2 2.0 mi NW 116-1 2.2 mi NNW 116-2 2.4 mi NNW 93 5" 02 1 , n" l _s

TABLE 8.4-1 (Cont'd) EXPOSURE PATHWAY SAMPLING OR TYPE AND FREQUENCY AND/OR SAMPLE SAMPLING OR MONITORING LOCATIONS COLLECTION FREQUENCY OF ANALYSIS 2. Direct Radiation 3 (Cont'd) c. Outer Rinq Quarterly Gamma dose quarterly 201-1 4.6 mi N 201-2 4.0 mi N 202-1 4.4 mi NNE 202-2 5.0 mi NNE 203-1 5.0 mi NE 203-2 4.5 mi NE 204-1 4.5 mi ENE 204-2 3.9 mi ENE 205-1 5.6 mi E 205-2 4.7 mi E 206-1 5.0 mi ESE 206-2 4.8 mi ESE 207-1 4.3 mi SE 207-2 4.6 mi SE o 208-1 4.4 mi SSE m 208-2 4.7 mi SSE y e 209-1 4.4 mi S n 209-2 4.5 mi S U 210-1 4.4 mi SSW p 210-2 4.4 mi SSW m 211-1 3.5 mi SW 212-1 5.4 mi WSW 212-2 4.7 mi WSW 213-1 4.7 mi W 213-2 5.5 mi W 214-1 4.4 mi WNW 214-2 4.4 mi WNW 215-1 4.8 mi NW 215-2 4.5 mi NW 216-1 4.5 mi NNW 216-2 4.2 mi NNW EN 95 5" De C t _s

TABLE 8.4-1 (Cont'd) EXPOSURE PATHWAY SAMPLING OR TYPE AND FREQUENCY AND/OR SAMPLE SAMPLING OR MONITORING LOCATIONS COLLECTION FREQUENCY OF ANALYSIS 3. Waterbornee a. Public Water Q-19 East Moline Water 16.0 mi SSW Weekly collection Gamma isotopic analysis Supply works composited monthly monthly Q-20 Davenport water 18.0 mi SSW Works b. Cooling Water Q-21 Inlet at station Weekly Gross beta analysis weekly Sample Q-22 Discharge at station c. Sediment Q-23 Lock and Dan 15.0 mi SSW Annually Gamma isotopic analysis No. 14 annually 4. Ingestione a. Milk Q-17 Hansen Dairy Farm 6.0 mi ENE Weekly collection when I-131 analysis on each Q-18 Musal Fara 5.5 mi SW animals in pasture sample (May to Oct.); monthly, g Nov. to March c ao b. Fish 0-24 Davenport Farm 15.0 mi SSW Semi-annually Gamma isotopic on Market (Pool edible portions of each O 014 of Miss. River) sample d E

Sas Figure 8.4-1.

b A gamma isotopic analysis shall be performed wherever the gross beta concentration in a sample exceeds by five tites (5X) the average concentration of the preceding calendar quarter for the sample location. Far field samples are analyzed when near field results are inconsistent with previous measurements c and radioactivity is confirmed as having its origin in airborne effluents released from the station, or at the discretion of the Emergency Planning Supervisor. Sae Figure 8.4-2.

San Figure 8.4-3.

S$ ON 5 98

== 3 se 9

TABLE 8.4-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS 9 IN ENVIRONMENTAL SAMPLES REPORTING LEVELS AIRBORNE PARTICULATE WATER ORGASgS FISH MILK FOOD PRODUCTS ANALYSIS (pCi/g) (pCi/m ) (pCi/Kg, wet) (pCi/t) (pCi/Kg, wet) 11 - 3 20,000* Mn-54 1,000 30,000 Fe-59 400 10,000 i m Co-58 1,000 30,000 o Co-60 300 10,000 5 ? Zn-65 300 20,000 Q 8 Zr-Nb-95 400** 5 m I-131 2 0.9 3 100 Cs-134 30 10' 1,000 60 1,000 Cs-137 50 20 1,000 70 2,000 Ba-La-140 200** 300** MN g 00 5"g

For drinking water samples.

This is 40 CFR Part 141 value. "Z l

- Total for parent and daughter.

$C A i W

TABLE 8.4-3 MAXIMUM VALUES FOR Tile LOWER LIMITS OF DETECTION (LLD) a, b AIRBORNE PARTICULATE WATER OR GASgS FISH MILK SEDIMENT ANALYSIS (pCi/t) (pCi/m ) (pCi/Kg, wet) (pCi/t) (pCi/Kg, dry) c Gross Beta 5 0.01 1,000 5 2,000 Gamma Isotopic 20 0.01 200 20 200 I-131 5 0.1 100 5(0.5)* d O co Cs-134 10 100 10 s a 4 Cs-137 10 100 5 A G 11 - 3 200 s E EN o5 In

== w i

QUAD-CITIES REVISION 11 DECEMBER 1985 = TABLE 8.4-3 (Cont'd) NOTES: a. Other radionuclides which are measurable and identifiable by gamma-ray spectrometry, together with the nuclides indicated in Table 8.4-3, shall also be identified and reported when an actual analysis is performed on a sample. Nuclides which are below the LLD for the analyses shall not be reported as being present at the LLD level for that nuclide. b. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95 percent probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system.(which may include radio-chemical separation) 4.66 - (Sb) D= (A) - (E) - (V) - (2. 22). (Y)- (exp (-Aa t) ). (t) Where: LLD is the "a priori" lower limit of detection for a blank sample or background analysis as defined above (as pCi per unit mass or volume). S is the square root of the background count or of a blank h sample count; it is the estimated standard error of a background count or a blank sample count as appropriate (in units of counts). E is the counting efficiency (as counts per disintegration). A is the number of gamma-rays emitted per disintegration for gamma-ray radionuclide analysis (A = 1.0 for gross alpha and tritium measurements). l V is the sample size (in units of mass or volume). l ) 2.22 is the number of disintegrations per minute per picocurie. Y is the fractional radio-chemical yield when applicable (otherwise Y = 1.0). 8.4-8

QUAD-CITIES REVISION 11 DECEMBER 1985 s TABLE 8.4-3 (Cont'd) Lambda is the radioactive decay constant for the particular radionuclide (in units of reciprocal minutes). Delta t is the elapsed time between the midpoint of sample collection and the start time of counting. (At = 0.0 for enviromental samples and for gross alpha measurements.) t is the duration of the count (in units of minutes). The value of "S " used in the calculation of the LLD for a detection sysNem shall be based on an actual observed background count or a blank sample count (as appropriate) rather than on an unverified theoretically predicted value. Typical values of "E", "V", "Y", "t", and " delta t" shall be used in the calculation. For gamma-ray ra'dionuclide analyses the background counts are determined from the total counts in the channels which are within plus or minus one FWHM (Full Width at Half Maximum) of the gamma-ray photopeak energy normally used for the quantitative analysis for that radionuclide. Typical values of the FWHM shall be used in the calculation. The LLD for all measurements is defined as an "a priori" (before the f act) limit representing the capability of a measurement system and not as an "a posteriori" (after the f act) limit for a particular measurement. c. Referenced to Cs-137. d. For thyroid. e. 0.5 pCi/L on samples collected during the pasture season. t r 8.4-9

REVISI0il 11 DECEMBER 1985 ( Mississippi t River Fulton ^ Clinton \\ US30 uS 30 7 15h ^ us30 s [ 202-1 16e 201-1 202-2 216-15g h p E k 216-2 03-1 215-13 lOWa lllinOIS 4 '4 q e. 21. 2,..,. E 04 2 uss7 i 14 9 m205-i g 213-2 3 I e2 2131E 9 i w 205 2 212 2E 206 1 e5 m 20s-2 211 1 (210 2 212-1m uS 61 3 207-1 se '3R,,>aga y=20w - 209-1 208-1 1 208-2 ILL 2 f 1 11e i s sc Davenport us er Rock River gjpv/,j/// ' lLL.34 SN'NN' s ILL 2, s .e.,.,,,,

olme lN oline N

l ), /- N I e Air Sampling Site 5 Outer Ring TLD Location i.74 l-s0 el I 10 15 2,0 Miles l Scale 0 5 10 15 20 25 30 km I QUAD-CITIES STATION Units 1 & 2 FIGURE 8.4-1 P FIXED AIR SAMPLING SITES AND OUTER RING TLD LOCATIONS IEe'l--3n 9

l REVISION 11 DECEMBER 1985 Q ~ ~ ./? $ ;; h;. s

y si

!) h[ {/p /s'"" u s-2 '/ !/- 1 Y '- t y,,.. 1 i /) /l- ./ / / " 5-2 r m iis-i ra 1 1 102IE E 102-2 ~ fj camanene ,/,t ', '.- 5,,<.2 s S 'i ( ,/ 4,pf j;i /f.s cue..o co., v , s ,ft 0" cWh. i '! /pjtf,,,., i E u.-i .,i i .A3 rl h.i / e,. o e ,o2., N. . j W ioi-i 5,.., h sy,-: ~ It ./s.1 y \\.. y 104 3 104-2 E k B113 2 / e e 1 ' Quad-tos-i / -[' id mn.[ ' e Cities 3 's . / g Station g / E 113-1 106-2 s .,,.\\ / I 107 1 / / s lj g./ [/ \\, J to7 2 11225 ,.,e 'h / 1 moe\\. 1,93 f 10!. 11215 I t

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I-, .@; / J igi ) Cordova (, I 1112 m ei i%ii i in s i,.__ i,y_.,Lqsy.g;j c I Princeton l / /* b'. .l r l lows / If i e M /ihlinois i se.i. QU AD-CITIES STATION i "s' Units 1 & 2 FIGURE 8.4-2 o a5 1km i = INNER RIf1G TLD LOCATIONS Io.'e$'.372

REVISI0il li \\ A DECEf1BER 1985 e i d'***"' Mississippe) ILL 84 t Clinton Y US 61 j IOWA 136 Fulton US 67 5" u 7e glinto ( C&NW DeWitt j I Caww 3,- US 30 M2 N Morrison Camanche Aidany wapsipenicon River t t 17 iLt 78 1 -r 22,21 a Illino.is q& Iowa Whiteside CMSTP&P gjg Cordgya l q Princeton I 4% US 61 f 1 = < ILL 2 Scott Erie l NOWA 130 l H'usdale BN \\ f G syron Rock' ,. o b island Davenport 2 24 y / 20,ge. g v3 tbo [ ,_" ' 21h$' \\ Oline \\ = Colona CRISP r Rock \\ { .go N \\ m Sampling Station l Scale 0 5 1,0 1,5 2,0 Miles ?...5 ? 5.s ap 2,s 3,0 mm QUAD-CITIES STATION Units 1 & 2 FIGURE 8.4-3 11 ILK, FISH, WATER, AND SEDIMEllT SAMPLE LOCATIONS 6415 2 10 372

?* QAP 1400-Tl Revision 2 CUA0 CITIES STATION CNSITE Sectemaer 1985 REVIEW ASSIGNMENT.- DATE l 131 $(I REVIEW NO. 39-33 REVIEW PARTICIPANTS: N fl, [, ( 4- \\ v-P.i b ag-s I h b 91 A. L e 20,, N e G 6 t= n c-a b bowett ASSICMtENT: b~ ~ l ' L oJ 1 SLA O QL Dn LLlk Y%J lo cc m). U btt-r n STATIC:I f:ANAJ F.F [ j APPP.0VED 1 OCT:.01905 ( n n31 ) 0.C.O.S.R. 1 9/0321a \\

-) Commonwrith Edison x 72 West Adams Street. Chicago, Ilknois V]' Chicago, Illinois 60690 - 0767 'V Address Reply to: Post Offics Box 767 November 7, 1985 To: T. Lihou

Subject:

Onsite Review of the Offsite Dose Calculation Manual, Revision 11 I Quad cities Station Site Specific Sections 7.2 and 8.0 Enclosed please find a copy of the revised site specific sections 7.2 and 8.0 of Quad cities Station's Offsite Dose Calculation Manual. This revision must go through an onsite review prior to submittal to the NRC and general distribution. The Quad Cities ODCM is scheduled to be included with the December Operating Report for submittal to the NRC in January 1986. Since the ODCM must also be offsite reviewed, I would appreciate the onsite review be completed by December 1, 1985. Your cooperation in expediting the review process is greatly appreciated. vY nc Rick L. Thacker Environmental llealth Physicist L} &.aW Caror/J. Bennett Lead Environmental Health Physicist ) cc: EPG-04-RE-ODCM-Revil W. Brenner J. Golden JCG/DMK/Imk/6451E/70

Rev. 7 i 3-1-B2 OSR FORM 1 RECCRO OF_ REGUEST l'OR GeFSITE RE'/IEW hL b.h[F3 Sta. ion Onsite Review No. 77"M _ Submittedby___N./_l roy Date /Afl2 /R[ t Test or experiment not involving an unrevie tad safety question. Proposec test or experiment involving an unreviewed safety questien Froposto ch;nge to procedure, equipment or System involving 30 unreviented safety question. Proposed change to Tech. Spec. or license, unanticipated deficiency of design or operation of safety related structures, systems, or components. froposed cnance to GSEP. f Referral by T. S. Supervisor, Station Superintendent, Division Vice President.'lucir;ar Stations, or Manager o f Quality Assurance ( teitional subject d6:cription: DOO/V7 See d > c p e

7. 2 a Q @J Supporting dccuments attached:

OT)CA7 [e tl y he o1,s O f? y vi .. tt T. ) b vh lac l t Date required for Offsite Review completion: If 2N!II Reason for specified cate: Met la D ewd i _ bo A E tj n9 %r o o e * * * * *............. *...........O.... * *bm \\

4*'A ^mG..I.7*S T. G......... '

b I I v. R3ceivetd by Date Senior Pa rt.icipant Of fsite Revicw No.

~ CAP 1400-T2 GUAD-CITIES STATION Revision 3 CN-SITE REVIEW REPORT September 1985 Reference Information: OSR Request Originator: OSR No: %E-33 Station Off-Stie Review Review Cate: fa[13l85' NLA Other' N lAll A,l g{ NFS Was Request Complete: Request Date: SNED Yes NO (Attach material submitted)

Subject:

Reason for Review: Tech. Spec. 6.1.G.2.a (On-Site) Tech. Spec. 6.1.G.I.a (Off-Site) Other: NRC Bulletin Deviation AIR Request _ Station Cr-Sito Deference Materials (attach): Safety Evaluation Procedures Affected Tech Spec Pages W ) Number FSAR Pages AIR Number CA."anual Pages Other (J D'M /AY Ok C 4 (OSR), {. 05 C Cff-Stie Comoletion Info: 5& % Chack List CoTplete Advance Notification Es.rm// M Ferward to Off-Site / Cate Cff-Site Review Number Persen 01!:ositlen: R utine ?secort Cif-sit-Eaview for Concurrence (T.S. 6.1.G.2.a.(5)) An Iss:.:1 (# ) F.C Sd ittal Needed T,chnical Specificaticn Change U.. reviewed Safety Questien G;"?r j No Furtt r Action Othar APPROVED o/c ~ma OCT :.01983

QAP 1400-T2 Revision 3 QUAO-CITIES STATION ON-SITE REVIEW REPORT OSR NO I b 3 3 7.05R A d i td ON-SITE REVIEW SUMMAF.f: ooc m 94 J W A PL J-j . Om mk "3 3 a L xLt LJLQ &&ry 9.1-9eJJ u 4~JaA 74d L R gd.L 7 b JL & J Q - Uk & Ltt LJL,~J .M1, d 0, y r. 4-2 IL, m Q f qd d,c . L JJ JL, ra atAJ1t. UA _y t A <. _ ? r t s _a t @t ".J A A _p a .g p J _ _t ta _u at. - w& ON-SITE REVIEW RECCMMENDATION: k OS k } Ik. %% k ,t _ m d - J 4 ELt : L,wLdtJ p ~ c -t- -.ude ev-qp vf-PAR TICIP,*.'4 TS : ( QA R 1 N L ' A h id .5< a d a Appr ed: Sta ica Manafer [ l AT TACEME.'<TS : Cate: )2 :) 3 *8$ - b o,u.d. 4 e l. b w g / c k il[8 f APPROVED OOCM W 7,24)OC M - ku b. Inal) ~ t 9/03221 ), O.C.O.S.R.

RECEIVED R&v. 1 1-25-85 FEB 26'86 OSR FORM - 5 g o a t: OFFSITE REVIEW REPORT A (Asst. suot.) __ ~B (Operatio05) _ C (MaintenanceL 1 D Admin. & TecN Facility: Quad Cities Onsite Review No. 85-33 i Personne_1._ " ~ Offsite Review No. 86-05 O I '* "~ - - Description y of

Subject:

ODCM Section 7.2 and 8 X_ The above listed onsite review does not constitute an unreviewed safety question. Onsite Review summary should be incorporated into ODCM. X_ Remarks noted above warrant additional Emergency Planning consideration. [ E. Bud chowski 2/13/86 Senior Participant Date O 00 M nf hv M. M. Servoss 2/18/86 J ider 2/19/86 Other Participant Date Superintendent of Date Offsite Review Copies to: _ Mgr. Dresden x B. Thomas /C. Reed E Mgr. Quad Cities K D. P. Galle _ Mgr. Zion x D. L. Farrar/J. Wojnarowski _ Mgr. LaSalle _ Mgr. Byron _ Mgr. Braidwood With Attachment (s) 0034n

O Commonwealth Edison Quad Cities Nuclear Power Station 22710 206 Avenue North Corcova. tilinois 91242 Telephone 309/654-2241 RAR-86-23 August 1, 1986 Director, Office of Inspection & Enforcement United States Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Document Control Desk Enclosed for your information is the Monthly Performance Report covering the operation of Quad-Cities Nuclear Power Station, Units One and Two, during the month of July, 1986. 0spectfully, 0 COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION f I I do l r -jCr R. A. Rob' y Services Superintendent bb i j Enclost : e G*d 0027H/0061Z j , i i}}

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