|
|
Line 3: |
Line 3: |
| | issue date = 02/22/1990 | | | issue date = 02/22/1990 |
| | title = Rev 6 to Plant Procedures Manual 13.8.2, Manual Offsite Dose Calculations. W/900222 Ltr | | | title = Rev 6 to Plant Procedures Manual 13.8.2, Manual Offsite Dose Calculations. W/900222 Ltr |
| | author name = PETERS J F | | | author name = Peters J |
| | author affiliation = WASHINGTON PUBLIC POWER SUPPLY SYSTEM | | | author affiliation = WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| | addressee name = | | | addressee name = |
|
---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17284A9121999-10-13013 October 1999 Proposed Tech Specs 3.3.6.1,Table 3.3. 6.1-1, Primary Containment Isolation Instrumentation. ML17284A8761999-08-27027 August 1999 Replacement Page 9 of 9 to Attachment 4 of Procedure 13.10.6 ML17284A8491999-07-29029 July 1999 Proposed Tech Specs,Revising SR 3.5.2.2 Re Condensate Storage Tank Water Level ML17284A8421999-07-29029 July 1999 Proposed Tech Specs Revising SR of TS 3.8.4, DC Sources - Operating & SR 3.8.5.1 of TS 3.8.5, DC Sources - Shutdown. ML17284A8461999-07-29029 July 1999 Proposed Tech Specs,Revising Table 3.3.5.1-1, ECCS Instrumentation Items 1.a,2.a,4.a & E.A. ML17284A8521999-07-29029 July 1999 Proposed Tech Specs 3.4.9, RHR Shutdown Cooling Sys - Hot Shutdown. ML17333A0021999-04-20020 April 1999 Proposed Tech Specs Section 3.4.11,replacing Existing Reactor Pressure Temp Limit Curves by 000630 ML17292B6341999-04-0707 April 1999 Proposed Tech Specs Modifying MCPR Safety Limits to Allow Continued Power Operation at Plant Following Restart from R-14 RFO ML17292B5731999-03-0101 March 1999 ODCM for WNP-2 ML17292B4881998-12-17017 December 1998 Proposed Tech Specs SR 3.8.1.8,allowing Capability to Manually Transfer Between Preferred & Alternate Offsite Power Sources During Modes 1 & 2 by 990125 ML20198A7051998-11-30030 November 1998 Revs 8 Through 13 to TS Bases & Revs 12 Through 15 of Licensee Controlled Specs ML17284A7181998-08-0505 August 1998 Proposed Tech Specs SR 3.8.4.7,allowing Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 1 & 3,125 Vdc Batteries E-B1-1 & HPCS-B1-DG3 & Div 1,250 Vdc Battery E-B2-1 ML17284A7071998-07-17017 July 1998 Proposed Tech Specs Modifying SR 3.8.4.7 to Allow Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 2,125 Vdc,Battery E-B1-2 ML17284A6431998-05-29029 May 1998 Revised Plant Procedure Sys for Site Wide Procedures, Replacing Pages Located in Manual W/Pages in Package ML17292B2831998-03-0909 March 1998 Proposed Tech Specs Establishing Interim SLMCPR for Siemens Power Corp ATRIUM-9X Fuel Applicable to Cycle 14 Only ML17292B2591998-01-31031 January 1998 Offsite Dose Calculation Manual. ML17292B1321997-12-0404 December 1997 Proposed Tech Specs Modifying Min Critical Power Ratio Safety Limits ML17292B0281997-08-14014 August 1997 Proposed Tech Specs Revising TS 5.5.6 by Adding Note That Would Extend Interval Requirement to Perform Full Stroke Exercise Testing of TIP-V-6 Until 1998 Refueling Outage ML17292A9691997-08-12012 August 1997 Proposed Tech Specs Supporting Request for Enforcement Discretion for Period of 45 Days from TS Action 3.6.1.3.A Required Actions to Isolate Purge Line & Verify Penetration Flow Path Isolated Every 31 Days ML17292A9421997-07-16016 July 1997 Proposed Tech Specs Adding New Min Reactor Vessel Pressure Versus Reactor Vessel Metal Temp (P/T) Curves,Applicable Up to 12 EFPYs ML17292A8901997-06-0606 June 1997 Revised Tech Spec Page 2.0-1 Modified to Indicate That SLMCPR for ATRIUM-9X Fuel Applies Only to Cycle 13 & Corresponding Bases Pages ML17292A8651997-05-20020 May 1997 Proposed Tech Specs,Requesting Mod of Minimum Critical Power Ratio Safety Limits by 970615 ML17292A8301997-03-31031 March 1997 Wppss WNP-2 RPV Surveillance Matls Testing & Analysis. ML17292A7621997-03-24024 March 1997 Rev 5 to TS Bases. ML17292A7631997-03-24024 March 1997 Rev 7 to Licensee Controlled Specs. ML17292A7581997-03-22022 March 1997 Proposed Tech Specs Modifying Response Time Testing SR for RPS Instrumentation,Primary Containment Isolation Actuation Instrumentation & ECCS Actuation Instrumentation ML17292A7531997-03-20020 March 1997 Proposed Tech Specs Re Response Time Testing Requirements ML17292A6591997-01-14014 January 1997 Proposed Tech Specs Reflecting Compilation of TS Change Requests Submitted to NRC in Ltrs Dtd 951208,960709 & 1212 ML17292A6341996-12-12012 December 1996 Proposed Tech Specs Requesting Conversion Based Upon NUREG-1434,rev 1 ML17292A6161996-11-19019 November 1996 Rev 1 to WNP-2 IST Program Plan (Pumps & Valves) 2nd Interval (941213-041212). ML17292A5511996-10-15015 October 1996 Proposed Tech Specs Re Secondary Containment & SGTS to Reflect Revised Secondary Containment Drawdown & post- Accident Analyses Results ML17292A5411996-10-10010 October 1996 Proposed Tech Specs Requesting Addition of Section 2B(6) Re Storage of Byproduct,Source & Special Nuclear Materials ML17292A4501996-09-0606 September 1996 Proposed Tech Specs,Containing Corrections to Factual Statements & Proposed Info to Clarify Evaluations ML17292A4111996-08-0909 August 1996 Proposed Tech Specs,Revising TS Section 6.3 Re Unit Staff Qualifications,By Changing Operations Manager Qualification Requirements Associated W/Operations Knowledge from Meeting Ansi/Ans N18.1-1971 ML17292A3561996-07-0909 July 1996 Proposed Tech Specs,Revising Rev a, Including Changes in Vol 7.Proposed Rev Does Not Change Conclusion of NSHC or Environ Assessment Provided Rev a ML17292A7241996-05-31031 May 1996 Offsite Dose Calculation Manual. ML17292A2741996-04-25025 April 1996 Rev 0 to UT-WNP2-208V0, Exam Summary Sheet. ML20107M3391996-04-24024 April 1996 Proposed Tech Specs,Modifying TS to Support Cycle 12, Scheduled to Begin Subsequent to Spring 1996 Outage ML17292A1511996-04-22022 April 1996 Proposed Tech Specs,Supplementing TS That Describes Administrative & Editorial Changes to Section 6.0, Administrative Controls. ML17291B2801996-03-19019 March 1996 Proposed Tech Specs Re Containment Leakage Testing ML17291B2491996-02-26026 February 1996 Proposed Tech Specs,Submitting Revised Copy of TS Bases Which Include Minor Changes & Clarifications Made Per Requirements of 10CFR50.59 ML17333A0201996-01-19019 January 1996 Proposed Tech Specs Re Primary Containment Leakage Testing ML17291B1751995-12-31031 December 1995 Reactor Power Uprate Startup Test Rept, for WNP-2. W/951215 Ltr ML17291B0941995-10-26026 October 1995 Proposed Tech Specs,Replacing Existing Reactor Recirculation Flow Control Sys W/Adjustable Speed Drive Sys ML17291A9911995-08-16016 August 1995 Proposed Tech Specs Page 3/4 4-4,incorporating Surveillance Notes in Front of Surveillances 4.4.1.2.1 & 4.4.1.2.2 for Jet Pump Operability to Clarify That Notes Apply to Each Surveillance ML17291A9591995-07-28028 July 1995 Operations Instructions OI-23,Rev a to, Human Performance Improvement Program. ML20087E2831995-07-26026 July 1995 Performance Enhancement Strategy 1995 ML17291A8401995-06-0606 June 1995 Proposed Tech Specs Index,Deleting Ref to Bases Pages ML17291A8371995-06-0606 June 1995 Proposed Tech Specs Section 6.9.3.2,adding Ref to Three TRs Describing Analytical Methods That May Be Used in Determining Reactor Core Operating Limits for Reload Licensing Applications ML17291A8441995-06-0606 June 1995 Proposed Tech Specs Section 6.0, Administrative Controls. 1999-08-27
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML17284A8761999-08-27027 August 1999 Replacement Page 9 of 9 to Attachment 4 of Procedure 13.10.6 ML17292B5731999-03-0101 March 1999 ODCM for WNP-2 ML17284A6431998-05-29029 May 1998 Revised Plant Procedure Sys for Site Wide Procedures, Replacing Pages Located in Manual W/Pages in Package ML17292B2591998-01-31031 January 1998 Offsite Dose Calculation Manual. ML17292A6161996-11-19019 November 1996 Rev 1 to WNP-2 IST Program Plan (Pumps & Valves) 2nd Interval (941213-041212). ML17292A7241996-05-31031 May 1996 Offsite Dose Calculation Manual. ML17292A2741996-04-25025 April 1996 Rev 0 to UT-WNP2-208V0, Exam Summary Sheet. ML17291A9591995-07-28028 July 1995 Operations Instructions OI-23,Rev a to, Human Performance Improvement Program. ML20087E2831995-07-26026 July 1995 Performance Enhancement Strategy 1995 ML17291B1621995-03-0606 March 1995 Rev 9 to Procedure Qci 6-4, Ultrasonic Exam Feedwater Nozzle Inner Radii. ML17291A1341994-06-16016 June 1994 Pages 9 & 10 to Rev 11 to PPM 13.12.15,inadvertently Omitted from Original Submittal ML17291A6661994-04-30030 April 1994 WNP-2 Odcm. ML17290A9951993-12-31031 December 1993 Amend 16 to Odcm. ML17290A3771993-05-27027 May 1993 Amend 1 to Inservice Insp Program Plan,First Insp Interval. New Relief Request Will Be Submitted to Define Areas of Limited Exam of RPV nozzle-to-shell Welds ML17272B0141993-04-28028 April 1993 Amend 1 to Vols 1-3 of ISI Program Plan. ML17289B2621993-02-22022 February 1993 Rev 1 to LTI7.4, Operations Liaison Responsibilities. ML17289B1931993-01-31031 January 1993 Offsite Dose Calculation Manual. ML17289A7811992-07-31031 July 1992 Revised Plant Procedures Manual Including Rev 10 to 13.8.2, Backup Emergency Dose Projection Sys Operations & Rev 7 to 13.11.1, Recovery Manager Duties. ML20097H7511992-04-23023 April 1992 Plant Procedure 10.25.89, One Hour - Three Hour Fire Barrier Installation ML17289A5031992-04-0101 April 1992 Washington Nuclear Plant - 2 Licensed Operator Requalification Program Corrective Action Plan Resolution Documentation. ML17286B1791991-11-21021 November 1991 Rev 4 to Pump & Valve Inservice Test Program Plan,WPPSS-2. ML17286A9051991-06-28028 June 1991 Odcm. ML17286A7381991-04-30030 April 1991 Revised Plant Procedures Manual Including,Procedures 13.7.7, 12.7.8,13.8.1 & 13.11.15 ML17286A4971990-12-0505 December 1990 Revised Epips,Including Rev 8 to 13.8.2,Rev 10 to 13.10.9, Rev 8 to 13.11.13,Rev 8 to 13.14.1,Rev 6 to 13.14.3,Rev 10 to 13.14.4 & Rev 7 to 13.14.9 ML17285B0621990-02-26026 February 1990 Amend 7 to Odcm. ML17285B0501990-02-22022 February 1990 Rev 6 to Plant Procedures Manual 13.8.2, Manual Offsite Dose Calculations. W/900222 Ltr ML20066K0451989-03-28028 March 1989 Rev 5 to Qci 6-4, Ultrasonic Exam Feedwater Nozzle Inner Radii ML17285A2621988-11-30030 November 1988 Amend 6 to Offsite Dose Calculation Manual. ML17285A2511988-11-30030 November 1988 Amend 6 to Offsite Dose Calculation Manual. ML20090M2951987-11-17017 November 1987 Rev 4 to FATE-84-100, Vipre Code Maint Procedures Manual ML20236N3071987-11-0606 November 1987 Corrected Page 16 of Rev 7 to Procedure 13.14.2, Process for Determining Protective Action Recommendations & Protective Action Decisions ML17279A5931987-10-0808 October 1987 Rev 3b to Pump & Valve Inservice Test Program Plan. ML17284A3901987-06-30030 June 1987 Draft A-3453-87-6, Washington Nuclear Plant 2 Generic PRA- Based Insp Plan. ML17278B1221986-11-17017 November 1986 Rev 2 to Emergency Procedure 5.3.6, Reactor Pressure Vessel Flooding (Contingency). ML20215B7551986-07-24024 July 1986 Rev 3 to NDE & I Instruction Qci 6-4, Ultrasonic Exam BWR Nozzle Inner Radius ML20215B7631986-03-20020 March 1986 Rev 3 to NDE & I Instruction Qci 6-13, Ultrasonic Exam of Piping Welds (Manual) ML17278A5681986-01-0606 January 1986 Rev 5 to Emergency Plan Implementing Procedure 13.14.7, Emergency Training. ML17278A5341985-12-20020 December 1985 Rev 3a to Pump & Valve Inservice Test Program Plan. ML17278A4731985-11-0101 November 1985 Revised Emergency Procedures,Including Rev 1 to Procedure 5.0.0, Emergency Procedure General Precautions, Rev 0 to Procedure 5.0.1, Emergency Operating Procedure Flow Chart & Rev 1 to Procedure 5.1.3, Reactor Power Control. ML17278A5491985-09-24024 September 1985 Rev 0 to Procedure Tp 8.6.6, Special Test Procedure for Tdas Class 1E Isolators. ML20133N3611985-09-0909 September 1985 WPPSS-2 Emergency Preparedness Exercise Manual for 850909-13 ML20129B5491985-05-0606 May 1985 Vol 1 of Rev 0 to Inservice Insp Program Plan ML17278A4291985-03-20020 March 1985 Rev 1 to Operating & Engineering Test Procedure 8.2.92, UHS Performance. ML17277B6461985-03-0505 March 1985 Amend 4 to 85-01, Preservice Insp Program Plan, Vols 1-4 ML17277B3101984-02-29029 February 1984 Control Room Design Review Program Plan. ML17277B3091984-02-17017 February 1984 Function & Task Analysis of Emergency Operating Procedures. ML17277B7331983-12-28028 December 1983 Rev 2 to 23A1900AA, RHR Sys. ML17277B0401983-11-0707 November 1983 Rev 6 to Administrative Procedure 1.3.8, Equipment Clearance & Tagging. ML17277B0421983-11-0707 November 1983 Rev 6 to Administrative Procedure 1.5.1, Tech Spec Surveillance Testing Program. ML17277B0361983-11-0707 November 1983 Rev 5 to Administrative Procedure 1.3.1, Standing Orders/ Night Orders. 1999-08-27
[Table view] |
Text
<gal.CCELERATED DI'.)T$HBUTION DEMONSTIWTION SYSTEM ,J.F.Washington Pubis.c Power Supply Sys RECIP.NAME RECIPIENT AFFILIATION pro
SUBJECT:
Rev 6 to Plant Procedures Manual 13.8.2,"Manual Offsite Dose Calculations." REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)~5 ACCESSION NBR:9003020278 DOC.DATE: 90/02/22 NOTARIZED:
NO , DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 0500039 AUTH.NAME AUTHOR AFFILIATION PETERS'tern DISTRIBUTION CODE: A045D COPIES RECEIVED:LTR TITLE: OR Submittal:
Emergency Preparedness Pl NOTES: ENCL SIZE: ns, Implement'g Procedures, C D RECIPIENT ID CODE/NAME PD5 PD INTERNAL: AEOD/DOA/IRB NUDOCS-ABSTRACT EXTERNAL: LPDR NSIC COPIES L TR ENCL 1 RECIPIENT ID CODE/NAME SAMWORTH,R J~P PEPB9D REC~FE 01 NRC PDR L OPIES TR ENCL 1 D D S D NOTE TO ALL"RIDS" RECIPIENTS:
D D PLEASE HELP US TO REDUCE WASrEI CONTACT THE.DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISIRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDI TOTAL NUMBER OF COPIES REQUIRED: LTTR ENCL 9
>~a gr v y wg~~z ('\~I G C (ll I' KASHIAGTOXi'UBLIC POKER SUPPLY SYSTE!v!, P.O.Box 968~3000 George Washington Way'ichland.Washington 99392 ACKNOMLEDGENENT OF RECEIPT DATE: FROM: TO: February 22, 1990 Laurie Hiller-Perez
, MNP-2 Plant Administration, N/Q 927A Organization Contro.l.l ed.Copy Number SUBDECT;PROCEDURE APPROVAUREVZSlON
-PACKAGE NO.90-57 The attached'.
Procedure(s) is, to be inserted into your.controlled:
copy of.the.Plant Procedures Nanua:1 and superseded revisions.
are.to be removed.and.destroyed., To verify receipt and inclusion of this Procedure(s),.
please sign, data, and.return this.receipt.within-TEN 10 MORKING.DAYS oi=the date of this;I,ON'.Volume 13 see attached memo Signature of Nanual Holder Control Copy Number 9003020278 900222 PDR ADOCK 0~000397 P PDC 1.2.4 Attachment O AQe'iu.'AaeQ 1.2.4-12 of 15 h
Control~CO 5I No.2 3 5 6 7 8 9 10 ll 12 17 20 21 24 25 26 27 28 29 30 31 33 34 35 36 37 41 42 46 47 49 50 51 52 53 54 55 56 57 58 59 60 61 63 64 66 68 69 73 74 75 DISTRIBUTION
-VOLUME 13 Location Control Room Shift Manager Plant Manager Licensed Training Simulator Technical Manager Operations Manager HP/Chemistry Manager Maintenance Manager Plant Admin.Manager Engineering Services Central Training Services (Sec.13.14)Chemistry Supervisor Health Physics Supervisor Plant QA/QC Manager Project Manager, Bechtel Region V, NRC Security Programs Manager Region V, NRC HNP-3 Technical Library E.O.F.Records Room TSC Emergency Response/Cabinet Admin.Security Specialist HP Technicians Office Resident Inspector Emergency Preparedness Program Mgr.of Emerg Plann 8 Environ Prog HNP-2 Security Maintenance Training I S8IFP Director Engineering Security Training/Evaluation Plant Emergency Director Energy Fac.Site Eval.Council Division of Emergency Management Dept.Soc.&Health Serv.Dept.Soc.8 Health Serv.(Seattle)Federal Emergency Mgmt.Agency U.S.Department of Energy Benton County Dept of Emerg.Ngmt.HNP-2 Security HNP-2 Security HNP-2 Security Operations Support Center/Cabinet Emergency Training Radwaste Control Room Simulator, Shift Manager Remote Shutdown Room (13.4.1)EOF Communications Center (EOFCC)Dept.Soc.&Health Serv.Dept.Soc.&Health Serv.Dept.Soc.&Health Sere.~Mail Dro 927A 927A 927M 1022 1034 988U 9270 927K 927S 927S 981G 1027 927A 927A 9568 964D 1021 700 1020 927A 927A 927AS 901A 1020 1020 913 184 982B 520 1021 927A¹913 913 913 Lunchroom 1020 927A 1034 927A 1021¹ DISTRIBUTION
-VOLUME 13 (cont'd)Contr ol~CQ p Na.78 80 82 83 86 t 87 90 91 92 93 94 95 96 97 98 102 104 105 106 114 123 126 127-132 133 N/A Location Shift Technical Advisor Plant Records EOF Decision Center MUDAC Simulator, Shift Technical Advisor (STA)Document Control Desk, NRC Corporate Communications Emergency Preparedness Program Emergency Preparedness Program Radiological Programs Offsite Agency Center Security Decision Center Crisis Management Center Technical Data Center Corporate Library Telecommunication Services Emergency Preparedness Program NRC Emergency Response Emergency Preparedness Program Emergency Training Planning 8 Scheduling Asst.Managing Director for Operations Licensed Training Emergency Planning Kathy McCullough (Memo Only)Plant Admin.w/o a~Mail Dro 927A 927A 1020 1020 1034 Hash D.C.325 1020 1020 1020 1020 1020 325 1020 330 1032 1020 1020 1020 1020 994E 1023 1020 1020 917Y 927A
~.r I, WASHINGTON POSllC POWER" 4N SUPPLY STEM'.INTEROF ICE MEMORANDU DISTRIBUTION:
MAIL DROP: DATE: TO: FROM:
SUBJECT:
February 22, 1990 Distribution
<J.F.Peter , Plant dministration, NNP-2 (927S)MNP-2 PLANT PROCEDURES MANUAL-VOLUME 13 DISTRIBUTION PACKAGE NO.90-57 D WNP-I FILE WNP-2 FILE WNP-3 FILE WNPA FILE WNP-5 FILE HGP FILE PKWD FILE LEGAL FILE ADMIN FILE
REFERENCE:
PPM*1 2 4 Due to an editorial change, please replace the following pages in your Yolume 13 Plant Procedures Manual: Procedure Rev Title~Pa e No.13.8.2 6 Manual Offsite Dose Calculations 6,7,8 8 13 of 18 JFP/imp Attachments WP.102 R4 (7.83)
O CONTROLLED COPP OFFSITE DOSE CALCULATION DATA SHEET DATE: TIME NAM CALCULAT N: REACTOR TURBINE RADWASTE BLDG DR.ELL BLDG SLOG A.Release P'nt (RX Bldg, DW, TG, RW)(Y or N)B.Meteorology 1.Stability Cl s (A-G)(1)(2)(3)(4)(5)(6)or aT/aZ or 2.Distance Downwind (1.2, 2.0, 5.0, 10.0 Hs es)3.Wind Speed 4.Wind Direction (From-To)C.Time Since Reactor Shutdown D.Stand By Gas Treatment System (SGTS)Efficiency r'C/100m Degrees HPH Minutes Degrees Miles (8)(10)(12)E.Release Point Flow Rate (C)F.Source Term-Radiation Ho itors, Field Data or Sample Re ults (R, F, or S)(If source term is b ed on sample results complete at ched sheet)CFH CFH CFH CFH (13)(14)1.Radiation Mo itor Reading Reactor~B1 d urbine Radwaste B 1 d~Bl d a 0 b.C.d High ange Elevated Release Poi (R/Hr)termediate (extended) ange Noble Gas Monitor (PHU)Low Range Noble Gas Monitor (CPM)Attachment A Page 1 of 3 R/hr PHU PMU CPM CPM XX PMU CPM (15)(16)PROCEDURE NUMBER 13.8.2 REVISION NUMBER PAGE NUMBER 6 13.8.2-6 of 18 CONTROLLEO COPP OFFSITE DOSE CALCULATION DATA SHEET (Continued) s 1'.Radiation Monitor Reading Reactor~Bl d Turbine~Bid Radwaste~Bid d.Drywell LOCA Rad Monitor (CMS-R IS-27E)e.Drywell LOCA Rad Monitor (CMS-RIS-27F) 2.Field Data a.Plume Centerline Dose Rate b.Plume Centerline Air Sample at (Complete attached Air Sample Data Sheet)G.Release Duration (Minutes)R/hr XX R/hr XX mR/hr at min XX XX mi 1 es miles (18)(19)(20)PROCEDURE NUMBER 13.8.2 WP 598 Rl (948)Attachment A Page 2 of 3 REYISlON NUMBER PAGE NUMBER 0I Eb-4 I I~'v a C.t j It 4 O CONTROLLED Car 8 SAMPLE RESULTS FOR GASEOUS RELEASE POINTS CONCENTRATIONS IN Ci/H or Ci/CM REACTOR NUCLIDE BUILDING PRE-SGTS POST SGTS Kr-83M DRYMELL TURBINE BUILDING POST-HEPA-MI RADt<ASTE'LUME BUILDING CENTER LINE PRE-HEPA i AT I Kr-85H Kr-85 Kr-87 Kr-88 Kr-89 Xe-131M Xe-133M Xe-133 Xe-135H Xe-135 Xe-137 Xe-138 I-1 31 I-1 32 I-1 33 I-134 I-135 Attachment A-1 Page 3 of 3 PROCEOURE NUMBER 13.8.2 WP-598 Rl (9.83)REVISION NUMBER PAGE NUMBER
.~i CQNTROLLED Car 8*
SUMMARY
OF EDPS OFFSITE DOSE CALCULATIONS ml Dose Rate REH/Hr Integrated Dose REH 1.2 Di st f Who 1 e Body J Nho 1 e Body Thyroid Dose Rate REH/Hr Dose REH Time Hrs Thyroid)Plume Transit)2.0 5.0 10.0 Other Time Release Started: Completed By: (Name)PROCEDURE NUMBER 13.8.2 WP 598 R1 (9 83}Attachment C REVISION NUMBER PAGE NUMBER 13.8.2-13 of 18 e