ML20210M729

Replacement Pages to PGE-1078, Trojan Nuclear Plant License Termination Plan. with D&D Modeling Runs for Determination of Screening Dcgls & Survey Area Maps Indicating Preliminary Survey Units

ML20210M729
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	08/05/1999
From:	PORTLAND GENERAL ELECTRIC CO.
To:
Shared Package
ML20210M593	List: ML20210M729 VPN-054-99, Rev 1 to License Change Application 247,dtd 990310,for Amend to License NPF-1,adding License Condition Denoting NRC Approval of PGE-1078, Trojan Nuclear Plant License Termination Plan. with Certificate of Svc
References
PGE-1078-ERR, NUDOCS 9908100158
Download: ML20210M729 (312)

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l l-ATTACIIMENT III

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PGE-1078," TROJAN NUCLEAR PLANT LICENSE TERMINATION PLAN" REPLACEMENT PAGES CONTENTS

-1. Ses: tion /Page Replacement Instructions (2 pages)

2. Front Matter Section (Pages i through xii) e Table of CorJents (7 pages) e List of Tables (2 pages) e List of Figures (2 pages) e List of Effective Pages (1 page)

3. Section 5," Final Survey Plan"(86 pages) 9908100158 990805 PDR ADOCK 05000344 W PDR

INSTRUCTION SHEET I.i .

The following information is provided as a guide for the insertion of new sheets for changes to the proposed PGE-1078, " Trojan Nuclear Plant License Termination Plan."

Remove Insert Front Matter Section (Pages i through xii) . Front Matter Section (Pages i through xii)

Table of Contents (Pages i through vii) . Table of Contents (Pages i through vii)

List of Tables (Pages viii and ix) List ofTables (Pages viii and ix)

List ofFigures (Pages x and xi) List of Figures (Pages x and xi)

List of Effective Pages (Page xii) List of Efrective Pages (Page xii)

Section 5," Final Survey Plan" Section 5," Final Survey Plan"

' (Including tables and figures) (Including tables and figures)

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f TROJAN LICENSE TERMINATIONPLAN f-

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TABLE OF CONTENTS

1. G E N E RAL I N FORM AT10N ..... ..................................................................................... 1 - 1 1.1 PURPOSE.......................................................................................................................1-1 1.2 - H I STORIC A L B A C KG R OUND . . .. . . ... . . . .. ... ... . ... .. ........ .. . .. .. ... . .. ... .......... .. . . . .... .. . . .. ... .. . .. 1 -2

~1.3

SUMMARY

OF MAJOR ACTIVITIES AND SCHEDULE.........................................1-3

-1.

3.1 DESCRIPTION

OF MAJOR ACTIVITIES ....................................................... 1-3 1.3.1.1 - Transition Period ... ... . ... ...... .. .. ....... . ....... .... .... ......... ........ ...... . ..... . ...... 1 -3 1.3.1.2 . Decontamination and Dismantlement............................................... 1 -4 1.3.1.3 S ite Restoration ... ...... ... .. . . . ....... . ........... . ... ....... ... .. . . .. ... .. ..... .. .. . .... .... 1 -4 1.3.2 FINAL RELEASE CRITERIA ...................... .................................................... 1 -5 1.3.3 SCHEDULE FOR DECOMMISSIONING / SITE RESTORATION A CTI V I TI E S . . . . . . . . . . .. . . . ... . . . . . .. . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . .. . . . . . . . . . . . . .. . . .. . . . . . .

1.4 P L AN S U M M A R Y . .. . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . .

1.4.1

SUMMARY

OF SECTION 1 - GENERAL INFORMATION .........................1-6 1.4.2

SUMMARY

OF SECTION 2 - S'.TE CHARACTERIZATION.......................1-6 1.4.3

SUMMARY

OF SECTION 3 -IDENTIFICATION OF REMAINING SITE DISM ANTLEMENT ACTIVITIES ................................................................... 1 -6 1.4.4

SUMMARY

OF SECTION 4 - REMEDIATION PLANS ...............................1-6 1.4.5

SUMMARY

OF SECTION 5 - FINAL SURVEY PLAN.................................1-7 1.4.6

SUMMARY

OF SECTION 6- COMPLIANCE WITH THE RADIOLOGICAL CRITERI A FOR LICENSE TERMINATION ................................................... 1 -7 s.) 1.4.7

SUMMARY

OF SECTION 7 - UPDATED SITE-SPECIFIC ESTIMATE OF REMAINING DECOMMISSIONING COSTS ................................................. 1 -7 1.4.8

SUMMARY

OF SECTION 8 - EVALUATION OF ENVIRONMENTAL EFFECTS OF LICEN SE TERMINATION........................................................ 1 -7 1

,1.5 R E FE REN C ES FOR S E CTION 1. .... ........ . .... . .. . .. . . . .... .. .. ........ . ..... .. ... . .. ... ..... ...... .. . ...... . 1 - 8 >

1

~ 2. S ITE C H ARACTE RI ZATION .......................... .............................................................. 2- 1 2.1 INTR O D U CTI O N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . .. . . . . ... . . . . . . . . . . . . . . . .. . . .. . . . . . . . . .. . . . . . . . . . . . . . . . . .. . . . . . . . 2 2.1.1 PURPOSE........................................................................................................2-1 2.1.2 DEVELOPMENT OF SITE CHAR /.CTERIZATION METHODOLOGY...... 2-1 2.2 FACI LITY RADIO LOGIC AL STATU S .... ......... ................. ...................................... 2-3 2.2.1 FAC I LITY H I STO RY .. .. . ... ... .... .. .. ... .. . . .. . . . . . ... . .. . . .. ..... . . .... .. ... .... ....... .. ... .. ..... .. . . 2-3 2.2.1.1 Operat i n e H i storv. . .......... ... . . ... . .. ..... .... . . .. . . .. . .... . . .. .. . .. . .. . . .. . . .. .. . . . . .. . . 2-3 2.2.1.2 Rad iol o nical H i st ory . .... . . ..... .. .. . .. ...... . .. .. .. . . . ... .... ......... ..... . . . .. . .. . . .. . 2-3 2.2.1.2.1 E fIl uents . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . .. . . . . . 2-3 2.2.1.2.2 Operational Events ... .................. ............ ..... ................ ..... 2-3 2.2.2 RADIOLOGICA L STATU S OF TNP... ..... ............ .............................. ..... .... 2-4 2.2.2.1 Structures ................ ............................................................2-6 ,

2.2.2.2 Svstems.........................................................................................2-7 2.2.2.3 A c t i va t i o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . 2 2.2.2.4 E n vi ro n m en t . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... . . . . . . . . . . 2- 1 0 2.2.2.4.1 S urface Soil S urvey ........... . .............. ...................... ..... . 2- 10 i August 1999

TROJAN LICENSE TERMINATION PLAN 2.2.2.4.2 p(j 2.2.2.4.3 Water S urvey . . . . . . . .. . . . . .. . . . . . . . . . . . . . . . .. .. . . . . . .. . . . .

Bottom Sediment Survey... .. . .... .. . . . . . . . . . . . . . . . .

... 2-11

.... 2-12 2.2.2.4.4 Pavement Survey......... .... ..... . . . . ....................2-13 2.2.2.4.5 Exposure Rate Survey . . . . . .. .... ...................... ... ...... 2- 14 2.2.3 C ON C LU S I O N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ...2-14 .........

2.3 OUALITY ASSURANCE PRACTICES AND PROCEDURES................................ 2-16 2.4 RE FERENC ES FO R S ECTION 2.. .......... ............. .. ...... .. ... .......... ...... ..... . . .... 2- 17 APPENDlX 2-1,

SUMMARY

OF NOTABLE RADIOLOGICAL CONTAMINATION EVENTS APPENDIX 2-2,

SUMMARY

OF STRUCTURAL SURVEY RESULTS

3. IDENTIFICATION OF REMAINING SITE DISMANTLEMENT ACTIVITIES..... 3-1 3.1 I N TR O D U CTI O N . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

3.2 DECOMMISSIONING ACTIVITIES. TASKS. AND SCHEDULES.. . ................. ... 3-2 3.2.1 INTRO DUCTI ON . . . . . ... . . . ... . . . . . . . . . . .. . . .. .. . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . .. . . . . . 3 -2 3.2.2 TRANSITION PERIOD. . .......................................................3-2 3.2.3 DECONTAMINATION AND DISMANTLEMENT PERIOD...... .. ............ 3-5 3.2.3.1 O verview . . . . .. .. . . . . . . .... .. .. . . .. . . . .. . . . . .. .............................3-5 3.2.3.2 Detailed Plannine and Enaineerine Activities.... ...... ... . .... . .. ..... 3-5 I 3.2.3.3 General Decontamination and Dismantlement Considerations... .... 3-6 A 3.2.3.4 Decontamination Methods..... .................................................3-7 U

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3.213.5 Dismantlement M ethods .............. ... . ......... ...... .... . . .. ........... 3-8 3.2.3.6 Removal Scauence and Material IIandline.. ....... . ... ....... .... .. 3-9 3.2.3.7 Syst em Deactivat ion ..... .... .. .. . .. .. .... . .. . . . .. .. .... . ............ .. ... .... 3 - 10 3.2.3.8 Temporary Systems to Sunnort Decommissionina............... .. .... 3-11 3.3 REMAINING DISM ANTLEMENT ACTIVITIES .. ............ ... ... .... .................... 3-12 3.3.1 IDENTIFICATION OF REMAINING SYSTEMS, STR.UCTURES, AND C O M P ON EN TS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 - 1 2 3.3.1.1 Remainine Structures. Systems. And Components Not Reauired For Soent Fuel Storace (Phase 1)........... ..... .............................3-12 3.3.1.2 Remainina Systems. Structures. And Components Associated With Spent Fuel Storace (Phase 2).... . . . . . . . . . . . . . . . . . . . . 3-13 3.3.1.3 Remainine Structures. Systems. And Components (Phase 3) . ... .3-14 3.3.2 GENERAL DESCRIPTION OF AND REMEDIATION CONSIDERATIONS FOR REMAINING SYSTEMS, STRUCTURES, AND COMPONENTS . .3-14 3.3.2.1 Reactor Vessel and Internals....... . . . . ..............................3-15 3.3.2.2 Chemical and Volume Control System.. .. . . . . . . .. . .3-15 3.3.2.3 Component Cooline Water System .... . . .................3-15 3.3.2.4 Service Water System .. . . ..... ... . . . . . . . . . . . . . . . . . . . . ..... .. 3 - 16 3.3.2.5 Spent Fuel Pool and Fuel llandline Eauipment.. . .. . .. . .. 3- 16 3.3.2.6 Spent Fuel Pool Cooline and Demineralizer System (Orininal System).... .. ... ... .. . . ... . . . . . . . . . . . . . . . 3-17

_D 3.3.2.7 Modular Spent Fuel Fool Cooline and Cleanup System . . . ...3-17

[O ii August 1999

TROJANIJCENSE TERMINATION PLAN o 3.3.2.8 Condensate Demineralizers .... .. . . . . . ..........................3-17

( ) 3.3.2.9 Stcam Generator Blowdown Svstem . ...... .. .... .. ...... .................. 3-17 3.3.2.10 Primary Makeup Water System and Refuelina Water S t ora ne Tan k . . ... . .. . . . . . . . . . .. . . . ... . .. . . . . . . . . . . . . . .. ....................3-17 3.3.2.11 Plant Effluent Svstem .......... . ...... . . ................................3-18 3.3.2.12 Containment Ventilation Systems...... ....... . .... . ............ .... .. .. 3-18 3.3.2.13 Fuel Buildina and Auxiliary Buildina Ventilation Systems.......... 3-19 3.3.2.14 Condensate Demineralizer Buildine Ventilation System..... . ...... 3-19 3.3.2.15 Instrument and Service Air System .... ........... .. . .. .. ............ .. 3-19 3.3.2.16 Gaseous Radioactive Waste System . . . ........ .......... ..... .... .... . .. 3-20 3.3.2.17 Solid Radioactive Waste System ... ................... ........... .. ........ ... 3-20 3.3.2.18 Liauid Radioactive Waste Svstem ... ........ ...... ..................... ...... 3-20 3.3.2.19 Radiation Monitorina Svstem...... ..... .................................3-21 3.3.2.20 Process Samplina Svstem . .... .... .. . ..... ..... . ...... ................ ... . . 3-21 3.3.2.21 Fi re Protect ion System ..... ... . ... ... . . . . . ......... .. .. . ............. .... . . .. . 3-22 3.3.2.22 Electrical Svstems... ... ....................................................3-22 3.3.2.23 Containment B uildin a .............. . . ... . ... .. . ... . ...... ..... ... . . . 3-22 3.3.2.24 Auxiliary Buildina (Includina Pine Facade)... . . . . . . . . . . . . . . . . . . . . . . . . 3 -2 3 3.3.2.25 Fu el B ui l d i n a .. . . . .. . . . .. . . .. . .. .. . . . . . . . . . . . . . . .. . . . . ... . . . . . . .. . . . . . . . . . . . . 3 -24 3.3.2.26 O t h er B ui l d i n as . . .. . . . .. . .. . . . .. . . . . . . . .. . . .. . ... . . . . .. . .. . . . . . .. . . .. . . .. . . . . . . . . . .. 3 -2 5 3.4 RADIOLOGICAL IMPACTS OF DECOMMISSIONING ACTIVITIES.. .. .. ... .... 3-26 3.4.1 OCCUPATIONAL EXPOSURE.......... .... . ... .... ........ . . ........ . . .... ...... 3-26 t

m )

3.4.2 RADIOACTIVE WASTE PROJECTIONS ................. .. ... . . ........ . .. . ..... 3-26 V

3.5 REFERENCES

FOR SECTION 3. .............................................................3-28

4. S ITE REM E D I ATI O N P L AN S ......................................................................................... 4- 1 4.1 IN T R O D U C TI O N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . 4 - 1 4.2 R E M E D I ATION L E V E L S . . . . .. .. . .. . . . . . . . . . ... . . . . . . . . . . . .. . . . .. . . . . .. .. .. . . . . .. . . . . . .. .. . .. .. .. . .. . . . ... 4-2 4.2.1 REMEDIATION LEVEL CALCULATION.. ... .. . .. . . . .. ..... .... . .. . .......... 4-2 4.2.2 CALC ULATION OF TOTAL COST...... . .. . ... ... . ...... . . . . . ........ ....... .... 4-3 4.2.3 DETERMINATION OF REMEDIATION ACTION EFFECTIVENESS.... .. 4-4 4.3 A L A R A EV A LU ATI ON . .. . . . . . . . . . . .. . . . .. . . . . . . . . . . . . . . . . . . .. . . . . .. . . .. . . . . . .. . . . .. .. .. . .. . . ... . .. . . . .. . . .. . 4-5 4.4 R E M E DI A TI ON A CTI ON S . . . . ... ... .... . . .. . . . . . . . . .. . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . 4-6 4.4.1 STRU CTU RES . . . . .. . . . . . . . .. .. .. . . . .. . . . . . . . . ... . . . . . . . . . . . ........................4-6 4.4.2 LAN D AREA S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 -7 4.4.3 S YSTE M S . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .........................4-7 l

4.5 REFERENCES

..........................................................................................4-8

5. FI N A L S U R VE Y P L A N ..................................................................................................... 5- 1 5.1 INTR O DUCTION . . ..... . ..... .. ............ .... .. ... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-1 5.1.1 PURPOSE ..... .. . . . . . . . . . . . . . . . . . . . . . . . .... . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 5-1 5.1.2 S COPE .. .. . .... . . .... ... .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .5-1

( ,)

v 5.1.3 S UM M ARY .. . . . . ..... . ... ....... . . .. . . . . . . . . . . . . . ...............5-1 iii August 1999

TROJANLICENSE TERMINATIONPLAN p 5.1.4 D E F IN I TI O N S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 -2 O 5.2 S U R V E Y O V E R V I E W . . . . . . . . . . . . . . . . . . . . . . . . . .. . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 - 8 5.2.1 IDENTITY OF RADIOLOGICAL CONTAMINANTS.................................... 5-8 5.2.2 S ITE RE L.EA S E C RITERI A . .. ... . .. . . . .. ..... . . .. . .. ... .. . . . . . . . . . . . . .. . .. . . . . . ... . . ... ... . . . . . .. . . 5- 8 5.2.2.1 Radiological Criteria For Unrestricted Use ........................ ............ 5-8 5.2.2.2 Conditions Satisfyine The Site Release Criteria............................... 5-8 5.2.3 DEVELOPMENT OF DERIVED CONCENTRATION GUIDELINE LEVELS.............................................................................................................5-9 5.2.3.1 Do se M od e l i n c . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 -9 5.2.3.1.1 Building Occupancy Scenario ............... ........... .... ........... 5-9 5.2.3.1.2 Building Renovation or Demolition Scenario....... . ....... . 5-10 5.2.3.1.3 Residential Farming Scenario.. ......................................... 5-10 5.2.3.2 Derived Concentration Guideline Levels......... .. ........... ........... ... 5-11 5.2.3.2.1 S creening DC G Ls ...... . . . . .. . .. . . . .... ... . . . .. ... . . . . . .. .. .... . . . . . . . .. . . .. .. 5- 1 1 5.2.3.2.2 Site-Specific DCG Ls ... ...................................................... 5- 12 5.2.3.2.3 S urrogate Ratio DCG Ls ............................. ... .................. 5-12 5.2.3.2.4 Gross Activity DCG Ls ............ .... .............. ... ......... ........... 5-14 5.2.3.2.5 Elevated Measurement Comparison (EMC) DCGLs........ 5-14 5.2.3.2.6 Uni ty R ul e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 - 1 5 l 5.2.4 FACILITY AND SITE CLASSIFICATION.. ...... ...... ............... ................... 5-15 5.2.4.1 No n-I m pact ed Areas . . ... . ... . ..... .. . . . . . ... . . . . . . . .... . . . . . . . . .... . ... .. . .. . . .. .. . . . .. . 5- 15 5.2.4.2 I m pa ct ed A reas .. . .. .. . . .... .. .. . . .. . . ... . .. . . .. . . .. . ... . .. . . . .. . ... .. . .. . .. . .. . .. ... . 5 - 15 j r' 5.2.4.2.1 Clas s 1 Areas . .. ... . . .. . . ... . . . . . . . . .. .. . . . . .. . .. .. . . . . . . .... . . ... . . . .. . . ... . 5- 16 1 5.2.4.2.2 Class 2 Areas ... .... ... ... . . . . .. .. .. .. . . .. .. . .. . .. .. . .... . . .. . . . .. . . . .. .. 5- 16 5.2.4.2.3 Clas s 3 Areas .. . .. .. ... .. . .. . .. . . . .... . . . .. . . . . .... ..... . .. . .. ... . . .. .. .. .. . . . . 5- 16 j

5.2.4.3 Initial Classi fication ..................... ........................... ........ ....... ...... 5- 16 i 5.2.4.4 Chances In Classi fication ............................................................... 5-17 I 5.2.5 FI NAL S U RV EY PROC ES S .. .. . ... .. .. .. . ... . . . . .. . ..... . . ... . ... .. .. .. . .. .. .. .. . . . . . . . .. . .. ... . . .. . . 5 - 17 5.2.5.1 S un'ev Preparat io n ... . . . . .. . . .. . ... . .. ... . .. ... . . . . . . ... . .. .. .. . . . .... .. . . ... . . .. .. . . . 5- 17 5.2.5.2 S u nrey De s i nn . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ......... 5- 18 5.2.5.3 Sun'ev Data Collection ...... .. .................. ............. ............... . ...... 5- 18 5.2.5.4 S un'ev Data A ssessment .................. ........................................ ..... 5- 19 5.2.5.5 S u n'ev R esul t s . . . . .. .. . . .. ... . . . . .. . .. . . . .. ... ... .. . . ..... .. ... . .. .. . ...... .. . . . . ..... . . ... . 5- 19 5.2.6 P ROJ ECT M AN A G EM ENT.. .. .. . . ... . .. .. . . . ... . . .. ... . . . ..... . . .... . . . . . . .. . .. ... . ..... . . .... .. . . . 5- 19 5.2.6.1 Final Survey Oreanization . .......... .......................................... ...... 5-19 5.2.6.2 Ouality Assurance And Ouality Control (OA/OC)...... .............. ... 5-20 5.2.6.3 Sun'ev Records And Documentation................... ..... .................... 5-21 5.2.6.3.1 Proced ures . . . . . . .... ..... ... . . .. ... . . ..... .. .. . .. . . . . .. . . .. . . . .. . . . . . . . .. . . 5 -21 5.2.6.3.2 Technical Basis Documents ................................ ............. 5-21 5.2.6.3.3 R e c o rd s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . .. . . . . . . . . . . . . . . . 5 -2 1 5.2.6.4 Audits And Indenendent Reviews .................................. ...... . .. . . 5-21 5.2.6.5 Control Of Vendor Supplied Sen ices ...................... ............. . ... 5-21 5.2.6.6 Tra i n i n a . . . . . . . . .. . . . .. . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 -2 2 5.2.6.7 S e h ed u l e . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 -2 2 P 5.3 S U R V EY P R E P A RATI ON .... .. .. .. .. .. .. .. . .. . . .. .. .. ... . . . .. . . .. . ... . .. . . .. . . . . . . . . . . . . .... . . . . . . 5 -2 3 5.3.i REM eDi ATiON tEvELS ............ . . . ...................... ...... ... .. .... . .. . ... .. .. 5-23 iv August 1999 l

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l TROJANUCENSE TERMINATIONPLAN p 5.3.2 A LARA EVA LU ATI ON . . . . . . . . . . . . .. . . . .. . . .. . . . .. . . . . . . . . . . . . . . . . . . . . . .. . . .. . . . . . .. . . . ... . . . . 5 -2 3

\ 5.3.3 TU RN O V E R . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 -2 4 5.3.3.1 Turnover U n i t s . . . . . . . . . . . .. . .. . . . . . . .. . .. . . .. .... ... . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 -2 4 5.3.3.2 Wa l k d o wn . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

5.3.3.3 Tu rn o ver C ri t eri a . . . . . . . . . . . . .. . . .. . . . . . . . . . .. . . . . . .. . . . . . . . . . . . . . ... .. . . . . . . . .. .. . .. . . 5 -24 5.3.3.4 Tra ns fer O f Control ... ............ .. .............. ...... ... . .. ..... ... ..... . . .. . 5-25 5.3.3.5 Isolation And Control Measures ................... .. .... .. ........ ............. 5-25 5.4 S U R V E Y D E S I G N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . .

5.4.1 S U R V E Y UN I TS . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . .

5.4.1.1 S urve v U ni t S i ze .... . . . . . . . .. . .. .. . . . . . ... .. ... .. ... . ... .. . . . . .. .. . . . . . . .... .. . . . . . . .. .. 5 -2 6 5.4.1.2 Reference Coordinate System .. ................. ........... .... .. .......... ... 5-27 5.4.1.3 Back cround Referenee Areas .................... ...... .... .. ...... .... .... ... 5-27 5.4.2 S CAN M EAS U REM ENTS . .. .. . .. . . . . .. .. . .. . ... . . . .. .. . . . . .. .. . . . . . .. . .. . . . .. . . . . . . .. .. . ... . . . . . . 5-2 8 5.4.3 STATI C M EA S U REM ENTS .. . . . . . .. . .. . . . .. . . .. . .. .. . .. . .. . . .. . . . . .. . . . . . . . . .. . . . . .... . . . . . ... . . . 5 -2 9 5.4.3.1 Number O f Measurem ents . . .... ............ .. ... . . ...................... . ........ 5-29 5.4.3.2 Measurement Locations .................... ...... .................. . ........ ....... .. 5-29 5.-4.3.3 Location Identi fi cation ........... .............. . ....... .... .. . .. ............... .... 5-3 0 1

5.4.4 DATA IN VESTIG ATION.................................... ....... .. . . . . . . . . . . . . . . . . . . . . . . 5 -3 0

! 5.4.4.1 I n vest i cat i o n Level s . . . . .. . . . . . ... . . .. ... .. ... . . . .. . .. . . . ... . . .. . . . . . . .. . .. . . . . . . .. . . 5-3 1 5.4.4.2 I n ve st i natio n . . . . . . . . . . . .. . . . . . .. ... .... ... . .. . .. . . . ... . .. .. . . .. . .. . . .. . . .. . . . . ... . ... . .. . . 5 -3 1 5.4.4.3 R em ed i at i o n . . . . . .. .. . .. . . .... . .. .. . . . . . .. . . . . . . .. . . .. . . . ... . . . . . .. . . . .. . . . .. .. . . . . . . 5-3 2 5.4.4.4 Reclassification..... . . . . ...... .................................................5-32 5.4.4.5 R e su rve v . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 -3 3 i

( 5.4.5 QUALITY CONTROL (QC) MEASUREMENTS.... . ..... .... ...... ......... ... ... 5-33 5.4.5.1 Tyne. Number. And Schedulin_g ............ . ...... ...... ... .... ... . .. . 5-33 5.4.5.1.1 Scan Measurements ..... ...... ....... ... .... ......... ......... .. ...... . ... 5-3 4 5.4.5.1.2 Static Surface Contamination Measurements.... . ...... .... . 5-34 5.4.5.1.3 Soil and Bulk Material Measurements .. . ......... ............... 5-35 1

5.4.5.2 Measurem ent A ccuraev.... ....... .............. .... . ... .... ..... .... ......... 5-3 5 1

1 5.5 SURVEY D ATA COLLECTI ON ... ... .... .... ............... .......... . ....... ........ .. ....... ... . . . 5-3 6 5.5.1 S U RVEY PERFO RM AN CE .. . . . . ... . . . ... . . . . .. .. . . .. . ... . . . . . . . . . . . . . . . . . .. . . . . . . . . . . .. .. . .. . 5-3 6 5.5.1.1 Turn over S u rvev . . . . .. . . . . . . . . .. . . . . . . . . . . . .. . . . . .. . . . . .. . . . . .. . .. . . .. . . . 5 -3 6 5.5.1.2 Fi n al S urve v . , . .. . . . . . . . . .. . . . .. .. . . . . .. . . . . .. . . . . .. . . . . . . . . . . . .. .. . . . .. . . . ..... . . . 5 -3 7 5.5.1.3 Investi nation S urvev .. . ..... .............. ........ . . .. .... . . . . . ... . .. .. .. .. 5-3 7 l 5.5.2 IN STRUM E NTATI ON . . . . . . .. ... . . . . . . . . . . . . .. . . . . . . .. .. . . . . . .. . . .. . .. . . ... . . . . . .. 5 -3 7 l 5.5.2.1 Instrument Selection .... . ... ... ....... ................ . . ..... ..............5-37 i 5.5.2.2 Calibration A nd M aintenance ............. ... .............. . ... ................. 5-3 7 i

5.5.2.3 Res po n se C h eck s . . . . . . . . . . . . .. . . . . . . . . . . . ... . . . . . . . . . . . . .. . .. . . . . . . .. . . . . . . . . 5 -3 8 l 5.5.2.4 Minimum Detectable Concentration (MDC).... ... . ..... ... ... ...... 5-3 8 l 5.5.2.4.1 Beta-Gamma Scan MDC for Structure Surfaces.. .. ........ 5-38 5.5.2.4.2 Alpha Scan MDC for Structure Surfaces.. .. . .. .. . . . . .... 5-39 l

5.5.2.4.3 Gamma Scan MDC for Land Areas .... .. . . . . . . . . . . . . . .... 5-39 l

1 5.5.2.4.4 Static MDC for Structure Surfaces........... . . . . .. . . . . . . . . . 5-3 9 5.5.2.5 Detection Sensitivity.. ........ . ...... ........... . . . .. . . . . . . . . . . 5 -4 0 p

\

5.5.3 SURVEY METilODS. .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 -4 0 l 5.5.3.1 Scan Measurements . . .. ... ... ... .. .. . .. . . . . .. .. . . . . . . 5-4 0 v August 1999

e a 1 TROJANUCENSE TERMINATIONPLAN i 5.5.3.2 Static Surface Contamination Measurements ................................. 5-41 5.5.3.3 Soil And Bulk Material Samples .................................................... 5-41 5.5.3.4 Special Measurem ent s .. .. .. . . .. . . .... . ..... . .. ....... ........ .. . . . ..... .. . .. ..... ... ... . 5-4 2 5.5.3.4.1 Cracks, Crevices, and Small Holes ..................... ............. 5-42 i 5.5.3.4.2 Paint Covered Surfaces ........................................... ......... 5-42 5.5.3.4.3 Plant Systems, Floor Drains, and Embedded Piping......... 5-42 5.5.3.4.4 Activated Concrete and Other Materials........................... 5-43 l 5.5.3.4.5 Paved Parking Lots, Roads, Sidewalks, and Other Paved -

Areas.................................................................................5-43 5.5.3.5 Investination Measurements ...... .................. ................................. 5-4 3 5.5.4 S AMPLE HANDLING AND ANALYSIS ............................. ........................ 5-43 5.5.5 DATA M ANA G EM ENT... . .. .. ... .. .. ..... . . ..... . . . ........ .... ..... . . ... . .... ... .. ... ......... ...... . 5-4 3 5.5.5.1 Scan Measurements .. . . . .. . . .... ...... .. . .. .. .. . . ... .... ... . ... ... .. . . . ....... ... . .. . . ..... 5-44 5.5.5.2 Static Measurement s ... ......... .. . ... ..... ... ... ....... ......... .... .... ... .. ... . .. .. . .... 5-44 5.5.5.3 Data Recordi ne .. ..... ........... .... ...... . .. . . .. . . ...... . ... ........... . .. .. ......... ...... . 5-44 5.6 S U R V E Y D ATA A S S E S S M ENT..... .. .... ..... .. .. .. .... . ... .. ................ .. ..... . .. ...... ... .. ... . .... ... 5-4 5 5.6.1 DATA VERIFICATION AND VALIDATION............................................... 5-45 5.6.2 GRAPHICAL DATA REVIEW .......................................................... ............. 5-46 i i

5.6.2.1- Po st i nn P l ot . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . .. . . . . . . . . . . . . .. . . . . . . . .. . . . .

5.6.2.2 Frea uenc y P l ot .... . .... .. . .. .. . . ... .... . . .... ..... .... .... .... ...... . ... . ..... ... . .... ... ..... 5-46 5.6.3 B ASIC STATISTICAL COMPARISONS ....................................................... 5-46 5.6.3.1 Range.............................................................................................5-47 5.6.3.2 Median............................................................................................5-47 l 5.6.3.3 Mean...............................................................................................5-48 5.6.3.4 Standard Deviat ion .. . . . ... ....... ........ ...... ....... ... ....... ...... . ... . .. . . . . .. ... ... . . 5-4 8 5.6.4 STATI STICA L TEST............ .. .... ....... .. . ... . . . .. ......... . ... . ... .... .... .. . .... . . .... . . .... .... . . 5-4 9 5.6.4.1 Application Of Statistical Test........................................................ 5-49 5.6.4.2 S i nn Te st .. . . . . . . . . .. . . . . .. .. . . . . .. ... . . . . . . . . . . . . . . . . . . . . . . . . .. . .. . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 5.6.4.3 Wilcoxon Rank Sum (WRS) Test................................................... 5-50 l 5.6.5 D ATA C ON C LU SION S ..... .... . .... ... .. ........... ... ...... .. .. .... ... . . ... .. . ..... .... . ... .. ...... . 5-52 5.7 S U R V E Y RE S U LTS . . . . . . . . . . . . . . . . .. . . .. . . . . . . . . . .. . . . . . . . . . . .. . . . .. . .. . . .. . . . . . . .. .. . . . . . . . .. . . . .. . . . . . . . . . . . . . . . . . . 5 5.7.1 H I STO RY FI L E . . .. . .. . . . . . . .. . .. . . . . . .. . . . .. . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . 5 -

5.7.2 SURVEY UNIT RELEAS E RECORD ............................... ............................ 5-53 5.7.3 FIN A L S URVEY REPO RT ........ ... ...... ... .... ... . ... . ...... ... ... .... ... . ... . . . ... . .... ... .. . .... 5-5 3 5.7.4 OTH E R REPO RTS . . . . .. . .. . . . ... . . . . . . . .. . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . .. . . . . . . . . . . .. . . . . . . . . . . . .. . . . . . . 5 -5 4 5.8 RE F E R EN C E S . . . . . . . . . . .. . . . . . .. . . . .. .. . . . . .. . .. . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . 5 - 5 l APPENDIX 5-1, ELEVATED MEASUREMENT COMPARISON (EMC)

! APPENDIX 5-2, NUMBER OF STATIC MEASUREMENTS i APPENDIX 5-3, BACKGROUND REFERENCE AREAS

6. COMPLIANCE WITH THE RADIOLOGICAL CRITERIA FOR LICENSE TERMINATION.................................................................................................................61 6.1 RI S C U S S I ON . . ......... . .......... ....... .. . ... . . . . .. . . ......................................................6-1 vi August 1999 l

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l

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TROJANLICENSE TERMINATIONPLAN

/m 6.2 R EFERENCES FO R S ECTION 6................... ......... ........ . ...... ................... ......... ... 6-2

\)

7. UPDATE OF SITE-SPECIFIC DECOMMISSIONING COSTS.................................. 7-1 7.1 I NTR O D U CTI ON . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. .. . .. . . . . .. . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . .

7.2 DECO M M I SS IONING COST ESTI M ATE........... ................... ................................... 7-2 7.2.1 CO ST ESTIM ATE RES ULTS .... . .. ...... . . ... .... ..... ... . .... .. .. ... ... .. .. ... .. .. ...... .. . ... .. . . 7-2 7.2.2 COST ESTIM ATE D ESCRIPTION........................................................... ....... 7-2 7.2.2.1 Radiolocical Decommissionine Costs .............................................. 7-3 7.2.2.2 Nonradiolocical Decommissionina Costs...................................... .. 7-4 7.2.2.3 S oent Fuel Management Costs..... .. ................................................. 7-4 7.2.2.4 Financial A ctivity Costs............................... ........................ .. ......... 7-4 i i

7.3 S PENT FUEL M ANAG EM ENT FUNDING PLAN .................. . ................................ 7-6 )

7.4 D ECO M MIS S IONING FUNDING P LAN .................................................................... 7-7 7.4.1 CURRENT DECOMMISSIONING FUNDING CAPABILITIES... ....... ........ 7-7 ]

7.4.2 TNP CO-OWNERS' DECOMMISSIONING FUNDING PLANS .............. .... 7-7 7.4.2.1 P G E Fu n d i n e . . . . . . . . . .. . . . . .. . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . .

7.4.2.2 E WE B /B P A Fund i n c ... . .. ... .. . . .. ..... ... .. . ... . .. ... ... .. ..... .. . .. .. .. . . . .. .... .... 7-8 7.4.2.3 P P& L F u n d i n c . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . .. . . . . 7-9 7.5 R E FERENC ES FOR S ECTION 7...................... . ..... ... .................... ......... ................ 7- 10

8. EVALUATION OF ENVIRONMENTAL EFFECTS OF LICENSE TERMINATION...

b o .........................................................................................................................................8-1 8.1 IN TR O D U CTI O N . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

8.2 CU RRENT ENVIRONMENT IM PACT ........ ............ .. ............................. . .. ..... .... 8-2

8.3 CONCLUSION

..........................................................................................................8-3 8.4 RE FE R ENC ES FO R S ECTION 8 ... .. . .. .. . . ... ... . . .. . . ... .. ... . ... . ..... . . . ... .. . .. ... .. . . ...... . ... .... ... . . 8-4 LIST OF ABBREVIATIONS AND ACRONYMS )

1 INDEX 1

o vii August 1999

p .. c .;

TROJANLICENSE TERMINATIONPLAN

f N

LIST OF TABLES FOR LICENSE TERMINATION PLAN l Table Title

!2-1 Radioactive Effluent Summary, Noble Gases 2-2 Radioactive Efiluent Summary, Iodine and Particulates (excluding tritium) 2-3. Radioactive Effluent Summary, Liquids 2-4 Structures Burial Volume and Contaminatiori Activity Projections 2-5 Status of Buildings in the Radiologically Controlled Area 2-6 System Burial Volume and Surface Activity Projections 2-7 Isotopic Distribution (Decay Corrected to 1994 and 1998) l 2-8 10 CFR Part 61 Classification by Component One Year After Shutdown 9 10 CFR Part 61 Classification by Component Five Years After Shutdown

j. 3-1 Status of Major TNP Systems, Structures, and Components as of January 1999 3-2 Major Components Removed (By Year) 3-3 Radiation Exposure Projections 3-4 Decommissioning Waste' Classification and Volume Projections 5-1 Screening DCGLs 5-2 Initial Classification of Trojan Facility and Site 5-3 Survey Design Summary

'5-4 Survey Unit Divisions of the Trojan Facility and Site as of August 1999 5-5 Data Results and Investigation Conclusions 5-6 Typical Survey Instrumentation 5-7 Typical Detection Sensitivities 5-8 Survey Results and Conclusions When A Background Reference Area Is Not Used 5-9. Survey Results and Conclusions When A Background Reference Area is Used 7-1 Estimate of" Trust Fund" Decommissioning Costs (1997 dollars) 7-2 Decommissioning Cost Estimate for Trojan Nuclear Plant itemized Decommissioning Expenditure Schedule (1997 $ x 1000) 7-3 Status of Decommissioning Trust Funds as of December 31,1998 l

lO viii August 1999

I TROJANLICENSE TERMINATIONPLAN l

Table Title 7-4 Portland General Electric Decommissioning Trust Fund Cash Flow As Of12/31/98 (Nominal $ x 1000)

'7-5 EWEB/BPA Decommissioning Tmst Fund Cash Flow As Of12/31/98 (Nominal $ x 1000) 7-6 Pacific Power & Light Decommissioning Trust Fund Cash Flow As Of12/31/98 (Nominal $ x 1000) l \

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1 l

l l

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ix August 1999 l

l 1

TROJANLICENSE TERMINATION PLAN r3 LIST OF FIGURES FOR LICENSE TERMINATION PLAN N,l Figure Title 2-1 Radiological Analysis Samples, Trojan Site, Zones 1 through 16 2-2 Radiological Analysis Samples, Zone 1 l

2-3 Radiological Analysis Samples, Zone 2 2-4 Radiological Analysis Samples, Zone 3 2-5 Radiological Analysis Samples, Zone 5 2-6 Radiological Analysis Samples, Zone 6 2-7 Radiological Analysis Samples, Zone 7 2-8 Radiological Analysis Samples, Zone 8 2-9 Radiological Analysis Samples, Zone 9 l

2-10 Radiological Analysis Samples, Zone 10 )

2-11 Radiological Analysis Samples, Zone 11 2-12 Radiological Analysis Samples, Zone 14 i n

) 2-13 Radiological Survey Data, Auxiliary Building, Elevation 5 ft 2-14 Radiological Survey Data, Auxiliary Building, Elevation 25 n 2-15 Radiological Survey Data, Turbine Building, Elevation 27 ft l 2-16 Radiological Survey Data, Turbine Building, Elevation 45 ft l 2-17 Radiological Survey Data, Main Steam Support Structure, Elevation 45 ft 2-18 Radiological Survey Data, Control Building, Elevation 45 ft 2-19 Radiological Survey Data, Auxiliary Building, Elevation 45 ft 2-20 Radiological Survey Data, Fuel Building, Elevation 45 ft 2-21 Radiological Survey Data, Containment, Elevation 45 ft 2-22 Radiological Survey Data, Turbine Building, Elevation 6311 2-23 Radiological Survey Data, Control Building, Elevation 61 ft and 65 ft 2-24 Radiological Survey Data, Auxiliary Building, Elevation 61 ft 2-25 Radiological Survey Data, Fuel Building, Elevation 61 ft 2-26 Radiological Survey Data, Main Steam Support Structure, Elevation 69 ft

,, 2-27 Radiological Survey Data, Containment, Elevation 61 ft

)

(j 2-2R Radiological Survey Data, Control Building, Elevation 77 ft x August 1999

TROJANLICENSE TERMINATIONPLAN Figure Title 2 Radiological Survey Data, Auxiliary Building, Elevation 77 ft 2-30 . Radiological Survey Data, Fuel Building, Elevation 77 ft 2-31 Radiological Survey Data, Containment, Elevation 77 ft 2-32 Radiological Survey Data, Turbine Building, Elevation 93 ft 2-33 Radiological Survey Data, Control Building, Elevation 93 ft 2-34 Radiological Survey Data, Auxiliary Building, Elevation 93 ft 2-35 Radiological Survey Data, Fuel Building, Elevation 93 ft l 2-36 Radiological Survey Data, Containment, Elevation 93 ft 3-1 Site Plan 3-2 Containment and Auxiliary Buildings, Plan Below Ground Floor 3-3 Containment and Auxiliary Buildings, Elevation 45 ft 3-4 Containment and Auxiliary Buildings, Elevation 61 ft 3-5 Containment and Auxiliary Buildings, Elevation 77 ft 3-6 Containment and Auxiliary Buildings, Operating Floor and Above 3-7 Turbine Building, Elevation 27 ft and 45 ft 3-8 Turbine Building, Elevation 61 ft and 63 ft 3-9 Turbine Building, Elevation 93 ft 9

3-10 Decommissioning / Site Restoration Schedule 5-1 Data Investigation Process 5-2 Data Assessment Process O

xi August 1999

TROJANLICENSE TERMINATIONPLAN LIST OF EFFECTIVE PAGES O

Section/Page Revised Date -

Title Page March 1999 Pages i through xii August 1999 Section 1 Pages 1-1 through 1-8 March 1999 Section 2 Pages 2-1 through 2-17 March 1999 Appendix 2-1 Pages 1 of 5 through 5 of 5 March 1999 Appendix 2-2 Pages 1 of13 through 13 of 13 March 1999 Tables 2-1 through 2-9 March 1999 Figures 2-1 through 2-36 March 1999 Section 3 Pages 3-1 through 3-29 March 1999 Tables 3-1 through 3-4 March 1999 Figures 3-1 through 3-10 March 1999 Section 4 Pages 4-1 through 4-8 March 1999 Section 5 Pages 5-1 through 5-56 August 1999 Appendix 5-1 Page1of1 August 1999 Appendix 5-2 Pages 1 of 6 through 6 of 6 August 1999 Appendix 5-3 Pages 1 of 2 and 2 of 2 August 1999 Tables 5-1 through 5-8 August 1999 Figures 5-1 through 5-2 August 1999 Section 6 Pages 6-1 and 6-2 March 1999 Section 7 Pages 7-1 through 7-10 March 1999 Tables 7-1 through 7-6 March 1999 Section S Pages 8-1 through 8-4 March 1999 1 List of Abbreviations and Acronyms (1 page) March 1999 I Index (2 pages) March 1999 J

O I xii August 1999

1 f^ .

Q TO: Distribution LGD-112-99 FROM: L. G. Dusek 2

/ ,

DATE: August 4,1999

SUBJECT:

Transmittal of Replacement Section 5 and Front Matter to the Proposed Trojan Nuclear Plant License Termination Plan, PGE-1078 Enclosed is your controlled copy of replacement Section 5 and Front Matter to the proposed PGE-1078, " Trojan Nuclear Plant License Termination Plan." The changes are to be incorporated following the instructions accompanying this letter.

Please acknowledge receipt of this document by completing the lower portion of this transmittal and returning it to the location given below.

LGD/CKC Enclosure 8/4/99  !

O i ACKNOWLEDGMENT O

Proposed PGE-1078," Trojan Nuclear Plant License Termination Plan" Replacement Pages l

1. Front Matter Section (Pages i through xii)  ;

e Table of Contents (7 pages) e List of Tables (2 pages)

• List of Figures (2 pages) e List of Effective Pages (1 page)

2. Section 5," Final Survey Plan"(86 pages)

I hereby acknowledge receipt of Controlled Copy Number (s) of the above subject documents.

Signature Date Return to: Pat Schaffran, TCB-3 Trojan Nuclear Power Plant i

71760 Columbia River Hwy.

Rainier,OR 97048 l

t

E TROJANLICENSE TERAflNATIONPLAN

5. FINAL SURVEY PLAN

/n

5.1 INTRODUCTION

5.1.1 PURPOSE In accordance with 10 CFR 50.82(a)(9)(ii)(D) (Reference 5-1) and Regulatory Guide 1.179 (Reference 5-2), this TNP Final Survey Plan describes the final survey process that will be used to demonstrate that the TNP facility and site meet the radiological criteria for license I

termination. This plan incorporates the site release criteria of 10 CFR 20.1402 (Reference 5-3) for unrestricted use of the TNP site.

5.1.2 SCOPE i

As detailed in Section 5.2.4, the final survey encompasses structures, land areas, and plant systems which, as a result oflicensed activities, are identified as contaminated or potentially contaminated. The majority of these are located within the Trojan Industrial Area, which is i!!ustrated in Section 3, Figure 3-1. At the time of final survey, the structures will be largely intact. The majority of the contaminated systems and components will have been removed prior to the initiation of the survey data collection in those areas.

The final survey does not include the ISFSI. The ISFSI site has been previously surveyed and the results of that survey are documented in PGE-1074, " Trojan Final Survey Report for the OV' ISFSI Site"(Reference 5-4). The final survey also does not include monitored gaseous and liquid plant effluent discharge pathways. As confirmed by characterization results summarized in Section 2, the Trojan Radiological Environmental and Effluent Monitoring Program (REMP)

(Reference 5-5) documents compliance with the ALARA criterion of 10 CFR 50, Appendix I (Reference 5-6), associated with monitored releases.

5.1.3

SUMMARY

This final survey plan describes the final survey process, as well as the methodology used to develop guideline values against which residual radioactivity levels remaining at TNP at the time of final survey will be compared. The final survey process is described as a series of sequential steps-survey preparation, survey design, data collection, data assessment activities, and final survey report preparation. However, in practice, this process is iterative since the results from one step may prompt repeating one or more previous steps.

Survey preparation activities begin once dismantlement activities are complete in a given area.

An ALARA evaluation is performed to determine, from a cost-benefit perspective, which remediation actions should be taken in addition to those already planned or completed. The area meets the site release ALARA criterion once any additional remediation actions are completed.

The area is divided into survey units that are classified according to their potential for residual radioactivity. Survey data are collected from the survey unit according to data collection patterns and frequencies established for each classification. Where residual radioactivity is (C measured above pre-set levels, an investigation is performed. Based on the results of the investigation, the survey unit may be remediated, reclassified, or resurveyed.

51 August 1999

i TROJAN LICENSE TERAllNATIONPLAN

') Three principal types of survey data are collected. They are: 1) scan measurements,2) static

.U' surface contamination measurements, and 3) laboratory analysis of soil and bulk material samples. Data are verified to be of adequate quantity and quality and to support underlying assumptions necessary for a statistical test to be applied. Where necessary, previous survey steps are re-evaluated and additional data are collected prior to statistical analysis. The survey unit l meets the site release dose criterion once the survey data pass the statistical test. Where the data fail the statistical test, the survey unit does not meet the site release dose criterion. The data are analyzed and additional data are collected or the survey unit is remediated and resurveyed.

l Upon completion of final survey activities, a final survey report will be prepared which summarizes the data and documents the conclusion that the TNP facility and site meet the 10 CFR 20.1402 release criteria and can be released for unrestricted use. '

5.1.4 DEFINITIONS Italicized words and phrases found within the definition of the term are also def~med.

l Action Level: The numerical value that will cause the decision maker to choose one of the l altemative actions. It may be a dose- or risk-based concentration level (e.g., DCGL), or a l reference-based standard. See investigation level.

ALARA (As Low As Reasonably Achievable): A basic concept ofradiation protection which

("}

'o specifies that exposure to ionizing radiation and releases of radioactive materials should be managed to reduce collective doses as far below regulatory limits as is reasonably achievable considering economic, technological, and societal factors, among others. Reducing exposure at a site to ALARA strikes a balance between what is possible through additional planning and management, remediation, and the use of additional resources to achieve a lower collective dose level.

ALARA Criterion: The residualradioactivity has been reduced to levels that are ALARA.

Alpha (a): Also referred to as afalsepositive decision error, it is the probability of passing a survey unit that should fail.

Area of elevated residual radioactivity: An area over which residualradioactivity exceeds a specified value DCGL.

1 Area Factor: A multiple of the DCGL that is permitted in the area ofelevatedresidual l radioactivity without requiring remediation.

I Background Reference Area: An area that has similar physical, chemical, radiological, and biological characteristics as the site area being remediated, but which has not been contaminated by site activities, from which representative reference measurements are performed for t

comparison with measurements performed in specific survey units.

G ,

l 5-2 August 1999

TROJANLICENSE TERA 11NAT10N PLAN Background Radiation: Radiation from cosmic sources, naturally occurring radioactive O material, including radon (except as a decay product of source or special nuclear material), and global fallout as it exists in the environment from the testing of nuclear explosive devices or from nuclear accidents like Chernobyl which contribute to background radiation and are not under the control of the cognizant organization. Backgroundradiation does not include radiation from source, byproduct, or special nuclear materials regulated by the cognizant Federal or State agency.

Beta (p): Also referred to as afalse negative decision error, it is the probability of failing a survey unit that should pass. The complement of beta (1- ) is referred to as the power of the test.

Bias: The systematic or persistent distortion of a measurement process which causes errors in one direction (i.e., the expected sample measurement is different from the measurement's true value).

Calibration: Comparison of a measurement standard, instrument, or item with a standard or instrument of higher accuracy to detect and quantify inaccuracies and to report or eliminate those inaccuracies by adjustments.

Chain of Custody: An unbroken trail of accountability that ensures the physical security of samples, data, and records.

Class 1 Area: An impactedarea where, prior to remediation, there are expected to be locations with concentrations of residual radioactivity that exceed the DCGL.

Class 2 Area: An impacted area where, prior to remediation, there are expected to be locations with concentrations of residual radioactivity detectable above background levels, but that do not exceed the DCGL.

Class 3 Area: An impactedarea where there am not expected to be locations with concentrations of residual radioactivity detectable above background levels.

Confidence Interval: A range of values for which there is a specified probability (e.g., 80%,

90%,95%) that this set contains the true value of an estimated parameter.

Critical Group: The group ofindividuals reasonably expected to receive the greatest exposure to residual radioactivity within the assumptions of the particular scenario.

Derived Concentration Guideline Level (DCGL): The concentration ofresidualradioactivity distinguishable from background radiation which, if distributed uniformly throughout a survey unit, would result in a TEDE of 25 mrem /yr to an average member of the criticalgroup. The average member of the criticalgroup is the individual who is assumed to represent the most likely exposure situation based on the assumptions and parameter values used in the dose model calculation.

p Decision Maker: The person responsible for the final decision regarding disposition of the survey unit. This person is the Manager, Personnel / Radiation Protection.

5-3 August 1999 l

l l

TROJAN LICENSE TERMINATIONPLAN f3 GI Decommissioning: The process of removing a facility or site from operation, followed by remediation, and license termination. Its objective is to reduce the residual radioactivity in structures, materials, soils, groundwater, and other media at the site so that the concentration of each radionuclide contaminant that contributes to residual radioactivity is indistinguishable from the backgroundradiation concentration for that radionuclide.

Direct Measurement: Radioactivity measurement obtained by placing the detector near the surface or media being surveyed. An indication of the resulting radioactivity level is read out directly.

Elevated Measurement Comparison (EMC): A simple comparison ofmeasured values against i a limit. It is described in Appendix 5-1. I Exposure Pathway: The route by which radioactivity travels through the environment to eventually cause radiation exposure to a person or group.

J False Negative Decision Error: The probability of failing a survey unit that should pass. A statistician usually refers to afalse negative decision error as a Type 11 decision error.

False Positive Decision Error: The probability ofpassing a survey unit that should fail. A statistician usually tefers to thefalsepositive decision error as a Type Idecision error.

pd Final Survey: Measurements and sampling to describe the radiological conditions of a site, following completion of remediation activities in preparation for release.

Final Survey Plan: A formal document describing in comprehensive detail the necessary quality assurance, quality control, and other technical activities that must be implemented to demonstrate that the Trojan facility and site meet the radiological criteria for license termination given in Subpart E of 10 CFR 20. Thefinalsurveyplan provides a process for obtaining data of sufficient quality and quantity in such a manner as to ensure that the results of the work performed satisfy the stated performance criteria.

Gray Region: A range of values of the parameter ofinterest for a survey unit where the consequences of making a decision error are relatively minor. The upper bound of the gray region is set equal to the DCGL, and the lower bound ofthe gray region (LBGR) is a site-specific variable.

Impacted Area: An area that has reasonable potential for residualradioactivity from licensed activities.

Independent Spent Fuel Storage Installation (ISFSI): A complex designed and constructed for the interim storage of spent nuclear fuel and other radioactive materials associated with spent fuel storage.

p Investigation Level: A level of radioactivity that is based on the site release dosexriterion Q which, if exceeded, initiates an investigation of the survey measurement.

5-4 August 1999

TROJANLICENSE TERMINATION PLAN i License Termination: Discontinuation of a license, the eventual conclusion to decommissioning.

Lower Bound of the Gray Region (LBGR): The concentration to which the survey unit must be cleaned in order to have an acceptable probability of passing the statistical test for meeting the site release dose criterion. It represents the lower bound of the area of uncertainty regarding the concentration of residual radioactivity in the survey unit. The DCGL represents the upper bound. The width of the gray region (DCGL-LBGR) is also referred to as the shift.

Mean (R): The average value obtained when the sum ofindividual values is divided by the number of values.

Median (0): The center of the data set when data points are ranked in order from smallest to largest.

Minimum Detectable Concentration (MDC): The a priori radioactivity level that a specific instrument and technique can be expected to detect 95% of the time.

Non-Impacted Area: An area where there is no reasonable potential for residualradioactivity from licensed activities.

Nonparametric Statistical Test: A test based on relatively few assumptions about the exact

-.) form of the underlying probability distributions of the measurements. As a consequence, nonparametric statistical tests are generally valid for a fairly broad class of distributions. The 1 Wilcoxon Rank Sum test and the Sign test are examples of nonparametric tests.

Outlier: A measurement that is unusually large or small relative to the rest and therefore is suspected of misrepresenting the population from which it was collected.

i i

Power: The probability of accepting a survey unit as meeting the site release dose criterion i when it actually does. The power is equal to one minus thefalse negative decision error or Type 11 decision error rate (i.e.,1-p).

Precision: A measure of mutual agreement among individual measurements of the same property, usually under prescribed similar conditions, expressed generally in terms of the standard deviation.

Quality Assurance (QA): An integrated system of management activities involving planning, implementation, assessment, reporting, and quality improvement to ensure that a process, item, or service is of the type and quality needed.

Quality Control (QC): The overall system of technical activities that measure the attributes and performance of a process, item, or service against defined standards to verify that they meet the stated requirements, operational techniques and activities that are used to fulfill requirements for

/,D quality.

V.

5-5 August 1999

TROJANLICENSE TERMINATION PLAN Range: The measure of dispersion between the largest and smallest values in the data set.

t

\

Reference Coordinate System: A set ofintersecting lines referenced to a fixed site location or benchmark. Typically the lines are arranged in a perpendicular pattern dividing the survey location into squares or blocks of equal areas. Other patterns include triangular, polar, and three-dimensional coordinate systems.

Relative Shift (A/a): The ratio of the difference between the DCGL and the LBGR divided by the standard deviation in the concentration.

Remedia' tion: The removal of radiological contaminants from, or their neutralization on, an area to within levels established as acceptable. Remediation is sometimes used interchangeably with decontamination.

Repeat Measurement: A repeated analysis of the same sample or a measurement repeated at the same location.

Residual Radioactivity: Radioactivity in structures, materials, soils, groundwater, and other media at a site resulting from activities under the cognizant organization's control. This includes radioactivity from all sources oflicensed activities, but excludes background radiation as specified by the applicable regulation or standard. It also includes radioactive materials remaining at the site as a result of routine or accidental releases of radioactive material at the site and previous burials at the site, even if those burials were made in accordance with the

/O provisions of 10 CFR 20.

(_/

Scan Measurement: Radioactivity measurement obtained by moving the detector over a surface at a specified speed and distance above the surface to detect radiation. An indication of the resulting radioactivity level is read out directly.

Sign Test: A nonparametric statistical test used to demonstrate compliance with the site release dose criterion when the radionuclide ofinterest is not present in background and the distribution of data is not symmetric. See also Wilcoxon Rank Sum test.

I Site: Any installation, facility, or discrete, physically separate parcel ofland, or any building or structure or portion thereof, that is being considered for survey and investigation.

Site Release Dose Criterion: The residualradioactivity that is distinguishable from background radiation results in a TEDE to an average member of the criticalgroup that does not exceed 25 mrem /yr, including that from groundwater sources.

Standard Deviation: The measure of dispersion from the mean of the data set.

Static Measurement: Radioactivity measurement obtained from a surface or medium at a fixed location.

l 4

C

(

Surface Contamination: Residualradioactivity found on building or equipment surfaces and expressed in units of activity per surface area (dpm/100 cm2). j 5-6 August 1999

TROJANLICENSE TERAflNATIONPLAN Survey: A systematic evaluation and documentation of radiological measurements with a correctly calibrated instrument or instruments that meet the sensitivity required by the objective i

of the evaluation.

Survey Unit: A physical area of specified size and shape with similar characteristics and potential for residual radioactivity for which data evaluation and statistical analysis are performed. A separate decision is made for each survey unit as to its acceptability for release.

Type 1 Decision Error: Seefalsepositive decision error.

' Type II Decision Error: Seefalse negative decision error.

l Unity Rule: A rule applied when more than one radionuclide is present at a concentration that is

l. distinguishable from background and where a single concentration comparison does not apply. In this case, the mixture ofradionuclide concentrations is compared against DCGLs by applying the

- unity rule. The sum of the ratios for all radionuclides in the inixture should not exceed 1.0.

- Unrestricted Release: Release of a site from regulatory control without requirements for future radiological restrictions. Also known as unrestricted use.

~

Validation: Confirmation by examination and provision of objective evidence that the particular requirements for a specific intended use are fulfilled. In design and development, validation t concerns the process of examining a product or result to determine conformance to user needs.

l l

Verification: Confirmation by examination and provision of objective evidence that the specified requirements have been fulfilled. In design and development, verification concerns the process of examining a result of given activity to determine conformance to the stated requirements for that activity.

Wilcoxon Rank Sum (WRS) Test: A nonparametric statistical test used to determine compliance with the site release dose criterion when the radionuclide of concern is present in background. See also Sign test.

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5-7 August 1999 L

TROJAN LICENSE TERMINA TIONPLAN

\

5.2 SURVEY OVERVIEW L/

This section describes the scope and methodology of the final survey process, including quality i assurance measures, access control procedures, and how implementation of the plan will demonstrate that the facility and site will meet the 10 CFR 20.1402 criteria for unrestricted release of the site and license termination. Also described is the methodology used to develop guideline values against which residual radioactivity levels remaining at TNP at the time of final survey will be compared.

5.2.1 IDENTITY OF RADIOLOGICAL CONTAMINANTS The gross radionuclide inventory at the Trojan site was estimated during site characterization in 1993-1994. The data are compiled in the Trojan Radiological Site Characterization Report (Reference 5-7) and summarized in Section 2 of this Trojan License Termination Plan. '

Additional data continue to be gathered on radionuclide inventory from routine operational and decommissioning surveys and supplemental site characterization work performed since 1993-1994. The predominant beta-gamma emitter on structure surfaces and in plant systems is "Co; in soil, bottom sediment, and pavement it is *Cs.

5.2.2 SITE RELEASE CRITERIA 5.2.2.1 Radiological Criteria For Unrestricted Use  ;

The site release criteria correspond to the radiological criteria for unrestricted use given in (Q) 10 CFR 20.1402, which are: '

i

1. Dose Criterion: The residual radioactivity that is distinguishable from background radiation results in a Total Effective Dose Equivalent (TEDE) to an average member of the critical group that does not exceed 25 mrem /yr, including that from groundwater sources of drinking water; and

)

)

2. ALARA Criterion: The residual radioactivity has been reduced to levels that are ALARA.

5.2.2.2 Conditions Satisfying The Site Release Criteria Levels of residual radioactivity that correspond to the allowable radiation dose and ALARA levels above are calculated (derived) by analysis of various scenarios and pathways (e.g., direct radiation, inhalation, ingestion, etc.) through which exposures could occur. These derived levels, referred to as derived concentration guideline levels (DCGLs), form the basis for the following conditions which, when met, satisfy the site release criteria:

1. The average residual radioactivity above background is equal to or below the DCGL; O

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l TROJANLICENSE TERMINA TION PLAN l

2. Individual measurements, representing small areas of residual radioactivity which

() exceed the DCGL, do not exceed the elevated measurement comparison DCGL.

V The elevated measurement comparison DCGL is described in Section 5.2.3.2.5; 1

3. Where one or more individual measurements exceed the DCGL, the average residual radioactivity passes the Sign or Wilcoxon Rank Sum (WRS) statistical test. The application of the statistical test is described in Section 5.6.4.1; and

4. Remediation is performed where it is ALARA to reduce the levels of residual radioactivity to below the concentrations necessary to meet the DCGLs.

5.2.3 DEVELOPMENT OF DERIVED CONCENTRATION GUIDELINE LEVELS 5.2.3.1 Dose Modeling Dose models based on NUREG/CR-5512, Volume 1 (Reference 5-8), and appropriate to Trojan are used to calculate the DCGLs. The dose model translates residual radioactivity levels into potential radiation doses to the public and is defined by three factors: 1) the scenario,2) the exposure pathways, and 3) the critical group. The scenarios described in NUREG/CR-5512 address the major exposure pathways of direct exposure to penetrating radiation and inhalation and ingestion ofradioactive materials. The scenarios also identify the critical group. The critical group is the group ofindividuals reasonably expected to receive the greatest exposure to residual radioactivity within the assumptions of the particular scenario. The scenarios and their modeling are specifically designed to be " reasonably conservative" by generally overestimating rather than t- underestimating potential dose.

Three scenarios were considered for Trojan. They are 1) building occupancy,2) building renovation or demolition, and 3) residential farming. These scenarios, described below, represent reasonable and plausible human activities and future uses of the Trojan facility and site. They are based on those described in NUREG/CR-5512 and use the same modeling assumptions. No conditions exist at Trojan, outside those incorporated in the NUREG/CR-5512 scenarios and modeling assumptions, which would cause the estimated potential dose to the public to increase.

5.2.3.1.1 Building Occupancy Scenario l i

i Because surface decontamination operations may not remove all of the surface radioactivity, a scenario describing surface contamination is considered. This scenario accounts for exposure to both fixed and removable thin-layer or surface radioactivity within a structure. This scenario assumes that individuals occupy the building in a passive manner without deliberately disturbing j the residual radioactivity on building surfaces. Occupancy of the building is assumed to begin l immediately after license termination. The exposure duration is assumed to be a full work year l (2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br />). The critical group consists of the building occupants, who are the people who i work in the building following license termination.

O i V 5-9 August 1999

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TROJAN LICENSE TERMINATIONPLAN The pathways that apply to the building occupancy scenario include:

O V' l. Extemal exposure to penetrating radiation from surface sources; 2.- Inhalation of resuspended surface contamination; and

3. Inadvertent ingestion of surface contamination.

1 5,.2.3.1.2 Building Renovation or Demolition Scenario At some point in time, the remaining site buildings may require renovation. Ultimately, they will be demolished. During renovation or demolition, surface and volume sources are disturbed, creating loose contamination. This loose contamination can produce higher concentrations of radionuclides in the air or on surfaces than the levels in an undisturbed building. ' This scenario assumes that building renovation or demolition activities occur immediately after license termination. The exposure duration is a short-term, one-time exposure assumed to occur over a six-month period. The critical group is the workers involved in building renovation or demolition who work in, on, and around the building following license termination.

The pathways that apply to the building renovation or demolition scenario include:

~

1. External exposure to penetrating radiation from volume sources;

)

2.- Inhalation of airborne radioactive dust; and d

3. Inadvertent ingestion ofloose surface contamination.

5.2.3.1.3 Residential Farming Scenario Soil at the site can be contaminated from licensed operations by accidental spills, long-term accumulation of material in the soil via effluent releases, or intentional disposal or burial of concrete rubble and other debris such as pavement, masonry, and structural steel with both surface and volumetric radioactive contamination. The residual radioactivity is assumed to be distributed in a surface soil layer covering the plant site on property that is used for residential j and light farming activities. The scenario assumes continuous exposure via multiple exposure  ;

pathways to the critical group. The critical group is the resident farming family who lives on the plant site following site remediation, grows some portion of their diet on the site, and drinks water from a source at the site.

The pathways that apply to the residential farming scenario include:

1. External exposure to penetrating radiation from volume soil sources while

- outdoors;

2. External exposure to penetrating radiation from volume soil sources while indoors; 5-10 August 1999

1 TROJAN LICENSE TERMINA TION PL4N

3. Inhalation exposure to resuspended soil while outdoors;

4. Inhalation exposure to resuspended soil while indoors;

5. 1 Inhalation exposure to resuspended surface sources of soil tracked indoors; l l

6. Direct ingestion of soil;

7. Inadvertent ingestion of soil tracked indoors;

8. Ingestion.of drinking water from a groundwater source;

9. Ingestion of plant products grown in contaminated soil;

10. Ingestion of plant products irrigated with contaminated groundwater;

11. Ingestion of animal products grown on-site (i.e., after animals ingest contaminated drinking water, plant products, and soil); and

12. Ingestion of fish from a contaminated surface water source. l l

5.2.3.2 Derived Concentration Guideline Levels 1

(']

U The surface contamination and radionuclide concentration levels of structures, land areas, and plant systems remaining at the time of the final survey are compared to DCGLs calculated using the dose models. A DCGL is defined as the concentration of residual radioactivity l distinguishable from background radiation which, if distributed uniformly throughout a survey l unit, would result in a TEDE of 25 mrem /yr to an average member of the critical group. The l average member of the critical group is the individual who is assumed to represent the most likely exposure situation based on the assumptions and parameter values used in the dose model calculation. The DCGLs are calculated based on the peak annual TEDE dose to the average member of the critical group expected within the first 1000 years after license termination. I DCGLs are presented in terms of surface or volumetric radioactivity concentrations and are 2

expressed in units of dpm/100 cm or pCi/g.

5.2.3.2.1 Screening DCGLs Screening DCGLs are intended to be used as the principle means of releasing the site. However, since Trojan is a radiologically complex site (i.e., multiple radionuclides found in various distributions throughout the site), the screening DCGLs are seldom, if ever, applied directly to determine compliance with the site release dose criteria. Rather, they are used to develop surrogate ratio, gross activity, or elevated measurement comparison (EMC) DCGLs, or are applied using the unity rule. Where the broad conservatism inherent in the screening DCGLs prove unrealistically restrictive, a set of site-specific DCGLs may be developed and used in their

~

place.

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5-11 August 1999

TROJANLICENSE TERMINATION PLAN

-s Screening DCGLs, given in Table 5-1, were calculated using DandD, the NRC's computerized (V) dose modeling software. DandD uses the conceptual and mathematical models developed in NUREG/CR-5512 and the generic input parameter values presented in draft NUREG-1549 l

(Reference 5-9). Screening DCGLs for surface and volumetric residual radioactivity were developed using the building occupancy and residential farming scenarios. For volumetric residual radioactivity, the residential farming scenario provides DCGLs which are more conservative than the building renovation or demolition scenario.

5.2.3.2.2 Site-Specific DCGLs Site-specific DCGLs may be developed by replacing generic input parameter values with site-specific parameters. The generic input parameter values presented in draft NUREG-1549 generally lie within the distributions of reported or expected values (i.e., are not at the extremes of the ranges) and explicitly exclude bounding or unrealistic assumptions. Physical parameters represent real conditions and expected variability across the United States. Behavioral and metabolic parameters represent the expected variability between individuals within the defined critical group. Site-specific data mayjustify the use of site-specific parameter values to reduce the conservatism of the screening DCGL and produce a more realistic estimate of site-specific conditions. Site-specific parameter values used in developing site-specific DCOLs are documented, including thejustification for their use. A treatment of uncertainty is included as l part of thejustification.

The DandD computer code is designed to permit simple modifications to input parameter values, O

V such as the exposure durations, intake rates, or concentrations in various pathway media.

Attachment I to draft NUREG-1549 provides information regarding the valid ranges for site-l specific parameter changes that can be made within DandD without an additional uncertainty 1 analysis. Where DandD cannot be easily modified to incorporate the use of site-specific data, other computerized dose modeling software, such as the US Department of Energy's RESRAD and RESRAD-BUILD, may be used to generate site-specific DCOLs.

l 5.2.3.2.3 Surrogate Ratio DCGLs 1 i

Surrogate ratio DCGLs may be established for areas where fairly constant radionuclide l concentration ratios can be demonstrated to exist. The established ratio among the radionuclide concentrations allows the concentration of every radionuclide to be expressed in terms of any one of them. Likewise, a surrogate ratio DCGL allows the DCGLs specific to hard-to-detect radionuclides in a mix to be expressed in terms of a single radionuclide which is more readily measured. The measured radionuclide is called the surrogate radionuclide.

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5-12 August 1999

TROJANLICENSE TERMINATION PLAN 7.. A sufficient number of measurements, spatially separated throughout the area ofinterest, are l

! i taken to establish a consistent ratio of radionuclide concentrations. The number of l kJ measurements needed to determine the ratio is based on the chemical, physical, and radiological characteristics of the radionuclides and the site. The surrogate ratio is based on the most conservative value from the measurement data set. Where the standard deviation of the data set i

is greater than 1/3 of the mean value, the 95% upper confidence bound is used in place of the l most conservative value. The 95% confidence level value of the mean, po, is calculated as follows (derived from EPA QA/G-9," Guidance for Data Quality Assessment"(Reference 5-10),

Box 3.2-1, Step 3 equation):

1 g

p, =

x + Ig uao /n' (Equation 5-1) where:

R =

l mean, calculated using Equation 5-10 l

=

t<95%,dr> t statistic for 95% confidence at n-1 degrees of freedom (values of t<95%,or) can be obtained from EPA QA/G-9, Table A-1) o =

standard deviation, calculated using Equation 5-11 n =

number of measurements Once an appropriate surrogate ratio is determined, the DCGL of the measured radionuclide is modified to account for the represented radionuclide according to the following equation (NUREG-1575 (Reference 5-11), Equation 4-1):

O]

DCGLsa = DCGLs., x DCGLac#

l (Equation 5-2)

[(Cam / Cs ,) (DCGLse)] + DCGLam l

where:

=

l DCGLsn modified DCGL for surrogate ratio

! DCGLsur = DCGL for surrogate radionuclide DCGLac, =

DCGL for represented radionuclide Ca,p =

Concentration of represented radionuclide Csur = Concentration of surrogate radionuclide When a surrogate ratio is established using data collected prior to remediation, additional post-remediation measurements are collected to ensure that the data used to establish the ratio are still appropriate and representative of the existing site condition. If additional post-remediation j

measurements are not consistent with the pre-remediation data, the surrogate ratio DCGL is re-established. Professionaljudgment is used to determine consistency.

g  !

(- )

5-13 August 1999 l

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TROJAN LICENSE TERMINA TION PLtN 5.2.3.2.4 Gross Activity DCGLs O) t V Where multiple radionuclides are present at concentrations which exceed 10 percent of their respective DCGLs, a gross activity DCGL may be developed. The gross activity DCGL enables field measurement of gross activity, rather than the determination ofindividual radionuclide activity, for comparison to the radionuclide-specific DCGL. The gross activity DCGL, or DCGLGA, or surfaces or volumes with multiple radionuclides is calculated using the following equation (NUREG-1575, Equation 4-4):

=

1 DCGLca (Equation 5-3) fi + f2 +*

f,,

DCGLi DCGL2 DCGL,,

where:

=

fo fraction of the total activity contributed by radionuclide n

=

DCGLo DCGL for radionuclide n

( Different radionuclides or radionuclide combinations may exist on different portions of the site l and require the calculation of one or more site-specific gross activity DCGLs. DCGLs are based i

upon previously determined radionuclide distributions for specific areas. For areas where the radionuclide distribution has not been determined, the most conservative distribution resulting in the lowest DCGL of those specified areas is used. The distributions are based on the 1

~'s radionuclides identified in composite samples from the specific areas collected both during (V power operation and decommissioning. If new radionuclide distribution data are obtained during )

j decommissioning and determined to be more appropriate for use, the DCGL may be re-evaluated I and altered during the course of the final survey.

For soil contamination, specific radionuclides, rather than gross activity, may be measured. For a known mixture of these radionuclides, each having a fixed relative fraction of the total activity, site-specific DCGLs for each radionuclide may be calculated by first determining the gross activity DCGL and then multiplying that gross activity DCGL by the respective fractional contribution of each radionuclide.

5.2.3.2.5 Elevated Measurement Comparison (EMC) DCGLs The EMC DCGL is the DCGL modified to account for small areas where elevated residual l radioactivity levels exceed the DCGL. It is the level of residual radioactivity over a small, but defined area, at which there is reasonable assurance the site release dose criterion is still satisfied. The EMC DCGL, or DCOLouc, is derived assuming that the residual radioactivity is concentrated in a much smaller area rather than uniformly over the entire survey unit area. It is l

calculated and applied where the minimum detectable concentration (MDC) for performing scan measurements is larger than the DCGL or where one or more static measurement data points exceed the DCGL. The methodology used to calculate and apply the DCGLt uc is given in Appendix 5-1.

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5-14 August 1999

1 TROJAN LICENSE TERMINATIONPLAN 5.2.3.2.6' Unity Rule

. When the concentrations of different radionuclides appear to be unrelated, such as where the radionuclides occurring in background have unknown or variable relative concentrations, there is little alternative to measuring the concentration of each radionuclide and using the unity rule.

The exception would be in applying the most restrictive DCOL to all of the radionuclides. The unity rule is applied using the following equation (NUREG-1575, Equation 4-5):

C1 C2 C,

+ +... 61 (Equation 5-4)

DCGLi DCGL2 DCGL, where:

Co. = Concentration of radionuclide n DCGLo =

DCGL for radionuclide n 5.2.4 FACILITY AND SITE CLASSIFICATION The facility and areas of the site do not all have the same potential for residual radioactivity and, accordingly, do not all need the same level of survey effort to demonstrate compliance with the site release criteria. Different parts of the facility and areas of the site are grouped into impacted and non-impacted areas based on the potential for residual radioactivity using the criteria given below. Classification is based on professional judgment, in consideration of operational history, site characterization data, operational surveys performed in support of decommissioning, and routine surveillances.

5.2.4.1 Non-Impacted Areas Areas that have no reasonable potential for residual radioactivity from licensed activities are designated as non-impacted areas. These areas do not need any level of survey coverage since there was no radiological impact from site operations. No surveys of non-impacted areas are performed.

5.2.4.2 Impacted Areas Areas that have reasonable potential for residual radioactivity from licensed activities are designated as impacted areas. Impacted areas are subdivided into three classes described below and illustrated in the following figure.

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5-15 August 1999

TROJANLICENSE TERMINATIONPLAN i O

(f CLASSES OF IMPACTED AREAS 8 .&

_=n.

^

co Ts m., .:" m .

. (Class 24 . n. .

-l $j

,j; Expected pre-remid}ation

" r w ' residual radioactiv.ity < DCGL' 5Y Class 3 No expected residual radioactivity l

5.2.4.2.1 Class 1 Areas Class 1 areas are impacted areas where, prior to remediation, there are expected to be locations with concentrations of residual radioactivity that exceed the DCGL. Examples of Class I areas are: 1) site areas previously subjected to remediation, 2) locations where leaks or spills are known to have occurred, and 3) areas where discrete radioactive particles may be found.

5.2.4.2.2 Class 2 Areas Class 2 areas are impacted areas where, prior to remediation, there are expected to be locations with concentrations of residual radioactivity detectable above background levels, but that do not exceed the DCGL. Examples of Class 2 areas are: 1) locations where radioactive materials were present in an unsealed form,2) potentially contaminated in-plant or on-site transport routes,

3) upper walls and overhead areas of buildings or rooms subjected to airbome radioactivity,

4) areas where low concentrations of radioactive materials were handled, and 5) areas on the perimeter of former contamination control areas.

5.2.4.2.3 Class 3 Areas Class 3 areas are impacted areas where there are not expected to be locations with concentrations of residual radioactivity detectable above background levels. Examples of Class 3 areas are:

1) buffer zones around Class 1 or Class 2 areas, and 2) areas with a very low potential for residual contamination but where information is insufficient to justify a non-impacted classification. Previous remediation precludes an area from being classified as a Class 3 area.

5.2.4.3 Initial Classification The initial classification of the facility and site is given in Table 5-2. It is based on site characterization data, the history of radioactive materials involvement or the known potential for contamination of an area, and the recommendations of Trojan personnel knowledgeable of site p conditions. Site characterization data and radiological history are summarized in Section 2.

O 1

5-16 i August 1999

TROJANLICENSE TERMINATIONPLAN The initial classification process incorporated the working hypothesis that all impacted areas i p. have a potential for radioactive contamination above the DCGL. This initia! assumption means V that areas were initially considered Class 1 areas unless some basis for classification as Class 2 or Class 3 was identified. The basis for classification is documented in the history file described in Section 5.7.1 5.2.4.4 Changes In Classification The classification of an area may be changed in accordance with approved plant procedures prior to the start of final survey data collection in the area. Changes in classification are based on survey data and other available information that indicate another classification is more appropriate.

5.2.5 FINAL SURVEY PROCESS Dismantlement activities occur prior to the start of the final survey process. Impacted systems and equipment are removed, remaining structures and surfaces are decontaminated, and operational radiation protection (RP) surveys of the work area are performed. The final survey process begins with survey preparation activities, followed by survey design, data collection, and data assessment activities, and concludes with documentation of survey results.

5.2.5.1 Survey Preparation

p. Survey preparation, described in Section 5.3, is the first step in the final survey process. The site

'V release ALARA criterion, that residual radioactivity has been reduced to ALARA levels, is

)

addressed during survey preparation. Remediation levels are established for various types of remediation actions. A remediation level is the level of residual radioactivity at which the desired beneficial effects due to the performance of a given remediation action are equal to the undesirable effects or costs of the action. Data from operational RP surveys are used to perform an ALARA evaluation. The ALARA evaluation examines the various remediation actions to determine which of them, if any, have a net benefit in further reducing the levels ofresidual radioactivity. Those remediation actions are taken and other preparations are made for survey i data collection.

Work areas are grouped into tumover units and prepared for survey data collection. A tumover l unit is an area which can be isolated and controlled to ensure that radioactive material is not introduced into the area from ongoing decommissioning activities in adjacent or nearby areas. l Tools, equipment, and materials not needed for survey data collection are removed.

Housekeeping and clean-up activities are completed. Scaffolding and other temporary ,

equipment or material needed for survey data collection are put in place. Routine access, equipment removal, material storage, and worker and material transit in or through the tumover unit are no longer allowed.

Once a walkdown has been performed and the turnover criteria met, control of activities within the tumover unit is transferred from the Decommissiining organization to the Final Survey p organization. The turnover unit is isolated and access is controlled. Isolation and control fh measures remain in place through survey data collection until license termination.

5-17 August 1999

c TROJANLICENSE TERMINA TIONPLAN 5.2.5.2 Survey Design f]

v Survey design, described in Section 5.4, identifies relevant components of the final survey process and establishes the assumptions, methods, and performance criteria to be used. Tumover units are divided into survey units and classified as Class 1, Class 2, or Class 3. Systematic scan and static measurements are prescribed according to a pattem and frequency established for each classification. Investigation levels are established which, if exceeded, initiate an investigation of the survey data. A measurement from the survey unit that exceeds an investigation level may indicate a localized area of elevated residual radioactivity. Such locations are marked and investigated to determine the area and the level of the elevated residual radioactivity. Depending on the results of the investigation, the survey unit may require remediation, reclassification, and/or resurvey.

Quality control (QC) measurements are prescribed to identify, assess, and control measurement error and uncertainty attributable to measurement methods or analytical procedures used in the data collection process. QC measurements provide qualitative and quantitative information to demonstrate that measurement results are sufficiently free of error to accurately represent the radiological condition of the facility and site.

5.2.5.3 Survey Data Collection

)

Survey data collection, described in Section 5.5, consists of the collection of survey data for p subsequent analysis and preparation of a final survey report. Survey data collection begins with V a turnover survey for survey units where areas of elevated residual radioactivity may be found.

The turnover survey, performed prior to the final survey, is designed to verify that residual radioactivity levels are acceptable and that no additional remediation will be necessary. It is performed using the same methodology, techniques, and quality control requirements as the final survey. The turnover survey is a biased survey which uses professionaljudgment to identify measurement locations most likely to have elevated levels of residual radioactivity. If an area of elevated residual radioactivity is identified and remediation is determined to be ALARA, it is remediated and resurveyed to ensure it meets the final survey requirements.

The data coll:cted during the turnover survey provides a sound basis for interpreting radiological conditions that rc.ay be encountered during the final survey. Also, because the tumover survey is conducted using the same methodology, techniques, and quality controls as those required for the final survey, certain data collected during the turnover survey may be used as part of the final survey data set.

I Following the turnover survey, a final survey is performed. The final survey is a confirmatory survey to ensure that any residual radioactivity meets the 25 mrem /yr TEDE site release dose criterion. Measurement results stored as final survey data constitute the final survey of record and are included in the data set used to determine compliance with the site release dose criterion.

3 (O

5-18 August 1999

1 TROJANLICENSE TERAflNATIONPLAN 5.2.5.4 Survey Data Assessment 1

Survey data assessment, described in Section 5.6, is performed to verify that the final survey data are of adequate quantity and quality. Graphical representations and statistical comparisons of the data are made which provide both qualitative and quantitative information about the data. An assessment is performed to verify the data support the underlying assumptions necessary for the statistical tests. If the quantity, quality, or one or more of the assumptions are called into question, previous survey steps are re-evaluated and additional data are collected as necessary prior to further statistical analysis.' The statistical tests are applied and conclusions are drawn from the data as to whether the survey unit meets the site release dose criterion.

5.2.5.5 Survey Results

' Survey results are documented in history files, survey unit release records, and in the final survey report. The final survey report is prepared which summarizes the data and states the conclusions.

5.2.6- PROJECT MANAGEMENT

- The planning and implementation of the final survey process is performed by Trojan personnel supplemented by contracted personnel. Aspects of the final survey project are outlined below.

5.2.6.1 Final Survey Organization The organization responsible for the final survey project is illustrated in the following figure.

The Manager, Personnel / Radiation Protection serves as the principal decision-maker and is responsible for the overall implementation of the final survey project. The Manager, Personnel / Radiation Protection is also responsible for the overall integration of the final survey project with decommissioning activities, and for the interface with the Nuclear Oversight organization on independent assessments and audits of final survey activities. Responsibilities and interfaces with other key plant positions are described in the Trojan Decommissioning Plan.

l i

I l l l

0 -

l 5-19 August 1999

TROJAN LICENSE TERMINATION PLAN p Final Survey Project Organization (v) e Quality Assurance -

1. "ajer,

g P Decommissioning

• I Final Survey Project Manager l

l l Survey Data I Survey Preparation Techm. cal Suppor' Collection ,

l The Final Survey Project Manager oversees survey design, implementation, and assessment  ;

activities and ensures they are performed in accordance with this plan. The Final Survey Project l Manager approves the final survey results and conclusions.

The Survey Preparation staffis responsible for ensuring that the facility and site are ,

m appropriately remediated and prepared for turnover to final survey. The Survey Data Collection teams are responsible for collecting survey data in accordance with this plan. The Technical Support staffis responsible for providing technical support such as survey des gn, procedure preparation, technical evaluations, scheduling and coordination of activities, and data review.

5.2.6.2 Quality Assurance And Quality Control (QA/QC)

QA/QC is an integral part of the final survey process. The objective of QA/QC, as applied to the final survey process, is to ensure the survey data collected are of the type and quality needed to demonstrate with sufficient confidence that the facility and site are suitable for release to unrestricted use. Steps are described in this plan to ensure: 1) the elements of this plan are correctly implemented as prescribed,2) the quality of the data collected is adequate, and

3) corrective actions, when needed, are implemented in a timely manner and confirmed to be effective.

In addition to the above, applicable provisions of the Trojan Nuclear Quality Assurance Program, PGE-8010 (Reference 5-12), are applied to final survey activities. The final survey process is performed in a controlled, deliberate manner, providing assurance of accurate results.

Surveys are performed by trained individuals with calibrated instruments following approved plant procedures, data are recorded and reviewed, and documentation is auditable.

I m

U l 5-20 August 1999

TROJAN LICENSE TERMINA TION PLAN 5.2.6.3 Survey Records And Documentation Generation, handling, and storage of final survey design information and survey data are controlled by approved plant procedures. Survey records and documentation are maintained as quality records and decommissioning records in accordance with approved plant procedures.

Where possible, they are maintained as electronic media to reduce data transfer errors and to facilitate the use of statistical tools and the eventual reporting of survey results.

5.2.6.3.1 ' Procedures Survey activities which are essential to survey data quality are implemented and controlled by approved plant procedures.

5.2.6.3.2 Technical Basis Documents Technical basis documents are prepared and maintained in accordance with approved plant procedures. Technical basis documents show what methods were used, how the methods are derived, underlying assumptions, the basis for deviations from this plan, and other information that should be properly documented. They may include position papers, calculations, computer code verification results, file memoranda, correspondence, etc.

DCGL documentation includes reports generated by DandD to verify the version of the software used in the analysis. Site-specific data supporting any changes made to input parameters also is (3 included. If other computer models are used, sufficient information is documented to allow for

() review of the model, scenarios, and parameters.

5.2.6.3.3 Records Records of activities affecting quality are maintained in accordance with approved plant l

procedures and the Trojan QA Program. The final survey report and records showing the results

)

of surveys and calibrations are maintained for a period of 3 years following the completion of the final survey.

5.2.6.4 Audits And Independent Reviews I Audits are performed to verify survey activities comply with established procedures and applicable aspects of the Trojan QA Program. Randomly selected survey unit release records and other final survey documentation are independently reviewed to ensure that the survey results are documented in accordance with approved plant procedures. Audits and independent reviews are performed, and the reports of the results are maintained in accordance with approved plant procedures.

5.2.6.5 Control Of Vendor Supplied Services Quality-related services, such as instrument calibration and laboratory analysis, are procured from qualified vendors whose internal QA program is subject to approval in accordance with the Q,3 Trojan Nuclear Quality Assurance Program.

5-21 August 1999

TROJANLICENSE TERMINATIONPLAN 5.2.6.6 Training Training is conducted to achieve initial proficiency and to maintain that proficiency throughout the final survey process. Personnel performing surveys receive training to qualify in the procedures being performed. Training includes:

1. Overview and objectives of this plan; i

2. Procedures governing the conduct of the final survey;

3. Operation of the appropriate field and laboratory instrumentation;

4. Collection of final survey measurements and samples; and

5. Survey data evaluation.

The extent of training and qualifications is commensurate with the education, experience, and proficiency of the individual and the scope, complexity, and nature of the activity. Records of training are maintained in accordance with approved plant procedures.

5.2.6.7 Schedule p Final survey activities are planned, scheduled, and tracked as a part of the overall

( decommissioning planning process. The schedule is dependent upon the progress and completion ofseveral decommissioning activities Presently, survey data collection is estimated to be completed in mid- to late-2002. Final sur.'ey activities are planned and discussed with the NRC and the Oregon Office of Energy sufficiently in advance to allow the scheduling of inspection activities.

5-22 August 1999

TROJANIJCENSE TERMINA TION PLAN 5.3 SURVEY PREPARATION (h

\v) Survey preparation is the first step in the final survey process. Remediation levels are established for various types of remediation actions. Using the remediation levels, an ALARA evaluation determines which remediation actions, if any, need to be performed. The necessary remediation actions are taken, and isolation and control measures are instituted in preparation for '

survey data collection. The site release ALARA criterion, that residual radioactivity has been reduced to ALARA levels, is satisfied once remediation actions determined necessary are completed.

4 5.3.1 REMEDIATION LEVELS Remediation levels are established for remediation actions such as chemical decontamination, wiping, washing, vacuuming, scabbling, spalling, abrasive blasting, and high pressure washing.

A remediation level is the level of residual radioactivity at which the desired beneficial effects due to the performance of a given remediation action are equal to the undesirable effects or costs of the action. The methodology for calculating remediation levels is based on draft Regulatory Guide DG-4006 (Reference 5-13) and is provided in Section 4.

5.3.2 ALARA EVALUATION An ALARA evaluation is performed for Class 1 and Class 2 areas since residual radioactivity may remain in these areas once dismantlement activities are completed. An ALARA evaluation is not performed for Class 3 areas, which by their classification are considered ALARA.

v The ALARA evaluation is prepared, approved, and maintained in accordance with approved plant procedures. The ALARA evaluation examines various remediation actions to determine which actions, if any, have a net benefit in further reducing the levels of residual radioactivity.

Operational RP survey data are used to perform the evaluation. Residual radioactivity levels are compared to calculated remediation levels of possible remediation actions which could be, but l have not been, taken. Where the level of residual radioactivity exceeds the remediation level, the remediation action is considered to have a net benefit. Therefore, it is considered cost effective and must be taken for the residual radioactivity to be considered ALARA. Conversely,if the concentration is less than the remediation level, the level of residual radioactivity is already considered ALARA and the remediation action is not required to be performed.

The ALARA evaluation is needed only to justify not taking a remediation action. If a decision has already been made to perform a given remediation action, there is no need to evaluate whether the action is necessary to meet the ALARA requirement. For example, if wiping down surfaces with loose radioactive contamination is a good practice that is applied regardless of radioactive contamination levels, then it does not need an ALARA evaluation. For those remediation actions considered but not taken, the ALARA evaluation includes the levels of residual radioactivity above which those remediation actions would have been justified.

Remediation levels do not represent concentration lim'its that cannot be exceeded. Rather, they (N represent the threshold at which the given remediation action is taken. The ALARA requirement

() is met by perfonning the appropriate remediation action and not by being below a specified 5-23 August 1999

g .-

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[ TROJANUCENSE TERMINATION PLAN '

e

. concentration after th' action is taken. The ALARA evaluation ensures that efforts to remove residual radioactivity are commensurate with the level of risk the residual radioactivity poses.

l 5.3.3 TURNOVER l:

' Due to the large scope of the final survey and the need for some survey ac.tivities to be conducted

in parallel with dismantlement activities, a systematic approach is established for the turnover of facility and site areas to the Final Survey organization.

5.3.3.1 Tumover Units The facility'and site are divided into turnover units. A turnover unit is a logical combination of structures, land areas, and/or plant systems where dismantlement activities are completed and

)

which can be isolated and controlled. Properly designed, turnover units facilitate the transfer of control of areas (and their subsequent removal from routine use) and minimize the impact on planned or ongoing dismantlement activities in adjacent areas.

5.3.3.2 Walkdown l

' - A walkdown of the turnover unit is performed prior to turnover. The principal objective of the walkdown is to assess the physical state of the turnover unit and the scope of work necessary to prepare it for final survey. During the walkdown, requirements are identified for accessing, isolating, and controlling the turnover unit. Support activities necessary to conduct the final O survey, such as scaffolding, interference removal, and electrical tag-outs, are identified. Safety concerns such as access to confined spaces, high walls, and ceilings are also identified. For systems, the walkdown includes a review of system flow diagrams and piping drawings. The walkdown is performed when the final configuration is known, usually near or after the completion of dismantlement ' activities.

5.3.3.3 Turnover Criteria The following criteria are satisfied prior to acceptance of a turnover unit by the Final Survey organization. The physical aspects of these criteria are verified during the walkdown.

1. Planned dismantlement activities within the turnover unit are completed;  !

2. Planned dismantlement activities affecting or adjacent to the turnover unit are completed OR are evaluated and determined to not have a reasonable potential to introduce radioactive material into the turnover unit;

3. An operational RP survey of the turnover unit is completed and outstanding items are addressed;

4. Planned physical work in, on, or around the turnover unit, other than routine surveillance or maintenance, is completed;

,V A

5-24I August 1999 I

i TROJAN LICENSE TERMINATIONPLAN

5. Tools, non-permanent equipment, and material not needed for suivey data collection are removed;

6. Housekeeping, clean-up, and remediation of the turnover unit are completed;

7. _ Scaffolding, temporary electrical and ventilation equipment and components, and other material or equipment needed for survey data collection are documented radiologically clean and left in place;

8. Transit paths to/through the turnover unit are eliminated or re-routed;

9. Appropriate measures are instituted to prevent the introduction of radioactive material into the turnover unit for ventilation, drain lines, system vents, and other potential airborne and liquid contamination pathways; and

10. Measures are instituted to control access and egress and otherwise restrict radioactive material from entering the turnover unit.

5.3.3.4 Transfer Of Control Once a walkdown has been performed and the turnover criteria met, control of activities within l

the turnover unit is transferred from'the Decommissioning organization to the Final Survey I organization. The need for localized remediation within the turnover unit may be identified after

. transfer of control. Localized remediation may be performed under the control of the Final Survey organization. Iflarge areas require remediation, the turnover unit may be transferred back to the Decommissioning organization to be reworked.

5.3.3.5 Isolation And Control Measures The turnover unit is isolated and access is controlled. Routine access, equipment removal, material storage, and worker and material transit through the area are no longer allowed. One or i more of the following administrative and physical controls are established to minimize the possibility ofintroducing radioactive material from ongoing decommissioning activities in adjacent or nearby areas.

1. Personnel training;

2. Installation of barriers to control access to area;

3. Installation of postings with access / egress requirements;

4. Locking or otherwise securing entrances to the area; and

5. Installation of tamper-evident seals or labels.

Isolation and control measures are implemented through approved plant procedures and remain

( in place through survey data collection until license termination.

5-25 August 1999

TROJANLICENSE TERMINA TION PLAN 5.4 SURVEY DESIGN The survey design identifies relevant components of the final survey process and establishes the assumptions, methods, and performance criteria to be used. The survey design is summarized in Table 5-3. For survey design purposes, impacted areas are categorized as one of three types:

1.

Structures, which include building interiors and exteriors, major free-standing exterior structures, exterior surfaces ofplant systems, and paved exterior ground surfaces;

2. Land areas, which include unpaved exterior ground surfaces; and 3.

Plant systems, which include interior surfaces of process piping and components.

The application of survey design criteria to structures and land areas will vary based on the type of survey media and the relative potential for elevated residual radioactivity. For plant systems, many of the survey design criteria applicable to structures and land areas do not apply or are dictated by the physical system layout and the accessibility to system piping and components.

To accommodate these factors, the survey design integrates both probability-based (random) and judgmental (biased) methods to data collection to achieve the overall objective of the final survey process.

5.4.1 SURVEY UNITS As reflected in Table 5-4, areas of the Trojan facility and site classified as impacted are divided into survey units to facilitate survey design. A survey unit is a physical area of specified size and shape with similar characteristics and potential for residual radioactivity for which data evaluation ar.d statistical analysis are performed. A separate decision is made for each survey unit as to its acceptability for release.

5.4.1.1 Survey Unit Size Professionaljudgment is used to divide the facility and site into appropriately sized survey units.

The area of each survey unit is sufficient to assure the total number of data points, based on the measurement frequency, enables a statistical evaluation of the data collected. Considerations for establishing survey units are physical characteristics, concentration levels, and previous remediation efforts, as well as spatial and logistical considerations.

Survey units are sized to ensure that survey data points are relatively uniformly distributed among areas of similar potential for residual radioactivity. As an example, a small, separate survey unit is created for an area of known residual radioactivity instead ofincluding it in a much larger survey unit where the probability for one or more measurements to be taken in the area of known residual radioactivity is greatly reduced.

Survey units conform to site characteristics to the extent practical. They have relatively compact shapes unless an unusual shape is appropriate for the site operational history or the site y topography. Where possible, existing facility or site characteristics such as horizontal and 5-26 August 1999

r l TROJAN LICENSE TERMINA TION PLAN l

l(3

d vertical structural support beams, concrete pour seams, or piping runs are used to define the boundaries of the survey units.

Survey unit sizes are given in Table 5-3. These sizes give a reasonable measurement density.

l They are based on floor or ground surface area only. The survey unit size may need to be l adjusted based on existing features of the facility or site. Where the survey unit surface area l includes or only consists of walls or ceilings, the survey unit is sized so as to preserve the dose l

modeling assumptions of the dose receptor within a contaminated room and/or receiving exposure from an infinite flat plane source. A justification is documented for those cases where the survey unit size does not conform to Table 5-3.

l l 5.4.1.2 Reference Coordinate System i

A reference coordinate system is used to facilitate the selection of measurement locations and to

! provide a mechanism for referencing a measurement to a specific location so that the measurement location can be relocated. ' A reference coordinate system is a set ofintersecting lines referenced to a fixed site location or benchmark. Typically, the lines are arranged in a perpendicular pattern, dividing the survey unit into squares of equal area; however, other types of patterns (e.g., triangular, polar, or three-dimensional) may be used. Table 5-4 illustrates the l types of reference coordinate systems that may be applied at Trojan.

Scale drawings, maps, or photographs of the survey unit are prepared, along with an overlay of

, the reference coordinate system or grid system. It should be noted that the reference coordinate iO system is intended primarily for reference purposes and does not necessarily dictate the actual b spacing or location of measurements.

l Physical gridding is used only where it is useful and cost effective. Where Class 1 and Class 2 survey units are gridded, the basic grid patterns are at 1 to 2 meter intervals on structure surfaces and at 10 to 20 meter intervals on land areas. For practical purposes, Class 3 areas may typically be gridded at larger intervals, for example,5 to 10 meters for large surfaces and 20 to 50 meters for land areas. The physical grid layout on structure surfaces is marked by chalk line or other appropriate means along the entire grid line or at line intersections. For land areas, the reference coordinate system is marked by wooden or metal stakes driven into the surface at line intersections, or by other appropriate surface markers. The selection c,f the appropriate marker depends on the characteristics and routine uses of the surface.

5.4.1.3 Background Reference Areas The residual radioactivity of a survey unit may be compared directly to the DCGL; however, the residual radioactivity may contain radionuclides which occur in background. To identify and evaluate those contributions attributable to licensed activities, representative background radionuclide concentrations are established using background reference areas. Background reference areas have similar physical, chemical, radiological, and biological characteristics as the survey unit being evaluated. They are usually selected hor non-impacted areas, but are not limited to natural areas undisturbed by human activitbs. Strveys are conducted of one or more A background reference areas to determine background levels for comparison with the conditions U

1 5-27 August 1999

TROJAN UCENSE TERMINATION PLAN j

l determined in specific survey units. Appendix 5-3 provides additional discussion in selecting l O and applying background reference areas.

)

l '

Background reference areas are not necessary where: 1) the residual radioactivity does not contain radionuclides occurring in background and the detection method is radionuclide-specific, I or 2) the background levels are known to be a small fraction of the DCGL.

5.4.2 SCAN MEASUREMENTS Scan measurements are performed to locate radiation anomalies that might indicate elevated areas of residual radioactivity that require further investigation. They are performed according to a preset pattern established for each classification. The level of scanning effort is proportional to the potential for finding elevated areas of residual radioactivity based on the history of the survey unit.

Scan measurements of Class I survey units are performed over 100 percent of the accessible' surface area. The scan survey is designed to detect small areas of elevated residual radioactivity that are not detected by the static measurements using the systematic pattern. If the sensitivity of the scanning technique is not sufficient to detect levels of residual radioactivity below the .

DCGL, the number of static measurements may need to be adjusted. Appendix 5-2 describes I how this is done. j Scan measurements of Class 2 survey units are performed over 10 to 50 percent of the surface p area. Class 2 survey units have a lower probability of areas of elevated residual radioactivity l

V than Class I survey units. Those areas with the highest potential for elevated residual radioactivity (e.g., corners, ditches, and drains), based on professionaljudgment, are selected for scanning. If the entire survey unit has an equal probability for areas of elevated residual radioactivity, systematic scans are performed along transects of the survey unit or of randomly selected grid blocks. A 10 percent scanning coverage is appropriate ifit is unlikely that any area would exceed the DCGL. Coverage of 25 to 50 percent is appropriate when there might be locations above the DCGL. Where scanning coverage of greater than 50 percent isjudged appropriate, the survey unit is reclassified as a Class 1 survey unit.

Scan measurements of Class 3 survey units are performed over usually less than 10 percent of the surface area. Class 3 survey units have the lowest probability of areas of elevated residual radioactivity. Those areas with the highest potential for elevated residual radioactivity, based on professionaljudgment, are selected for scanning. This provides a qualitative level of confidence that no areas of elevated residual radioactivity were missed by the random measurements and that there were no errors made in the classification of the survey unit.  ;

Scan measurements of plant systems are performed, where possible, according to the scan coverage for the class of survey unit. The amount of accessible surface area dictates the actual percentage of the surface area to be scanned.

m 3

} (v) Personnel health and safety are taken into consideration when determining whether an area is accessible.

l 5-28 August 1999

e TROJANLICENSE TERMINATIONPLAN 5.4.3 STATIC MEASUREMENTS Static measurements provide a quantitative measure of the radioactivity present at the location measured. Static measurements are collected at a frequency and at representative locations throughout the survey unit such that a statistically sound conclusion regarding the radiological condition of the survey unit can be developed. Static measurements may also be collected at locations of elevated residual radioactivity identified by scan measurements. The types of static measurements taken are direct surface contamination measurements and soil and bulk material measurements.

If the instruments and techniques used for scan measurements are capable of providing data of the same quality as static measurements (e.g., detection limit, location of measurements, ability to record and document results), then scan measurements may be used in place of static measurements. The results of scan measurements are documented for at least the minimum number of static measurements. The same logic may be applied far using in situ gamma j spectrometry instead of soil and bulk material measurements.

5.4.3.1 Number Of Measurements As described in Appendix 5-2, the MARSSIM process incorporates design constraints that ensure that an adequate number of sample measurements are taken per survey unit. However, to simplify the final survey process and to ensure conservatism without an associated unreasonable expenditure of resources, a minimum number of 30 sample measurements per survey unit' will be collected. Using the methodology described above, PGE has determined that collecting 30 O. data points per survey unit is more than adequate to ensure sufficient data points to attain the desired power level with the statistical tests and to allow for possible lost or unusable data.

The number of 30 measurements per survey unit is based on the design goals and constraints described in Appendix 5-2. The methodology and assumptions used to develop the minimum number of 30 measurements and to detennine any additional measurement requirements are clarified in Appendix 5-2.

i 5.4.3.2 Measurement Locations Measurements in Class 3 survey units and background reference areas are taken in random locations. Random means that each measurement location in the survey unit has an equal probability of being selected. The random selection process uses random numbers that correspond to the survey unit reference coordinates to establish the measurement locations. The random numbers are generated using a random number generator or other random selection method.

For plant systems and embedded piping, system size and accessibility to system interior surfaces may not allow the full number of measurements. In these cases, the same MARSSIM approach encompassing historical, O characterization, remediation, and turnover survey data is used as a basis for biased scanning and sampling to the extent practicable to ensure that the release criteria are met, i

5-29 August 1999 i  !

TROJAN LICENSE TERMINATIONPLAN For Class I and Class 2 survey units, a random-start systematic pattern is used in place of a random pattern. This is done to meet a survey design objective to locate small areas of elevated d(N residual radioactivity that may exist within the survey unit. The starting point is determined by the random selection process. For a square grid, the physical spacing of the measurement locations, L, is determined as follows (NUREG-1575, Equation 5-6):

A L '= -

(Equation 5-5) n where n is the number of measurements and A is the total surface area of the survey unit. The calculated value of L is rounded down to the nearest 1/10 meter. Using the reference coordinates, the measurement locations are identified around the starting point in a perpendicular manner at intervals of L. This process is repeated to identify the pattern of measurement locations throughout the survey unit. Where other than a square grid system is used, the physical spacing of the measurement locations is determined such that they are distributed around the starting point in a systematic, equidistant manner across the survey unit area.

Measurement locations selected using a random selection process or a systematic pattem that do not fall within the survey unit area or that cannot be surveyed due to site conditions, including health and safety considerations, are replaced with other measurement locations determined using the random selection process. Supplemental measurement locations are also determined using the random selection process.

D Q Measurement locations selected based on professionaljudgment violate the assumption of unbiased measurements used to develop the statistical tests and are not used in the statistical evaluation. However, special considerations are necessary for survey units with surface areas 2 2 less than 10 m , land areas less than 100 m , and some plant ;ystems. The data generated from these smaller survey units are obtained based on professionaljudgment, rather than on systematic or random design.

5.4.3.3 Location Identification Measurement locations within the survey unit are clearly identified and documented to ensure that they can be relocated if necessary. Actual measurement locations are marked with tags, self-adhesive labels, permanent markings, stakes, notations on survey maps, or equivalent methods.

Each measurement location is identified by a unique identification code or number. The number convention allows survey data to be referenced to specific measurement locations identified on the photographs, drawings, or maps of the survey unit.

5.4.4 DATA INVESTIGATION The data investigation process is illustrated in Figure 5-1. Investigation results are documented in accordance with approved plant procedures.

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5 August 1999 l

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l TRO.lANLICENSE TERMINATIONPLAN 5.4.4.1 Investigation Levels l (,)

Investigation levels, shown in the following table, are radioactivity levels that are based on the site release dose criterion which, if exceeded, initiate an investigation of the survey measurement. Investigation levels are established for each class of survey unit.

1 Investigation Levels

{

Survey Unit Classification Scan Measurements' Static. Measurements Class'I >DCGL >DCGL

\

i Class 2 >DCGL >DCGL Class 3 >DCGL >0.5 x DCGL i

• If the MDC . (see Section 5.5.2.4) is greater than the DCGL, the investigation level is the MD The principal purpose ofinvestigation levels is to guard against the possible misclassification of the survey unit. They also serve as a QC check on the final survey process. A survey '

measurement that exceeds an investigation level may indicate that the survey unit has been improperly classified. It may also indicate a failing survey instrument or a localized area of l elevated residual radioactivity where there was a failure in the remediation process.

,-m For a Class 1 survey unit, while measurements above the DCGL are not necessarily unexpected,

() any measurement exceeding the DCGL is investigated. The site release dose criterion allows individual measurements representing small areas of residual radioactivity to exceed the DCGL.

However, any measurement that exceeds the DCGL is subject to the elevated measurement comparison (EMC), described in Appendix 5-1. For a Class 2 survey unit, any measurement above the DCGL is unexpected and is investigated. As there is a low expectation for residual radioactivity in a Class 3 survey unit, any static measurement exceeding 0.5 x DCGL is investigated. If the scanning MDC exceeds the DCGL, any indication of residual radioactivity during the scan is also investigated.

If a background reference area is to be applied to the survey unit, the mean of the background reference area measurements may be added to the appropriate investigation level to which the survey measurements are cc,mpared. Where an excessive number of measurements exceed the investigation level, the results are reviewed to ensure that the applied background reference area is appropriate. If any background reference area is determined to be inappropriate, it is adjusted as necessary and documented.

5.4.4.2 Investigation Locations, identified by scan or static measurements, with residual radioactivity which exceeds the investigation level are marked and investigated. The elevated survey measurement is verified or confirmed to actually exceed the investigation level. The area around the elevated measurement is inurtigated to determine the extent of the elevated residual radioactivity and to (v ) provide reasonable assurance that other undiscovered areas of elevated residual radioactivity do 5-31 August 1999

l l

TROJANLICENSE TERMINATION PLAN l l

not exist. Scan coverage of the area being investigated is increased to 100 percent. Static 3

(V measurements are also taken if scan measurements are not capable of providing sufficient data to characterize the elevated residual radioactivity. A posting plot, described in Section 5.6.2.1, is generated to document the area investigated and the levels of residual radioactivity found.

Depending on the results of the investigation, the survey unit may require remediation, reclassification, and/or resurvey. Possible data results and investigation conclusions are shown in Table 5-5.

l Static measurements above the investigation level that should have been but were not identified by scan measurements may indicate that the scanning method is inadequate. In that case, the scanning method is evaluated and appropriate corrective actions are taken and documented.

Corrective actions may include rescanning affected survey units.

i 5.4.4.3 Remediation Areas of elevated residual radioactivity above the DCGL uc E are remediated to reduce elevated residual radioactivity to acceptable levels. Based on survey data, it may be necessary to remediate all or a portion of a survey unit. Remediation activities are beyond the scope of the final survey process and are addressed in Section 4 of this License Termination Plan.

l 5.4.4.4 Reclassification q If survey measurements in a Class 2 or Class 3 survey unit exceed the DCGL or suggest that u./ there may be a reasonable potential that contamination is present in excess of the DCGL, the survey unit is reclassified as a Class 1 survey unit. A Class 2 or Class 3 survey unit which is remediated is reclassified as a Class I survey unit. If survey measurements in a Class 3 survey unit exceed 0.5 x DCGL, the survey unit is reclassified as a Class 2 survey unit.

If the extent of the elevated residual radioactivity (and corresponding remediation) is limited, that area of the survey unit containing the elevated measurements may be separated out into a new survey unit and classified. The remainder of the original survey unit retains its original classification. This is illustrated in the following figure.

Reclassification of Elevated Area of Survey Unit uw-Survey Unit G28045A i Class 2 i l

area of l

' elevated f'7-activity <

._ /  !

__ Survey Unit G28045B l Class 1 l fh

\

Q,) _

l 5-32 August 1999

f l

TROJAN LICENSE TERMINA TION PLAN l 5.4.4.5 Resurvey 1

3 (V If a survey unit is reclassified or if remediation activities are performed, then a resurvey using i

the methods and frequency appropriate for the new survey unit classification is performed.

Other than additional scanning, a complete resurvey of a Class 2 survey unit determined to be a '

Class 1 survey unit is not necessary provided remediation is not performed.

l In the case where a new survey uait is separated out from an existing survey unit, Class 3 survey units need only additional randomly located measurements to complete the survey data set.

Class 1 and Class 2 survey units require a new survey design based on random-start systematic measurement locations.

1 Where only a small fraction of the area of a Class 1 survey unit is remediated, replacement measurements are collected within the remediated area. Their locations are determined using the '

l random selection process.

5.4.5 QUALITY CONTROL (QC) MEASUREMENTS '

QC measurements are a component of the survey quality assurance process, and include quality checking and repeat measurements. Quality checking and repeat measurements are performed to  ;

identify, assess, and monitor measurement error and uncertainty attributable to measurement  !

5 methods or analytical procedures used in the data collection process . Quality checking includes direct observations of survey data and sample collections, and sample preparation and analyses.

hp Repeat measurements are multiple measurements at the same location. Repeat measurements provide quantitative information to demonstrate that measurement results are sufficiently free of error to accurately represent the radiological condition of the facility and site. Results of QC measurements are documented in accordance with approved plant procedures.

5.4.5.1 Type, Number. And Scheduling The type, number, and scheduling of QC measurements are determined by a performance-based method, as described in Section 4.9.2 of NUREG-1575, and in accordance with approved plant procedures. This method is based on the potential sources of error and uncertainty, the likelihood of occurrence, and the consequences in the context of final survey data accuracy. The primary factors considered here are: 1) the number of persons or organizations involved in the data collection,2) the number of measurement types or analytical methods used, and 3) the time interval over which the data are collected. Other factors include:

1. Number of survey measurements collected;

2. Experience of personnel involved;

3. Types of measurement methods or sampling and analytical procedures used; 5

The error and uncertainty introduced by the instrumentation used to collect the data are assumed to be g controlled by the performance of instrument calibration (Section 5.5.2.2) and response checks (Section 5.5.23).

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I TROJANUCENSE TERMINATIONPLAN

4. Variability of survey instruments used; <

r\ j C) 5. Level of radioactivity in the survey unit; and

(

j 6.

How close the measurement level is to the detection limit.

The collection of QC measurements is initiated early in the data collection process to identify problems and establish estimates of accuracy. QC measurements continue to be collected for the duration of the survey to verify sources of error and uncertainty are minimized and controlled.

The factors that influence measurement accuracy are incorporated in the QC measurement l collection design.

Measurement results from survey units may not readily lend themselves to the QC measurement process (e.g., direct measurement results at or near the detection limit). In this and similar cases, test areas may be set up with hidden radioactive sources or spiked media to allow the collection of the QC measurements.

5.4.5.1.1 Scan Measurements Quality checking of surface scanning surveys are performed to evaluate the effectiveness of l scanning methods for identifying areas of elevated residual radioactivity. Repeat measurements for scan surveys are not meaningful, as scan surveys are qualitative and not quantitative. The frequency of quality checking of.ecan surveys is dependent on: 1) the number of surveyors,

2) the number ofscanning methods employed,3) the time interval over which scanning data are (o) collected, and 4) professionaljudgement. In addition to quality checking, the ability of surveyors to identify areas of elevated residual radioactivity by scanning is periodically tested in accordance with approved plant procedures.

5.4.5.1.2 Static Surface Contamination Measurements Repeat measurements of static surface contamination measurements are performed to assess error and uncertainty associated with field measurement methods. Measurement locations are selected based on meamrement results and represent the entire usable range of residual radioactivity found. The usable range of radioactivity includes the highest measurement result and the lowest measurement result with an acceptable measurement uncenainty compared to the desired level of accuracy. Repeat measurements with results at or near t he detection !imit are not used because the measurement uncertainty is usually greater than the oesired level of accuracy.

The number of repeat measurements is dependent on 1) the number of surveyors,2) the number of static surface contamination measurement methods employed, and 3) the time interval over which the measurement data are collected. For these measurements, the survey objective is to estimate the variance in the accuracy for the specific method between zero and two times the estimated variance at the 95% confidence level. Fifteen repeat measurements, based on Table 4.3 of NUREG-1575, provide this level of confidence. As a planning guideline,15 repeat measurements are performed using each static surface contamination measurement method per g surveyor per year.

U 5-34 August 1999

p-..

TROJAN 12 CENSE TERMINATIONPLAN 5.4.5.1.3 Soil and Bulk Material Measurements QC measurements for soil and bulk materials are performed on split samples to assess error and 6

uncertainty associated with sample meth'odology and analytical procedures . A split sample is a collected sample that has been homogenized and divided into two or more aliquots for subsequent analysis. Selected samples are split into two separate samples. Both samples are analyzed using the same method, but by different laboratories. An altemative is to submit both samples to the same laboratory for analysis.

The number of QC measurements for soil and bulk materials is dependent on: 1) the number of laboratories,2) the number of analytical methods used, and 3) the time interval over which lab analysis' of the samples is performed. As discussed in Section 5.4.5.1.2, the baseline number for discrete QC measurements is 15. As a planning guideline,15 QC measurements are performed .

using each analytical method per laboratory per year.

5.4.5.2L Measurement Accuracy .

Measurement accuracy is estimated using the results of QC repeat measurements compared to the results of original measurements. Forlaboratory analysis,' the results of the split samples are compared to one another. The accuracy estimates based on two or more surveyors (or laboratories) refer to the agreement expected when differe'nt surveyors or laboratories perform the same measurement using the same method.

O Acceptance criteria for measurement accuracy are established by approved plant procedures.

Where the acceptance criteria are not met, an investigation of the data collection and/or sample analysis p*ocess is initiated to assess and identify the extent of error or uncertainty. The results of the investigation and the corrective actions taken are documented, l

I l

O by the laboratory internal QC program.'The error introduced by laboratory i l 1 L

5-35 August 1999 t

I TROJAN LICENSE TERMINATION PLAN I

7 5.5 SURVEY DATA COLLECTION l r

V; Survey data collection begins after the survey unit has been isolated and controlled to ensure that i

radioactive material is not introduced from ongoing decommissioning activities in adjacent or nearby areas.

5.5.1 SURVEY PERFORMANCE Survey data are collected from the tumover survey, the final survey, and any investigation surveys performed. The final survey uses both random and biased data collection methods and is performed using the methodology, techniques, and quality control requirements prescribed in i this plan. The turnover and investigation surveys are biased surveys performed using the same methodology, techniques, and quality control requirements as the final survey. A turnover survey, when performed, precedes the final survey. Investigation surveys are performed during the tumover or final surveys, as dictated by survey data results.

5.5.1.1 Turnover Survev i l

A turnover survey of Class 1 and Class 2 survey units is performed where extensive dismantlement activities occurred and operational RP surveys performed do not provide sufficient confidence that the survey unit is ready for the final survey. The turnover survey is designed to verify that residual radioactivity levels are acceptable and that no additional i

remediation is necessary. It is conducted using the same methodology, techniques, and quality 3 controls as those required for the final survey. Professionaljudgment is used to: 1) identify (V measurement locations most likely to have elevated levels of residual radioactivity, and 2) establish the scanning coverage and the number of static measurements to be taken.

The data collected during the turnover survey provides a sound basis for interpreting radiological conditions that may be encountered during the final survey. Also, because the turnover survey is conducted using the same methodology, techniques, and quality controls as those required for the final survey, certain data collected during the turnover survey may be used as part of the final survey data set. The data from the turnover survey also provide assurance to the Decommissioning organization that dismantlement and remediation activities are complete.

The following example illustrates how the turnover survey and the data collected may be used.

Dismantlement activities are completed and isolation and control measures are instituted in an i area classified as a Class I suney unit. A turnover survey, consisting of 100 percent scan coverage and biased static measurements, is performed. The survey data collected indicate that there are no areas which exceed the DCGL. Later, however, isolation and control measures are removed and the survey unit is used as a temporary lay-down and storage area. Some or all of the tumover survey data may no longer represent the radiological condition of the survey unit and cannot be used as final survey data. Still, that data coupled with the knowledge of the use of the area since the turnover survey was performed justifies the survey unit being classified as Class 2 for the final survey.

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1 TROJANLICENSE TERMINATION PLAN 5.5.1.2 Final Survey

/'~'s Y) A final survey of each survey unit is performed. The objective of the final survey is to collect data of a sufficient type, quantity, and quality such that the statistical tests can be applied to the survey unit and conclusions drawn with confidence regarding the radiological condition of the survey unit.

The final survey uses both random and biased data collection methods. Scan measurements are i

taken from biased selection measurement locations. Static measurement results used in the l statistical tests are obtained from randomly selected measurement locati~ons.

5.5.1.3 Investigation Survey An investigation survey is performed when one or more survey measurements exceed an investigation level as described in Section 5.4.4. The purpose of the investigation survey is to define the area and level of the elevated residual radioactivity. The data collected during the investigation survey are used to characterize the area being investigated and to provide the basis for any further actions to be taken.

i l

5.5.2 INSTRUMENTATION Commercially available portable and laboratory instruments and detectors are used to perform three types of measurements: 1) surface scanning,2) direct surface contamination measurements, and 3) laboratory analysis of soil and bulk materials. Instrumentation is used to perform other i b types of measurements as dictated by survey data collection needs. The issuance, control, and l

operation of survey instrumentation and the use of radioanalytical programs are controlled by approved plant procedures. Related quality records are maintained in accordance with approved plant procedures.

)

l 5.5.2.1 Instrument Selection Radiation detection and measurement instrumentation is selected based on reliable operation, detection sensitivity, operating characteristics, and expected performance in the field. As a l

general rule, instruments used for static measurements are capable of detecting the radiations of concern to an MDC less than 50 percent of the DCGL. This allows detectability of residual radioactivity in Class 3 survey units at the investigation level of 0.5 times the DCGL.

As a general rule, instruments used for scan measurements are capable of detecting the radiations of concern to an MDC less than the DCGL. Typical instrumentation that may be used is identified in Table 5-6. The detectors used for direct surface contamination measurements are typically operated with data logging survey meters.

5.5.2.2 Calibration And Maintenance Instruments and detectors are calibrated for the radiation types and energies ofinterest at the site.

l p Instrument calibration and maintenance are performed in accordance with approved plant Q/ procedures. If vendor services are used, these services are conducted in accordance with I 5-37 August 1999

TROJANLICENSE TERMINATIONPLAN approved procedures and an internal QA program that is subject to approval in accordance with Y the Trojan Nuclear Quality _ Assurance Program.: Radioactive sources used for calibration purposes are traceable to the National Institute of Standards and Technology (NIST) for both Trojan and vendor operations.

5.5.2.3 Response Checks -

i Instrument response checks are conducted to assure constancy in instrument response, to verify the detector is operating properly, and to demonstrate that measurement results are not the result of detector contamination. - Instrument response is checked before instrument use each day.

Portable instruments are also checked after instrument use each day. A check source is used that emits the same type of radiation (i.e., alpha, beta, and/or gamma) as the radiation being measured and that gives a similar instrument response. The check source does not necessarily use the same radionuclide as the radionuclide being measured. The response check is performed using a specified source-detector alignment that can be easily repeated. If the instrument fails its -

response check, it is not used until the problem is resolved. Measurements made between the last acceptable response check and the failed check are evaluated and discarded, if appropriate.

5.5.2.4 Minimum Detectable Concentration (MDC)

The MDC is determined for the instruments and techniques that are used for survey data collection. The MDC is the concentration that a specific instrument and technique can be expected to det:et 95 percent of the time under actual conditions of use.

,V'b 5.5.2.4.1' Beta-Gamma Scan MDC for Structure Surfaces 1-l The scan MDC, or MDC,c.n, for scanning structure surfaces for beta and gamma emitters is determined from Equation 5-6 (draft Regulatory Guide DG-4006, Equation 2):

(1.38) 5 .

(Equation 5-6)

MDC,,,,= h Eo E, (A /100) I where:

=

MDC c.n minimum detectable concentration for scanning surfaces (dpm/100 cm2 )  ;

1.38 =

scan performance criteria, from draft Regulatory Guide DG-4006 B =

number of background counts in time interval t (ents) l p =

surveyor efficiency,0.5, from draft Regulatory Guide DG-4006

=

Ei instrument efficiency for emitted radiation (cpm /dpm)

=

E. source efficiency for emissions / disintegration i A

l. = 2 area of detector (cm )

t ' =

time interval of observation while detector passes over the source (min) l The value of p represents a mean value for normal field conditions and is discussed in

! ' Section 6.6 of NUREG-1507, " Minimum Detectable Concentrations With Typical Radiation Survey Instruments for Various Contaminants and Field Conditions"(Reference 5-14). , j

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TROJANLICENSE TERMINATIONPL4N I

The value of E, is detennined taking the dose modeling into consideration. For example, for the o building occupancy scenario, the residual radioactivity is assumed to be on the surface, not I

V embedded. Thus for embedded material, adjustments in E, are made to account for attenuation I

by overlying material. When the internal pathways (inhalation and ingestion) are dominant, a '

value for E, that does not account for embedding of residual radioactivity or surface roughness is appropriate for the dose modeling and is therefore applied.

The value of t is the actual time that the detector can respond to the source of radioactivity. It depends on scan speed, detector size in the direction of the scan, and the area of elevated residual radioactivity.

5.5.2.4.2 Alpha Scan MDC for Structure Surfaces Scanning for alpha emitters differs significantly from scanning for beta and gamma emitters in that the expected background response ofmost alpha detectors is close to zero. Since the time an area of elevated residual radioactivity is under the probe varies and the background count rate may be less than 1 cpm, it is not practical to determine a fixed MDC for scanning. Instead, another approach described in Section 6.7.2.2 of NUREG-1575 is used. Given the DCGL and a known scan rate, the probability of detecting an area of elevated residual radioactivity is calculated. When one or more counts are registered, the surveyor pauses scanning and waits for a time to determine whether the counts are from elevated residual radioactivity. The time interval of the pause corresponds to a 90 percent probability of detecting counts associated with elevated residual radioactivity at the DCGL.

,q lQ 5.5.2.4.3 Gamma Scan MDC for Land Areas i

' For scanning land areas with a sodium iodide gamma detector, the MDC,c n values given in Table 6.7 of NUREG-1575 are used.

5.5.2.4.4 Static MDC for Structure Surfaces For static measurements of surfaces, the MDC mie may be calculated using Equation 5-7 (draft i

Regulatory Guide DG-4006, Equation 3):

l

' MDC.,,,,,,, = 3 + (4.65) 5 .

(Equation 5-7)

(K) (t) where:

MDC,wie =

minimum detectable concentration for static counting (dpm/100 cm2 )

B background counts during measurement time interval t (ents) t measurement counting time interval (min)

K =

calibration constant (ents/ min per dpm/100 cm2)

The value of K may include correction factors for the detection efficiency and detector geometry.

A b

5-39 August 1999

TROJAN UCENSE TERMINATION 1'4N g 5.5.2.5 Detection Sensitivity U The detection sensitivity of typical detectors for surface contamination measurements is estimated and the results are summarized in Table 5-7. The results are shown for the principal instruments that are expected to be used for alpha and beta-gamma direct surface contamination measurements.

Count times are selected to ensure that the measurements are sufficiently sensitive with respect to the DCGL. For example, the count times associated with measurements for surface contamination and gamma spectral analysis (soil and bulk materials) are normally set to ensure an MDCsuuc no greater than 50 percent of the DCGL. The scan rate associated with surface scans is normally set to ensure an MDCsc n of no more than 75 percent of the DCGL. If the MDCsc.n exceeds the DCOL, additional static measurements may be required, as discussed in 1

Appendix 5-1.

5.5.3 SURVEY METHODS Survey measurements are performed in accordance with specific instructions contained in approved plant procedures. Measurements include surface scans, static surface contamination measurements, and laboratory analysis of soil and bulk materials. Other measurements, such as removable surface contamination and exposure rate measurements, may be obtained as required.

5.5.3.1 Scan Measurements

/~3 Scanning is performed to locate small areas of residual radioactivity above the investigation l level. If an area of elevated residual radioactivity is identified during the scan of a survey unit, I the area is marked for investigation.

Structure and plant system surfaces are scanned for beta-gamma emitting radionuclides. Beta scintillation or thin window gas-flow proportional detectors are normally used. Typically, the detector is held less than 2 cm from the surface and moved at 5 cm/s. The scan rate is adjusted l such that residual radioactivity can be detected at or below the investigation level.

Scanning for alpha emitters and low-energy beta emitters (<100 kev) are limited to interior structure surfaces which are relatively smooth and impermeable. Porous or exterior structure surfaces and land areas are generally not scanned because of problems with attenuation and media interferences. Where scanning is performed, alpha scintillation or thin window gas-flow l proportional detectors are typically used. The detector is kept close to the ground, usually less than 1 cm, and moved at a rate such that there is a high probability of detecting elevated residual radioactivity.

Land areas are scanned for gamma-emitting radionuclides. Sodium iodide scintillation detectors are normally used. The detector is held close to the ground surface, usually less than 6 cm, and moved in a serpentine (S-shaped) pattern while walking at a speed that allows the surveyor to detect the residual radioactivity at or below the investigation level. A scan rate of approximately 0.5 m/s is typically used; however, this rate is adjusted depending on the expected detector 0)

C response.

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TROJAN LICENSE TERMINATION PLAN

( ) 5.5.3.2 Static Surface Contamination Measurements  ;

Static measurements are taken to detect surface contamination. Static measurements are generally performed by placing the detector on or near the surface to be measured, taking a )

discrete measurement for a pre-determined time interval, and recording the reading. A one minute integrated count is a practical time interval for most field survey instrumentation and provides detection sensitivities that are usually below the DCGL. However, longer time intervals may be used as warranted.

2 2 I Static measurements are taken with 100 cm detectors or are corrected to reflect a 100 cm area.

When large area detectors are used, the observed contamination is limited to that contamination that would be acceptable when confined to an area of 100 cm2. Since it cannot be discemed that the observed contamination is uniformly distributed, it is assumed that it could be attributed to an 2

area of 100 cm or less. In the event that contamination in excess of what would be acceptable I 2

for an area of 100 cm is observed when using a large area detector, an evaluation is performed to ascertain compliance with the DCGL.

Static measurements are typically restricted to relatively smo'oth, impermeable surfaces where the radioactivity is present as surface contamination. Because the detector is used in close

)

proximity to the potentially contaminated surface, contamination of the detector or damage to the detector caused by irregular surfaces is considered before performing direct measurements.

O G

5.5.3.3 Soil And Bulk Material Samples

. Soil and bulk material samples are collected and measured. Soil samples are generally collected down to a depth of 15 cm at static measurement locations. Sampling at greater depths is done in i areas where site characterization or other infonnation indicates potential contamination at depths

)

greater than 15 cm. Sample preparation may include, but is not limited to, removing extraneous material, homogenizing, splitting, drying, compositing, and final preparation for counting. For QC repeat measurements, the sample obtained from the selected measurement location is homogenized and divided into separate containers. The separate containers are treated as separate samples throughout the remaining sample handling and analytical process.

Samples of paint chips, tank sediment, sewage sludge, roofing material, concrete, pavement, and other bulk materials are collected for laboratory analysis as part of biased static measurements.

Such samples may be collected in drain receptacles, sumps, and other catchments in affected areas. Selected storm drain catchments are sampled in accessible locations on the site. These samples are quantitatively analyzed by gamma spectroscopy for principal gamma-emitting radionuclides and the results compared to the DCGL.

If residual radioactivity can be measured at DCGL levels by in situ techniques, this method may be used to replace or supplement the sampling and laboratory analysis approach. For gamma-emitting radionuclides, the above data may also be supplemented by several exposure rate and/or in situ gamma spectrometry measurements.

V 5-41 . August 1999

q 1

TROJANLICENSE TERMINATIONPLAN 5.5.3.4 Special Measurements  !

O) i

' There are situations, described below, that need special consideration. The historical site I

l assessment and site characterization surveys are used to indicate if residual radioactivity may be present and its extent.  !

5.5.3.4.1 Cracks, Crevices, and Small Holes Surface contamination on non-planar or irregular structure surfaces, such as cracks, crevices, and small holes, may be difficult to measure directly using field survey detectors and established techniques. Where no remediation has occurred and residual radioactivity is not expected above background levels, cracks, crevices, and small holes are assumed to have the same level of residual radioactivity as that found on adjacent surfaces. The accessible surfaces are surveyed the same as other structure surfaces and no special measurement methods are applied.

Where remediation has occurred on surrounding surfaces or where residual radioactivity above background levels is suspected, a representative sample of the surface contamination within the crack, crevice, or small hole is obtained. The level of residual radioactivity is measured and ,

detection sensitivities are adjusted such that reasonable approximations may be made using i indirect measurement techniques. The accessible surfaces are surveyed the same as other structure surfaces except that they are included in places receiving judgmental scans when scanning is done at less than 100 percent coverage.

5.5.3.4.2 Paint Covered Surfaces l Surfaces painted to fix loose contamination in place are remediated prior to survey data collection. For other surfaces painted after plant start-up, representative samples in areas where it is suspected that elevated levels of residual radioactivity could have been covered over are taken and analyzed. Detection sensitivities are adjusted or remediation is performed as dictated by the sample analysis results. No special measurement methods are applied to surfaces which were painted prior to plant start-up and have not been painted since.

5.5.3.4.3 Plant Systems, Floor Drains, and Embedded Piping Surface contamination on internal surfaces, such as plant systems, floor drains, and embedded piping, may be inaccessible or difficult to measure directly using field survey detectors and established techniques. Where no remediation has occurred and residual radioactivity is not expected above background levels, inaccessible or difficult to measure internal surfaces are assumed to have the same level of residual radioactivity as that found on accessible surfaces. No special measurement methods are applied.

Where remediation has occurred or where residual radioactivity above background levels is suspected, representative samples of the internal surfaces are obtained. The levels of residual radioactivity are measured and detection sensitivities are established such that reasonable approximations may be made using indirect measurement techniques or calibrated detectors (3 extended into piping runs in a controlled manner. Accessible internal surfaces are surveyed the V

5-42 August 1999

TROJAN LICENSE TERMINA TION PLAN same as other structure sorfaces. Scale and sediment samples may be obtained,if appropriate Q

v and as allowed by system size and accessibility to intemal surfaces, 5.5.3.4.4 Activated Concrete and Other Materials Residual radioactivity within activated concrete and other materials is measured by mass.

Representative samples of the activated concrete or other material are collected and analyzed.

Detection sensitivities are established such that reasonable approximations may be made using indirect measurement techniques, such as direct surface measurements or in situ gamma spectrometry.

5.5.3.4.5 Paved Parking Lots, Roads, Sidewalks, and Other Paved Areas Paved parking lots, roads, sidewalks, and other paved areas are treated as structure surfaces.

Scan and static measurements are taken as prescribed by the survey design. Where remediation has occurred or where residual radioactivity above background levels is suspected, direct surface contamination measurements are taken and representative subsurface samples are collected and analyzed. Depending on the size of the paved area and the distribution of the residual radioactivity, the paved area may be a separate survey unit or included as part of a larger survey unit.

5.5.3.5 Investigation Measurements Removable activity, exposure rate, and in situ gamma spectrometry measurements may be taken (A) and used as diagnostic tools to further characterize the radiological conditions and to evaluate potential response actions.

5.5,4 SAMPLE HANDLING AND ANALYSIS When sample custody is transferred (e.g., when samples are sent off-site to another lab for analysis), a sample tracking record accompanies the sample for tracking purposes. The sample tracking (or chain of custody) record documents the custody of samples from the point of measurement or collection until final results are obtained. Sample tracking records are controlled and maintained in accordance with approved plant procedures.

! On-site laboratory capabilities are used to perform gamma spectroscopy, liquid scintillation, and gas proportional counting of soil and bulk materials and other samples. Off-site laboratory radioanalysis services are procured as needed. Laboratory analytical methods are generally capable of measuring levels at 10 to 50 percent of the DCGL.

5.5.5 DATA MANAGEMENT Survey data are collected from the turnover survey, if performed; the final survey; and any investigation surveys. QC measurements are not recorded as final survey data. The following table illustrates acceptable sources of final survey data. Measurement results stored as final l

survey data constitute the final survey of record and are included in the data set for each survey (p) unit used for calculations to determine compliance with the site release dose criterion.

j 5-43 August 1999 l

l l t l L I

l TROJAN LICENSE TERMINATION PLAN l Sources Of Final Survey Data o

Type of Type of Survey Measurement Turnover Final Investigation Scan v v v Static v v \

5.5.5.1 Scan Measurements Scan measurements performed during the turnover survey and investigation surveys may be accepted as final survey data provided the following conditions are met: 1) survey data collection requirements prescribed in Section 5.5 are adhered to; 2) no remediation is performed or, if performed, is localized in nature, contamination is controlled, and the area is rescanned; and

3) isolation and control measures are applied and maintained. Scan measurements are not recorded as discrete location measurements except where they are used in place of static measurements.

5.5.5.2 Static Measurements Static measurements performed during the tumover survey and investigation surveys are based on professionaljudgment. Since they are biased and not random, they may not be used in the l statistical tests. However, this does not necessarily preclude their acceptance as final survey 1

( ) data. Static measurements performed during the tumover survey may be accepted as final survey v' data provided: 1) survey data collection requirements prescribed in Section 5.5 are adhered to;

2) 30 or more data points are collected within the survey unit (except potentially for certain plant ,

systems and embedded piping as provided in Section 5.4.3.1, Footnote 4); and 3) none of the l

data points exceeds the DCGL. The data are stored as characterization data when they do not meet these criteria.

Where a survey unit is remediated and/or reclusified subsequent to a final survey, the affected data are stored as characterization data; otherwise, the data are retained as final survey data.

5.5.5.3 Data Recording l Measurements are recorded in units appropriate for comparison to the DCGL by correcting for background, efficiency, geometr,y, detector area, and measurement size as applicable. The recording units are dpm/100 cm' for surface contamination and pCi/g for radionuclide concentration. Measured numerical values are recorded and include values below the MDC and values that are negative (when the measured value is below the average background).

Measurement results from laboratory analyses that are below the MDC are reported as the MDC value.

Records of survey data are maintained in accordance with approved plant procedures. Survey data records include the identification of the surveyor, type of messurement, measurement

/^; location, measurement instrumentation used, measurement results, and time and date V measurement was taken.

5 August 1999

TROJAN LICENSE TERMINATION PLAN 5.6 SURVEY DATA ASSESSMENT r'

(_)\ The survey data assessment process is illustrated in Figure 5-2. Final survey data, described in Section 5.5, are reviewed to verify they are of adequate quantity and quality. Graphical representations and statistical comparisons of the data are made which provide both quantitative and qualitative information about the data. An assessment is performed to verify the data support the underlying assumptions necessary for the statistical tests. If the quantity, quality, or one or more of the assumptions are called into question, previous survey steps are re-evaluated and additional data are collected as necessary prior to further statistical analysis. The statistical tests are applied and conclusions are drawn from the data as to whether the survey unit meets the site release dose criterion.

5.6.1 DATA VERIFICATION AND VALIDATION The final survey data are reviewed to verify they are authentic, appropriately documented, and technically defensible. The review criteria for data acceptability are:

1.

The instruments used to collect the data are capable of detecting the radiation of interest at or below the investigation level. If not, acceptable compensatory measures have been taken; -

2.

The calibration of the instruments used to collect the data is current and radioactive sources used for calibration are NIST traceable;

3. Instrument response is checked before and, where required, after instrument use each day data are collected;

4. The MDCs and the assumptions used to develop them are appropriate for the instruments and the survey methods used to collect the data;

5. The survey methods used to collect the data are appropriate for the media and types of radiation being measured;

6. Special measurement methods used to collect the data are applied as warranted by survey conditions;

7. The custody of samples collected for laboratory analysis are tracked from the i point of collection until fmal results are obtained; and

8. The fmal survey data set consists of qualified measurement results that are representative of the current facility status and randomly collected as prescribed i by the survey design.

A discrepancy exists where one or more criteria are not met. The discrepancy is reviewed and the reasons for acceptability of the data or the corrective actions taken to restore data acceptability are documented.

5-45 August 1999

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TROJAN LICENSE TERMINATION PLAN

,,s 5.6.2 GRAPHICAL DATA REVIEW Survey data are graphed to identify patterns, relationships, or potential anomalies in the data that might go unnoticed using purely numerical methods. A posting plot and a frequency plot are used. Other graphical data representation tools may be used, as appropriate, in addition to or in lieu of those described here.

5.6.2.1 Posting Plot Posting plots, generated during investigation surveys, are used to identify spatial patterns in the data. A posting plot is simply a map of the survey unit with the data values entered at the measurement locations. The posting plot can reveal spatial inhomogeneities in the survey unit such as patches of elevated residual radioactivity or groupings of measurements that exceed the DCGL. Even in a background reference area, a posting plot may reveal spatial trends in background data that might affect the results of the statistical tests. In some cases, the trends could be due to residual radioactivity, but may also be due to inhomogeneities in the survey unit background material.

5.6.2.2 Frequency Plot A frequency plot is used to examine the general shape of the data distribution. A frequency plot is a bar chart of the number of data points within a certain range of values. The frequency plot may reveal any obvious departures from symmetry, such as skewness or bimodality (two peaks),

O in the data distributions for the survey unit or background reference area. When the data V distribution is highly skewed, it is often because there are a few elevated areas of residual radioactivity The presence of two peaks in the data may indicate the existence ofisolated areas of residual radioactivity or a mixture of background concentration distributions due to different soil types, construction materials, etc. The greater variability in the data due to the presence of such a mixture will reduce the power of the statistical tests to detect an adequately remediated survey unit. These situations may indicate the need to more carefully match background reference areas to the survey unit or to divide the survey unit into survey units with more homogeneous backgrounds.

5.6.3 BASIC STATISTICAL COMPARISONS  !

Statistical quantities (range, median, mean, and standard deviation) are calculated for the fir,al survey data set where one or more data points exceed the DCGL. The calculated quantities are compared to the values shown in the following table. The statistical comparison values represent assumptions underlying the statistical test to be used. Where the statistical quantity fails the comparision, the data set and/or survey design assumptions are examined.

> O l V l

5-46 August 1999 l l

l

TROJAN LICENSE TERMINATION PLAN Basic Statistical Comparisons p

U Statistical Quantity Value Failure Response Range (R) Rs5o Examine data for outliers i Median (0) l (0 - R) / ol s 0.5 Examine data for outliers and anomalies Mean (R) R s DCGL Apply background reference area or remediate Standard Deviation (c) o s 0.2 x DCGL' Determine if additional measurements are necessary

• The survey design assumes an initial standard deviation value less than or equal to 0.2 x DCGL.

5.6.3.1 Range The range, R, is a measure of dispersion between the largest and smallest values in the data set.

l It is calculated simply by subtracting the smallest value from the largest value. When there are 30 or fewer data points, values of the range larger than 5 standard deviations are unusual. The l range may be wider for larger data sets. '

Where the range is greater than 5 standard deviations, the data are examined for outliers. I Outliers are measurements that are extremely large or small relative to the rest of the data and, therefore, are suspected of misrepresenting the population from which they were collected.

r3 Outliers may result from measurement collection and recording errors. Outliers may also l

V represent true extreme values of a distribution, such as areas of elevated residual radioactivity, and indicate more variability in the population than was expected. Not removing true outliers and removing false outliers both lead to a distortion of estimates of population parameters. Tests  ;

developed to detect outliers in a data set may be used to identify data points that require further  !

examination. A test alone cannot determine whether a statistical outlier should be discarded or corrected; this decision is based on professionaljudgment.

5.6.3.2 Median I t

The median,0, is the center of the data set when the data points are ranked in order from smallest to largest. If the number of data points is odd, it is calculated using Equation 5-8 below:

=

17 xq. . , p :, (Equation 5-8)

If the number of data points is even, then it is calculated using Equation 5-9:

7 = xr < 2> + ru, e n - i' (Equation 5-9) 2 O

V where the data are ordered from smallest to largest and labeled xm, xm, . . ., xm>-

5-47 August 1999

TROJANLICENSE TERMINATIONPLAN Large differences between the mean and the median are an indication of the skewness in the data. A simple test for skewness is to subtract the mean from the median and divide by the

. standard deviation. Where the result is greater than *0.5, the data are examined for outliers or anomalies and professionaljudgment is used to discard or correct suspect data.

5.6.3.3 Mean The mean, R, is the arithmetic average of a data set. It is calculated using Equation 5-10:

n 1

x =- I . x, (Equation 5-10) i=1 where:

n =

number of measurements

=

xi measurement value for the ith measurement

- The mean is compared directly to the DCGL to obtain a preliminary indication of the survey unit -

status. If the mean exceeds the DCGL, there are two options. Either the survey unit is remediated since it clearly does not meet the site release dose criterion or a background reference area, described in Section 5.4.1.3, may be applied to the survey unit. The mean of the O - background reference area is subtracted from the mean of the survey unit and the difference compared to the DCGL. Where the difference exceeds the DCGL, the survey unit is rejected and remediated.

5.6.3.4 Standard Deviation The standard deviation,'o, is a measure of the dispersion from the mean of the data set. It is calculated using Equation 5-11:

n I (x . x J' s

1 /=/

cr = (Equation 5-11) n-I where the variables have been previously defined.

j Where the value of the calculated standard deviation is larger than that estimated in the survey I design (the initial value is 0.2 x DCGL - see Appendix 5-2), an insufficient number of

. measurements may have been taken and additional measurements may be necessary.  ;

O  :

5-48 I August 1999

TROJANLICENSE TERMINATIONPLAN 5.6.4 STATISTICAL TEST

' The Sign or the Wilcoxon Rank Sum (WRS) statistical test is applied to the final surve where one or more measurements exceed the DCGL. The statistical test is based o hypothesis that the level of residual radioactivity in the survey unit exceeds the DCGL. There must be sufficient survey data with levels of residual radioactivity at or below the DCGL to reject this statistical hypothesis and to conclude the survey unit meets the site release dose criterion.

The Sign test and the WRS test are nonparametric tests. The basic distinction between parametric and nonparametric statistical tests is that the parametric tests use specific assump about the probability distributions of the measurement data. The most commonly made assumption is that the data fit a normal distribution. A nonparametric test does not assume normal data distribution. It uses fewer assumptions than a parametric test, and consequently

• requires less information to verify these assumptions and is less vulnerable to being found incorrect when these assumptions are violated. That is, the correct decision is more likely mad about whether or not the survey data mean exceeds the DCGL, even when the data come from a skewed distribution.

The Sign test and WRS test assume the data are independent random measurements, and that the data are statistically independent or that there are no trends in the data. The WRS test also assumes the data are in a symmetric, but not necessarily normal, distribution and that the background reference area and survey unit distributions are the same except for a possible shift O

(

in the mean. Both statistical tests are tests of the median. The parameter ofinterest, though, is the mean. If the assumption of symmetry is valid, then the median and the mean are effectively equal, and the tests also are tests of the mean. If the assumption of symmetry is violated, then the nonparametric tests of the median approximately test the mean.

(

If outliers or anomalies are present in the data set, the statistical test is performed both with and l without the questionable data to see what effect they may have on the results. The statistical test results are documented in accordance with approved plant procedures.

5.6.4.1 Application Of Statistical Test l The statistical test does not need to be performed when the survey data clearly show that the survey unit meets the site release dose criterion. The survey unit clerirly meets the criterion if:

1) every measurement in the survey unit is less than or equal to the DCGL, or,2) where a background reference area is used, the difference between the maximum survey unit measurement and the minimum background reference area measurement is less than or equal to the DCGL. In these instances, the statistical test is not applied.

The statistical test is applied where one or more measurements exceed the DCGL. Similarly for a survey unit where a background reference area is used, the statistical test is applied where the difference between any survey unit measurement and any background reference area measurement is greater than the DCGL.

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1ROJANUCENSE TERMINATIONPLAN 1

l Survey results and the corresponding conclusions, both when a background reference area is not  !

! /~N used and when one is used, are shown in Tables 5-8 and 5-9, respectively.

d 5.6.4.2 Sign Test 1 The one-sample Sign statistical test is used if the radienuclide of concern is not present in

' background and radionuclide-specific measurements are made. The Sign test may also be used if one or more radionuclides are present in background at such small fractions of the DCGL as to ,

be considered insignificant. In this case, background concentrations of the radionuclides are included with the residual radioactivity (in other words, the entire amount is attributed to facility I operations). Thus, the total concentration of the radionuclides are compared to the site release I dose criterion. This option is only used ifit is expected that ignoring the background concentration does not affect the outcome of the statistical test. The advantage ofignoring a small background concentration is that no background reference area is needed.

The Sign test is applied as follows:

1. List the survey unit measurements, xi, i = 1,2,3, . . ., n; where n = the number of measurements.

2. Subtract xi from the DCGL to obtain the difference (DCGL - xi, i = 1,2,3, . . . , n).

1

/m 3. Discard differences where the value is exactly zero and reduce n by the number of b such zero measurements.

4. Count the number of positive differences. The result is the test statistic S+. Note that a positive difference corresponds to a measurement below the DCGL and contributes evidence that the survey unit meets the site release dose criterion.

5. Compare the value of S+ to the critical va'ues in Table 1.3 of NUREG-1575. The table columns equate to the false positive decision error rate, n. The value of a is the probability of passing a survey unit which actually fails to meet the site release dose criterion, which is obtained from the survey design (the initial value is 0.05 - see Appendix 5-2). If S+ is greater than the critical value for the false positive decision error rate given in the table, the smvey unit meets the site release dose criterion. If S+ is less than the critical value, the survey unit fails to meet the criterion.

5.6.4.3 Wilcoxon Rank Sum (WRS) Test The two-sample WRS statistical test is used when the radionuclide of concern appears in background or if measurements are used that are not radionuclide-specific. Because gross l

activity measurements are not radionuclide-specific, they must be performed for both the survey unit being evaluated by the WRS test and for the corresponding background reference area.

\,~

V I

5-50 August 1999

TROJAN LICENSE TERMINATIONPLAN ,

The WRS test is applied as follows:

b 1.

Adjust the background reference area measurements by adding the DCGL to each background reference area measurement, X i (Xi + DCGL).

2.

Sum the number of adjusted background reference area measurements, m, and the number of survey unit measurements, n, to obtain N (N = m + n).

3. Pool and rank the measurements in order ofincreasing size from 1 to N. If several measurements have the same value, they are all assigned the average rank of that group of measurements.

4. Sum the ranks of the adjusted background reference area measurements to obtain W,. l 1

5.

Calculate the critical value using Equation 5-12 (Equation 1.1, NUREG-1575)7:

Critical value = m (n + m + 1) + z n m (n + m + 1) (Equation 5-12) 2 12  ;

where z is the (1 - a) percentile of a standard normal distribution, which can be found in the table be' low.

U Values For a and z a z 0.001 3.090 0.005 2.575 0.01 2.326 0.025 1.960 0.05 1.645 0.1 1.282 The value of a is obtained from the survey design (the initial value is 0.05 - see Appendix 5-2). Where m and n are less than 20, the critical value is given in Table I.4 of NUREG-1575.

6. Compare the value of W, with the critical value calculated above. If W,is greater than the critical value, the survey unit meets the site release dose criterion. If W, is less than the critical value, the survey unit fails to meet the criterion.

() ' Equation 1.2, NUREG-1575, is used if there are several measurements that have the same values.

5-51 August 1999

TROJAN OCENSE TERMINATION PLAN 5.6.5 DATA CONCLUSIONS The results of the statistical test allow one of two conclusions to be drawn. The first conclusion is the survey unit meets the site release dose criterion. The data have provided statistically '

significant evidence that the level of residual radioactivity in the survey unit does not exceed the site release dose criterion. The decision that the survey unit is acceptable for unrestricted release can be made with sufficient confidence and without further analysis.

The second conclusion that can be drawn is the survey unit fails to meet the site release dose criterion. The data do not provide sufficient statistically significant evidence that the level of residual radioactivity in the survey unit does not exceed the site release dose criterion. The data are analyzed further to determine why the statistical test result led to this conclusion.

Possible reasons the survey unit fails to meet the site release dose criterion are: 1) it is in fact true,2) it is a random statistical fluctuation, or 3) the test did not have sufficient power to detect that it is not true. The power of the test is primarily based on the actual number ofmeasurements obtained and their standard deviation. A retrospective power analysis for the test may be performed as described in Appendices I.9 and I.10 of NUREG-1575. If the power of the test is insufficient due to the number of measurements, additional data may be collected. Ifit appears that the failure may be due to statistical fluctuations, the survey unit may be resurveyed and another set of discrete measurements collected for statistical analysis. A larger number of measurenlents increases the probability ofpassing if the survey unit actually meets the site O release dose criterion. Ifit appears that the failure was caused by the presence of residual radioactivity in excess of the site release dose criterion, the survey unit is remediated and resurveyed.

l ,

l I i

l l

1 l'

i l-l-

l O

5-52 August 1999

TROJANLICENSE TERMINATION PLAN 5.7 SURVEY RESULTS (3

O Survey results are documented in history files, survey unit release records, and in the final survey report. Other detailed and summary data reports may be generated as requested by the NRC.

5.7.1 HISTORY FILE A history file of relevant operational and decommissioning data is compiled in a standardized format. The purpose of the history file is to provide a substantive basis for the survey unit classification, and hence, the level ofintensity of the final survey. The history file contains:

1. Operating history which could afrect radiological status;

2. Summarized scoping and site characterization data; 1

3. Summary of radiological surveys performed during decommissioning; and i

4. Other relevant information.

5.7.2 SURVEY UNIT RELEASE RECORD 1

A separate release record is prcpared for each survey unit. The survey unit release record is a l stand-alone document which contains the information necessary to demonstrate compliance with l A the site release criteria. This record includes: I

1. Description of the survey unit;

2. Survey unit design information; l

3. Survey unit ALARA evaluation,ifperformed; l

4. Survey measurement locations and corresponding data;

5. Survey unit investigations performed and their results; and

6. Survey unit data assessment results.

When the survey unit release record is given final approval, it becomes a quality record.

5.7.3 FINAL SURVEY REPORT A final survey report will be prepared and submitted to the NRC. The report will provide a summary of the ALARA evaluations and survey data results and overall conclusions which demonstrate that the Trojan facility and site meet the radiological criteria for unrestricted use.

Information such as the number and type of measureriients, basic statistical quantities, and

n. statistical test results will be included in the report. The level of detail will be sufficient to

() clearly describe the final survey program and to certify the results.

5-53 August 1999

TROJANLICENSE TERAf1NATIONPLAN 4

h 5.7.4 OTHER REPORTS Ifrequested by the NRC, computer-generated detailed and summag data reports for one or more survey units are provided in hardcopy or electronic form. Survey data include date, instrument, location, type of measurement, and mode ofinstrument operation. Other data, such as conversion factors, background reference areas, and the MDCs used, are available which allow independent verification of the results. Measurement results may also be presented gmphically.

O 8

5-54, August 1999

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5.8 REFERENCES

5-1 Code of Federal Regulations, Title 10, Part 50.82, " Termination of License."

5-2 Regulatory Guide 1.179, " Standard Format and Content of License Termination Plans for Nuclear Power Reactors," January 1999.

5-3 Code of Federal Regulations, Title 10, Part 20.1402, " Radiological Criteria for Unrestricted Use."

5-4 Portland General Electric Topical Report PGE-1074, " Trojan Nuclear Plant Final Survey Report for the ISFSI Site."

5-5 Portland General Electric Topical Report PGE-1021, "Offsite Dose Calculation Manual," Revision 17.

5-6 Code of Federal Regulations, Title 10, Part 50, Appendix I, " Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion 'As Low As Reasonably Achievable' For Radioactive Material in Light-Water-Cooled Nuclear Power Reactor Effluents."

5-7 Portland General Electric, " Trojan Nuclear Plant Radiological Site Characterization Report," Revision 0.1, February 8,1995.

5-8 NUREG/CR-5512," Residual Radioactive Contamination From Decommissioning, Final Report," Volume 1, October 1992.

5-9 Draft NUREG-1549,"Using Decision Methods for Dose Assessment to Comply With Radiological Criteria for License Termination," July 1998.

5-10 EPA QA/G-9," Guidance for Data Quality Assessment: Practical Methods for Data Analysis," January 1998.

5-11 NUREG-1575/ EPA 402-R-97-016," Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM)," December 1997.

5-12 Portland General Electric Topical Report PGE-8010, " Trojan Nuclear Quality Assurance Program," Revision 22, 5-13 Draft Regulatorv Guide DG-4006," Demonstrating Compliance with the Radiological Criteria for License Termination," August 1998.

5-14 NUREG-1507," Minimum Detectable Concentrations With Typical Radiation Survey Instruments for Various Contaminants and Field Conditions," June 1998.

5-55 August 1999

r TROJAN LICENSE TERMINA TION PLAN i

APPENDIX 5-1 (O) ELEVATED MEASUREMENT COMPARISON (EMC)

The EMC, sometimes called a " hot spot test," is a simple comparison of measured values against a limit. There are two applications of this comparison in the final survey process. It is used when the sensitivity of the scanning technique is not sufficient to detect levels ofresidual

{

radioactivity below the DCGL (i.e., where the MDCmn is greater than the DCGL). In this application, the number of static measurements may need to be adjusted. Appendix 5-2 {

l describes how this is done. The second application, described in this appendix, is when one or more scan or static measurement data points exceed the DCGL. The use of the EMC for 1

measurements above the DCGL provides assurance that unusually large measurements receive '

the proper attention and that any area having the potential for significant dose contributions is identified. The EMC is intended to flag potential failures in the remediation process.

Locations, identified by scan or static measurements, with levels of residual radioactivity which exceed the DCGL are investigated (see Section 5.4.4). The size of the area where the elevated residual radioactivity exceeds the DCGL and the level of the residual radioactivity within the area are determined. The average level of residual radioactivity is then compared to the DCGLouc. If a background reference area is to be applied to the survey unit, the mean of the background reference area measurements may be added to the DCGL or the DCGL E uc to which the average level of residual radioactivity is compared.

The DCGLouc is calculated using the following equation (NUREG-1575, Equation 8-1):

l DCGLuc = Area Factorx DCGL The area factor is the multiple of the DCGL that is permitted in the area of elevated residual radioactivity without requiring remediation. The area factor is related to the size of the area over

{

which the elevated residual radioactivity is distributed. That area, denoted Atuc, is generally bordered by levels of residual radioactivity below the DCGL and is determined by the investigation. The area factor is the ratio of dose per unit area or volume for the default surface are for the applicable dose modeling scenario to that generated using the area ofelevated residual radioactivity, A tuc. It is calculated based on the methodology given in Appendix D of draft NUREG-1549.

If the average level of the elevated residual radioactivity is less than the DCGLouc, there is reasonable assurance the site release dose criterion is still satisfied and the area does not require remediation. Radioactivity at the DCGLouc distributed over the area Acuc delivers the same calculated dose as does residual radioactivity at the DCGL distributed over the default surface area. If the DCGl uct is exceeded, the area is remediated and resurveyed.

I o

b Appendix 5-1 1 of 1 August 1999

r

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TROJANLICENSE TERMINATIONPLAN I

' APPENDIX 5-2 A

O NUMBER OF STATIC MEASUREMENTS.

The method described in NUREG-1575 for determining the number of survey measurements necessary to assure a population set sufficient for statistical analysis is summarized here in the manner it is applied at Trojan. An effective survey design slightly overestimates both the number of survey measurements and the standard deviation to ensure adequate power of the statistical test. This ensures that a survey unit is not subjected to additional remediation simply because the final survey is not sensitive enough to detect that residual radioactivity is below the DCOL.

TERMS AND STATISTICAL PARAMETERS A minimum number ofmeasurements are needed to obtain sufficient statistical confidence that the conclusions drawn from the survey data are correct. Several terms and statistical parameters are described in this section that are used in determining the number of measurements needed to apply the statistical tests.

, Lower Bound Of Gray Region (LBGR)

The LBGR is the concentration to which the survey unit must be cleaned in order to have an acceptable probability of passing the statistical test for meeting the site release dose criterion. It represents the lower bound of the area of uncertainty regarding the concentration of residual radioactivity in the survey unit. The DCGL represents the upper bound. The width of the gray

(

region is equal to the difference between the DCGL and the LBGR, as illustrated in the figure below.

c6 GRAY REGION

• E 2 e a D.vE 82 0$a n nDerived Concentration Guideline Level (DCGL)

, 4 s } h . -.- .

@h & m, i ig g a u.a -

-o Lower Bound of Gray Region (LBGR)

- The default value of the LBGR is arbitrarily set at 0.4 times the DCGL. There is no technical basis for the selection of this value. As discussed later, the LBGR is adjusted as needed to result in a relative shift of 1.5 to 3.

The survey design goal is to achieve an LBGR between 0.4 and I times the DCGL. Since the LBGR serves as the clean-up goal for decommissioning activities, generally the smaller the LBGR, the more rigorous are the requirements for dismantlement, remediation, and turnover surveys. As the LBGR approaches the value of the DCGL and the band of uncertainty narrows, t

Appendix 5-2 1of7 August 1999

TROJANLICENSE TERMINATIONPLAN the number of samples needed to demonstrate compliance with the site release dose criterion

' rises.

Standard Deviation (c)

The standard deviation, denoted by a, represents the spatial variability in the concentration of the residual radioactivity in the survey unit. It is calculated using Equation 5-11.-

An estimated value of a may be calculated using existing data, such as operational RP survey data. The value selected as an estimate of a for the survey unit may be based on data collected only from within that survey unit or from data collected from a much larger area of the site, since there may be some difficulty in determining which individual measurements from a preliminary survey may later represent a particular survey unit. Alternatively, if data are unavailable, a reasonable estimate based on available site knowledge may be used.

The default 'value of a is set at 0.2 x DCGL. As discussed below, with an LBGR of 0.4 x DCGL,

- this results in a relative shin of 3.

The survey design goal is to avoid an estimated a that is overly optimistic or conservative If the value is grossly underestimated, the number of measurements will be too few and may result in unnecessary remediation or resurvey. If the value is grossly overestimated, the number of measurements will be unnecessarily large.

Relative Shift (No)

The number of measurements needed depends on a ratio involving the concentration to be measured relative to the variability in the concentration. The ratio is called the relative shift, denoted by No. It is defined as (draft Regulatory Guide DG-4006, Equation 4):

A/ a = DCGL - LBGR  ;

a l where the variables have been previously defined.

i The survey design goal is to achieve No values between 1.5 and 3. The number of measurements needed rises dramatically when No is smaller than one. Conversely, little is usually gained by making No larger than about three. If No is greater than three, the LBGR should be increased until the relative shift is equal to three.

l Decision Errors A decision error is the probability of making an error in the decision on a survey unit, either passing a survey unit that should fail or failing a survey unit that should pass. The first decision error, passing a survey unit that should fail, is referred to as a false positive decision error. The probability of making this error is denoted by a. Setting a high value for a results in a higher risk of passing a survey unit that should fail. Setting a low value of a lowers the risk of passing a Appendix 5-2 2 of 7 August 1999 i

[E TROJANLICENSE TERMINATION PLAN L

Vp survey unit that should fail. The second decision error, faihng a survey umt that should pass, is refened to as a false negative decision error and is denoted by . Selecting a high value for p results in a higher risk of failing a survey unit that should pass and subjecting it to further investigation. Selecting a low value for p lowers the risk and minimizes these investigations.

The cost of setting a low value for either a or E is a higher value for the other or an increased number of measurements to demonstrate compliance with the site release dose criterion.

An a decision error no larger than 0.05 is used when No exceeds 1.5. When using the statistical test (see Section 5.6.4), larger decision errors may be unavoidable.when encountering difficult or adverse measuring conditions. This is particularly true when trying to measure residual radioactivity concentrations close to the variability in the concentration of those materials in natural background. In order to avoid an unreasonable number of samples when No is very small, larger values of a may be considered as shown in the table below. This table is based on the assumptions that the LBGR should not have to be set to less than 0.4 times the DCOL, and that if a is allowed to increase, p will also be allowed to increase.

Acceptable Decision Error a as A Function of DCGL DCGL/o a  :

>3 0.05 1.2 to 3 0.10 0.6 to 1.2 0.25 l < 0.6 0.30 There are no constraints on the value of . However, decreasing increases the number of measurements needed, making very small values of unattractive. The default values of a and p are set at 0.05.

As described later, the survey design goal is to establish the value of a equal to or less than 0.05 and to minimize the value of E while maintaining the number of measurements at an optimal number. In general, increasing a decreases p and vice versa, holding all other variables constant.

Increasing the number of meas.urements typically results in a decrease in both a and p.

NUMBER OF MEASUREMENTS The statistical parameters a, p, and No are used to estimate the number of measurements that produce the desired values of a and p. The number of measurements is based on the statistical test that is applied to the survey unit. The two statistical tests used in the final survey are the Sign test and the Wilcoxon Rank Sum (WRS) test. A third test used is not a formal statistical test but a simple comparison, the Elevated Measurement Comparison (EMC). The criteria for the use of statistical tests are summarized in the following table.

Q Appendix 5-2 3 of 7 August 1999

TROJAN LICENSE TERMINATIONPLAN Statistical Tests and Criteria for Their Use (3

V Statistical Test Criteria for Use WRS Test Radionuclide of concem appears in background, or measurements are used that are not radionuclide-specific.

Sign Test Radionuclide of concem is not present in background and radionuclide-specific measurements are made, or radionuclides are present in background at such small fractions of the DCGL as to be considered insignificant.

EMC For Class 1 survey units, when the concentration that can be detected by scanning, MDC c.n, is larger than the DCGL. Used in addition to the WRS or Sign test.

The number of measurements is determined by rounding up the number calculated using the appropriate statistical test and adding 20 percent more measurements. The additional number of measurements is to protect against the possibility oflost or unusable data.

It should be noted that if the same values for a, E, and A/o are used, the required number of measurements is independent of survey unit classification. This means that the same number of measurements could be performed in a Class 1, Class 2, or Class 3 survey unit, which illustrates the importance ofidentifying appropriate survey units.

'N Wilcoxon Rank Sum (WRS) Test (G

The number of measurements needed for the WRS test is determined from the following equation (draft Regulatory Guide DG-4006, Equation 5):

" '* Y n = 1/ 2 x (3) (Pr - 0.5J' l

l where:

i n =

number of measurements in survey unit

=

Z i.a percentile represented by decision error a (NUREG-1575, Table 5.2)

=

i Z i.s percentile represented by decision error p (NUREG-1575, Table 5.2) i P, =

probability that a random measurement from survey unit exceeds random measurement from background reference area by less than DCGL when survey unit median is equal to LBGR concentration above background (NUREG-1575, Table 5.1)

% =

factor included in Equation 5-1 ofNUREG-1575 to define n as the number of measurements in a survey unit An additional n measurements are also needed in the background reference area.

^'

(V  :

Appendix 5-2 4 of 7 August 1999

F TROJAN LICENSE TERMINATION PLAN Sign Test i

The number of measurements needed for the Sign test is determined from the following equa (draft Regulatory Guide DG-4006, Equation 6):

1 n= 1.,

+ Zid (4)(Signp - 0.5/

where Sign p is the estimated probability that random measurement for a survey unit is less than l

' the DCOL when the survey unit median concentration is actually at the LBGR, from Table 5.4 of NUREG-1575. All other variables have been previously defined.

Elevated Measurement Comparison (EMC)

The EMC is used to determine if additional measurements may be needed when the level of residual radioactivity that can be detected by scanning (MDC.c.n, see Section 5.5.2.5) is larger than the DCGL. The WRS and Sign tests evaluate whether or not the residual radioactivity l

exceeds the DCGL for contamination that is approximately uniform across the survey unit.

l These tests may not successfully detect small areas of elevated contamination. Instead,

)

systematic measurements, in conjunction with surface scanning, are used to obtain adequate assurance that small areas of elevated radioactivity will meet the DCGL. When the MDC,c.n exceeds the DCGL, the EMC provides the reasonable level of assurance that any small areas of elevated residual radioactivity that could be significant are not missed during the final survey.

The number of measurements needed to detect an elevated concentration, ntuc, in a survey unit area, A, is (draft Regulatory Guide DG-4006, Equation 8):

1 1

A nue =

Auc The Atue is the area over which elevated residual radioactivity (greater than the DCGL) may be distributed without requiring remediation. The A uc t corresponds to an area factor. The area factor is the multiple of the DCGL that is permitted in the area of elevated concentration. It is equal to the ratio of the MDC c.n to the DCGL (draft Regulatory Guide DG-4006, Equation 7): i Area Factor = WCuan DCGL Once the area factor is determined, the corresponding value for tA ue can be obtained (see Appendix 5-1) and the value ofneuc calculated.

If ntuc is larger than n, additional samples (up to a total in the survey unit of as many as ntuc) may be needed to demonstrate that areas of elevated residual radioactivity meet the site release dose criterion. In cases where ntuc is larger than n, the site characterization should be considered b

and, based on what is known about the site, it may be possible to estimate a concentration that is i Appendix 5-2 5 of 7 August 1999

TROJAN UCENSE TERMINATIONPLAN unlikely to be exceeded. This maximum concentration may be converted into an area factor p)

(

(multiple of the DCGL), and then the corresponding A EMcvalue obtained (see Appendix 5-1) and used in the above equation. Similarly, based on knowledge of the site it may be possible to estimate the smallest area likely to have elevated levels ofresidual radioactivity. If this is so, that area can be used in the above equation. Likewise, knowledge of how the residual radioactivity would be likely to spread or diffuse could determine an area to be used in this equation. It should be noted that extensive experience with sampling suggests that at 2

measurement densities of 1 measurement per m in buildings and 1 measurement per 25 m2 outdoors rarely need to be exceeded.

The EMC is only applied to Class 1 survey units, since areas of elevated residual radioactivity should not be present in Class 2 or Class 3 survey units.

Optimizing the Number of Measurements Once the acceptable design values have been established, survey design constraints may be changed to evaluate how these changes affect the number of measurements for several basic measurement designs. The survey design constraints are:

1. Limits on the decision error probabilities a and p;

. 2. Width of the band of uncertainty or gray region (by adjusting the LBGR); and m 3 Survey unit boundaries (it may be possible to reduce the number of measurements Q by changing or eliminating survey units that may require different decisions).

The process may be iterative in that the initial values selected must be modified to allow dependent variables to fall within the survey design constraints.

Selecting a Minimum Number of Measurements As discussed above, the MARSSIM process incorporates design constraints that ensure that an adequate number of sample measurements are taken per survey unit. However, to simplify the final survey process and to ensure conservatism without an associated unreasonable expenditure of resources, a minimum number of 30 sample measurements per survey unit will be collected.

Using the methodology described above, PGE has determined that collecting 30 data points per survey unit' is more than adequate to ensure sufficient data points to attain the desired power level with the statistical tests and to allow for possible lost or unusable data.

The number of 30 measurements per survey unit is based on the design goals and constraints described above. Decision error probabilities are established with limitations on the value of a

'For plant systems and embedded piping. system size and accessibility to system interior surfaces may not allow the full number of measurements. In these cases, the same MARSSIM approach encompassing historical, characterization, remediation, and turnover survey data is used as a basis for biased scanning and sampling to the p extent practicable to ensure that the release criteria are met. l j

i V Appendix 5-2 6 of 7 August 1999

I l 1

TROJANLICENSE TERMINATIONPLAN equal to or less than 0.05, while minimizing the value of p. Based on site characterization data l (')

(_) and the results of post-remediation surveys, PGE expects to maintain the ability to adjust LBGR to ensure relative shift values well in excess of 3.0 for the majority of the site survey areas. As I stated above, the design goal for relative shift is for values to range between 1.5 and 3.0. For the vast majority of site areas, collecting 30 sample measurements per survey unit while maintaining a relative shift 21.5 results in a probability ofpassing a survey unit which actually fails to meet the release criteria ofless than 2.5%, i.e., a = 0.025. By comparison, NRC guidance states 5%,

or n = 0.05. Collecting 30 sample measurements per survey unit while maintaining a relative shift 23 further reduces the probability of passing a survey unit which actually fails to meet the site release dose criterion to less than 0.5%, i.e., a = 0.005.

i i

\

4 i

s Appendix 5-2 7 of 7 August 1999

f TROJAN LICENSE TERMINATION PLAN APPENDIX 5-3

.p BACKGROUND REFERENCE AREAS V

Background reference areas are used if: (1) the residual radioactivity contains a radionuclide that occurs in background, or (2) the measurements to be made are not radionuclide-specific.

Background reference areas are not needed when radionuclide-specific measurements are used to measure concentrations of a radionuclide that is not present in background. They also are not i needed when one or more radionuclides are present in background at such small fractions of the DCGL as to be considered insignificant. Surveys are conducted in one or more background reference areas to determine background levels for comparison with the conditions determined in specific survey units.

SELECTION Background reference areas are selected which have similar physical, chemical, radiological, and biological characteristics as the survey unit being evaluated. They are usually selected from non-impacted areas, but are not limited to natural areas undisturbed by human activities. Generally, l background reference areas are not part of the survey unit being evaluated. However, where necessary, they may be associated with the survey unit being evaluated, but cannot be potentially l contaminated by site activities. For example, background measurements may be taken from core samples of concrete, pavement, or other types of surface materials. Occasionally, the survey unit itself may serve as the background reference area when a surrogate radionuclide in the survey  ;

unit can be used to determine the background. For example, it may be possible to use the l

q measured alpha- or beta-emitting fraction of an established radionuclide distribution in '

Q embedded piping to calculate a net activity and subtract it from a gross activity to determine background levels.  ;

For materials present on the site, either in buildings or as non-soil materials present in outdoor survey units (e.g., concrete, brick, drywall, fly ash, petroleum product wastes, etc.), background reference areas of non-impacted materials that are as similar as possible to the materials on the site are used. Sometimes such materials are not available. In those situations, a good faith effort is made to find the most similar materials readily available or use appropriate published estimates.

Each background reference area should have an area at least as large as the survey unit, if practical, in order to include the full potential spatial variability in background concentrations.

MARKEDLY DIFFERENT SURVEY UNIT MATERIAL BACKGROUNDS Survey units may sometimes contain a variety of materials with markedly different backgrounds.

An example might be a room with drywall walls, concrete floor, glass windows, metal doors, wood trim, and plastic fixtures. A separate survey unit is not made for each material. If one material is predominant or if there is not too great a variation in background among materials, a background ref:rence area comprised of the predominant material may be appropriate. For example, a room may be mostly concrete but with some metal beams, and the residual n radioactivity may be mostly on the concrete. In this situation where the presence of concrete Q predominates, the background for concrete is used for the room. If a measurement location on the random-start grid falls on the metal beam, the measurement location may be moved to be on A'ppendix 5-3 1of2 August 1999

TROJANLICENSE TERMINATIONPLAN

' the nearest piece of concrete. Alternately, the measurement could be taken on the metal, but this

. is then noted on the survey record so that an unusual reading can be explained.

When there are different materials with substantially different backgrounds in a survey unit, a non-impacted room with roughly the same mix of materials may be used as a background l

reference area. Alternately, measured backgrounds for the different materials or for groups of

{ similar materials may be used. In this' case, it is acceptable to perform the Sign test on the difference between the paired measurements from the survey unit and from the appropriate background material.

MARKEDLY DIFFERENT BACKGROUND REFERENCE AREAS If significant differences in backgrounds among background reference areas are found, a value of three times the standard deviation of the mean between the background reference areas is added to the mean background for all background reference areas to dcEne a background concentration.

The value of three times the standard deviation of the mean is chosen to minimize the likelihood that a survey unit that contains only background would fail the statistical test for release. The WRS ;est is then used to test whether the survey unit meets the radiological criteria for license termination.

/

O f

\

- ,l O

Appendix 5-3 2 of 2 August 1999

N o 4 i L r

} P 1 2 2 0 0 a

n

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5 e

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A d J e O s a

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S

l TROJAN LICENSE TERMINA TION PLAN l l

/~3 Table 5-2 V

l Initial Classification Of Trojan Facility And Site l

l NON-IMPACTED DESCRIPTION IMPACTED Class Class Class 1 2 3 Areas within the Floor, lower wall, and other surfaces, RCA or with and land areas contaminated during potential or known plant operations' V radioactive contaminat. ion Hallways, vestibules, stairways, upper walls, overhead, and other surfaces, and land areas' v b

Embedded piping V

Plant systems (interior surfaces)*

V c'

V)

( Areas outside the RCA but inside the Interior and exterior surfaces and land areas d

Industrial Area v Plant systems, including embedded piping' V

Areas outside the Industrial Area V  !

i

' Containment, Fuel Bldg, Auxiliary Bldg, portions of Control Bldg and Turbine Bldg, Radwaste ProcessinF/ Condensate Demin Bldg, Main Steam Support Structure, Electrical Penetration Area, and Tank Farm area 6

Auxiliary Bldg Radwaste, Chemical Radwaste, Clean Radwaste, and Dirty Radwaste systems

' Service Water; Turbine Bldg Cooling Water; Process & Auxiliary Steam; Turbine Bldg HVAC; Condensate Water Storage & Transfer; Condensate Demineralizer; Condenser & Air Removal; Condensate System; Feedwater; Extraction Steam; Feedwater Heaters, Vents, & Drains; Steam Generator Feedwater Pump Turbine Drivers; Oil &

Waste Storm Drains; Miscellaneous Gas Supply; Main Steam; Reheat & Moisture Separation; Turbine Steam Scaling & Seal Drain; Main Turbine & Turbine Controls; and Miscellaneous systems; and outside buried piping

• Majority ofControl Bldg and Turbine Bldg Maintenance Bldg, Chlorine Bldg, Guardhouse, Technical Support Center, Security Bldg, Trojan Central Bldg. Materials Warehouse, Combustible Liquid Storage Warehouse, Paint & Sheet Metal Shop, Intake Structure, Circulating Water Pump Pit, Transformers, Solids Settling Basin, and Industrial Area (excluding the ISFSI)

• Domestic Water, Ghlorination, Fire Protection. Bearing Cooling Water, Instrument & Service Air, Water

[] Pretreatment, Makeup Demin Water, Diesel Fuel Oil, Lube Oil Storage & Filtration, Circulating Water, Chilled V Water, Generator Hydrogen & Seal Oil, Stator Cooling, and Main Generator & Excitation systems August 1999

TROJANLICENSE TERAflNA TION PL4N i

O Table 5-3 l

\_) 1 1

i Survey Design Summary Class 1 l Class 2 Class 3 i Speenfication Structures Plant Land Areas Structures Land Areas Structures Land Areas Systems l SURVEY UNIT Size

• 10 to 100 to 10 to 100 to 2

No limit N/A 100 m 2000 m2 1,000 m 2 10,000 m 2 Reference I to 2 m 10 to 20 m 1 to 2 m 10 to 20 m 5 to 10 m 20 to 50 m N/A Coordinate Grid

• SCAN MEASUREMENTS Scan Coverage 100 % 10 to 50%' 0 to 10% Variable d Scan Area Accessible' surface area Judgmental; systematic Judgmental; random Judgmental; Selection along transects or of accessible' randomly selected grids surface area STATIC MEASUREMENTS Default 30

' 308 Number' Location Random starting point, systematic spacing

• Random Accessible Selection points Spacing (L)* L = (A/n)v2 for square grid N/A N/A A = total survey unit area; n = # of measurements Type' SC SO SC Sd SC Sd SC'

• Floor or ground surface areas only.

D A square grid system pattern is used unless survey needs dictate otherwise.

• Where scanning coverage greater than 50% is judged appropriate, the survey unit is reclassified as a Class I surv y unit.

l Performed, where possible, according to the scan coverage for the class of survey unit. The amount of l accessible surface area dictates the actual percentage of the surface area to be scanned.

• Includes health and safety considerations.

I This number is sufficient for survey units where the estimated mean is less than or equal to 0A times the

, DCGL and the estimated standard deviation is less than or equal to 0.2 times the DCGL. Where these conditions are not expected to hold true, the methodology described in Appendix 5-2 is used to determine if additional measurements are required.

8 ,

As allowed by plant system size and accessibility to system interior surfaces. '

I Except where statistical test is not applied (i.e., tumover survey data are all less than DCGL).

! SC repre>ents surface contamination measurements; SO represents soil measurements.

J Subsurface samples may be obtained from randomly selected locations to evaluate the potential for subsurface residual radioactivity.

() Scale and sediment samples may be obtained, if appropriate.

August 1999

TRO14N UCENSE TERMIN4 TION PL4N l

q Q Table 5-4 Page 1 of 10

)

{

Survey Unit Divisions of the Trojan Facility and Site As Of August 1999*

Number Reference

""'p Cd Description C "" " " 'I Area (m )' of Coordinate 1l2l3 Floor'l Other e Samples System CONTAINMENT BUILDING S01025A Cont Elev 15' Reactor Cavity & Access Tunnel x 76 l 350 30 2D S01025B Cont Elev 25' Tendon Gallery x 373 1240 30 2D S01044A Cont Elev 44' ENE Floor Quadrant x 98 0 30 2D S01044B Cont Elev 44' ESE Floor Quadrant x 95 0 30 2D S01044C Cont Elev 44' NNE Floor Quadrant x 81 0 30 2D S01044D Cont Elev 44' NE Floor Quadrant x 97 0 30 2D S01044E Cont Elev 44' SE Floor Quadrant x 97 0 30 2D S01044F Cont Elev 44' SSE Floor Quadrant x 78 0 30 2D S01044G Cont Elev 44' NNW Floor Quadrant x 82 0 30 2D S01044H Cont Elev 44' NW Floor Quadrant x 79 0 30 2D S010441 Cont Elev 44' SW Floor Quadrant x 79 0 30 2D S01044K Cont Elev 44' SSW Floor Quadrant x 80 0 30 2D S01044L Cont Elev 44' WNW Floor Quadrant x 100; O 30 2D S01044M Cont Elev 44' WSW Floor Quadrant x 97 0 30 2D S01044N Cont Exterior Between N & SE Tendon Access Ridges x 0 2900 30 2D

[,. S01044P Cont Exterior Between SE & SW Tendon Access Ridges x 0 2900 30 2D S01044R Cont Exterior Between SW & N Tendon Access Ridges x 0 2900 30 2D S01044S Cont Elev 44' interior ESE Wall Quadrant x 0 225 30 2D S01044T Cont Elev 44' Interior SSE Wall Quadrant x 0 225 30 2D S01044U x-S01044V Cont Elev 44' Interior SSW Wall Quadrant 0' 225 30 l 2D S01044W Cont Elev 44' Interior WSW Wall Quadrant x 0 225 30 l 2D S01044X Cont Elev 44' Interior WNW Wall Quadrant x 0 225 30 l 2D Cont Elev 44' interior NNW Wall Quadrant x 0 225 30 l 2D S01044Y Cont Elev 44' Interior NNE Wall Quadrant x 0! 225 2D 30 l S01044Z Cont Elev 44' Interior ENE Wall Quadrant x 225 30 2D 0l S01093A Cont Elev 93' Interior ESE Wall Quadrant x 225 30 2D 0l S01093B Cont Elev 93' Interior SSE Wall Quadrant x 225 30 2D 0l S01093C Cont Elev 93' interior SSW Wall Quadrant x 0l 225 30 2D S01093D Cont Elev 93' Interior WSW Wall Quadrant x 0; 225 30 l 2D S01093E Cont Elev 93' Interior WNW Wall Quadrant x 0 225 30 l 2D S01093F Cont Elev 93' interior NNW Wall Quadrant x l 0 225 30 2D S01093G Cont Elev 93' Interior NNE Wall Quadrant x l 0 225 30 2D S01093H Cont Elev 93' Interior ENE Wall Quadrant x l 0 225 30 2D S0ll42A Cont Elev l42' Interior ESE Wall Quadrant x 0 210 30 2D-S01142B Cont Elev 142' Interior SSE Wall Quadrant x 0 210 30 2D S01142C Cont Elev 142' interior SSW Wall Quadrant xl 0, 210 30 2D  ;

S0ll42D l Cont Elev 142' interior WSW Wall Quadrant xl O! 210; 30 l 2D '

S0ll42E l Cont Elev 142* Interior WNW Wall Quadrant xl l 0: 210) 30 l 2D S0ll42F iCont Elev 142' Interior NNW Wall Quadrant xl l Oj 210l 30 l 2D August 1999

TROJAN LICENSE TERMINATION PLAN O

h Table 5-4 Page 2 of10 Survey Unit Divisions of the Trojan Facility and Site As Of August 1999' Survey Survey Number Reference Description Class ID Codeb 2

Area (m )' of Coordinate 1 2 l 3 Floor'lOthere Samples System S01142G Cont Elev 142' Interior NNE Wall Quadrant x 0 210 30 2D S01142H Cont Elev 142' Interior ENE Wall Quadrant x 0 210 30 2D S01187A Cont Elev 187' Interior ESE Dome Quadrant x 0 186 30 P S01187B Cont Elev 187' Interior SSE Dome Quadrant x 0 186 30 P S01187C Cont Elev 187' Interior SSW Dome Quadrant x 0 186 30 P S01187D Cont Elev 187' Interior WSW Dome Quadrant x 0 186 30 P S01187E Cont Elev 187' Interior WNW Dome Quadrant x 0 186 30 P

,S01187F Cont Elev I87' Interior NNW Dome Quadrant x 0 186 30 P S01187G Cont Elev 187' Interior NNE Dome Quadrant x 0 186 30 P S01187H Cont Elev 187' Interior ENE Dome Quadrant x 0 186 30 P S0ll87J Cont Elev 187' Interior SE Dome Quadrant x 0 190 30 P S0ll87K Cont Elev l87' Interior SW Dome Quadrant x 0 190 30 P S0ll87L Cont Elev l 87' Interior NW Dome Quadrant x 0 190 30 P

S01187M Cont Elev 187' interior NE Dome Quadrant x 0 190 30 P S01187N Cont Polar Crane and Lifting Gear x 0 1240 30 2D O TURBINE BUILDING S02027A TB Elev 27' Neutralizing Tank Room Floor & Walls x 119 239 30 2D S02027B TB Elev 27' Neutralizing Tank Room Equip, Stairway, & Ceiling x 0 157 30 3D S02027C TB Elev 27' Condensate Pump Area Floor & Walls x 104 230 30 2.D S02027D TB Elev 27' Condensate Pump Area Equipment & Ceiling x 0 94 30 3D S02027E TB Elev 27' Turbine Building Sump x 70 30 30 2D S02027F TB Elev 35' Mezzanine Floor & Walls x l 410 30 2D '

S02027G TB Elev 35' Mezzanine Equipment & Ceiling ,x 160 330 30 3D S02027H TB Elev 35' N, W. & 5 Condenser Drain & Sump Areas x 160 330 30 2D S02045A TB Elev 45' SE Stairwell x Oj 260 30 2D S02045B TB Elev 45' Auxiliary Feedwater Pump Rooms x 150j l 400 30 3D S02045C TB Elev 45' Water Treatment Area / East Corridor Floor & Walls x 8001 500 30 2D S02045D TB Elev 45' Freight Elevator, Shaft, & Mechanical Room x 0 3601 30 2D S02045E TB Elev 45' Lube Oil Room xl 120 420 30 3D S02045F TB Elev 45' SW Stairwell l xl 0 300 30 2D S02045G TB Elev 45' Steam Packing Exhauster Drain Trough Area Floor i x 0 80l 30 2D S02045H {

TB Elev 45' South Condenser Area & So Corridor Floor & Walls x 600 i 200 30 2D S020451 TB Elev 45' South Condenser Area Equipment & Ceiling x- 0 600 30 3D S02045J ,TB Elev 45' West Condenser Area Floor & Walls xl 700 570 30 2D  :

502045K TB Elev 45' North Condenser Area Floor & Walls lxl 1500 900 30 2D {

S02045L TB Elev 45' Turbine Bay Equipment & Ceiling jxl 0 800 30 3D l S02045M JTB Elev 45' East Condenser Area Floor lxi 320; 0 30 2D S02045N iTB Elev 45' East Condenser Area Equipment & Ceiling S02045P iTB Elev 45' Survey for Release Facility (East End) i lxl Oj 320, 30 3D  ;

l Ix; j 240; 440l 30 2D S02045Q !TB Elev 45' Survey for Release Facility (West End) l lxi l 240l 440l 30 2D v

August 1999

TROJAN LICENSE TERAflNA TION PL4N G

C Table 5-4 Page 3 of 10 Survey Unit Divisions of the Trojan Facility and Site As Of August 1999*

Survey Class Survey Number Reference ID Code n Description Area (m')' of Coordinate 1l2l3 Floor lOthere Samples d

System S02045R TB Train Bay x 240 780 30 2D S0204 S TB Lower North Exterior Wall x 0 220 30 2D S02045T TB Lower West Exterior Wall x 0 1690 30 2D S02045U TB Lower So & East Exterior Walls (excluding MSSS area wall) x 0 2770 30 2D S02045V TB Upper North Exterior Wall x 0 1105 30 2D S02045W TB Upper West Exterior Wall x 0 1284 30 2D S02045X TB Upper South Exterior Wall 'x 0 1105 30 2D S02045Y TB Elev 45' West Condenser Area Equipment & Ceiling x 0 700 30 3D S02045Z TB Elev 45' North Condenser Area Equip, Stairway, & Ceiling x 0 1500' 30 3D S02063A TB Elev 69'"A" Switchgear Room x 370 1270 30 3D S02063B TB Elev 69' Main Switchgear Area x 320 1065 30 3D S02063C TB Elev 63' Feedwater Heaters 3 & 4 Area Floor & Walls x 840 490 30 2D S02063D TB Elev 63' Feedwater Heaters 3 & 4 Area Equipment & Ceiling x 0 1600 30 3D S02063E TB Elev 63' Main Steam Stop Valve Remediated Area x 80 0 30 2D S02063F TB Elev 63' East Side Floor Grating Area x 240 0 30 2D S02063G TB Elev 63' Machine Battery Room x O S02063H TB Elev 63' Lube Oil Reservoir Area Floor x 60 580 120 0

30 30 2D 2D S02063J TB Elev 63' & 73' West Side Floor Grating & Platforms x 800 0 30 2D S02063K TB Elev 63' Lube Oil Reservoir Area Equip, Walls, & Ceilings x 0 1600 30 3D S02063L TB Elev 63' Blow Off& Drain Tank Floor Area x 170 0 30 3D S02093A TB Elev 93' Laydown Area Floor & Walls x 740 1800 30 2D S020938 TB Elev 93' Feedwater Heater 5 & 6 Area Floor x 750 0 30 2D S02093C TB Elev 93' East Moisture Separator Reheater Area Floor x 11001 0 30 2D S02093D TB Elev 93' Condenser Air Discharge Monitor / Air Ejector Area x 180l 0 30 2D S02093E TB Elev 93' West Moisture Separator Reheater Area Floor x 880l 0 30 2D S02093F TB Elev 93' Turbine Hoods x 0 700 30 2D S02093G TB Elev 93' Feedwater Heater 5/6 Area Equip, Walls, & Ceiling x 0 1340 30 3D S02093H TB Elev 93' East Moisture Separator Reheater Area Equipment x 0 0 30 3D S02093J TB Elev 93' West Moisture Separator Reheater Area Equipment x 0 0 30 3D S02093K TB Elev 93' Main Bay East, South, & West Walls x 0 3100l 30 2D S02093L TB Elev 93' Main Bay Ceiling x 0 3840j 30 2D S02093M TB Elev 93' Turbine Building Crane & Lifting Gear x 0 480l 30 2D S02093N TB Roof- North Half x 1920 O i

30 2D S02093P TB Roof- South Half x 1920 0 30 2D S02093R TB Turbine Bay Roof x 880 0 30 2D S02093W TB Upper East Exterior Wall x 30 0{ 1290 2D MAIN STEAM SUPPORT / ELECTRICAL PENETRATION AREA /SGBD BLDG S03045A Area Between Containment & Auxiliary Building '

l xl 89l 600j 30 l 2D S03045B Area Between EPA & Turb/Cntrl Bldgs (incl Elev 64* Platform) x l 197l 760! 30 2D S03045C l EPA Elev 45'& 51' Areas xi 100l 200l 30 2D August 1999

I t

TROJAN LICENSE TERMINATION PLAN O Table 5-4 Page 4 of10 Survey Unit Divisions of the Trojan Facility and Site As Of August 1999' Survey Number Reference Codp Description Cl*** 2 Area (m ). of Coordinate 1 2 !3 Floor' l Other. Samples System 503045D MSSS Passageway x 36 420 30 2D S03045E MSSS Elev 44' Access Area x 39 240 30 2D S03045F MSSS Pit Below "D" Auxiliary Feedwater Line x 5 50 30 2D S03045G MSSS Pit Below "C" Auxiliary Feedwater Line x 5 50 30 2D S03045H MSSS Room Below "B" Auxiliary Feedwater Line x 9 i 100 30 2D j S03045J SGBD Bldg Interior x 17 90 30 2D S03045K SGBD Bldg Exterior x 0 90 30 2D S03059A. MSSS Elev $9' "A" & "D" Aux Feedwater Line Areas x 40 190 30 2D S03059B MSSS Elev 59'"C" & "B" Aux Feedwater Line Areas x' 23 90 30 2D S03059C EPA Elev 61' Areas (open to Elev 93') x 70 450 30 2D S03069A MSSS Elev 69' & 79'"A" Main Steam /Feedwater Line Areas x 40 200 30 2D S03069B MSSS Elev 69' & 79D" Main Steam /Feedwater Line Areas x 27 I80 30 2D S03069C MSSS Elev 69' & 79'"C" Main Steam /Feedwater Line Areas x 27 150 30 2D S03069D MSSS Elev 69' & 79'"B" Main Steam /Feedwater Line Areas x 36 l 150 30 2D S03093A MSSS Elev 93' Containment Purge Supply Fan Area x 152 100 30 2D S03100A iMSSS Safety Relief Valve Area x 52 250 30 2D FUEL BUILDING SO4045A FB Train Bay x 550 191 30 2D SO4045B FB Elev 45' Hold-Up Tank "C" Room x 46 430 30 2D SO4045C ; FB Elev 45' Hold-Up Tank "B" Room x 46 430 30 2D SO4045D FB Elev 45' Hold-Up Tank "A" Room x 46 430 30 2D SO4045E FB Elev 45' Hold-Up Tank Recire Pump Room x 29 130 30 2D SO4045F lFB North Stairwell l x 17l 530 30 2D SO4045G lFB Elev 45' Condensate Tank & Pump Room lx! 35l 130 30 2D SO4045H lFB Elev 45'"A" & "B" Component Cooling Water Pump Area l x 173 520j 30 2D 5040451 lFB Elev 45' Component Cooling Water Heat Exchanger Area l x 158 320l 30 2D SO4045K lFB Radwaste Annex Clean Laundry Area & Corridor j x 59 400! 30 2.D SO4045L lFB Radwaste Annex Dirty Laundry Sorting Area lx 32 160 30 2D SO4045M !FB Radwaste Annex Waste Compacting Area !x 43 290 30 2D SO4045N lFB Lower North & West Exterior Walls l xl 0 173 30 2D SO4045P lFB Lower East Exterior Wall (North End) ll x 0l 175 30 2D SO4045R {FB Lower East Exterior Wall (South End) l x 0l 200 30 2D I - S04045S lFB Upper North & West Exterior Walls j x 0 1008 30 2D SO4045T !FB Upper East Exterior Wall (North End) x 0 422 30 2D SO4045U IFB Upper East Exterior Wall (South End) x 0 430 30 2D SO4045V lFB Radwaste Annex Roof l xl 175 0 30 2D SO4045W iFB Lower South Exterior Wall I j ixj OI 440 30 2D SO4045X ,FB Upper South Exterior Wall  ! i ix 290; 30 2D 0l g SO4061 A ;FB Elev 66' Boric Acid Tank Room ixI i 87i 400j 30 ! 2D l l SO4061B FB Elev 61'CVCS Monitor Tank Room xl l l 143j 350j 30 l 2D l

/

August 1999 l

i I

TROJAN LICENSE TERMINA TION PLAN Page 5 of 10 Table 5-4 l

l Survey Unit Divisions of the Trojan Facility and Site As Of August 1999' Survey Number Reference

" Y '*"

p Description Area (m,)* of Coordinate 2 l 3 Floor Other e Samples System d

1 l SO4061C FB Elev 61' SFP Heat Exchanger Area x 100 510 30 2D SO406)D FB Elev 61' Respirator Maintenance Facility x 39 80 30 2D SO4061E FB Elev 61' Corridor & Boric Acid Panel Area x 590 82 30 2D l SO4061F FB Elev 61' Solid Waste Drumming Area x $8 290 30 2D l SO4061G FB East Stairwell x 250 12 30 2D SO4077A FB Elev 77' Radwaste Cone /CVCS Holding Tank & Pump Rms x 44 290 30 2D SO4077B FB Elev 77' Cask Wash Pit x 30 170 30 2D SO4077C FB Elev 7T New Fuel Storage Area x 28 120 30 2D SO4077D FB Elev 77' East Boric Acid Evaporator Room x 240

$3 30 2D SO4077E FB Elev 77' Spent Fuel Pool Skimmer Pump Area x 51 380 30 2D SO4077F FB Elev 77' Radwaste Control Panel Area x 124 300 30 2D SO4093A FB Elev 93' & 105' Boric Acid Batching Area Floor & Equip x 89 0 30 2D

! SO40938 FB Elev 93' Hot Tool Room & Hoistway Area Floor x 173 0 30 2D SO4093C FB Elev 93' Decon/ Spray Booth Area Floor x 263 0 30 2D SO4093D FB Elev 93' Laydown Area Floor x 183 0 30 2D SO4093E FB Elev 93' Spent Fuel Pool Area Floor x 249 0 30 2D SO4093F FB Elev 93' Spent Fuel Pool x 102 610 30 2D SO4093G FB Elev 93' Fuel Transfer Canal x 38 380 30 2D l

l SO4093H FB Elev 93' Cask Load Pit x 13 180 30 2D SO4093J FB Elev 93' North Wall x 0 270 30 2D SO4093K FB Elev 93' East Wall (North End) l lx 1 0 400 30 2D l SO4093L lFB Elev 93' East Wall (South End) x l 0 360 30 2D l SO4093M FB Elev 93' South Wall x l 0 280 30 2D l

SO4093N FB Elev 93' Containment Wall x 0 310 30 2D i SO4093P FB Elev 93' West Wall Between Cont & Aux Bldg Roll-Up Door l x 0 240 30 2D SO4093R FB Elev 93' West Wall (North End) x l 0 380' 30 2D i SO4093S FB Elev 93* Ceiling (North End) x 0 540 30 2D SO4093T FB Elev 93' Ceiling (South Erid) x 0 520 30 2D SO4093U FB Elev 93' Crane & Lifting Gear x. l 0 230 30 2D SO4093V FB Roof lxl 1060 0l 30 2D AUXILIARY BUILDING S05005A AB Elev 5' NE Stairwell .x 30i 630 30 2D J

S05005B AB Elev 5'"B" Safety injection Pump Room x 19 130 30 2D S05005C AB Elev 5'"A" Safety injection Pump Room x 21 160 30 2D S05005D AB Elev 5'"B" Containment Spray Pump Room x 23 150 30 2D S05005E AB Elev 5'"B" RHR Heat Exchanger Room x 19 310 30 2D S05005F AB Elev 5'"B" RHR Pump Room x 35 180l 30 l 2D S05005G AB Elev 5'"A" RHR Pump Room x 36 180j 30 l 2D S05005H AB Elev 5'"A" RHR Heat Exchanger Room x 22 30 i 2D l 310l

,S05005J lAB Elev 5' Waste Receiver & Drain Pump Rooms x  ! 41 320l 30 1 2D August 1999

TROlkN LICENSE TERMINA TION PLAN A Page 6 of10

() Table 5-4 Survey Unit Divisions of the Trojan Facility and Site As Of August 1999' b" ** Survey Number! Reference C escription Area (m')* of Coordinate 1 l2 '3 Floord lOther e Samples System S05005K AB Elev 5' Drain Tank Room x 12 90 30 2D S05005L AB Elev 5' Nonh Hallway & Sump Area x 42 240 30 2D S05005M AB Elev 5' Central Hallway x 72 160 30 2D S0500$N AB Elev 5' Diny Waste Tank & Pump Rooms x 33 210 30 2D S05005P AB Elev 5* "A" Containment Spray Pump Room x 25 150 30 2D S05005R AB Elev 17' Pipe Chase - East x 43 100 30 2D S05005S AB Elev 17' Pipe Chase - West x 43 100 30 2D S05025A AB Elev 25' North Corridor x 29 140 30 2D S05025B AB Elev 25' Reciprocating Charging Pump Room x 25 150 30 2D S05025C AB Elev 25' Sodium Hydroxide Tank Room x 25 140 30 2D 1 S05025D AB Elev 25' Reactor Coolant Drain Tank Pump Room x 14 100 30 2D S05025E AB Dev 25' val e Gallery x 17 130 30 2D S05025F AB East RHR Pipe Chase (to Elev 61') x 0 160 30 2D S05025G AB West RHR Pipe Chase (to Elev 61') x 0 160 30 2D S05025H AB Elev 25' Primary Make-Up Water Pump Room x 15 80 30 2D S05025J AB Elev 25' Boric Acid injection Tank Room & Valve Gallery x 26 180 30 2D O S05025K AB Elev 25' Clean Waste Receiver Tank Room S05025L AB Elev 25' Chemical Waste Drain Tank & Pump Rooms x

x 56 28 430 220 30 30 2D 2D S05025M AB Elev 25' Laundry Drain Tank Area x 35 150 30 2D l S05025N AB Elev 25' "A" Centrifigal Charging Pump Room x 31' 150 30 2D S05025P lAB Elev 25'"B" Centrifigal Charging Pump Room x 30 150 30 2D S05025R !AB Elev 25' Central Hallway x 505025S AB Elev 37' Pipe Chase 47 140 i 30 2D ,

x 0 2501 30 2D I S05045A AB Elev 45' Hot Lab x 52 130j 30 l 2D l S05045B lAB Elev 45' Treated Waste Monitor Tank Room x 102 2D 240l 30 S05045C LAB Elev 45' Service Water Booster Pump Area x 113 270 i 30 2D S05045D AB Central Pipe Chase & 61' & 77' Pipeways x 0l 620 30 2D S05045E AB Elev 45'"C" Component Cooling Water Pump Area x 97l 320 30 2D j S05045F AB Elev 45' Pipe Facade Valve Gallery x 171 50 30 2D S05045G iAB Elev 45' Pipe Facade x 440 74l 30 2D l S05045H AB Elev 45' Pipe Penetration Area 'x 33 180 30 2D S05045J AB Elev 45' Spent Fuel Pool Cooling Pump Rooms x 23 150j 30 2D S05045K AB Elev 45' Corridor x 360 611 30 2D S05045L AB Elev 45' Dirty Waste Monitor Tank & Pump Rooms x 38l 170 30 2D S05045M lAB Elev 45' Rad Sample Room x 3lj 120 30 2D S05045N iAB Lower Nonh Exterior Wall x O! 233 30 2D l S05045P !AB Upper North Exterior Wall xl 552 30 2D 0l .

l S05061 A LAB Elev 61* Nonh & NW Corridors l x i 120l 620 30 l 2D 15050618 i AB Elev 61' Waste Gas Decay Tank Valve Gallery lx i 49l 240, 30 1 2D OS05061C AB Elev 61' Radwaste Evap/ Waste Gas Surge Tank Rooms lxl l 330l 30 l 2D 68l S0506 t D ' AB Elev 61' Waste Gas Compressor Rooms

{xi ! l 41l 210! 30 1 2D August 1999

F TROJAN LICENSE TERMINATION PLAN

• l l

1 f) v- Page 7 of 10 Table 5-4 Survey Unit Divisions of the Trojan Facility and Site As Of August 1999' Survey Number Reference I Code 6 eSerlP tion 2 Area (m )* of Coordinate 1l2 13 Floor'l Other. Samples System S05061E AB Elev 61' Spent Resin Storage Tank x 17 70 30 2D S05061F AB Elev 61' Spent Resin Storage Tank Pump Room x 14 70 30 2D S05061G AB Elev 61' Letdown Heat Exchanger Room x 29 200 30 2D S05061H AB Elev 61' Volume Control Tank Room x 29 10n 30 2D S05061J AB Elev 57' Pipe Penetration Area outside Vol Cntrl Tnk Rm x 37 200 30 2D S05061K AB Elev 63' South Pipe Facade Area x 30 160 30 2D S05061L AB Elev 61' East Waste Gas Decay Tank Rooms x 51 170 30 2D S05061M AB Elev 61' West Waste Gas Decay Tank Rooms x 46 170 30 2D S05077A AB Elev 77' North & NW Corridors x 129 680 30 2D S05077B AB Elev 77' NW Valve Gallery & Demineralizer Beds x 86 170 30 2D S05077C AB Elev 77' Filter Pits x 0 380 30 2D S05077D AB Elev 77' NE Valve Gallery & Demineralizer Beds x 62 210 30 2D l S05077E AB Elev 77' West Boric Acid Evaporator Room x 82 320 30 2D S0$077F AB Elev 77' Component Cooling Water Surge Tank Area x 67 190 30 2D S05077G AB Elev 77'SE Valve Gallery x 36 160 30 2D S05077H AB Elev 77' SW Valve Gallery x 51 200 30 2D S05093A AB Elev 93' Load Center Area x 177 650 30 2D S05093B AB Elev 93' Containment Purge Exhaust Room x 104 330 30 2D

! S05093C AB Elev 93' Tool Area / Corridor x 217 630 30 2D S05093D AB Elev 93' Containment Personnel Lock Area x 46 350 30 2D S05093E AB Elev 93' Aux / Fuel Bldg Exhaust Fan Room x 148 300 i 30 2D S0$093F AB Elev 93' Spent Fuel Pool Exhaust Fan Room x 87 190' 30 2D S05093G AB Roof x 590- 0 30 2D

~

S05093H AB Elev 105' Aux / Fuel Bldg Exhaust Fan Area x 235 410 30 2D CONTROL BUILDING S06045A CB Elev 45'I&C Shop & Office Areas x 178l 510 30 2D S06045B CB Elev 45' Counting Room x 110 30 2D 18l-S06045C CB Elev 45' RCA Access / Egress Area & Corridor x 69 340 30 2D S06045D CB Elev 45' SE Elevator, Shaft, & Equipment Room x 11 250 30 2D S06045E CB Elev 45' SE Stairwell x 44! 380 30 2D S06045F CB Elev 45' RP Offices, Restrooms, & Lobby x 257l 1230 30 2D l S06045G CB Elev 45' SW Stairwell x 441 380 30 2D l S06045H CB Elev 45' SW Elevator, Shaft, & Equipment Room x 10 450 30 2D S06045J CB Elev 53' RP/ Ops Study / Break Area x 220 510 30 2D l S06045L CB Lower North & East Exterior Walls x Ol 209 30 2D S06045M CB Upper North & East Exterior Walls x 0! 579 30 2D S06061A CB Elev 61'"B" Switchgear & Electrical Auxiliaries x 408; 1090 30 3D S06061B CB Elev 61' Mechanical & Telephone Equipment Rooms x 141; 700 30 3D r

S06077A ,CB Elev 77' Cable Spreading Room x 446! 4050; 30 3D S060778 lCB Elev 77' Lobby, Mechanical & Computer Rooms xl 119. 570l 30 3D August 1999 e

TROJAN IJCENSE TERMINATION PLAN O Table 5-4 Page 8 of10 Survey Unit Divisions of the Trojan Facility and Site As Of August 1999*

Survey Class Survey Number Reference ID Codeb Description 8 Area (m )* of Coordinate 1l2 3 Floor lOthere Samples d System S06077C CB Pipe Chase x 0 220 30 2D S06093A CB Elev 93' Control Room & Shift Manager's Officer x 364 530 30 3D S06093B CB Elev 93' Cold Lab x 50 230 30 3D S06093C CB Elev 93' Lobby, Restroom, & Kitchen x 69 230 30 2D S06093D CB Elev93' Containment Access Area x 58 230 30 2D S06093E CB Elev 105' Viewing Gallery x 62 30 136 2D S06093F CB Elev 105' Mechanical Room x 10 40 30 2D S06093G CB Roof x 730 0 30 2D INTAKE STRUCTURE S07023A Intake Structure Interior x 156 900 30 2D S07023B Intake Structure Exterior x 340 210 30 2D MAINTENANCE BUILDING S08045A Mtnce Bldg Tool Room & Carpenter Shop lxl 268 490 30 2D S08045B Mtnce Bldg Machine Shop l lx 349 660 30 2D S08045C Mtnce Bldg Offices I x 137 870 30 2D

- S08045D Mtnce Bldg Weld Shop x 109 330 30 2D S08045E Mtnce Bldg Lower North Exterior Wall x 0 72 30 2D S08045F Mtnce Bldg Lower West Exterior Wall x 0 434 30 2D S08045G Mtnce Bldg Lower & Upper South Exterior Wall & Patio x 0 940 30 2D S08045H Mtnce Bldg Lower East Exterior Wall i x 0 425 30 2D S08045J Mtnce Bldg Upper North, East, & West Exterior Walls I xl 0 387 30 2D S08059A Mtnce Bldg Lunchroom, Kitchen, Mechanical Rooms xl 255 640 30 2D S08059B Mtnce Bldg Roof (excluding Patio) -  ! lxl 9431 0 30 2D CHLORINE BUILDING S09045A Chlorine Bldg Interior l l xl 236l 780 30 2D SO9045B Chlorine Bldg Exterior 1 i xi 390 30 2D 236l CIRCULATING WATER PUMP PIT S10029A l Circulating ' Water Pump Pit l l lxl 340; 250l 30 l 2D GUARDHOUSE S11032A Guardhouse Lower Level Interior i ix i 88: 530 30 2D S11043A Guardhouse Main Level Interior . 'xi l19; 440 30 2D S11043B Guardhouse Exterior Walls, Roof, & Stairs l !xi 130; 200 30 2D TRANSFORMER S12045A l Transformers, Dividing Walls, and Busses l l lxl 0l 500l 30 l 2D CONDENSATE DEMINERALIZER BUILDING Sl3019A lCond Demin Bldg Elev 5' & 19' Backwash Tank Area ixl l 75i 190 30 2D S13019B lCond Demin Bldg Elev 19' Demineralizer Tank Area Ix; i 150' 460 30 2D Sl3019C lCond Demin Bldg Elev 19' Waste Filtrate Tanks & Hopper Rm l- :x! , 212- 210 30 2D

/ S13032A ;Cond Demin Bldg Elev 32' l x! i 206. 210' 30 l 2D S13044A lCond Demin Bldg Elev 44' Control Panel / Resin Storage Areas I ix; ! 260 560 30 l 2D l

l August 1999 l

TROJAN LICENSE TERMINA TION PLAN

(~3 Page 9 of 10

() Table 5-4 Survey Unit Divisions of the Trojan Facility and Site As Of August 1999' 8" I I'"

Survey Number Reference f Description Area (m*)* of Coordinate 1l2 l3 Floor d Other e Samples System l S13044B Cond Demin Bldg Interior Ceiling x 0 480 30 2D S13044C Cond Demin Bldg Exterior x 440 460 30 2D TECIINICAL SUPPORT CENTER S14038A TSC Lower Level x 490 1800 30 2D S14051A TSC Main Elevation x 525 1930 30 2D S14051B TSC Exterior x 550 530 30 2D OILY WATER SEPARATOR S15020A l Oily Water Separator l lxl l 60l 200l 30 l 2D SECURITY BUILDING S16045A Security Building Interior x 305 360 30 2D S16045B Security Building Exterior '

x 305 860 30 2D TROJAN CENTRAL BUILDING S17045A lTCB Commons Area x 509 870 30 2D S170458 TCB North Stairwell x 49 240 30 3D S17045C TCB Central Stairwell x 102 340 30 3D

, , S17045D TCB Elevators

' x 0 280 30 2D S17045E TCB West Stairwell x $6 240 30 3D S17045F TCB Health Physics Lab x 99 270 30 2D S17045G TCB Ist Floor Balance x 1755 3160 30 3D S17045H TCB Exterior Walls x 0 3590 30 2D S17059A TCB 2nd Floor x 2735 5300 30 3D S17073A TCB 3rd Floor x 2982 5580 30 3D S17073B TCB Roof x 2982 0 30 2D MATERIALS WAREHOUSE S18045A Materials Warehouse Interior S18045B Materials Warehouse North & East Exterior Wa!!s xl 1420l 2780 30 2D x 0 668 30 2D S18045C Materials Warehouse South & . West Exterior Walls x 0 670 30 2D S18045D l Materials Warehouse Roof xl 1340, 0 30 2D GAS BOTTLE STORAGE BUILDING S19045A Gas Bottle Storage Building Interior x 272 510 30 2D S19045B Gas Bottle Storage Building Exterior Surfaces x 0 410 30 2D SHEET METAL SHOP S20045A Sheet Metal Shop Interior x 474 1030 30 2D S20045B Sheet Metal Shop Exterior x 0 860 30 2D SOLIDS SETTLING BASIN S21026A l Solids Settling Basin l l lxl 156l 330l 30 l 2D YARD AREAS i G22045A jNortheast Yard G22045B ll Southeast Yard x 4588l 0l 30 l 2D x 7895l Oj 30 2D g G22045C l Tank Farm Area x 2743! 30 2D 0)

August 1999

MOJAN LICENSE TERMINA TION PL4N age 10 of10 Table 5-4 Survey Unit Divisions of the Troian Facility and Site As Of August 1999' Survey Class 8"rV'Y Number Reference ID Code

• Description Area (m,), of Coordinate 1 2 3 Floord ! Othere Samples System G22045D Southwest Yard x 4674 0 30 2D G22045E Northwest Yard x 7354 0 30 2D G22045F ISFSI AdjacentYard x 3078 0 30 2D

• Represents planning as ofJuly 1999. Systems and Embedded Piping survey area designations await the completion of further remediation activities.

• The 7-digit code consists of a 1-digit category code (S - structure or G - land area / ground), a 2-digit refere l identification number, a 3-digit number reflecting plant elevation, and a sequential alphabetic designator.

• Survey units sized to ensure survey data points are relatively uniformly distributed among areas of similar potential for residual radioactivity, Where survey unit includes or consists of walls or ceilings, survey unit is sized so as to preserve dose modeling assumptions.

Includes floor or ground surface area only; may also include flat roof area.

• Includes balance of surface area in survey unit.

b U

I

(

. /

August 1999

TROJAN LICENSE TERMINA TION PL4N Table 5-5 Data Results and Investigation Conclusions Applicability Data Results* Investigation Conclusion Class 1 Class 2 Class 3 One or more data points Remediate and,if Class 2 or Class 3, y g g

> DCGLE uc reclassify to Class 1 All data points s DCGLruc v Acceptable One or more data points

> DCGL v v Reclassify to Class 1 All data points s DCGL v v Acceptable One or more data points

> 0.5 x DCGL v Reclassify to Class 2 All data points  !

s 0.5 x DCGL bk O ' The methodology used to calculate and apply the DCGLme is given in Appendix 5-1.

(O j

)

l

[N O

August 1999

TROJAN LICENSE TERAflNATION PLAN f' Table 5-6 s

Typical Survey Instrumentation Measurement Effective Detector Area Instrument Detector I Type ** ' IP*

and Window Density and Model Model 2

• 126 cm Alpha Scan

g al 0.8 mg/cm2 Aluminized Ludlum 2350-1 Ludlum 43-68 p

Mylar Bem-Ganuna Gasaow Scan 0.8 mg/c uminized Ludlum 2350-1 Ludlum 43-68 proportional My'lu Gamma Scan 2" diameter x 7.3" length Scintillation Ludlum 2350-1 Ludlum 44-2 l

Static Surface Gas-flow 0.8 mg/c uminized Ludlum 2350-1 Ludlum 43-68 Contammation proportional MW Soil and Bulk High-purity 1.60" x 1.94",2.16" x 2.32" Material Germanium N/A Ortec N/A ex .

U August 1999

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TROJAN LICENSE TERMIN4 TION PLAN Table 5-8

(.,

'y/ Survey Results and Conclusions When A Background Reference Area Is Not Used l

Conclusion:

Survey unit meets site release dose Survey Result criterion Yes No All measurements less than or equal to DCGL V Mean greater than DCGL v

Any measurement greater than DCGL with mean less than or equal to DCGL which passes Sign test y

Any measurement greater than DCGL with mean less than or equal to DCGL which fails Sign test y a

O August 1999

r' TROJAN LICENSE TERMINA TION PLAN l Table 5-9 O

1(Q Survey Results and Conclusions When A Background Reference Area Is Used l l

Conclusion:

Survey unit meets site release dose Survey Result criterion Yes No Difference between maximum survey unit measurement and minimum background reference area measurement less than or v equal to DCGL Difference between survey unit mean and background reference area mean greater than DCGL '

g Difference between any survey unit measurement and any background reference area measurement greater than DCOL and y

difference between survey unit mean and background reference area mean less than or equal to DCGL which passes WRS test 1

Difference between any survey unit measurement and any background reference area measurement greater than DCGL and y

difference between survey unit mean and background reference

)

area mean less than or equal to DCOL which fails WRS test 1 i

l i

l

\

O August 1999 i

L

h TROJAN LICENSE TERMINA TION PLAN I

Figure 5-1 Data Investigation Process I

g Review Survey Data Data points [

below YES ,( Perfonn data investigation assessment level *? a NO

' Investigation levels are:

Verify or confirm data Scan measurements ....... DCGL Static measurements

+ Class 1 and 2........... DCGL Determine area and level of Class 3 ........... 0.5 x DCGL elevated contamination D

d Class 1 survey un117 YES

> Calculate DCGLt uc

+

NO . 1 Compare data with Subdivide survey unit and/or DCOLtue reclassify

+

Resurvey or augment data set Data below YES ,

DCGLtuc7

+

NO Remediate

+

Subdivide survey unit and/or reclassify,if needed

+

Resuney O ,- +

/

August 1999

TROJAN LICENSE TERAf1 NATION PLAN l Figure 5-2 i Data Assessment Process )

,m r

i Collect additional data v .

Y Review survey data Calculate range, median YES survey unit meets site mean. & standard deviation release dose criteria All data points below DCGL?

Range, median, and std deviation YES below values'?

• statistical comparison values are:

Range- RsSo Median . . l(0 - nyol s 0.5 sta Deviation ....o s 0.2 x DCGL NO 6

Examm.e data; discard The minimum number of data points I outliers and anomahes needed for the statistical test may be l determined using appropriate equations v in Appendix 5-2.

NO sufficient YES Data mean YES l

< number of data below y Perform sign test points"? DCGL?

NO Apply background reference area Remediate and resurvey NO Adjusted data mean survey unit below DCGL?

A r YES Perform WRs test Data pass YES y statistical test?

NO NO Failure due t YES Power of NO statistical statistical test fluctuation? sufficient?

'ES Resurvey survey unit August 1999

L l

l ATTACHMENT V to VPN-054-99

)

TROJAN NUCLEAR PLANT DandD MODELING RUNS FOR DETERMINATION OF SCREENING DCGLs (108 pages) i i

Program  : DandD Version 1.0 Session  : Screening DCGLs - Building Occupancy Scenario Description :

i Calculation of radionuclide-specific activity resulting in 25 mrem /yr Executed  : 03/25/99 at 22:33:51 NRC Report Occupancy Input Section Execution Options History file will not be generated.

Implicit progeny doses will not be included with explicit parent.

Concentration data will be calculated.

Initial Radionuclide Activities Chain dpm/100cma 2 3H 1.23E+008 Code-Generated Radionuclide Activities Chain dpm/100cm^2 3H 1.2300E+000 Variable Parameters No parameters have been changed.

Occupancy Output Section i

1 Maximum Annual TEDE This scenario started 0.00 year (s) from now and ran for 1.00 year (s).

The peak dose of 2.50E+001 TEDE (mrem) occurred 1.00 year (s) after license termination.

p,-

4 Pathway Component of Maximum Annual Dose P'athway TEDE (mrem) Percentage External 0.00E+000 0.00 Inhalation 1.60E+001 64.17 Ingestion 8.96E+000 35.83 Total 2.50E+001 100.00 Radionuclide Component of Maximum Annual Dose l

l Radionuclide TEDE (mrem) Percentage 3H 2.50E+001 100.00 Total 2.50E+001 100.00 ,

1 1

4 l

i l

1 1

1

Program 1: DandD Version 1.0 Session. ': Screening DCGLs'- Building Occupancy Scenario i j

Description :

j Calculation'of radionuclide-specific activity resulting I in.25 mrem /yr Executed  : 03/25/99 at 22:35:18 i NRC Report occupancy Input Section l

Execution Options-  !

History file will be generated.

Implicit. progeny doses will not be included with e::plicit parent.

-Concentration data will be calculated. .l 1

-Initial Radionuclide Activities -

Chain dpm/100cm^2 14C 3.66E+006 Code-Generated Radionuclide Activities Chain dpm/100cm^2

........................................ i 14C 3.6600E+006 i

Variable. Parameters No parameters have been changed. I Occupancy Output Section I Maximum Annual TEDE This scenario started 0.00 year (s) from now and ran~for 1.00 year (s). j The peak dose of 2550E+001 TEDE (mrem) occurred 1.00 year (s) after license termination.

l

l Pathway Component of Maximum Annual Dose .

Pathway: TEDE (mrem) Percentage -

! External 8.26E-002 0.33

' Inhalation 1.60E+001 63.96

' Ingestion 8.93E+000 35.71 Total 2.50E+001 100.00 Radionuclide Component of Maximum Annual Dose l

l Radionuclide TEDE'(mrem) Percentage 1

14C 2.50E+001 100.00 i Total 2.50E+001 '100.00 l

l l

, I l.

1 \

t

/  ;

l l

l

i l

Program  : DandD Version 1.0 Session  : Screening DCGLs - Building Occupancy Scenario Description :

Calculation of radionuclide-specific activity resulting in 25 mrem /yr Executed  : 03/25/99 at 22:36:03

NRC Report Occupancy Input Section Execution Options l History file will be generated. l Implicit progeny doses will not be included with explicit parent.

Concentration data will be calculated.

Initial Radionuclide Activities i

Chain dpm/100cm^2 55Fe 4.47E+006 l Code-Generated Radionuclide Activities l Chain dpm/100cm^2 55Fe 4.4700E+006 Variable Parameters No parameters have been changed.

Occupancy Output Section Maximum Annual TEDE This scenario started 0.00 year (s) from now and ran for 1.00 year (s) .

The peak dose of 2.50E+001 TEDE (mrem) occurred 1.00 year (s) after license termination.

g L

h I 1

l .

L Pathway Component of

' Maximum Annual Dose-

' Pathway- .TEDE (mrem) Percentage

. External 0.00E+000. 0.00 Inhalation 2.22E+001 88.80 Ingestion 2.80E+000 11.20 l Total 2.50E+001 100.00-Radionuclide Component of -

Maximum Annual Dose r

l l

t Radionuclide- TEDE (mrem) Percentage

' 55Fe 2.50E+001 100.00' l

Total 2.50E+001 100.00 l

1 l

.1 e

i i.

E, e

' Program  : DandD Version 1.0 Session'  : Screening DCGLs - Building Occupancy Scenario Description :

Calculation of radionuclide-specific-activity resulting in 25 mrem /yr Executed'  : 03/25/99 at 22:36:52 NRC Report Occupancy Input.Section j i

I l

Execution. Options 4 History file will be generated.

Implicit. progeny doses will not be included with explicit parent.

Concentration data will be calculated.

Initial Radionuclide Activities Chain dpm/100cm^2 )

........................................ 1 60Co 7040.00  !

L Code-Generated Radionuclide Activities

_ Chain- dpm/100cma2  ;

60Co 7.0400E+003 i

Variable Parameters No parameters have been changed.

Occupancy Output Section Maximum Annual TEDE This scenario started 0.00 year (s) from now and ran for 1.00 year (s).

The peak, dose of 2.50E+001 TEDE (mrem) occurred 1.00 year (s) after license termination.

l l

Pathway Component of Maximum Annual Dose Pathway TEDE (mrem) Percentage j

External I 2.18E+001 87.07 I

Inhalation 3.02E+000 12.10 1 Ingestion 2.08E-001 0.83 Total 2.50E+001 ,100.00 Radionuclide Component of Maximum Annual Dose Radionuclide TEDE (mrem) Percentage 60Co 2.50E+001 100.00 1

_____________________________________________ l Total 2.50E+001 100.00 1

l

[

i

F l 1

l Program  : DandD Version 1.0 l Session  : Screening DCGLs - Building Occupancy Scenario i Description :

Calculation of radionuclide-specific activity resulting in 25 mrem /yr i l Executed  : 03/25/99 at 22:37:35 NRC Report Occupancy Input Section l

Execution Options '

History file will be generated.

l Implicit progeny doses will not be included with explicit parent.

Concentration data will be calculated. '

t Initial Radionuclide Activities  !

.........--..............m.............. i Chain dpm/100cm^2 59Ni 4.23E+006 1 Code-Generated Radionuclide Activities Chain dpm/100cm^2 59Ni 4.2300E+006 Variable Parameters

.......................o..............................................

No parameters have been changed.

Occupancy Output Section Maximum Annual TEDE This scenario started 0.00 year (s) from now and ran for 1.00 year (s). ,

The peak dose of 2.'50E+001 TEDE (mrem) occurred 1.00 year (s) after license termination.

l l

I l i 1

Pathway Component of Maximum Annual Dose Pathway TEDE (mrem) Percentage

............................................. l External 0.00E+000 0.00 l Inhalation 2.40E+001 95.85 Ingestion 1.04E+000 4.15 Total 2.50E+001 100.00 Radionuclide Component of Maximum Annual Dose Radionuclide TEDE (mrem) Percentage 59Ni 2.50E+001 100.00 Total 2.50E+001 100.00 I i

J 1

i i

i

/

Program  : DandD Version 1.0 Session  : Screening DCGLs - Building Occupancy Scenario Description :

Calculation of radionuclide-specific activity resulting in 25 mrem /yr Executed  : 03/25/99'at 22:38:26 NRC Report Occupancy Input Section Execution Options History file will be generated.

Implicit progeny doses will not be included with explicit parent. I Concentration data will be calculated.

)

Initial Radionuclide Activities Chain dpm/100cm^2 63Ni 1.81E+006 Code-Generated Radionuclide Activities Chain dpm/100cm^2 63Ni 1.8100E+006 Variable Parameters No parameters have been changed.

Occupancy Output Section Maximum Annual TEDE This scenario started 0.00 year (s) from now and ran for 1.00 year (s).

The peak dose of 2.50E+001 TEDE (mrem) occurred 1.00 year (s) after license termination.

l

Pathway Component of Maximum Annual Dose l Pathway TEDE (mrem) Percentage External 0.00E+000 0.00 Inhalation 2.38E+001 95.13 l Ingestion 1.22E+000 4.87 Total 2.50E+001 100.00 Radionuclide Component of Maximum Annual Dose Radionuclide TEDE (mrem) Percentage 63Ni 2.50E+001 100.00 Total 2.50E+001 100.00 I i

w Program.  : DandD Version 1.0

' Session  : Screening DCGLs - Building Occupancy Scenario iDescription.:

Calculation of radionuclide-specific activity resulting in 25 mrem /yr Executed  : 03/25/99 at 22:39:13-NRC Report Occupancy Input Section Execution Options History file will be generated.

~

Implicit progeny' doses will not be included with explicit parent.

Concentration data will be calculated.

Initial Radionuclide Activities

Chain dpm/100cm^2 90Sr 8650.00 I

Code-Generated:Radionuclide Activities Chain. dpr/100cm^2 ,

90Sr 8.6500E+003 90Y 0.0000E+000 Variable Parameters  !

No parameters.have been changed. )

1 Occupancy Output Section s l

1 l I Maximum Annual TEDE I 1

.This . scenario started 0.00 year (s) from now and ran for-1.00 year (s).

l The peak dose of 2.50E+001 TEDE (mrem) occurred 1.00 year (s) after

-license termination.

i

Pathway Component of i

Maximum Annual Dose

>~

Pathway. .TEDE (mrem) Percentage 1

External 6.66E-002 0.27.

Inhalation'- 2.34E+001 93.61 Ingestion 1.53E+000 6.12

. Total. 2.50E+001- 100.00 Radionuclide Component of Ma :imum Annual Does Radionuclide TEDE (mrem) Percentage 90Sr 2.47E+001 98.72

- 90Y. 3.19E-001 1.28 Total 2.50E+001 100.00

. I 1

M

1 I

Program  : DandD Version 1.0 Session  : Screening DCGLs.- Building Occupancy Scenario Description : .

J Calculation of radionuclide-specific activity resulting in 25 mrem /yr-Executed.  : 03/25/99 at 22:40:07

.NRC Report

)

Occupancy Input Section l

)

l Execution Options History file will be generated.

Implicit progeny doses will not be included with explicit parent.

Concentration data will be calculated.  !

f

• l Initial Radionuclide Activities -

Chain dpm/100cm^2 l 94Nb 8200.00 Code-Generated Radionuclide Activities Chain dpm/100cm^2 94Nb 8.2800E+003 l Variable Parameters No parameters have been changed.

Occupancy Output Section i

l Maximum Annual TEDE l i

1 This scenario started 0.00 year (s) from now and ran for 1.00 year (s). i 3  !

The peak dose of 2'50E+001 TEDE (mrem) cecurred 1.00 year (s) after license termination.

l l

l l i

1 I

i i

~ 1 i

Pathway Component of  !

j

' Maximum Annual Dose l

Pathway 1TEDE (mrem) Percentage External 11.78E+001 70.98 Inhalation 7.19E+000 28.74 Ingestion- 6.92E-002 0.28-Total. 2.50E+001 100.00 1

Radionuclide Component of.

Maximum Annual Dose-Radionuclide. ' TEDE. (mrem) Percentage 94Nb 2.50E+001 100.00 Total 2.50E+001 100.00 l

J O

f'

/

l

v e

Program  : DandD Version 1.0 Session  : Screening DCGLs - Building Occupancy Scenario Description :

Calculation of radionuclide-specific activity resulting in 25 mrem /yr Executed  : 03/25/99 at 22:40:53 NRC Report Occupancy Input Section Execution Options History file will be generated.

Implicit progeny doses will not be included with explicit parent.

Concentration data will be calculated.

Initial Radionuclide Activities Chain dpm/100cm^2 125Sb 44300.00 Code-Generated Radionuclide Activities Chain dpm/100cm*2 125Sb 4.4300E+004 125mTe 0.0000E+000 Variable Parameters v No parameters have been changed.

Occupancy Output Section 1

Maximum Annual TEDE This scenario started 0.00 year (s) from now l

and ran for 1.00 year (s).

The peak dose of 2.50E+001 TEDE (mrem) occurred 1.00 year (s) after license termination.

I

Pathway Component of Maximum Annual Dose Pathway TEDE (mrem) Percentage l

i External 2.37E+001 94.92 i Inhalation 1.11E+000 4.44 Ingestion 1.59E-001 0.64 Total 2.50E+001 100.00 Radionuclide Component of Maximum Annual Dose .

Radionuclide TEDE (mrem) Percentage

............................................. l I

125Sb 2.45E+001 98.02 125mTe 4.95E-001 1.98

_____________________________________________ i Total 2.50E+001 100.00 l l

l

i Program  : DandD Version 1.0 '

Session  :

Screening DCGLs - Building Occupancy Scenario Description :

Calculation in 25 mrem /yr of radionuclide-specific activity resulting i

Executed  : 03/25/99 at 22:43:16 NRC Report Occupancy Input Section Execution Options History file will be generated.

Implicit progeny doses will not be included with explicit parent. I Concentration data will be calculated. '

1 Initial Radionuclide Activities Chain dpm/100cm^2 134Cs 12750.00 Code-Generated Radionuclide Activities Chain dpm/100cm^2 134Cs 1.2750E+004 Variable Parameters No parameters have been changed.

Occupancy Output Section Maximum Annual TEDE This scenario started 0.00 year (s) from now and ran for 1.00 year (s).

The peak dose of license termination. 2.50E+001 TEDE (mrem) occurred 1.00 3 ear (s) after

r i

1 i

Pathway Component of Maximum Annual Dose Pathway TEDE (mrem) Percentage External 2.30E+001 92.10 Inhalation 1.05E+000 4.19

' Ingestion 9.2BE-001 3.71 Total 2.50E+001 100.00 Radionuclide Component of Maximum Annual Dose

.............................. i Radionuclide TEDE (mrem) Percentage 134Cs 2.50E+001 100.00 1

1 Total 2.50E+001 100.00 l

1

IL Il i

Program  : DandD Version 1.0-

? Session  : Screening DCGLs.- Building Occupancy Scenario

' Description :

Calculat' ion of radisnuclide-specific activity resulting in 25 mrem /yr Executed  : '03/25/99 at'22:44:06 NRC Report Occupancy. Input Section

^

Execution ~ Options History file will be generated. . .

Implicit progeny doses will not be included with explicit parent.

Concentration data will be calculated. '

a Initial Radionuclide' Activities -

Chain dpm/100cm^2 i

l 137Cs 28000.00 Code-Generated Radionuclide Activities

........................................ I Chain. 'dpm/100cm^2 r

137Cs. 2.8000E+004' i

137mBa. 0.0000E+000

' Variable Parameters No parameters have been changed.

Occupancy Output Section  ;

Maximum Annual TEDE

- This scenario started 0.00 year (s) from now

. and ran for 1.00 yea (s). - ' i The peak dose of 2.50E+001 TEDE (mrem) occurred 1.00 year (s) after license termination.

Pathway Component of Maximum Annual Dose

.............................. l Pathway TEDE (mrem) Percentage External 2.15E+001 86.13 Inhalation 1.85E+000 7.41 Ingestion 1.62E+000 6.47 Total 2.50E+001 100.00 Radionuclide Component of Maximum Annual Dose Radionuclide TEDE (mrem) Percentage 137Cs 3.48E+000 13.92 137mBa 2.15E+001 86.08 Total 2.50E+001 100.00 i l

l l

/

/

l k '* .

i J- Program.

i

DandD Version 1.0 Session  : Screening DCGLs - Building Occupancy Scenario' l Description ~:

Calculation of radionuclide-specific ~ activity resulting '

in 25 mrem /yr 1 Executed  : 03/25/99 at 22:44:49 NRC Report

t. .

Occupancy Input Section s

! Execution Options History file will be generated.

Implicit progeny doses will:not be included with explicit parent.

Concentration data will be calculated.

Initial'Radionuclide Activities

' Chain dpm/100cm^2 152Eu; 12700.00 Code-Generated Radionuclide Activities Chain dpm/100cm^2

-152Eu 1.2700E+004 152Gd 0.0000E+000 l

Variable Parameters No parameters have'been changed. i l

Occupancy Output Section Maximum Annual TEDE This ~ scenario started 0.00 year (s) from now and ran for 1.00' year (s).

The. peak dose of 2.50E+001 TEDE (mrem) occurred 1.00 year (s) after

. license termination.

r Pathway Component of Maximum Annual Dose Pathway TEDE (mrem) Percentage External 1.92E+001 76.70 Inhalation 5.73E+000 22.93 Ingestion 9.37E-002 0.38 Total 2.50E+001 100.00 Radionuclide Component of Maximum Annual Dose Radionuclide TEDE (mrem) Percentage 152Eu 2.50E+001 100.00 152Gd 8.98E-014 0.00

-Total 2.50E+001 100.00

Program  : DandD Version 1.0 Session  : Screening DCGLs - Building Occupancy Scenario Description :

Calculation of radionuclide-specific activity resulting in 25 mrem /yr Executed  : 03/25/99 at 22:46:07 NRC Report Occupancy Input Section Execution Options

.....n..............

History file will be generated.

Implicit progeny doses will not be included with explicit parent.

Concentration data will be calculated.

Initial Radionuclide Activities Chain dpm/100cm^2 154Eu 11470.00 Code-Generated Radionuclide Activities Chain dpm/100cm^2 154Eu 1.1470E+004 Variable Parameters No parameters have been changed.

Occupancy Output Section Maximum Annual TEDE This scenario started 0.00 year (s) from now and ran for 1.00 year (s).

The peak dose ~of 2.50E+001 TEDE (mrem) occurred 1.00 year (s) after license termination.

r h

Pathway Component.of Maximum Annual Dose Pathway-

=..........................................ge TEDE (mrem) Percenta External 1.83E+001 73.08 Inhalation 6.61E+000' 26.43 Ingestion 1.23E-001 0.49 Total 2.50E+001 100.00-Radionuclide Component of Maximum Annual Dose Radionuclide~ TEDE (mrem) Percentage 154Eu 2.50E+001 100.00 l

Total 2.50E+001 100.00

)

1 i

I i

l Program  : DandD Version 1.0 Session  : Screening DCGLs - Building Occupancy Scenario Description :

Calculation of radionuclide-specific activity resulting in 25 mrem /yr Executed  : 03/25/99 at 22:46:53 NRC Report Occupancy Input Section Execution Options History file will be generated.

Implicit progeny doses will not be included with e::plicit parent.

Concentration data will be calculated. ',

Initial Radionuclide Activities Chain dpm/100cm^2 155Eu 156000.00 Code-Generated Radionuclide Activities Chain dpm/100cm^2 155Eu 1.5600E+005 Variable Parameters No parameters have been changed.

Occupancy Output Section Maximum Annual TEDE This scenario started 0.00 year (s) from now I and ran for 1.00 year (s). .

I The peak dose of 2;50E+001 TEDE (mrem) o$ curred 1.00 year (s) after license termination.

7-c.

i I'

t..

! t f.

I l"

Pathway Component of

-Maximum Annual Dose

............................... 1 i

j' Pathway. TEDE (mrem) Percentage I

External 1.21E+001 48.32 Inhalation. 1.26E+001 50.64 Ingestion 2.60E-001 .1.04 Total 2.50E+001 100.00 Radionuclide^ Component of Maximum Annual Dose Radionuclide TEDE'(mrem) Percentage 155Eu- 2.50E+001 100.00 Total 2.50E+001 100.00 i

l i

I e

i i

1 t

/

Program  : DandD Version 1.0

-Session  : Screening DCGLs - Building Occupancy Scenario Description :

Calculation of radionuclide-specific activity resulting in 25 mrem /yr Executed  : 03/25/99 at 22:47:44 NRC Report Occupancy Input Section Execution Options History Cile will be generated.

Implicit progeny doses will not be included with explicit parent.

Concentration data will be calculated.

Initial Radionuclide Activities Chain dpm/100cm^2 2330 88.10 Code-Generated Radionuclide Activities l Chain dpm/100cm^2 2330 8.8100E+001 229Th 0.0000E+000 225Ra 0.0000E+000 225Ac 0.0000E+000 221Fr 0.0000E+000 217At 0.0000E+000 213Bi 0.0000E+000 213Po 0.0000E+000*

209T1 0.0000E+000 l 209Pb 0.0000E+000 Variable Parameters No parameters have been changed.

F s

Occupancy Output Section Maximum Annual TEDE This scenario started 0.00 year (s) from now and ran for 1.00 year (s).

The peak dose of 2.50E+001 TEDE (mrem) occurred 1.00 year (s) after license termination.

Pathway Component of Maximum Annual Dose Pathway TEDE (mrem) Percentage External 9.00E-005 0.00 Inhalation 2.50E+001 99.88 Ingestion 2.98E-002 0.12 Total 2.50E+001 100.00 Radionuclide Component of Maximum Annual Dose Radionuclide TEDE (mrem) Percentage 233U 2.50E+001 99.92 229Th 1.87E-002 0.07 225Ra 6.20E-005 0.00 225Ac 7.76E-005 0.00 221Fr 1.42E-007 0.00 217At 1.44E-009 0.00 213Bi 7.56E-007 0.00 213?o 0.00E+000 0.00 209T1 1.96E-007 0.00 209Pb 2.96E-009 0.00 Total 2.50E+001 100.00 1

l I

. i Program  : DandD Version 1.0 Session  : Screening DCGLs - Building Occupancy Scenario Description _:

Calculation of radionuclide-specific activity resulting in 25 mrem /yr z Executed  : 03/25/99 at 22:48:24 '

NRC Report i

Occupancy Input Section Execution Options History file will-be generated.

Implicit progeny doses will not be -included with explicit parent.

' Concentration data will be calculated.

' Initial Radionuclide Activities Chain dpm/100cm^2 234U 90.10, Code-Generated Radionuclide Activities Chain- dpm/100cma2 234U 9.0100E+001 230Th 0.0000E+000-226Ra- 0.0000E+000 222Rn 0.0000E+000 218Po 0.0000E+000 i 214Pb 0.0000E+000 218At ~0.0000E+000 214Bi 0.0000E+000 214Po 0.0000E+000 210Pb~ 0.0000E+000 l

~

210B1 0.0000E+000 210Po 0.0000E+000 l.

Variable Parameters No parameters'have been changed.

Occupancy Output Section Maximum Annual TEDE This scenario started 0.00 year (s) from now and ran for 1.00 year (s).

The peak dose of 2.50E+001 TEDE (mrem) occurred 1.00 year (s) after license termination.

Pathway Component of Maximum Annual Dose 1

Pathway TEDE (mrem) Percentage j

.....................--........---........... I External 9.45E-005 0.00 i 99.88 I Inhalation 2.50E+001 Ingestion 2.99E-002 0.12 Total 2.50E+001 100.00 Radionuclide Component of Maximum Annual Dose Radionuclide TEDE (mrem) Percentage 234U 2.50E+001 100.00 230Th 2.77E-004 0.00 226Ra 1.15E-009 0.00 222Rn 3.11E-014 0.00 218Po 6.99E-016 0.00 214Pb 2.01E-011 0.00 218At 0.00E+000 0.00 214Bi 1.12E-010 0.00 214Po 6.39E-015 0.00 210Pb 1.48E-011 0.00 I

21081 1.65E-013 0.00 210Po 2.35E-012 0.00 Total 2.50E+001 100.00

I

()

Program  : DandD Version 1.0 Session  : Screening DCGLs - Building Occupancy Scenario Description :

Calculation of radionuclide-specific activity resulting in 25 mrem /yr Executed  : 03/25/99 at 22:49:08 NRC Report Occupancy Input Section Execution Options History file will be generated.

Implicit progeny doses will not be included with explicit parent.

Concentration data will be calculated. l Initial Radionuclide Activities Chain dpm/100cm^2

........................................ I 235U 97.10 Code-Generated Radionuclide Activities

........................................ I Chain dpm/100cm^2 2350 9.7100E+001 231Th 0.0000E+000 231Pa 0.0000E+000 227Ac 0.0000E+000 223Fr 0.0000E+000 227Th 0.0000E+000 223Ra 0.0000E+000 219Rn 0.0000E+000 215Po 0.0000E+000 211Pb 0.0000E+000 21181 0.0000E+000 211Po 0.0000E+000 207T1 0.0000E+000 Variable Parameters No parameters have been changed.  !

1

)

Occupancy Output Section Maximum Annual TEDE This scenario started 0.00 year (s) from now and ran for 1.00 year (s).

The peak dose of 2.50E&001 TEDE (mrem) occurred 1.00 year (s) after license termination.

Pathway Compor4ent of Maximum Annual Dose I

Pathway TEDE (mrem) ge Percenta 1

External 2.27E-002 0.09 Inhalation 2.50E+001 99.79 Ingestion 3.04E-002 0.12 Total 2.50E+001 100.00 Radionuclide Component of  !

Maximum Annual Dose Radionuclide

..........................................ge TEDE (mrem) Percenta 2350 2.50E+001 99.98 231Th 2.84E-003 0.01 231Pa 2.74E-003 0.01 227Ac 1.50E-004 0.00 223Fr 1.50E-011 0.00 227Th 2.89E-007 0.00 223Ra 1.31E-007 0.00 219Rn 5.78E-010 0.00 215Po 1.84E-012 0.00 211Pb 6.75E-010 0.00 211Bi 4.83E-010 0.00 211Po 2.24E-013 0.00 207T1 3.95E-011 0.00 Total 2.50E+001 100.00

/

1

4 Program  : DandD Version 1.0 Session  : Screening DCGLs - Building Occupancy Scenario Description :

Calculation of radionuclide-specific, activity resulting in 25 mrem /yr >

Executed  : 03/25/99 at 22:49:52 NRC Report Occupancy Input Section Execution Options History file will be generated.

Implicit progeny doses will not be included with explicit parent.

Concentration data will be calculated.

Initial Radionuclide Activities Chain dpm/100cm^2 236U 95.20 Code-Generated Radionuclide Activities Chain dpm/100cm^2 236U 9.5200E+001 232Th 0.0000E+000 228Ra 0.0000E+000 228Ac 0.0000E+000 228Th 0.0000E+000 224Ra 0.0000E+000 220Rn 0.0000E+000 l 216Po 0.0000E+000 212Pb 0.0000E+000 212Bi 0.0000E+000 i l

212Po 0.0000E+000 208T1 0.0000E+000 '

Variable Parameters No parameters have been changed.

i' Occupancy Output Section Maximum Annual TEDE This scenario started 0.00 year (s) from now and ran for 1.00 year (s) .

The peak dose of 2.50E+001 TEDE (mrem) occurred 1.00 year (s) after license termination.

Pathway Component of Maximum Annual Dose Pathway TEDE (mrem) Percentage External 8.67E-005 0.00 Inhalation 2.50E+001 99.88 Ingestion 2.99E-002 0.12 Total 2.50E+001 100.00 Radionuclide Component of Maximum Annual Dose Radionuclide TEDE (mrem) Percentage 236U 2.50E+001 100.00 232Th 8.07E-009 0.00 228Ra 1.07E-012 0.00 228Ac 1.79E-013 0.00 228Th 5.57E-012 0.00 224Ra 5.19E-014 0.00 220Rn 3.93E-018 0.00 216Po 1.71E-019 0.00 212Pb 4.43E-015 0.00 212Bi 2.17E-015 0.00 212Po 0.00E+000 0.00 208T1 1.10E-014 0.00 Total 2.50E+001 100.00 1

Program  : DandD Version 1.0 Session  : Screening DCGLs - Building Occupancy Scenario Description :

Calculation of radionuclide-specific activity resulting in 25 mrem /yr Executed  : 03/25/99 at 22:55:39 NRC Report Occupancy Input Section Execution Options History file will be generated.

Implicit progeny doses will not be included with explicit parent.

Concentration data will be calculated.

Initial Radionuclide Activities Chain dpm/100cm^2 238U 100.50 Code-Generated Radionuclide Activities C'hain dpm/100cm^2 238U 1.0050E+002 234Th 0.0000E+000 234mPa 0.0000E+000 234Pa 0.0000E+000 234U 0.0000E+000 230Th 0.0000E+000 226Ra 0.0000E+000 222Rn 0.0000E+000 218Po 0.0000E+000 214Pb 0.0000%+000 218At- 0.0000E+000 214Bi 0.0000E+000 214Po 0.0000E+000 210Pb 0.0000E+000 210Bi 0.0000E+000 210Po 0.0000E+000 Variable Parameters No parameters have been changed.

i l

Occupancy Output Section Maximum Annual TEDE This scenario started 0.00 year (s) from now and ran for:1.00 year (s).

The peak dose of.. 2.50E+001;TEDE (mrem) occurred 1.00 year (s) after license termination.

Pathway Component' of Maximum Annual Dose-

-Pathway TEDE (mrem) Percentage

~ External 3.55E-003 0.01 Inhalation 2.49E+001 99.86 Ingestion 3.14E-002 0.13 Total' 2.50E+001 100.00 Radionuclide Component of Maximum Annual Dose l Radionuclide TEDE (mrem) Percentage 2380- 2.50E+001 99.95 234Th ~9.19E-003 0.04 234mPa '1.95E-003 0.01 234Pa 4.70E-004 0.00 234U 3.28E-005 0.00 230Th 2.23E-010 0.00 226Ra 1.13E-015' O.00 222Rn 1.97E-020 0.00 218Po 4.43E-022 0.00 214Pb 1.27E-017 0.00  !

218At 0.00E+000 0.00

- 214Bi 7.10E-017 0.00 214Po 4.05E-021 0.00 210Pb 1.19E-015 0.00 210Bi~ 7.51E-018 0.00 210Po 8.52E-016 0.00 Total 2.50E+001 100.00 1-s

i Program  : DandD Version 1.0 Session  : Screening DCGLs - Building Occupancy Scenario Description :

Calculation of radionuclide-specific activity resulting in 25 mrem /yr Executed  : 03/25/99 at 22:56:37 i NRC Report i I

Occupancy Input Section Execution Options

• History file will be generated.

Implicit progeny doses will not be included with explicit parent.

' Concentration data will be calculated.

• Initial Radionuclide Activities -

Chain dpm/100cm^2

............ .......................... i 238Pu 30.40 Code-Generated Radionuclide Activities Chain dpm/100cm^2 238Pu 3.0400E+001 234U 0.0000E+000 230Th 0.0000E+000 226Ra 0.0000E+000 222Rn 0.0000E+000 218Po 0.0000E+000 214Pb 0.0000E+000 218At 0.0000E+000 214Bi 0.0000E+000 214Po 0.0000E+000 1

210Pb 0.0000E+000

! 210Bi 0.0000E+000 i

210Po 0.0000E+000

Variable Parameters

! No parameters have been changed.

/

l 1 L

Occupancy Output Section Maximum Annual TEDE This scenario started 0.00 year (s) from now and ran for 1.00 year (s).

The peak dose of 2.50E+001 TEDE (mrem) occurred 1.00 year (s) after license termination.

Pathway Component of Maximum Annual Dose Pathway TEDE (mrem) Percentage External 3.56E-005 0.00 Inhalation 2.49E+001 99.55 Ingestion 1.13E-001 0.45 Total 2.50E+001 100.00 Radionuclide Component of Maximum Annual Dose Radionuclide TEDE (mrem) Percentage 238Pu 2.50E+001 100.00 2340 1.19E-005 0.00 230Th 8.82E-011 0.00 226Ra 2.74E-016 0.00 222Rn 7.31E-021 0.00 218Po 1.64E-022 0.00 214Pb 4.72E-018 0.00 218At 0.00E+000 0.00 214Bi 2.63E-017 0.00 214Po 1.50E-021 0.00 210Pb 2.90E-018 0.00 21081 2.87E-020 0.00 210Po 3.69E-019 0.00 Total 2.50E+001 100.00

/

+-

I i

I 1

Program.  :-DandD Version 1.0 Session.  : Screening DCGLs - Building Occupancy Scenario Description.:

Calculation of radionuclide-specific activity resulting in 25 mrem /yr Executed  : 03/25'/99 at 22:57: 16 NRC Report >

Occupancy Input Section

)

Execution Options

. History file will be generated.  !

Implicit progeny doses will not be included with explicit parent.

Concentration data will be calculated.

Initial Radionuclide Activities Chain dpm/100cm^2 23'9Pu 27.70 Code-Generated Radionuclide Activities Chain dpm/100cm^2 239Pu 2.7700E+001

.2350 0.0000E4000 1231Th 0.0000E+000 231Pa 0.0000E+000 227Ac 0.0000E+000 223Frf .0.0000E+000 227Th 0.0000E+000 223Ra 0.0000E+000 219Rn 0.0000E+000 215Po 0.0000E+000 211Fb- 0.0000E+000 21181- 0.0000E+000 211Po 0.0000E+000

-207T1 0.0000E+000

)

Variable Parameters No parameters have.been changed. t

Occupancy Output Section Maximum Annual TEDE

.This scenario started 0.00 year (s) from now and ran for 1.00 year (s).

.The peak dose of. 2.50E+001 TEDE (mrem) occurred 1.00 year (s) after license termination.

Pathway Component of Maximum Annual Dose Pathway TEDE (mrem) Percentage External 1.43E-005 0.00 Inhalation 2.49E+001 99.54 Ingestion- 1.15E-001 0.46 Tecal 2.50E+001 100.00 Radionuclide Component of Maximum Annual Dose Radionuclide TEDE (mrem) Percentage 239Pu 2.50E+001 100.00 235U 3.52E-009 0.00 231Th 3.98E-013 0.00 231Pa 2.56E-013 0.00 227Ac 1.05E-014 0.00 223Fr 1.05E-021 0.00 227Th- 1.91E-017 0.00 223Ra' -8.26E-018 0.00 219Rn 3.66E-020 0.00 215Po 1.17E-022 0.00 211Pb 4.28E-020 0.00 21181- 3-06E-020

. 0.00 211Po 1.42E-023 0.00 207T1 2.50E-021 0.00 Total 2.50E+001 100.00

Program  : DandD Version 1.0 Session  : Screening DCGLs - Building Occupancy Scenario Description :

Calculation of radionuclide-specific activity resulting in 25 mrem /yr Executed  : 03/25/99 at 22:57: 57 NRC Report 1

1 1

Occupancy Input Section I Execution Options History file will be generated.

Implicit progeny doses will not be included with explicit parent.  !

Concentration data will be calculated.

Initial Radionuclide Activities Chain dpm/100cma 2 240Pu 27.70 i

Code-Generated Radionuclide Activities Chain dpm/100cm^2 240Pu 2.7700E+001 2360 0.0000E+000 <

232Th 0.0000E+000  !

228Ra 0.0000E+000  ;

228Ac 0.0000E+000 228Th 0.0000E+000 224Ra 0.0000E+000 220Rn 0.0000E+000 216Po 0.0000E+000 212Pb 0.0000E+000 212B1 0.0000E+000 212Po 0.0000E+000 208T1 0.0000E+000 Variable Parameters No parameters have been changed.

1 l

Occupancy Output Section I

l Maximum Annual TEDE This scenario started 0.00 year (s) from now j and ran for 1.00 year (s). '

The peak dose of 2.50E+001 TEDE (mrem) occurred 1.00 year (s) after license termination.  ;

Pathway Component of Maximum Annua 3 Dose Pathway TEDE (mrem) Percentage External 3.12E-005 0.00 Inhalation 2.49E+001 99.54 1 Ingestion 1.15E-001 0.46 Total 2.50E+001 100.00 Radionuclide Component of Maximum Annual Dose Radionuclide TEDE (mrem) Percentage 240Pu 2.50E+001 100.00 236U 1.08E-007 0.00 f 232Th 2.32E-017 0.00 228Ra 2.34E-021 0.00 228Ac 3.91E-022 0.00 228Th 9.14E-021 0.00 224Ra 9.53E-023 0.00

)

1 220Rn 7.22E-027 0.00 i 216Po 3.14E-028 0.00 212Pb 9.73E-024 0.00 212Bi 4.76E-024 0.00 212Po 0.00E+000 0.00 208T1 2.42E-023 0.00 Total 2.50E+001 100.00

Program  : DandD Version 1.0 Session  : Screening DCGLs - Building Occupancy Scenario Description :

Calculation of radionuclide-specific activity resulting in 25 mrem /yr Executed  : 03/25/99 at 22:59:13 NRC Report i

I Occupancy Input Section Execution Options History file will be generated. l Implicit progeny doses will not be included with explicit parent.

Concentration data will be calculated. l Initial Radionuclide Activities j Chain dpm/100cm^2 241Pu 1415.00 Code-Generated Radionuclide Activities Chain dpm/100cm^2 241Pu 1.4150E+003 241Am 0.0000E+000 2370 0.0000E+000 237Np 0.0000E+000 233Pa 0.0000E+000 2330 0.0000E+000 229Th 0.0000E+000 225Ra 0.0000E+000 225Ac 0.0000E+000 221Fr 0.0000E+000 217At 0.0000E+000 213Bi 0.0000E+000 213Po 0.0000E+000 209T1 0.0000E+000 209Pb 0.0000E+000 Variable Parameters t No parameters have been changed.

I e

e-Occupancy Output Section Maximum Annual TEDE This scenario started 0.00 year (s) from now and ran for 1.00 year (s).

The peak dose of 2.50E+001 TEDE (mrem) occurred 1.00 year (s) after license termination.

Pathway Component of Maximum Annual Dose Pathway TEDE (mrem) Percentage External 5.30E-005 0.00 Inhalation' 2.49E+001 99.54 Ingestion 1.15E-001 0.46 Total 2.50E+001 100.00 Radionuclide Component of Maximum Annual Dose Radionuclide TEDE (mrem) Percentage 1

241Pu 2.40E+001 95.84 241Am 1.04E+000 4.16 2370 6.66E-006 0.00 237Np 1.43E-007 0.00 233Pa 2.81E-011 0.00 233U 2.73E-014 0.00 229Th 1.93E-017 0.00 225Ra 3.16E-020 0.00 225Ac 8.65E-020 0.00 221Fr 1.58E-022 0.00 217At 1.61E-024 0.00 21381 8.42E-022 0.00 213Po 0.00E+000 0.00 l 209T1 2.18E-022 0.00 209Pb 3.30E-024 0.00 Total 2.50E+001 100.00

/

Program.  : DandD Version 1.0 Session  : Screening DCGLs - Building Occupancy Scenario.

Description :

Calculation of radionuclide-specific activity resulting in 25 mrem /yr 9

Executed  : 03/25/99 at 23:00:02 NRC Report i

Occupancy Input Section 1 Execution Options

' History file will be generated.

Implicit progeny doses will not be included with explicit parent.

Concentration data will be calculated.

Initial-Radionuclide Activities Chain' dpm/100cm^2 242Pu 28.90 Code-Generated Radionuclide Activities Chain dpm/100cm^2-242Pu 2.8900E+001 238U- 0.0000E+000 234Th 0.0000E+000 234mPa 0.0000E+000 234Pa 0.0000E+000

-2340 0.0000E+000 230Th 0.0000E+000

-226Ra' O.0000E+000 222Rn- =0.0000E+000

~218Po 0.0000E+000 214Pb 0;0000E+000 218At 0.0000E+000 l 214B1- 0.0000E+000 I ~214 Pol 0.0000E+000 l 210Pb 0.0000E+000 210Bi' O.0000E+000 Variable Parameters No parameters have been changed.

l

Occupancy Output Section Maximum Annual TEDE This scenario started 0.00 year (s) from now and ran for 1.00 year (s).

The peak dose of 2.50E+001 TEDE (mrem) occurred 1.00 year (s) after license termination.

Pathway Component of Maximum Annual Dose Pathway TEDE (mrem) Percentage External 2.70E-005 0.00 Inhalation 2.49E+001 99.55 Ingestion 1.14E-001 0.45 Total 2.50E+001 100.00 Radionuclide Component of Maximum Annual Dose Radionuclide TEDE (mrem) Percentage 242Pu 2.50E+001 100.00 238U 5.57E-010 0.00 234Th 1.88E-013 0.00 234mPa 3.98E-014 0.00 234Pa 9.61E-015 0.00 234U 4.50E-016 0.00 230Th 0.00E+000 0.00 226Ra 1.29E-020 0.00 222Rn 0.00E+000 0.00 218Po 0.00E+000 0.00 214Pb 0.00E+000 0.00 218At 0.00E+000 0.00 214Bi 0.00E+000 0.00 214Po 0.00E+000 0.00 210Pb 2.16E-020 0.00 210Bi 2.47E-022 0.00 Total 2.50E+001 100.00

i Program  : DandD Version 1.0 Session  : Screening DCGLs - Building Occupancy Scenario Description :

Calculation in 25 mrem /yr of radionuclide-specific activity resulting Executed  : 03/25/99 at 23:00:51 NRC Report I

l

~

I Occupancy Input Section Execution Options i

.................... )

History file will be generated.

Implicit progeny doses will not be included with explicit parent.

Concentration data will be calculated.

Initial Radionuclide Activities Chain dpm/100cm^2 241Am 26.80 Code-Generated Radionuclide Activities Chain dpm/100cm^2 241Am 2.6800E+001 237Np 0.0000E+000 233Pa 0.0000E+000 233U 0.0000E+000 229Th 0.0000E+000 225Ra 0.0000E+000 225Ac 0.0000E+000 221Fr 0.0000E+000 217At 0.0000E+000 21381 0.0000E+000 213Po 0.0000E+000 209T1 0.0000E+000 209Pb 0.0000E+000 Variable Parameters No parameters have been changed.

E Occupancy Output Section Maximum Annual TEDE'

~This scenario started 0.00 year (s) from now and ran for 1.00 year (s).

The peak doso of- 2.50E+001 TEDE (mrem) occurred 1.00 year (s) after license termination.

Pathway Component of Maximum Annual Dose Pathway TEDE (mrem) Percentage External 1.03E-003 0.00 Inhalation- 2.49E+001 99.54

-Ingestion 1.14E-001 0.46 Total 2.50E+001 100.00 Radionuclide Component of Maximum Annual Dose Radionuclide TEDE (mrem) Percentage 241Am 2.50E+001 100.00 237Np 4.93E-006 0.00 233Pa 1.05E-009 0.00 233U 1.33E-012 0.00 229Th 4.60E-016 0.00 225Ra 1.34E-018 0.00 225Ac 1.56E-018 0.00 221Fr 2.86E-021 0.00  !

217At 2.91E-023 0.00 213Bi 1.52E-020 0.00 213Po 0.00E+000 0.00 209T1 3.94E-021 0.00 l 209Pb 5.96E-023 0.00

)

Total 2.50E+001 100.00

Program  : DandD Version 1.0 Session  : Screening DCGLs - Building Occupancy Scenario Description :

Calculation in 25 mrem /yr of radionuclide-specific activity resulting Executed  : 03/25/99 at 23:02:02 NRC Report Occupancy Input Section Execution Options ~

History file will be generated.

Implicit progeny doses will not be included with explicit parent.

Concentration data will be calculated. ,

i Initial Radionuclide Activities '

Chain dpm/100cm^2 243Cm 39.20 Code-Generated Radionuclide Activities Chain dpm/100cm^2 i

243Cm 3.9200E+001

-243Am 0.0000E+000 239Np 0.0000E+000 239Pu 0.0000E+000 2350 l 0.0000E+000 j 231Th- 0.0000E+000 I 231Pa 0.0000E+000 227Ac 0.0000E+000 '

223Fr 0.0000E+000 227Th 0.0000E+000 '

Variable Parameters No parameters have been changed.

t

/

n' e

Occupancy Output Section Maximum Annual TEDE This scenario started 0.00 year (s) from now and ran for 1.00 year (s).

The peak dose of 2.50E+001 TEDE (mrem) occurred 1.00 year (s) after license termination.

Pathway Component of Maximum Annual Dose Pathway TEDE (mrem) Percentage External 6.79E-003 0.03 Inhalation 2.49E+001 99.52 )

Ingestion 1.14E-001 0.45 Total 2.50E+001 100.00 i

Radionuclide Component of Maximum Annual Dose '

Radionuclide TEDE (mrem) Percentage 243Cm 2.50E+001 100.00 243Am 4.05E-006 0.00 239Np 1.02E-009 0.00 239Pu 5.05E-004 0.00 235U 4.74E-014 0.0J 231Th 5.34E-018 0.00 231Pa 2.58E-018 0.00 227Ac 6.96E-020 0.00 223Fr 7.00E-027 0.00 227Th 1.49E-022 0.00 Total 2.50E+001 100.00

/

\

l Program  : DandD Version 1.0 Session  : Screening DCGLs - Building Occupancy Scenario Description :

Calculation of radionuclide-specific activity resulting in 25 mrem /yr s Executed  : 03/25/99 at 23:02:40 NRC Report i

Occupancy Input Section Execution Options  !

History file will be generated.

Implicit progeny doses will not be included with explicit parent.

Concentration data will be calculated.

Initial Radionuclide Activities Chain dpm/100cm^2

........................................ i I

244Cm 48.90 i Code-Generated Radionuclide Activities I Chain dpm/100cm^2 244Cm 4.8900E+001 240Pu 0.0000E+000 236U 0.0000E+000 232Th 0.0000E+000 228Ra 0.0000E+000 228Ac 0.0000E+000 228Th 0.0000E+000 224Ra 0.0000E+000 220Rn 0.0000E+000 216Po 0.0000E+000 212Pb 0.0000E+000 212Bi 0.0000E+000 222Po 0.0000E+000 208T1 0.0000E+000 Variable Parameters No parameters have been changed.

l i

1 1

l

Occupancy Output Section Maximum Annual TEDE This' scenario started 0.00 year (s) from now and ran for 1.00 year (s).

The peak dose of 2.50E+001 TEDE (mrem) occurred 1.00 year (s) after license termination.

Pathway Component of Maximum Annual Dose Pathway TEDE (mrem) Percentage External 5.91E-005 0.00 Inhalation 2.49E+001 99.55 Ingestion 1.13E-001 0.45 Total 2.50E+001 100.00 Radionuclide Component of Maximum Annual Dose Radionuclide TEDE (mrem) Percentage 244Cm 2.50E+001 99.99 240Pu 2.31E-003 0.01 236U 6.65E-012 0.00 232Th 1.10E-021 0.00 228Ra 2.50E-025 0.00 228Ac 4.18E-026 0.00 228Th 1.14E-023 0.00 224Ra 0.00E+000 0.00 220Rn 0.00E+000 0.00 216Po 0.00E+000 0.00 212Pb 6.73E-027 0.00 212Bi 3.29E-027 0.00 212Po 0.00E+000 0.00

, 208T1 1.67E-026 0.00 Total 2.50E+001 100.00 i

l

[

l Program  : DandD Version 1.0 Session  : Screening DCGLs - Residential Scenario Description :

Calculation of radionuclide-specific activity resulting in 25 mrem /yr Executed  : 03/24/99 at 19:03:17 NRC Report I

Residential Input Section I

Execution Options History file will be generated. )

Implicit progeny doses will not be included with explicit parent.

Concentration data will be calculated.

Initial Radionuclide Activities Chain pCi/ gram 3H 78.86 Code-Generated Radionuclide Activities Chain pCi/ gram I

3H 7.8860E+001 )

Variable Parameters No parameters have been changed.

Residential Output Section l

Maximum Annual TEDE This scenario started 0.00 year (s) from now and ran for 1000.00 year (s).

The peak dose of 2.50E+001 TEDE (mrem) occurred 1.00 year (s) after license termination.

Pathway Component of Maximum Annual Dose Pathway TEDE (mrem) Percentage External 0.00E+000 0.00 Inhalation 3.07E-007 0.00 Agricult. 2.41E+001 96.36 Soil 6.95E-005 0.00 Drinking 4.76E-001 1,91 Irrigated 4.22E-001 1.69 Aquatic 1.00E-002 0.04 Total 2.50E+001 100.00 Radionuclide Component of Maximum Annual Dose Radionuclide TEDE (mrem) Percentage 3H 2.50E+001 100.00 Total 2.50E+001 100.00 1

m_

i 9

Program  : DandD Version 1.0

. Session.  :: Screening DCGLs - Residential, Scenario Description _:

Calculation of radionuclide-specific activity resulting in 25 mrem /yr.

Executed  : 03/24/99 at 19:06:52..

NRC Report Residential Input Section Execution Options History file will be generated.

Implicit progeny doses will not be included with explicit parent.

Concentration data will be calculated, t

1 Initial Radionuclide Activities <'

Chain pCi/ gram i

14C 3.87 Code-Generated Radionuclide Activities Chain: pC1/ gram.

14C 3.8700E+000 Variable Parameters No parameters have been changed.

Residential Output Section Maximum Annual TEDE

.............................. I This scenario started 0.00 year (s) from now and ran for 1000.00 year (s). l i

i The peak dose of .2.50E+001 TEDE (mrem) occurred 5.00 year (s) after license termination. ' j l

i

Pathway Component of Maximum Annual Dose Pathway

...........................................ge TEDE (mrem) Percenta External 2.04E-006 0.00 Inhalation 3.99E-008 0.00 Agricult. 3.71E-002 0.15 Soil 9.18E-006 0.00 Drinking 2.23E-001 0.89 Irrigated 3.15E+000 12.59 Aquatic 2.16E+001 86.37 Total 2.50E+001 100.00 Radionuclide Component of Maximum Annual Dose Radionuclide

...........................................ge TEDE (mrem) Percenta 14C 2.50E+001 100.00 Total 2.50E+001 100.00 1

I I

/

f Program.  : DandD Version 1.0 Session.  : Screening DCGLs - Residential Scenario Description :

Calculation.of radionuclide-specific activity resulting in 25 mrem /yr Executed  : 03/24/99 at 19:08:19 NRC Report Residential Input Section Execution Options History file will be generated.

Implicit progeny doses will not be included with explicit parent. j Concentration data will be calculated. I Initial Radionuclide Activities Chain pCi/ gram 55Fe 9469.70 Code-Generated Radionuclide Activities Chain pCi/ gram 55Fe' 9.4697E+003 I i

Variable Parameters No parameters have been changed.

l Residential Output Section Maximum Annual TEDE This scenario started 0.00 year (s) from now and ran for 1000.00 year (s).

The peak dose of 2.50E+001 TEDE (mrem) occurred 1.00 year (s) after license termination.

Pathway Component of Maximum Annual' Dose Pathway TEDE (mrem) Percentage External 0.00E+000 0.00 Inhalation 1.49E-003 0.01 Agricult. 2.48E+001 99.20 Soil 7.17E-002 0.29 Drinking 2.76E-003 0.01 Irrigated 7.28E-003 0.03 Aquatic 1.16E-001 0.47 Total 2.50E+001 100.00 Radionuclide Component of Maximum Annual Dose Radionuclide TEDE (mrem) Percentage 55Fe 2.50E+001 100.00 Total 2.50E+001 100.00

l l'

i Program  : DandD Version 1.0

' Session  :-Screening DCGLs'- Residential Scenario

. Description :

Calculation of radionuclide-specific activity resulting

'in 25 mrem /yr Executed  : 03/24/99 at 19:09:48 NRC Report i

Residential Input Section

. Execution Options History file will be generated.

Implicit progeny. doses will not be included with' explicit parent.

Concentration data will be calculated.

4 Initial Radionuclide Activities Chain pCi/ gram 60Co 3.64 Code-Generated Radionuclide Activities Chain .pci/ gram 60Co 3.6400E+000 l Variable Parameters No parameters have been changed.

1 j ' Residential Output Section Maximum Annual TEDE This scenario started 0.00 year (s) from now and ran for 1000.00 year (s).

The peak dose of. 2.50E+001 TEDE (mrem) occurred 1.00 year (s) after license termination.

y Pathway Component of Maximum Annual Dose

. Pathway TEDE (mrem) Percentage External 2.26E+001~ 90.28 Inhalation 4.77E-005 0.00 Agricult. 2.43E+000 9.71 Soil 1.30E-003 0.01 Drinking 6.50E-006- 0.00

.. Irrigated - 2.43E-005 0.00-Aquatic 4.52E-005 0.00 Total 2.50E+001- 100.00 Radionuclide_ Component of Maximum Annual Dose.

.............................. 1 Radionuclide TEDE (mrem) Percentage 60Co 2.50E+001 100.00 Total 2.50E+001- 100.00

Program  : DandD Version 1.0 Session  : Screening DCGLs - Residential Scenario Description :

Calculation of radionuclide-specific activity resulting in 25 mrem /yr Executed  : 03/24/99 at 19:11:49 NRC Report Residential Input Section Execution options History file will be generated.

Implicit progeny doses will not be included with explicit parent.

Concentration data will be calculated, i

i Initial Radionuclide Activities >

Chain pCi/ gram 59Ni 4098.36 Code-Generated Radionuclide Activities Chain pCi/ gram 1

I 59Ni 4.0984E+003 Variable Parameters No parameters have been changed.

l Residential Output Section Maximum Annual TEDE This scenario started 0.00 year (s) from now and ran for 1000.00 year (s).

The peak dose of 2.50E+001 TEDE (mram) occurred 1.00 year (s) after license termination. '

i

Pathway-Component of.

i Maximum Annual Dose Pathway TEDE (mrem) Percentage External 0.00E+000- 0.00 Inhalation 6.82E-004 0.00 Agricult.' 2.44E+001 97.71' Soil l'22E-002

. 0.05

. Drinking- 9.73E-002 0.39 Irrigated 2.57E-001 1.03 Aquatic 2.05E-001 0.82 l

. Total. 2.50E+001 100.00 Radionuclide Component of Maximum Annual Dose Radionuclide TEDE (mrem) _ Percentage 59Ni 2.50E+001- 100.00 Total- 2.50E+001 100.00 1

l l

f l

/

Program  : DandD Version 1.0 Session  : Screening DCGLs - Residential Scenario Description :

Calculation of radionuclide-specific activity resulting in 25 mrem /yr Executed  : 03/24/99 at 19:13:31 NRC Report i

i Residential Input Section Execution Options History file will be generated.

Implicit progeny doses will not be included with explicit parent.

Concentration data will be calculated.

Initial Radionuclide Activities 1 i

1 Chain pCi/ gram 63Ni 1497.01 Code-Generated Radionuclide Activities Chain pCi/ gram 63Ni 1.4970E+003 Variable Parameters No parameters have been changed.

Residential Output Section  ;

i l Maximum Annual TEDE l

This scenario started 0.00 year (s) from now and ran for 1000.00 year (s).

The peak dose of 2.50E+001 TEDE (mrem) occurred 1.00 year (s) after license termination.

I i

b

Pathway Component of Maximum Annual Dose Pathway TEDE (mrem) Percentage External 0.00E+000 0.00 Inhalation 5.79E-004 0.00 Agricult. 2.44E+001 97.72 Soil 1.22E-002 0.05 Drinking 9.73E-002 0.39 Irrigated 2.56E-001 1.02 Aquatic 2.05E-001 0.82 Total 2.50E+001 100.00 Radionuclide Component of Maximum Annual Dose Radionuclide TEDE (mrem) Percentage 63Ni 2.50E+001 100.00 Total 2.50E+001 100.00

Program  : DandD Version 1.0-Session  : Screening DCGLs - Residential Scenario

~

Description :-

Calculation of:radionuclide-specific activity resulting-in 25 mrem /yr Executed  : 03/24/99 at 19:15:20 NRC Report Residential Input Section Execution Options History file will'be generated.

Implicit progeny doses will not be included with explicit parent.

Concentration data will be calculated.

Initial Radionuclide Activities

-Chain pCi/ gram 90Sr. 0.42 Code-Generated Radionuclide Activities Chain pCi/ gram 90Sr- 4.2090E-001 90Y 0.0000E+000 Variable Parameters No parameters have been changed.

Residential Output Section Maximum Annual TEDE

.This scenario started 0.00 year (s) from now

.and ran for 1000.00. year (s).

The peak dose of 2.50E+001 TEDE (mrem) occurred 1.00 year (s) after license termination.

l l

l l

1 I Pathway Component of Maximum Annual Dose

. Pathway

~

TEDE (mrem) Percentage' l

External- '4.61E-003 0.02 Inhalation 3.37E-005 0.00 Agricult. 2.50E+001 99.75 Soil 9.01E-004 0.00 Drinking ,9.80E-003 0.04 Irrigated. 3.71E-002 0.15 Aquatic 9.99E-003 0.04 Total-- 2.50E+001 100.00 Radionuclide Component of

' Maximum Annual' Dose Radionuclide TEDE (mrem) Percentage

.................--aa==

90Sr 2.39E+001 95.63 90Y 1.09E+000- 4.37 Total 2.50E+001 100.00 l

1 l

1 1 i

l

?~

l Program  : DandD Version 1.0 Session ~  : Screening DCGLs - Residential Scenario

Description's f l

Calculation of radionuclide-specific activity resulting i in 25 mrem /yr l Executed.  : 03/24/99 at '19:16:53 NRC Report Residential Input Section l

l Execution Options -

History file will be generated.

Implicit progeny doses will not be' included with explicit parent.

l Concentration data will be calculated.

i Initial Radionuclide Activities ,$

, Chain pCi/ gram l ........................................

94Nb 1.43 Code-Generated Radionuclide Activities Chain pCi/ gram

'94Nb 1.4290E+000 l

Variable Parameters No parameters have been changed.

Residential Output Section Maximum Annual TEDE This scenario started 0.00 year (s) from now and ran for 1000.00 year (s).

l }

l The peak dose of 2.50E+001 TEDE (mrem) occurred 3.00 year (s) after L license termination.

l-1 1'

L L

I i

Pathway Component of Maximum Annual Dose Pathway TEDE (mrem) Percentage External 3.21E-001 1.29 Inhalation 1.99E-006 0.00 Agricult. 1.38E-002' O.06 Soil 7.87E-006 0.00 Drinking 7.72E-001 3.09 Irrigated 2.06E+001 82.55 Aquatic 3.25E+000 13.02 Total 2.50E+001 100.00 Radionuclide Component of Maximum Annual Dose Radionuclide TEDE (mrem) Percentage 94Nb 2.50E+001 100.00 Total 2.50E+001 100.00 2

1 i

I l.

4 Program  : DandD Version 1.0 '

Session  : Screening DCGLs - Residential Scenario Description :

Calculation of radionuclide-specific activity resulting inL25 mrem /yr Executed 2 03/24/99 at.19:18:20 NRC Report.

Residential Input Section i

Execution Options History file will be generated.

Implicit progeny doses will not be included with explicit parent.

Concentration data will be calculated.

Initial Radionuclide Activities Chain pCi/ gram 125Sb- 25.54 Code-Generated Radionuclide Activities Chain pCi/ gram 125Sb 2.5536E+001 125mTe 0.0000E+000 Variable Parameters No parameters have been changed.

Residential Output Section Maximum Annual TEDE L ..............................

This scenario started 0.00 year (s) from now  !

and ran for 1000.00 year (s).  !

The peak dose of 2.50E+001 TEDE-(mrem) occurred 1.00 year (s) after license termination.

t

Pathway Component of Maximum Annual Dose

.............................. 1 Pathway TEDE (mrem) Percentage External 2.44E+001 97.60 Inhalation 1.94E-005 0.00 (

Agricult. 5.99E-001 2.40 I Soil 1.11E-003 0.00 Drinking 1.46E-006 0.00 l Irrigated 9.47E-007 0.00 Aquatic 1.23E-005 0.00 Total 2.50E+001 100.00 Radionuclide Component of Maximum Annual Dose Radionuclide TEDE (mrem) Percentage

)

...............................--............ i i

125Sb 2.48E+001 99.36 l 125mTe i 1.61E-001 0.64

_____________________________________________ i Total  ;

2.50E+001 100.00

l l

Program  : DandD Version 1.0 Session  : Screening DCGLs - Residential Scenario

' Description :

Calculation of radionuclide-specific activity resulting in 25 mrem /yr ,

Executed  : 03/24/99 at 19:22:11 NRC Report i

Residential Input Section Execution Options History file will be generated.

Implicit progeny doses will not be included with explicit parent.

Concentration data will be calculated.

Initial Radionuclide Activities Chain pCi/ gram 134Cs 1.75 Code-Generated Radionuclide Activities Chain pCi/ gram 134Cs 1.7540E+000 Variable Parameters No parameters have been changed.

Residential Output Section Maximum Annual TEDE This scenario started 0.00 year (s) from now and ran for 1000.00 year (s).

The peak dose of 2.50E+001 TEDE (mrem) occurred 3.00 year (s) after license termination.

l Pathway Component of i

Maximum Annual Dose '

Pathway TEDE (mrem) Percentage External 8.79E-001 3.52 Inhalation 6.75E-007 0.00 Agricult. 1.70E-001 0.68 Soil 2.23E-004 0.00 Drinking 4.88E-001 1.95 Irrigated 2.88E+000 11.53 Aquatic 2.06E+001 82.32 Total 2.50E+001 100.00 Radionuclide Component of Maximum Annual Dose Radionuclide TEDE (mrem) Percentage j

i l

134Cs 2.50E+001 100.00 Total 2.50E+001 100.00  !

l l

W..

i Program ~  : DandD Version-1.0'

-Session  : Screening DCGLs - Residential Scenario Description :

Calculation of radionuclide-specific activity resulting in 25 mrem /yr .

Executed  : 03/24/99 at 19:23:51 NRC Report '

Residential Input Section

. Execution Options .

History file will be generated.

Implicit progeny doses will not be included with explicit parent.

Concentration data will be calculated.

t Initial Radionuclide Activities , 3 Chain pCi/ gram 137Cs 0.88 Code-Generated Radionuclide Activities Chain pC1/ gram l

.137Cs 0.8340E-001-

137mBa 0.0000E+000 Variable Parameters .

No parameters have been changed. 1 i

Residential Output Section s

Maximum Annual TEDE This scenario started 0.00 year (s) from now and ran for 1000.00 year (s).  ;

Th'e peak dose of 2(50E+001 TEDE (mrem) occurred 6.00 year (s) after

. license termination.

i l

l

. . l Pathway Component of j

Maximum Annual Dose Pathway

...........................................ge TEDE (mrem) Percenta External 1.22E-001 '0.49

. Inhalation 1.63E-007 0.00 Agricult. 4.73E-002 0.19 Soil 5.84E-005 0.00 Drinking ~4.96E-001 1.99 Irrigated 3.39E+000 13.56 Aquatic 2.09E+001 83.78 Total .2.50E+001 100.00 Radionuclide Component of Maximum Annual Dose Radionuclide TEDE (mrem) Percentage 137Cs 2.49E+001 99.51 137mBa -1.22E-001 0~ 49 {

Total 2.50E+001 100.00 I

l l

4 i

/

Program  : DandD Version 1.0 Session  : Screening DCGLs - Residential Scenario Description :

Calculation of radionuclide-specific activity resulting in 25 mrem /yr Executed  : 03/24/99 at 19:26:14 NRC Report Residential Input Section Execution Options History file will be generated.

Implicit progeny doses will not be included with explicit parent.

Concentration data will be calculated.

Initial Radionuclide Activities Chain pCi/ gram 152Eu 8.65 Code-Generated Radionuclide Activities Chain pCi/ gram 152Eu 8.6500E+000 152Gd 0.0000E+000 Variable Parameters No parameters have been changed.

Residential Output Section Maximum Annual TEDE This scenario started 0.00 year (s) from now and r&n for 1000. 00 year (s) .

The peak dose of 2.50E+001 TEDE (mrem) occurred 1.00 year (s) after license termination.

1

'P f-

-Pathway Component of Maximum Annual Dose-Pathway TEDE (mrem) Percentage External 2.47E+001 99.10

' Inhalation- 1.16E-004 0.00

- Agricult. 2.23E-001' O.89 Soil- 7.73E-004 0.00-Drinking 1.01E-005. 0.00

. Irrigated 1.90E-005 0.00 Aquatic 5.35E-006 0.00 Total 2.50E+001 100.00 Radionuclide Component of Maximum Annual Dose Radionuclide TEDE (mrem) Percentage t

152Eu 2.50E+001 -100.00 152Gd 3.17E-013 0.00 Total 2.50E+001 100.00 l

^

l l

J

i Program  : DandD Version 1.0 Session  : Screening DCGLs - Residential Scenario Description : i Calculation of radionuclide-specific activity resulting in 25 mrem /yr  !

i Executed  : 03/24/99 at 19:27:31 NRC Report Residential Input Section 1

I Execution Options History file will be generated. l Implicit progeny doses will not be included with explicit parent.

Concentration data will be calculated.

Initial Radionuclide Activities i I

Chain pCi/ gram 154Eu 8.01 Code-Generated Radionuclide Activities Chain pCi/ gram 154Eu 8.0130E+000 Variable Parameters No parameters have been changed.

Residential Output Section Maximum Annual TEDE This scenario started 0.00 year (s) from now and ran for 1000.00 year (s) .

The peak dose of 2.50E+001 TEDE (mrem) occurred 1.00 year (s) after license termination.

Pathway Component of Maximum Annual Dose Pathway TEDE (mrem) Percentage External 2.47E+001 98.80 Inhalation 1.39E-004 0.00 Agricult. 2.98E-001 1.19 Soil 1.04E-003 0.00 Drinking 1.36E-005 0.00 Irrigated 2.50E-005 0.00 i Aquatic 7.16E-006 0.00

_____________________________________________ l Total 2.50E+001 100.00 Radionuclide Component of Maximum Annual Dose Radionuclide TEDE (mrem) Percentage 154Eu 2.50E+001 100.00 Total 2.50E+001 100.00 4

l l

a Program  : DandD Version 1.0 Session  : Screening DCGLs - Residential Scenario Description :

Calculation of radionuclide-specific activity resulting in 25 mrem /yr Executed  : 03/24/99 at 19:28:53 NRC Report Residential Input Section Execution Options History file will be generated.

Implicit progeny doses will not be included with explicit parent.

Concentration data will be calculated. ',

Initial Radionuclide Activities Chain pCi/ gram 155Eu 281.85 Code-Generated Radionuclide Activities Chain pCi/ gram 155Eu 2.8185E+002 Variable Parameters No parameters have been changed.

Residential Output Section

(

Maximum Annual TEDE i

This scenario started 0.00 year (s) from now f and ran for 1000.00 year (s). l

- 1 l

The peak dose of 2(SOE+001 TEDE (mrem) occurred 1.00 year (s) after license termination.

i

I l

1 Pathway Component of Maximum Annual Dose Pathway TEDE (mrem) Percentage External 2.34E+001 93.56 Inhalation 6.98E-004 0.00 Agricult. 1.60E+000 6.41 i Soil 5.69E-003 0.02 i Drinking 7.31E-005 0.00 Irrigated 1.30E-004 0.00 Aquatic 3.86E-005 0.00 Total 2.50E+001 100.00 Radionuclide Component of Maximum Annual Dose Radionuclide TEDE (mrem) Percentage 155Eu 2.50E+001 100.00 Total 2.50E+001 100.00 l

l i

f

/

L

' Program  : DandD. Version-1.0 Session  : Screening DCGLs - Residential Scenario Description :

Calculation of radionuclide-specific activity resulting in 25 mrem /yr

-Executed  : 03/24/99 at 19:32:13 NRC Report Residential Input Section

+

Execution Options History file will be generated.

Implicit progeny doses will not.be included with explicit parent.

Concentration data will be calculated.

Init'ial Radionuclide Activities Chain pCi/ gram 233U 0.46 Code-Generated Radionuclide Activities

Chain pCi/ gram 2330 4.6200E-001 229Th 0.0000E+000 225Ra 0.0000E+000

225Ac 0.0000E+000 221Fr 0.0000E+000 217At 0.0000E+000 213Bi 0.0000E+000 213Po 0.0000E+000 209T1 0.0000E+000 209Pb 0.0000E+000 Variable Parameters No. parameters have been changed.

I l

i I

r k

Residential Output Section Maximum Annual TEDE This scenario started 0.00 year (s) from now and ran for 1000.00 year (s).

The peak dose of 2.50E+001 TEDE (mrem) occurred 4.00 year (s) after license termination.

Pathway Component of Maximum Annual Dose

...........u..................

Pathway TEDE (mrem) Percentage External 4.34E-005 0.00 Inhalation 2.76E-004 0.00 Agricult. 4.45E-002 0.18 Soil 1.35E-004 0.00 Drinking 6.03E+000 24.14 Irrigated 1.25E+001 50.19 Aquatic 6.37E+000 25.49 Total 2.50E+001 100.00 Radionuclide Component of Maximum Annual Dose Radionuclide TEDE (mrem) Percentage 2330 2.49E+001 99.82 229Th 3.96E-002 0.16 225Ra 3.70E-003 0.01 225Ac 8.44E-004 0.00 221Fr 2.18E-006 0.00 217At 2.37E-008 0.00 213Bi 1.58E-005 0.00 213Po 0.00E+000 0.00 209T1 3.44E-006 0.00 209Pb 1.63E-006 0.00 Total 2.50E+001 100.00

E l Program  : DandD Version l.0 Session  : Screening DCGLs - Residential Scenario Description :

Calculation of radionuclide-specific activity resulting in 25 mrem /yr Executed-  : 03/24/99 at 19:37:29 l NRC Report Residential Input Section Execution. Options History file will be generated.

- Implicit progeny doses will not be included with explicit parent.

- Concentration data will be calculated.

Initial Radionuclide Activities

.......................................n Chain pCi/ gram

'2340 0.47 Code-Generated Radionuclide Activities 1 t

Chain 'pCi/ gram

........................................ j i

a 234U 4.7170E-001 230Th 0.0000E+000 226Ra' O.0000E+000 222Rn' O.0000E+000 218Po 0.0000E+000:

214Pb 0.0000E+000 218At 0.0000E+000 21481- 0.0000E+000 214Po 0.0000E+000 210Pb 0.0000E+000' '

210Bi 10.0000E+000 210Po 0.0000E+000 Variable Parameters No parameters have been changed.

Residential Output Section Maximum Annual TEDE This scenario started 0.00 year (s) from now and ran for 1000.00 year (s).

The peak dose of 2.50E+001 TEDE (mrem) occurred 4.00 year (s) after li' cense termination.

Pathway Component of Maximum Annual Dose Pathway TEDE (mrem) Percentage External 6.52E-006 0.00 Inhalation 2.71E-004 0.00 Agricult. 4.41E-002 0.18 Soil 1.34E-004 0.00 Drinking 6.03E+000 24.15 Irrigated 1.25E+001 50.19 Aquatic 6.36E+000 25.48 Total 2.50E+001 100.00 Radionuclide Component of Maximum Annual Dose Radionuclide TEDE (mrem) Percentage 234U 2.50E+001 100.00 230Th 5.98E-004 0.00 226Ra 5.18E-007 0.00 222Rn 3.16E-012 0.00 218Po 7.31E-014 0.00 214Pb 2.08E-009 0.00 218At 0.00E+000 0.00 214Bi 1.22E-008 0.00 214Po 6.66E-013 0.00 210Pb 8.18E-008 0.00 21081 6.95E-011 0.00 210Po 4.33E-008 0.00 Total 2.50E+001 100.00 I

I i l l

l l

l I

).

1 Program  : DandD Version 1.0 Session  : , Screening'DCGLs - Residential Scenario Description : .

Calculation of radionuclide-specific activity resulting in 25 mrem /yr.

Executed  : 03/24/99 at 19:40:55

-NRC Report Residential Input Section Execution Options History file will'be generated.

Implicit progeny doses will not be included with explicit parent.

Concentration data will be calculated.

l Initial Radionuclide Activities Chain pCi/ gram 2350 0.50 Code-Generated Radionuclide Activities Chain ~ pCi/ gram 235U 4.9900E-001 231Th 0.0000E+000 231Pa. 0.0000E+000

'227Ac- 0.0000E+000 223Fr- 0.0000E+000 227Th -0.0000E+000 223Ra 0.0000E+000

-219Rn 0.0000E+000 215Po 0.0000E+000 211Pb 0.0000E+000 211B1 0.0000E+000 -

211Po- 0.0000E+000 207T1 0.0000E+000- j i

Variable Parameters No parameters have been changed. l l

< i

Residential Output Section i

Maximum Annual TEDE This scenario started 0.00 year (s) from now and ran for 1000.00 year (s).

The peak dose of 2.50E+001 TEDE (mrem) occurred 4.00 year (s) after license termination.

l Pathway Component of Maximum Annual Dose 1

Pathway TEDE (mrem) Percentage External 1.27E-002 0.05 Inhalation 2.67E-004 0.00 Agricult. 4.42E-002 0.18 Soil 1.34E-004 0.00 Drinking 6.03E+000 24.12 Irrigated 1.25E+001 50.12 Aquatic 6.39E+000 25.53 Total 2.50E+001 100.00 I i

Radionuclide Component of 1 Maximum Annual Dese Radionuclide TEDE (mrem) Percentage

............................................. i 235U 2.48E+001 99.21 231Th 1.56E-001 0.62 231Pa 3.85E-002 0.15 227Ac 1.61E-003 0.01 223Fr 1.40E-008 0.00 227Th 5.36E-006 0.00 223Ra 8.04E-005 0.00 219Rn 4.02E-008 0.00 215Po 1.30E-010 0.00 211Pb 1.02E-007 0.00 21181 3.32E-008 0.00 211Po 1.64E-011 0.00 207T1 2.47E-009 0.00 Total 2.50E+001 100.00 l

Program  : DandD Version 1.0 Session  : Screening DCGLs - Residential Scenario Description :

Calculation of radionuclide-specific activity resulting in 25 mrem /yr i Executed  : 03/24/99 at 19:44:00 NRC Report Residential Input Section Execution Options History file will be generated.

Implicit progeny doses will not be included with explicit parent. i I

Concentration data will be calculated.

Initial Radionuclide Activities Chain pCi/ gram 2360 0.50 Code-Generated Radionuclide Activities Cnain pCi/ gram 236U 4.9800E-001 232Th 0.0000E+000 228Ra 0.0000E+000 228Ac 0.0000E+000 228Th 0.0000E+000 224Ra 0.0000E+000 220Rn 0.0000E+000 216Po 0.0000E+000 212Pb 0.0000E+000 212Bi 0.0000E+000 212Po 0.0000E+000 208T1 0.0000E+000 Variable darameters No parameters have been changed.

1

/

f 1

l

p Residential Output Section Maximum Annual TEDE

, This scenario started 0.00 year (s) from now i- and ran for 1000.00 year (s).

The peak dose of 2.50E+001 TEDE (mrem) occurred 4.00 year (s) after i

license termination.

l l Pathway Component of Maximum Annual Dose l ..............................

Pathway TEDE (mrem) Percentage l External 3.66E-006 0.00 t

Inhalation 2.71E-004 0.00 Agricult. 4.41E-002 0.18 Soil 1.34E-004 0.00 Drinking 6.04E+000 24.15 Irrigated 1.25E+001 50.19 Aquatic 6.37E+000 25.48 l Total 2.50E+001 100.00 l Radionuclide Component of l

Maximum Annual Dose Radionuclide TEDE (mrem) Percentage l 236U 2.50E+001 100.00 l 232Th 1.73E-000 0.00 228Ra 8.25E-010 0.00 228Ac 1.18E-011 0.00 228Th 5.77E-011 0.00 224Ra 4.81E-011 0.00 l 220Rn 1.55E-015 0.00 216Po 6.87E-017 0.00 212Pb 7.06E-012 0.00 212Bi 9.07E-013 0.00 212Po 0.00E+000 0.00 208T1 4.89E-012 0.00 Total 2.50E+001 100.00 l

i I

i...

9

' Program  : DandD Version-1.0

. Session  : Screening DCGLs - Residential Scenario Description 2 .

Calculation of radionuclide-specific activity resulting in 25 mrem /yr Executed  : 03/24/99 at 19:51:47 NRC Report i i

l i

Residential Input Section Execution Options-

, History file will be generated.

. Implicit progeny doses will not be included with explicit parent.

Concentration data will be calculated. I i

Initial'Radionuclide' Activities

. Chain pCi/ gram-

........................................ i 238U 0.50 Code-Generated Radionuclide Activities Chain pC1/ gram 4

238U 4.9500E-001 234Th 0.0000E+000-234mPa 0.0000E+000 234Pa 0.0000E+000 234U 0.0000E+000 230Th 0.0000E+000' 226Ra 0.0000E+000 222 Rn -- 0.0000E+000 218Po 0.0000E+000 214Pb- 0.0000E+000 218At- 0.0000E+000 21481 0: 0000E+000

-214Po. 0.0000E+000 210Pb 0.0000E+000 21081 0.0000E+000 210Po 0.0000E+000 Variable Parameters j

...................................................................... j No parameters have.been changed. I 1

F~

]

f Residential Output Section l

Maximum Annual TEDE

'This scenario started 0.00 year (s) from now and ran for 1000.00 year (s). l The peak dose of . 2.50E+001 TEDE (mrem) occurred 4.00 year (s) after licerica termination. l Pathway Component of Maximum Annual Dose Pathway TEDE (mrem) Percentage External 2.14E-003 0.01 Inhalation 2.55E-004 0.00 Agricult. 4.36E-002 0.17 Soil 1.33E-004 0.00 Drinking 5.97E+000 23.86 I Irrigated 1.24E+001 49.61 Aquatic 6.59E+000 26.35 Total 2.50E+001 100.00 Radionuclide Component of

' Maximum Annual Dose Radionuclide TEDE (mrem) Percentage 238U 2.35E+001 94.17 234Th 1.46E+000 5.82 234mPa 1.36E-003 0.01 234Pa 8.12E-004 0.00  !

234U 2.67E-004 0.00 l 230Th 4.82E-009 0.00 I 226Ra 3.34E-012 0.00 222Rn 6.75E-018 0.00 218Po 1.56E-019 0.00 214Pb 5.32E-015 0.00 218At 0.00E+000 0.00 214Bi 2.66E-014 0.00 214Po 1.42E-018 0.00 i 210Pb 3.94E-013 0.00 l 210Bi 3.34E-016 0.00 210Po 1.62E-013 0.00 i Total 2.50E+001 100.00 i

I l'

i _ -

Program  : DandD Version 1.0 Session  : Screening DCGLs - Residential Scenario Description :

Calculation of radionuclide-specific activity resulting in 25 mrem /yr Executed  : 03/24/99 at 19:58:13 NRC Report Residential Input Section Execution Options History file will be generated.

Implicit progeny doses will not be included with explicit parent. '

Concentration data will be calculated. '

Initial Radionuclide Activities

\

Chain pCi/ gram

........................................ l 238Pu 0.10 Code-Generated Radionuclide Activities Chain FCi/ gram I 238Pu 1.0246E-001 2340 0.0000E+000 230Th 0.0000E+000 226Ra 0.0000E+000 222Rn 0.0000E+000 218Po 0.0000E+000 214Pb 0.0000E+000 218At 0.0000E+000 21481 0.0000E+000 214Po 0.0000E+000 210Pb 0.0000E+000 21081 0.0000E+000 210Po 0.0000E+000 Variable Parameters No parameters have been changed.

)

Residential Output Section Maximum Annual TEDE

' This scenario started 0.00 year (s) from now and ran for 1000.00 year (s).

The peak dose of 2.50E+001 TEDE (mrem) occurred 8.00 year (s) after license termination.

Pathway Component of Maximum Annual Dose Pathway- TEDE (mrem)- Percentage External 7.41E-007 0.00 Inhalation 2.44E-004 0.00 Agricult. 1.22E-001 0.49 Soil 4.56E-004 0.00 Drinking 3.15E+000 12.60 Irrigated- 5.12E+000 20.48 Aquatic 1.66E+001 66.43 Total 2.50E+001 100.00 Radionuclide Component of Maximum Annual Dose Radionuclide TEDE (mrem) Percentage 238Pu 2.50E+001 100.00 2340 1.03E-004 0.00 230Th 2.41E-009 0.00 226Ra 2.22E-012 0.00 222Rn 1.79E-017 0.00 218Po 4.15E-019 0.00 214Pb 1.16E-014 0.00 218At 0.00E+000 0.00 214B1- 6.95E-014 0.00 214Po. 3.79E-018 0.00 210Pb 5.24E-013 0.00 210B1 4.35E-016 0.00 210Po 3.79E-013 0.00 Total '2.50E+001 100.00

/

Program  : DandD Version 1.0 Session  : Screening DCGLs - Residential Scenario Description :

Calculation of radionuclide-specific activity resulting in 25 mrem /yr 1

Executed  : 03/24/99 at 20:04:06  !

1 NRC. Report Residential Input Section i

Execution Options I History file will be generated.

Implicit progeny doses will not be included with explicit parent.

Concentration data will be calculated.

Initial Radionuclide Activities Chain pC1/ gram 239Pu 0.09 Code-Generated Radionuclide Activities Chain pCi/ gram 239Fu 8.6800E-002 2350 0.0000E+000 l 231Th 0.0000E+000 231Pa 0.0000E+000 227Ac 0.0000E+000 223Fr 0.0000E+000 227Th 0.0000E+000 223Ra 0.0000E+000 219Rn 0.0000E+000 215Po 0.0000E+000 211Pb 0.0000E+000 21181 0.0000E+000 211Po 0.0000E+000 207T1 0.0000E+000 Variable Parameters No parameters have been changed.

I l

I

, Residential Output Section i

Maximum Annual TEDE This scenario started 0.00 year (s) from now and ran for 1000.00 year (s).

l The peak dose of 2.50E+001 TEDE (mrem) occurred 10.00 year (s) after license termination. .

Pathway Component of Maximum Annual Dose

.............................. i Pathway TEDE (mrem) Percentage

............................................. +

External 1.14E-006 0.00 Inhalation 2.18E-004 0.00 Agricult. 1.11E-001 0.44 Soil 4.14E-004 0.00 Drinking 3.15E+000 12.59 Irrigated 5.15E+000 20.56 Aquatic 1.66E+001 66.40 Total 2.50E+001 100.00 Radionuclide Component of Maximum Annual Dose

.............................. l i

Radionuclide TEDE (mrem) Percentage 239Pu 2.50E+001 100.00 2350 3.66E-008 0.00 231Th  !

2.30E-010 0.00 231Pa 7.38E-011 0.00 227Ac 3.53E-012 0.00 223Fr 3.15E-017 0.00 227Th 1.22E-014 0.00 223Ra 1.82E-013 0.00 219Rn 1.73E-016 0.00 215Po 5.59E-019 0.00 211Pb 3.08E-016 0.00 21181 1.43E-016 0.00 211Po 7.06E-020 0.00 207T1 1.06E-017 0.00 Total 2.50E+001 100.00 t

e Program  : DandD Version 1.0 Session  : Screening DCGLs - Residential Scenario Description :

Calculation of radionuclide-specific activity resulting in 25 mrem /yr Executed  : 03/24/99 at 20:08:59 '

NRC Report Residential Input Section Execution Options I

.................... \

History file will be generated.

Implicit. progeny doses will not be included with explicit parent. 4 Concentration data will be calculated. f Initial Radionuclide Activities Chain 'pC1/ gram 240Pu 0.09 Code-Generated Radionuclide Activities Chain pCi/ gram d

240Pu 8.6800E-002 2360 0.0000E+000 232Th 0.0000E+000 228Ra 0.0000E+000 228Ac. 0.0000E+000 228Th' 'O.0000E+000 224Ra 0.0000E+000 220Rn 0.0000E+000 216Po- 0.0000E+000 212Pb~ 0.0000E+000 212Bi '0.0000E+000 212Po 0.0000E+000 208T1 0.0000E+000

= Variable Parameters No parameters have been changed.

l

}

l Residential Output Section I Maximum Annual TEDE l

This scenario started 0.00 year (s) from now and ran for 1000.00 year (s) .

.The peak dose of 2.50E+001 TEDE (mrem) occurred 10.00 year (s) after license termination.

Pathway Component of Maximum Annual Dose j j

Pathway

...........................................ge TEDE (mrem) Percenta External 5.91E-007 0.00 Inhalation 2.18E-004 0.00 Agricult. 1.11E-001 0.44 k Soil 4.14E-004 0.00 Drinking 3.15E+000 12.59 Irrigated 5.14E+000 20.56 Aquatic 1.66E+001 66.40 Total 2.50E+001 100.00 Radionuclide Component of Maximum Annual Dose Radicauclide TEDE (mrem) Percentage 240Pu 2.50E+001 100.00 2360 1.11E-006 0.00 232Th 7.87E-016 0.00 228Ra 4.16E-017 0.00 228Ac 9.87E-019 0.00 228Th 4.11E-018 0.00 224Ra 3.40E-018 0.00 i 220Rn 1.91E-022 0.00 216Po 8.46E-024 0.00 212Pb 5.32E-019 0.00 212Bi 1.04E-019 0.00 212Po 0.00E+000 0.00 208T1 6.03E-019 0.00 Total 2.50E+001 100.00

e 1

1 Program  : DandD Version 1.0 Session  : . Screening DCGLs - Residential Scenario Description :

Calculation of radionuelide-specific activity resulting in 25 mrem /yr Executed  : 03/24/99 at 20:16:16 NRC Report Residential Input Section Execution Options History file will be generated, i

Implicit progeny doses will not be included with explicit parent. I Concentration data will be calculated. .'

Initial Radionuclide Activities Chain pCi/ gram l

241Pu 5.62 '

Code-Generated Radionuclide Activities Chain pCi/ gram j 241Pu 5.6180E+000 241Am 0.0000E+000 2370 0.0000E+000 237Np 0.0000E+000 233Pa 0.0000E+000 233U 0.0000E+000 229Th 0.0000E+000 225Ra 0.0000E+000 225Ac 0.0000E+000 221Fr 0.0000E+000 217At 0.0000E+000 213Bi 0.0000E+000 213Po 0.0000E+000 209T1 0.0000E+000 209Pb 0.0000E+000 Variable Parameters No parameters have been changed.

l

Residential Output Section Maximum Annual TEDE This scenario started 0.00 year (s) from now and ran for 1000.00 year (s).

The peak dose of 2.50E+001 TEDE (mrem) occurred 6.00 year (s) after license termination.

Pathway Component of

)

Maximum Annual Dose j

Pathway TEDE (mrem) Percentage  ;

External 3.60E-004 0.00 Inhalation 7.47E-004 0.00 '

Agricult. 3.83E-001 1.53 .

Soil 1.42E-003 0.01 l Drinking 3.10E+000 12.40 Irrigated 5.16E+000 20.64 i Aquatic 1.64E+001 65.42 Total 2.50E+001 100.00 Radionuclide Component of Maximum Annual Dose Radionuclide TEDE (mrem) Percentage 241Pu 2.27E+001 90.61 241Am 2.35E+000 9.39 2370 1.73E-005 0.00 237Np 1.26E-005 0.00 l

233Pa 1.03E-008 0.00 2330 1.37E-011 0.00 l 229Th 1.48E-014 0.00 225Ra 1.37E-015 0.00 225Ac 3.17E-016 0.00 221Fr 4.23E-019 0.00 217At 4.61E-021 0.00 21381 4.07E-018 0.00 213Po 0.00E+000 0.00 209T1 6.69E-019 0.00 209Pb 6.10E-019 0.00 Total 2.50E+001 100.00 l

Program  : DandD Version 1.0 Session  : Screening DCGLs - Residential Scenario Description :

Calculation of radionuclide-specific activity resulting in 25 mrem /yr Executed  : 03/24/99 at 20:26:05 NRC Report Residential Input Section l

Execution Options History file will be generated.

Implicit progeny doses will not be included with explicit parent.

Concentration data will be calculated.

Initial Radionuclide Activities t I

Chain pCi/ gram 242Pu 0.09

{

Code-Generated Radionuclide Activities Chain pCi/ gram I ....--..................................

242Pu 9.1240E-002 238U 0.0000E+000 234Th 0.0000E+000 234mPa 0.0000E+000 234Pa 0.0000E+000 '

234U 0.0000E+000 230Th 0.0000E+000 226Ra 0.0000E+000 222Rn 0.0000E+000 218Po 0.0000E+000 214Pb 0.0000E+000 218At 0.0000E+000 214Bi 0.0000E+000 214Po 0.0000E+000 210Pb 0.0000E+000 210Bi 0.0000E+000 Variable Parameters No parameters have been changed.

Residential Output Section Maximum Annual TEDE This scenario started 0.00 year (s) from now and ran for 1000.00 year (s).

The peak dose of 2.50E+001 TEDE (mrem) occurred 10.00 year (s) after license termination.

Pathway Component of Maximum Annual Dose Pathway TEDE (mrem) Percentage External 5.42E-007 0.00 Inhalation 2.20E-004 0.00 Agricult. 1.11E-001 0.44 Soil 4.14E-004 0.00 Drinking 3.15E+000 12.59 Irrigated 5.14E+000 20.56 Aquatic 1.66E+001 66.40 Total 2.50E+001 100.00

)

Radionuclide Component of Maximum Annual Dose Radionuclide TEDE (mrem) Percentage 242Pu 2.50E+001 100.00 2380 5.81E-009 0.00 234Th 3.57E-010 0.00 234mPa 3.49E-013 0.00 234Pa 2.03E-013 0.00 234U 9.09E-014 0.00 230Th 2.00E-018 0.00 226Ra 5.81E-020 0.00 222Rn 0.00E+000 0.00

, 210Po 0.00E+000 0.00 214Pb 1.25E-023 0.00 218At 0.00E+000 0.00 214Bi 5.66E-024 0.00 214Po 0.00E+000 0.00 210Pb 6.71E-021 0.00 21081 3.85E-023 0.00 Total 2.50E+001 100.00

f Program  : DandD Version 1.0 Session  : Screening DCGLs - Residential Scenario Description :

Calculation of radionuclide-specific activity resulting in 25 mrem /yr Executed  : 03/24/99 at 20:45:51 NRC Report i

Residential Input Section Execution Options History file will be generated.

Implicit progeny doses will not be included with explicit parent.

Concentration data will be calculated.

Initial Radionuclide Activities Chain pCi/ gram  ;

241Am 1.79 Code-Generated Radionuclide Activities Chain pCi/ gram 241Am 1.7900E+000 237Np 0.0000E+000 233Pa 0.0000E+000 2330 0.0000E+000 229Th 0.0000E+000 225Ra 0.0000E+000 225Ac 0.0000E+000 221rr 0.0000E+000 217At 0.0000E+000 213Bi 0.0000E+000 213Po 0.0000E+000 209T1 0.0000E+000 209Pb 0.0000E+000 Variable Parameters No parameters have been changed.

i

P l Residential Output Section j 1

Maximum Annual TEDE This scenario started 0.00 year (s) from now and ran for 1000.00 year (s).

The peak dose of 2.50E+001 TEDE (mrem) occurred 1.00 year (s) after license termination.

Pathway Component of Maximum Annual Dose

......~........................

Pathway TEDE (mrem) Percentage External 3.81E-002 0.15 Inhalation 4.89E-002 0.20 Agricult. 2.48E+001 99.27 Soil 9.22E-002 0.37 Drinking 5.30E-004 0.00 Irrigated 8.66E-004 0.00 Aquatic 2.80E-003 0.01 Total 2.50E+001 100.00 Radionuclide Component of Maximum Annual Dose Radionuclide TEDE (mrem) Percentage 241Am 2.50E+001 100.00 237Np 3.21E-005 0.00 ,

233Pa 1.30E-007 0.00 1 233U 5.81E-012 0.00 229Th 2.44E-015' O.00 225Ra 2.21E-016 0.00 225Ac 5.52E-017 0.00 221Fr 3.23E-019 0.00 217At 3.52E-021 0.00 213B1 1.89E-018 0.00 213Po 0.00E+000 0.00 209T1 5 10E-019 0.00 209Pb 1.07E-019 0.00 Total 2.50E+001 100.00

Program  : DandD Version 1.0 Session  : Screening DCGLs - Residential Scenario Description :

Calculation of radionuclide-specific activity resulting in 25 mrem /yr Executed  : 03/24/99 at 20:55:08 NRC Report l

Residential Input Section 1

Execution Options History file will be generated. I Implicit progeny doses will not be included with explicit parent. I Concentration data will be calculated.

)

Initial Radionuclide Activities Chain pCi/ gram 243Cm 2.58 Code-Generated Radionuclide Activities l Chain pCi/ gram

........................................ i i

243Cm 2.5830E+000 l 243Am 0.0000E+000 l 239Np 0.0000E+000 239Pu 0.0000E+000 2350 0.0000E+000 231Th 0.0000E+000 231Pa 0.0000E+000 227Ac 0.0000E+000 223Fr 0.0000E+000 227Th 0.0000E+000 Variable Parameters No parameters have been changed.

Residential Output Section Maximum Annual TEDE This scenario started 0.00 year (s) from now and ran for 1000.00 year (s).

The peak dose of 2.50E+001 TEDE (mrem) occurred 1.00 year (s) after license termination.

Pathway Component of Maximum Annual Dose Pathway .TEDE (mrem) Percentage i

i External 7.03E-001 2.81 Inhalation 4.86E-002 0.19 Agricult. 2.42E+001 96.63 Soil 9.08E-002 0.36 Drinking 5.24E-005 0.00 Irrigated 8.56E-005 0.00 Aquatic 2.76E-004 0.00 Total 2.50E+001 100.00 j Radionuclide Component of Maximum Annual Dose

.............................. l Radionuclide TEDE (mrem) Percentage 243Cm 2.50E+001 100.00 243Am 6.14E-006 0.00 239Np 1.05E-007 0.00 239Pu 1.18E-003 0.00 2350 1.20E-013 0.00 231Th 8.88E-016 0.00 231Pa 3.97E-017 0.00 227Ac 6.21E-019 0.00 223Fr 5.63E-024 0.00 227Th 1.48E-021 0.00 Total 2.50E+001 100.00

/

Program  :.DandD Version 1.0 Session  : Screening DCGLs - Residential Scenario Description :

Calculation of radionuclide-specific activity resulting in 25 mrem /yr Executed  : 03/24/99 at 21:04:26 NRC Report Residential Input Section Execution Options History file will be generated.

Implicit progeny doses will not be included with explicit parent.

Concentration data will be calculated.

Initial Radionuclide Activities Chain pCi/ gram

• 244Cm 3.35 1

Code-Generated Radionuclide Activities q

Chain pCi/ gram 244Cm 3.3467E4000 )

240Pu 0.0000E+000 236U 0.0000E+000 232Th 0.0000E+000 228Ra 0.0000E+000 228Ac 0.0000E+000 228Th 0.0000E+000 224Ra 0.0000E+000 220Rn 0.0000E+000 216Po 0.0000E+000 212Pb 0.0000E+000 4 212B1 0.0000E+000 I 212Po 0.0000E+000 208T1 0.0000E+000 Variable Parameters No parameters have been changed.

F Residential Output Section i

Maximum Annual TEDE This scenario started 0.00 year (s) from now and ran for 1000.00 year (s).

The peak dose of 2.50E+001 TEDE (mrem) occurred 1.00 year (s) after license termination.

J i

Pathway Component of Maximum Annual Dose Pathway TEDE (mrem) Percentage External 2.02E-004 0.00 Inhalation 5.07E-002 0.20 Agricult. 2.49E+001 99.41 Soil 9.37E-002 0.37 Drinking 2.49E-004 0.00 Irrigated 4.06E-004 0.00 Aquatic 1.31E-003 0.01 Total 2.50E+001 100.00 Radionuclide Component of Maximum Annual Dose Radionuclide TEDE (mrem) Percentage 244Cm 2.50E+001 99.98 240Pu 5.58E-003 0.02 2360 1.67E-011 0.00 232Th 3.46E-021 0.00 228Ra 6.84E-023 0.00 228Ac 1.35E-024 0.00 228Th 2.33E-024 0.00 224Ra 2.32E-024 0.00  !

220Rn 5.49E-028 0.00 216Po 2.43E-029 0.00 212Pb 7.75E-025 0.00 212Bi 4.80E-025 0.00 212Po 0.00E+000 0.00 20BT1 3.04E-024 0.00 Total 2.50E+001 100.00

P I

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4 ATTACHMENTIV to VPN-054-99 TROJAN NUCLEAR PLANT SURVEY AREA MAPS INDICATING PRELIMINARY SURVEY UNITS (56 pages) l l

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g i i E0lFMENT & SYSTEMS SHOWN ARE NCLUDED AS MSTORICAL NFORMATION ONLY.

SURVEY LNT DESIGNATIONS REPRESENT PLANNNG AS OF AUGUST l.1999.

TMS SURVEY L?IT MAP IS MANTA #ED BY R.P.

S(RVEY LMITS NOT SHOWN CSBd E 45C 3 LOWER NORTH & WEST EXTERIOR WALLS (SBd.fi45' ) LOWER EAST EXTERIOR WALL (NORTH ENO)

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TMS SLRVEY LNT MAP IS MANTADED BY R.P.

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SURVEY UPET DESIGNATIONS REPRESENT PLA.494G AS OF AUGUST I,1999.

TMS SURVEY LNT MAP 15 MAINTAINED BY R.P.

_ . W

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SLEVEY LNT DESIGNATIONS REPRESENT PLAl#GdG AS OF AUGUST I,1999.

T)tS SURVEY LNT MAP IS MANTA # G BY R.P.

e -

SLRVEY LMITS NOT SHOWN SLRVEY IMITS NOT SHOWN

( S; F %3J) NORTH WALL CSO40CG)] WEST WALL BETVEEN CDP (T & A.B. ROLL LP DOOR (S ICI '<30 EAST WALL (NORTH END)

( Sil40(IM ) WEST WALL (NORTH END)

(S Jo +3. ) EAST WALL (SOUTH END) ( Sf!40CG3) CEILINO (NORTH END)

( Sij%ct3e ) SOUTH WALL ( Sil40CF ) CEILING (SOUTH END)

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- CHECKED BY J COOPER DWG REFERENCE SC E (HETE AREA DESCRIPTION m-

_ _ _ _ _ . _ . - - . _ _ _ _ - - . - _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ~ - ' - - - - - - - - -

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SLRVEY L90T DESIGNATIONS ftEPftESENT PLAf00dC AS OF AUGUST 1.1999.

TMS SURVEY UMT MAP 15 MADITAINED BY ft.P.

1 i

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- CHECKED BY J COOPER DWG REFERENCE B 1 2 3 4 5 SCALE (METERS) AREA DESCRIPTION m N MATION 5-FT

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SURVEY LNT DESIGNATIONS REPRESENT PLANPSdG AS OF AUOUST l.1999.

TMS S(RVEY LNT MAP IS MANTADED BY RI.

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TMS SURVEY LNT WAP iS MANTANED BY R.P.

~~

1 .

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\

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