ML20155F803

Viewgraphs from Meeting on New Radwaste Facilities at Plants

ML20155F803
Person / Time
Site:	Surry, North Anna, 05000000
Issue date:	09/07/1988
From:	VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML20155F796	List: IA-88-419, Final FOIA Request for Documents Re Radwaste Facilities at Plants.Forwards App B Document.App a & B Documents Available in PDR ML20155F791 ML20155F803
References
FOIA-88-419 NUDOCS 8810130392
Download: ML20155F803 (37)

Text

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j VIRGINIA POWER I j NEW RADWASTE FACILITIES 1

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! o392 88o907 sesoigebe-4tv eo" 9 7. o -1 e 9 9 po B/i l.

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l TO PROVIDE PROVEN STATE-OF-THE-ART LIQUID AND SOLID RADWASTE i

PROCESSING CAPABILITY IN SUPPORT OF THE NUCLEAR POWER STATIONS.

j IMPROVED RADWASTE PROCESSING CAN: l REDUCE V0 LUES l

REDUCE EFFLUENT RELEASES i

REDUCE PERSONNEL EXPOSURE l REDUCE COST THROUGH INCREASED EFFICIENCY i

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NRF MAJOR GOALS AND OBJECTIVES

1. On-sita storage requirements for all waste types and forms shall be one(1) year.

2. Liquid-waste discharges shall not exceed .

0.1 Ci/ year / site excluding triti'um

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50% of NPDES limits

3. Low specific active shipped off-site shall not exceed .

8,000 CF/ reactor / year (16.000 CF/ year / site)

4. There shall be no in' advertent radioactiv~e ga'seous releases from the NRF.

s ADDITIONAL NRF GOAL.S AND OBJECTIVES ,

h' . 2 IN NRF SHALL EFFECT EXISTING POWER STATION OPERATION.  ;

NO WASTE TREATED AND/0R VOLUME REDUCED BY THE NRF SHALL EXCEED CLASS C

CLASSIFICATION CRITERIA.

1 THE FACILITY DESIGN SHALL BE BASED ON SOUND ALARA PRINCIPLES.

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i PROJECT SCOPE  ;

NRF BUILDING - JGC SCOPE 1

IN-PLANT MODS - VP SCOPE (VIA SWEC)

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SITE INTERFACE TO NRF - VP SCOPE (VIA SWEC)  :

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RADWASTE OPERATIONS TRANSITION - VP SCOPE i

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NEW RADWASTE FACILITY RADWASTE CONTROL ROOM LIQUID WASTE PROCESSING EQUIPMENT 30 GPM EVAPORATOR 60 GPM DEMINERAll2ER LAUNDRY WASTE PROCESSING EQUIPMENT FILTER EVAPORATION OPTION HIGH PRESSURE SHREDDER / COMPACTOR ASPHALT SOLIDIFICATION SYSTEM EVAPORATOR CONCENTRATES SPENT RESINS  :

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1. LIQUID WASTE SYSTEM

2. DAW SYSTEM

3. SPENT RESIN HANDLING SYSTEM

4. DECONTAMINATION SYSTEM l

5. BITUMEN SOLIDIFICATION SYSTEM l

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1. DEMINERALIZED WATER SYSEM

2. COOLING WATER SYSTEM

3. SEAL WATER SYSTEM

4. COMPRESSED AIR SYSTEM

5. RADIATION MONITORING SYSTEMS

6. DISTRIBUTED CONTROL SYSTEM (DCS) l 1

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5. SANITARY SEWER SYSTEM I

6. BUILDING DRAINS

7. MATERIAL HANDLING SYSTEM

8. FIRE PROTECTION

9. ELECTRICAL LIGHTING

10. COMMUNiUATIONS

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1 NRF INTERFACES LIQUID WASTE TRANSFER i

LAUNDRY WASTE TRANSFER UTILITY TIE-INS (ELEC., WATER, FIRE, ETC.)

FINAL LANDSCAPING i

COMPOUND SECURITY FENCE 1

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NRF DESIGN BASIS FACILITY DESIGNED IN ACCORDANCE WITH THE FOLLOWING Kf,X DOCUMENTS 10CFR20 10CFR50 10CFR61 ,

40CFR190 l

i 1 RG 1.143 RG 1.140 RG 8.8

- RG 1,109 RG 1.21 SPECIFIC KEX TITLE 10CFR SECTIONS

- 10CFR20,101 10CFR20.103 l 10CFR20.105

- 10CFR50, APP.A - CRITERION 60

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- 10CFR50, APP,A - CRITER10N 64

- 10CPR50, APP.I 10CFR50.34(A) 10CFR50.36(A) l' ALL STATED DESIGN BASIS CONDITIONS IN THE UFSAR FOR EACH STATION ARE I MAINTAINED 1

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. TA81.E 3.1 2 INDUSTRY AND FEDERAL REGULATIONS CODE AND GUIDES Occument Description Title 10 CFR Part 20 "Standards for Protection Against Radiation" Title 10 CFR Part 20 Appendix B "Concentrations Background."

in Air and Water Above Material Title 10 CFR Part 20.101 "Radiation Dose Standards for Individuals in Restricted Areas." Limits exposure of personne; ,

to below prescribed limits.

Title 10 CFR Part 20.103 "Exposure of Individual to Concentrations of Radioactive Materials in Air in Restricted Areas." Limits exposure of personnel from inhalation or absorption to limits described in Part 20, Appendix 8. Table !. Assessment of intake of radioactive material is given 1.n RG 8.9.

Title 10 CFR Part 20.105 "Permissible levels of Radiation in Unrestrictec Areas."

Title 10 CFR Part 20.106 "Radioactivity in Effluents to Unrestricted Areas." Limits exposure to personnel in unrestricted areas to the limits of Part 20, Appendix B Table !!.

Title 10 CFR Part 20.302 "Method for Obtaining Approval of Proposed Disposal Procedures." Requires that proposed procedures for disposal should include a  ;

description of material to be disposed of and procedures to minimize risk to unexpected or hazardous exposures. 1 Titla 10 CFR Part 30

• "00mestic Licensing of Production and

, ,-l ' Utilization Facilities.

10CFR50 / '

App. A. Criterion 60 "Control of Releases of Radioactive Materials to the Environment."

10CFR50 "Monitoring Radioactivity Releases."

App. A, Criterion 64 Requires monitoring of effluent discharge paths and plant environs for radioactivity frem normal operations, operational occurrences, and p postulated accidents. jf.

l 21b

_ TABLE 3.1-2(Continuedj t Document Description Title 10 CFR Part 50 "Numerical Guides for Design Objectives and '

Appendix !

Limiting Conditions for Operation to Meet the Criterion As Low As is Reasonably Achievable fo-Radioactive Material in Light Water Cooled Nuclear Power Reactor Effluents."

Title 10 CFR Part 50.34(a) "Design Objectives for Equipment to Control Releases of Radioactive Material in Effluents -

Nuclear Power Reactors." Requires that guides '

set out in Part 50, Appendix 1, be observed. ,

Title 10 CFR Part 50.36(a) "Technical Specifications on Effluents from l Nuclear Powar Reactors." Requires that '

semiannual effluent reports be submitted to the NRC in addition to requirements of Parts 20.016 '

and 50.34(a).

Title 10 CFR Part 50.59 "Changes, Test and Experiments" '

Titli 10 Part 61 "Licensing Requirements for Land Disposal of Radioactive Waste."

Title 10 CFR Part 71.5 "Transportation of Licensed Material."  !

Implements 00T requirements in Title 49 CFR t Parts 170 through 189.

Title 40 CFR Part 190 "Environmental Radiation Protection Standards '

for Nuclear Power Operations." Limits annual i dose to any menter of public to 25 millirems. '

This includes centributions from entire plant, including I-129 and Kr-85.

Title 49 CFR Parts 170-189 Lists guidelines and procedures for transportation of LLWI including categorizations, packaging, labeling, and

, transportation dose rates.

R. G. 1. 2L -

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"Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Peleases of i

Radioactive Materials and Liquid and Gaseous Effluents from Light Water Cooled Nuclear Power J Plants." Requires that wastes be sampled to determine isotopic concentrations.

R.G. 1.10g "Calc of knaal Doses...tvaluating Compliance with 10 CFR Part 50 Appendix 1."

T, l4Ut.G. 1.110 "Cost-Senefit Analysis for Radweste Systems for Light Water Cooled Nuclear Power Reactors."# l l -

21c 1

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_ TABLE 3.1-2 (Continued)

Document Description R.G. 1.112 "Calculation of release of Radioactive Material in Liquid and Gaseous Effluent from Light-Water-Cooled Reactors."

R.G. 1.120 "Fire Protection Guidelines for Nuclear Power Plants."

R.G. 1.140 "Design. Testing, and Maintenance Criteria for Normal ventilation Exhaust System Air Filtraticn and Absorption Units of Light-Water-Cooled Nuclear Power Plants."

R.G. 1.143 "Design Guidance for Radicactive Waste Management Systems, Structures and Components Installed in Light-Water-Cooled Nuclear Power Plants."

R.G. 8.8 "Information Relevant to Ensuring that Occupational Radiation Exposures at Nuclear Power Stations will be As Low As Reasonably Achievable."

BTP ESTB 11-3 "Design Guidance for Solid Radioactive Waste Management System Installed in Light-Water-Cooled Nuclear Power Plants."

"J[6:ANS 40.35 "Volume Reduction of Low Level Radioactive -

Waste"j/4 e

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l Design Conci: ions Wastes North Anna Surry

. Liquid Waste Quantity (gal / Day) 15,000 15,000 Specific Activity ( ACl/cc) 2.2 E-3, 2.5 E-2 Boron Content (ppm) 300 300 Laundry Waste -

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Quantity (gaJ/ Day) 5,000 9,395  !

Specific Activity ( #Cl/cc) 1.9 E-5 5.0 E-5 Spent Resin Quantity High Active Resin (cf/ Year) 800 800 Low Active Bead Resin (cf/ Year) 1,920 1,920 l

Low Active Powdex Resin (cf/ Year) 3,350 -

. Olty Waste Quantity (gal / Year) 4.760 4,211

. CoMPACTABLE DAW l Quantity (cf/ Year) 50,000 50,000

. Non-coMPACTABLE DAW Quantity (cf/ Year) 6,000 6,000 4

Results of Treatment by NRF System (2) l

! 1. No. of Generated Drums North Anna Surry l

(1) Olly Waste (No. of Drums) 119 105 (2) Solidified Waste (No of Drums) i o Concentrate 195 23 5 oSludge 10 117 oBead Resin 272 279 oPowdered Resin 205 -

(Total) (682) (631)

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2. DAW (North Anna /Surry) North Anna Surry oCompacted DAW (ft'/y) 6,000 6,000

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i NRF WASTE FORMS LSA BOXES COMPACTED DAW  ;

MISC UNCOMPACTABLE WASTE & COMPONENTS HIC'S DEWATERED LOW ACTIVITY RES!N l j i -

DEWATERED HIGH ACTIVITY RESIN (LESS THAN HIC LIMITS) l MISC. HOT DAW CEMENT SOLIDIFIED LINERS HIGH ACTIVITY RES!NS (GREATER THAN HIC LIMITS)  :

j -

PRIMARY FILTERS  !'

BITUMEN DRUMS

• LOW ACTIVITY RES!N EVAPORATOR CONCENTRATES SLUDGES APPROVED ATI TOP! CAL EXPECTED j '

WASTE CLASSIFICATION I

) FACILITY G0AL: NOTHING GREATER THAN CLASS C 1

l CLASSIFICATION SYSTEM UNCHANGED (RADMAN) g b "*

1  !

I _ _,_ - - ..__ _ .

._,-_ _ _-_ _ _ D.

t .

CONTRACT PERFORMANCE SCHEDULE 1987 1988 1989 1990 f1991 BASIC E ESIGN I

OVIL / STRUCTURE DESIGN I I MECH I ELECJISC DESIGN I I I I I PACKAGED SYSTEM DESIGN / FA8RICATION I

I

, TANK / PUMP FABRIACATION I

J I I

ELEC / INST / HVAC EQUPMENT FABRICATION I I I

MO81L / EXCAV Cl i NORTH ANNA CONSTRUCTION NORTH ANNA I l TESTING I I I MOSIL / DEMOL / EXCAV T I SURRY CONSTRUCTION I I SURdY TESTING I

I c3 HOT TEST I

I __-_ _ . - _ _ - _ - _ _ _ _ _ _ _ - _ - _ _ _ _ - _ _ _ _ _ - - _ _ _ _ _ _ _ - - _ _ - _ _ _ _ - _ _ -- _ .-_ _. - . _ . . _ - . _

NOTIFICATION TO NRC OE RADWASTE PROCESSING CHANGES i

INITIAL BRIEFING OVERVIEW ACTION PLAN LICENSE REQUIREMENTS ,

OL NORTH ANNA l UNIT 1 LICENSE CONDITION 2.B(3)e UNIT 2 LICENSE CONDITION 2G NO PARTICULAR TIME FRAME IDENTIFIED PROPOSE VI A TECH SPEC REPORTING REQUIREMENT  :

l, OL SURRY ,

i No LICENSE CONDITION REQUIREMENT TECH SPEC REPORTING REQUIREMENTS NORTH ANNA l 1

NORTH ANNA UNIT 1 - TS 6.16 NORTH ANNA UNIT 2 - TS 6.15 REQUIRED FOR CHANGES TO SOLID WASTE SYSTEMS 4

l (WILL ALSO INCLUDE LIQUID EFFLUENTS)

SURRY SURRY UNITS 1 AND 2 - TS 6.9 REQUIRED FOR CHANGES TO LIQUID, SOLID & GASEsdS SYSTEMS l l l SUBMITTAL SCHEDULE KEYED TO SNSOC APPROVAL  !

i i

a

SAFETY EVALUATION l 10CFR50.59 REVIEW PROCESSES STRUCTURES  :

POTENTIAL ACCIDENTS / RELEASES COMPARISON TO UFSAR RELEASES COMPARISON TC iXISTING RADWASTE SYSTEMS COMPARISON TO APP.! EVALUATION ENVIRONMENTAL REVIEW (NON-RADIOLOGICAL) .

PER NAPS ENVIRONMENTAL PROTECTION PLAN (EPP)  ;

EVALUATE POTENTIAL "UNREVIEWED ENVIRONMENTAL QUESTION" l

I AIR QUALITY IMPACT I

+

, WATER QUALITY IMPACT (NPDES) .

j GROUND WATER IMPACT -

l -

EVALVATION PROCESS APPLIED TO BOTH SURRY AND NORTH ANNA

RADIOLOGICAL IMPACT EVALUATED BY 10CFR50.59 BOTH 10CFR50.59 AND ENVIRONMENTAL EVALUATION TO BE SUBMITTED FOR SNSOC 1

j APPROVAL AS PART OF NRF SAFETY ANALYSIS REPORT l i

4 i

1 r

A 4

h

" + i o

i TECH SPEC REVISIONS NO CHANGES REQUIRED FOR NORTH ANNA l

l SURRYTSREQUIRECHANGESONLYBECAUSESPECIFICMARKNUMBERS*OFEFFLUENT!

MONITORS ARE SPECIFIED

• i SINCE EFFLUENT MONITORING MUST BE IN ACCORDANCE WITH APPROVED STAT!0N PROCEDURES, NRF EFFLUENTS WILL BE CONTROLLED AS PER TS 4 .

' NOTE: A PROPOSED TS CHANGE REQUEST (INITIATED INDEPENDENT OF NRF PROJECT)

WOULD EllMINATE THE SUBJECT MARK NUMBERS AT SURRY. IF THIS IS APPROVED, NO CHANGES TO TS WOULD BE REQUIRED FOR EITHER NORTH ANNA 4

OR SURRY, -

4 i

l

.I 1 .

I f

i l

i .-- _

4 CONTROLLED DOCUMENT REVISIONS UPDATED FSAR FOLLOWING COMPLET!0N OF FACILITY (2/91)

PER ANNUAL UPDATE REQUIREMENT (6/92) l - POSSIBLE EARLY, STANDALONE UPDATE 0FF-SITE DOSE CALCULATION MANUAL (0DCM)

CHANGES APPROVED BY SNSOC CHANGES SUBMITTED VIA SEMI-ANNUAL EFFLUENT REPORT l CHANGES ADMINISTRATIVE IN NATURE (SAMPLING LOCATIONS) -

j -

NO CHANGES TO METHODOLOGY OR PARAMETERS l l

) PROCESS CONTROL PROGRAM (PCP) -

CHANGES APPROVED BY SNSOC

CHANGES SUBMITTED VIA SEMI-ANNUAL EFFLUENT REPORT ADDITION OF APPROVED PCP FOR BITUMEN SOLIDIFICATION I f -

POSSIBLE ADDITION OF APPROVED PCP FOR WASTE Oil SOLIDIFICATION .

i

! l l l I

I i i

i

- - - - - -+--4 --m% a y+w- em ----,ce--m- - - ,-m=

-w--w---'im.y+w,-+-m-w a g-wq+e -e w-y-g- -- +*.yp-- yb cw,--w ww w

NRF SECURJTY REQUIREME_NI PROTECTED AREA NOT REQUIRED NO "SPECIAL NUCLEAR MATERIAL" NO SAFETY RELATED EQUIPMENT GENERIC LETTER 81-38 REQUIREMENTS FOR STORAGE FACILITY (INCLUDES PROCESSING)

ON PLANT SITE PHYSICAL SECURITY

, FENCE

. LOCKED AND ALARMED GATES / DOORS

, PERIODIC PATROL (IF NECESSARY)

RADIOLOGICAL PROTECTION PROVISIONS

. UNRESTRICTED AREA - OUTSIDE NRF FENCE

, RESTRICTED AREA (NON-RCA) - NRF FENCE REQUIRED

. RESTRICTED AREA (RCA) - ACCESS CONTROL SYSTEMS REQUI SHOULD NOT REQUIRE USE OF PUBLIC ROADS TRANSFER TRENCH REQUIRES COMPLIANCE WITH SECURITY PROGRAM VEMICIE TRANSPORT BETWEEN NRF AND STATION MUST COMPLY WiiH STATION SECURITY PROGRAM i

l I

i NRF LICENSING PLAN SCHEDjjkE  !

i t

j VA. POWER COMPLETE SAR - 6/88  !

t l

SNSOC REVIEW & APPROVAL - 7/88  !

1 INDEPENDENT REVIEW & APPROVAL - 8/88 i  ;

) (START OF CONSTRUCTION - 9/88) j SUBMITTAL 0F TS REPORTING REQUIREMENTS - 2/89 7 3 j SURRY TS CHANGE (IF REQUIRED) - 1/90 t .

i ,

l

) (COMPLETION OF FACILITY - 2/91) j!

j i 4

SUBMITTAL OF ODCM a PCP REVISIONS - 8/91 l l

1 SUBMITTAL OF UFSAR UPDATE - 6/92 (LATEST) '

I i

1 1

1 i

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_ - . _ _ - - _ - . . - - - . _ - . _ _ - . - _ _ . . . - . -.