ML20080R090

Rev 7 to Process Control Program for Re Ginna Nuclear Power Plant

ML20080R090
Person / Time
Site:	Ginna
Issue date:	11/09/1994
From:	ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17263A955	List: ML17263A954 ML17263A956 ML20080R090
References
PROC-941109, NUDOCS 9503090162
Download: ML20080R090 (28)

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I PROCESS CONTROL PROGRAM FOR I

R.E.

GINNA NUCLEAR POWER PLANT h

Rochester Gas & Electric Corporation Revision 7 PORC:

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. PURPOSE LI 1 SCOPE 1..............

Page.1.

4 I

n V

LIII REFERENCESi, i.

Page.:2 -

IV: LRESPONSIBILITIES:.

Page.2.

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.V-LDEFINITIONSL z.

1 VIL PREREQUISITES.

lPage'4 REQUIREMENTS (FOR PROCESSING VENDORS

,. LPage 5-VII r

Page.6 VIII WASTE MANAGEMENT PRACTICES 1.0= Waste. Stream Sampling.

Page 6 2.0 Waste Classification PageJ8-l 3.0 Waste 1 Packaging...

Page 8-4.0 ' Chemical-Control-

-Page 9' 5.0 Volume' Reduction Page;9 6.0 Solidification, Stabilization, and Encapsulation'Page~9 7.0 Dewatering..

Page;11 80 Ra'dioactive Material Shipments Page-11 9.0 Quality Control for. Sampling and Classification-Page!11

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IX

' INTERIM STORAGE:

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ATTACHMENTS Page 13

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ProcL :: Control Program Paga 1 RADIOACTIVE-WASTE PROCESS CONTROL PROGRAM

- I PURPOSE:

To provide a description of the radioactive waste Process Control Program (PCP) at the Ginna Nuclear Power Plant (Plant).

Methods are described for processing, classification and packaging of low-level. radioactive waste into a form acceptable for disposal in accordance with 10 CFR.Part 61 and current disposal site criteria.

II SCOPE:

Sampling, classification, processing and packaging of radioactive waste.

1.0 Waste Stream Identification Nine different waste streams have been identified for classification purposes.

Examples of waste streams are:

1.1 Dry Active Waste (DAW) paper wood plastic metal cloth rubber glass soil oil and grease NOTE Contaminated oil is classified the same as DAW.

1.2 Primary Bead Resin

1. 3 Liquid Waste Processing (LWP) Bead Resin 1.4 LWP Activated Charcoal 1.5 LWP Filters LWP cartridge filters LWP bag filters Waste Hold Up Tank (WHUT) cartridge filters L

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Reactor Coolant (Rx) ' filters

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Boric Acid Storage Tank L.(BAST). filters.

Seal. Water: Return filters Seal WaterfInjection filters Reactor Cavity filters g4.

Ion Exchange: filters filters' i

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Concentrates Holding Tank:(CHT).

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Spent Fuel Cartridge Filters d

1.7 Spent Fuel' Pool (SFP) Skimmer filters Spent Fuel Pool' filters

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Tri-Nuclear filters (3 uM).

Tri-Nuclear filters (10 uM) 1.8 Secondary Filters.

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Sludge Lance cartridge filters.

High Conductivity Waste Tank (HCWT) bag (filters

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fl.9 Secondary Bead; Resins AVT Bead Resins l

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III

REFERENCES:

A current set of DQT, NRC, EPA, New-York Stdte, Volume

-Reduction Facility, and Disposal Site regulations and' requirements shall be maintained'at the Plant and.readily l

available for: reference.

A listingLof most of these references is given in Attachment 1.

L(Reference NRC IEB 79-19)

L

?IV RESPONSIBILITIES:

q The Health Physiciat responsible.for Radwaste has'the overall-responsibility for implementingLthe PCP.

Implementing responsibilities include the followingi a)

Preparing and. reviewing implementing procedures.

b)

Ensuring that radioactive waste is characterized and classified in accordance with-10 CFR Part 61.55 and-

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Part 61.56.

c)

Providing a point of contact with any volume reduction facility or disposal site.

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Maintaining records of on-site and off-site sample analysis of waste streams.

i V

DEFINITIONS:

I Batch: An isolated quantity of feed waste to-be processed having: essentially constant physical and chemical characteristics.

I Chelatina Acents: The NRC Branch Technical Position 1983 refers to EDTA, DPTA, hydroxy-carbolic' acids', citric-acid,Jcarbolic acid and glucinic acid as chelating

' agents.

Dewatered Waste: Wet waste that has been processed by means other than solidification or encapsulation to meet the free standing liquid requirements of 10 CFR Part 61.56 (a) (3) and (b) (2).

Encaosulation: A means of providing stability for certain waste types.by surrounding the waste with an appropriate encapsulation media.

Gamma-Soectral-Analysis: Using gamma spectroscopy to identify radioisotopes.

Homoceneous: Uniformly distributed throughout the waste material. Most waste streams are considered homogeneous for purposes of waste classification.

Low-Level Radioactive Waste (LLRW) :. Waste not classified.

as High-Level radioactive waste, transuranic waste, spent nuclear fuel, or by-product material as defined in section 11e. (2) of the Atomic Energy Act - (uranium or thorium tailings and waste).

Radioactive wastes that are acceptable for disposal in a land disposal-facility comprised of source, special nuclear, or by-product material.

Processing: Changing, modifying, and/or packaging radioactive waste into a form that.is acceptable to a disposal facility.

Scalina Factor: A dimension less number which relates the-concentration of one easily measurable nuclide (usually.a t

gamma emitter) to another nuclide that is usually difficult to measure (usually a beta and/or alpha emitters).

e Sionificant Ouantity: For the purposes of waste classification the following radionuclide values shall be considered significant and must be reported on the disposal manifest:

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' Contro.1 Program Pag 3 4 k-a)

.Any real value or the LLD for H-3, C-14, Tc-99 or I-129.

b)

Greater than or equal to 1 percent of. concentration limits listed in 10 CFR 61.55 Table 1.

c).

' Greater than or equal to 1 percent of the Class A concentration limits listed in 10 CFR'61.55 Table 2 except' isotopes having half-lives less'than.5 years.

d) 7 uCi/cc for Isotopes with half-lives less than 5 years and radionuclides not listed in 10 CFR 61.55.

e)

Greater than or equal to 1. percent of the total activity.

f)

Greater than or equal to 1 percent of the Reportable Quantity limits listed in 49 CFR Part 172.101 Table 2

Soecial Radionuclides: The RADMAN computer code term used to describe 10 CFR 20, Appendix F, required radionuclides.

Stability: The waste form will maintain its structural integrity under the expected conditions of disposal.

Trainina: A systematic program that ensures a person has knowledge of contaminated hazardous materials and contaminated hazardous materials regulations.

Waste Container: A vessel of any shape, size, and composition used to contain the final processed waste.

Waste Form: Waste in its container, in a final form, that is acceptable for disposal at a licensed disposal facility.

Waste Stream: A Plant specific source of waste with a distinct radionuclide content and distribution.

Waste Tvne: A single packaging configuration and waste form tied to a specific waste.

VI PREREQUISITES:

1.

Mainten&nce of Regulatory Material A current set of DOT, NRC, EPA, New York State, Volume Reduction Facility, and Disposal Site regulations and requirements chall be maintained at the Plant and readily available for reference.

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. Representative Radionuclide: Sample-Data kg,

Current-representati'.ve radionuclide-sample. data;shall be'

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Jon.fileffor each active ~ waste' stream. <When. operating conditions changeLor processing' methods require increased d

sampling. frequency, new sample data will be: generated.

Data is-considered to be current'if it meets the q-T'

'following:

.a).

NRCLClass A' waste streams: sampled 1within last-tw'o.

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years.

1 b)

'NRC Class B or' Class C waste streams and waste streams that have the potential to be NRC Class B or Class C sampled.within last year.

(Reference Branch Technical. Position Paper 1983).

3.

Initial and Cyclic Training

. imp 1'emented: and i

A training program is developed, maintained for all plant personnel involved,in processing,-packaging and handling of radioactive waste-(Reference NRC'IEB 79-19).

Training is required for each person: who:

a)

Classifies hazardous materials b)

Packages hazardous materials t

c)

Marks and labels packages containing hazardous materials j

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-Prepares shipping papers.for hazardous-materials e)-

Marks or placards transport vehicles; f)

Inspects or: tests packages or transport vehicles t

.4.

Only trained personnel will characterize or package ~

radioactive waste or radioactive materials.

VII REQUIREMENTS FOR PROCESSING VENDORS:

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The Health Physicist responsible for Radwaste or a designee shall review vendcr(s) topical reports and test procedures.

2.

Plant PORCLshall assure that the vendor's operations and requirements are compatible with the responsibilities-and operation of the Plant.

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, Vendors shall provide'. documentation:they maintain;

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?L documentation that tests for stability of the final' product'have been completed'successfullyLand demonstrate that they. meet the criteria given iniAttachment'2.

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LVIII'-

WASTE MANAGEMENT PRACTICES:

Y L1. 0 Waste Stream Samulina x1.1l The following general requirements apply to Plant waste e

stream sampling:

a)

Each waste stream is treated separately for classification' purposes.

P b)

The minimum sample 1 frequency requirements.are' met.

c)

' Samples are representative of'the waste' stream.

d)

An in-house analysis is performed'_for gamma emitting radionuclides for each sample sent to an independent.

laboratory.

e)

As waste is generated, an in-house. analysis is

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. performed for gammatemi' ting radionuclides to:

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~ compare to the current database values. The current database is usually.the mostJrecent independent laboratory results.

l 1.2 Changes in plant operating conditions'which may affect waste streams may require increasing sampling

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frequencies. Increased sampling requirements.are given in implementing procedures.

1 1.3 Infrequent or abnormal waste types requirements are:

.l a)

The Health Physicist responsible for Radwaste or designee'shall determine if the waste can-be correlated to an existing. waste stream.

The. Health Physicist responsible for Radwaste ore 1

b).

designee shall ensure specific sampling and analysis j

requirements are met to properly classify the material..

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The Health Physicist responsible for Radwaste or designee shall resolve:any discrepancies between

-in-house results and the independent laboratory-results for the same or replicate samples.

d)

The Health Physicist responsible _for Radwaste or

' designee shall maintain records of on-site-and off-site sample analysis and evaluations of waste streams.

1.4 Scaling factors _are established where by concentrations of radionuclides which cannot be readily measured are

. estimated through ratioing to radionuclides which can be readily measured a)

Scaling factor relationships are developed on a-waste stream specific basis.

These relationships are periodically revised to reflect current independent laboratory data from direct measurement of samples.

b)

Hard to detect activation product radionuclides and C-14 are estimated by using scaling factors based on measured Co-60 activities.

c)

Hard to detect fission product radionuclides are estimated by using scaling factors with measured-Cs-137 activities.

d)

Hard to detect transuranic radionuclides are estimated by using scaling factors with measured Ce-144 activities.

When Ce-144 cannot be readily measured, transuranics are estimated by using Cs-137-activities.

e)

As a minimum, the following radioisotope activities will be determined by direct measurement or calculated from developed scaling factors.

H-3 Zn-65 Ag-110m Ce-144 C-14 Sr-89 Sb-124 Np-237 Cr-51 Sr-90 Sb-125 Pu-238 Mn-54 Nb-94 I-129 Pu-239 Fe-55 Nb-95 I-131-Pu-240 Co-57 Zr-95 Cs-134 Pu-241 Co-58 Tc-99 Cs-137 Am-241 Fe-59 Ru-103 Ba-140 Cm-242 Ni-59 Ru-106 La-140 Cm-243 Co-60 Ag-108m Ce-141 Cm-244 Ni-63 f)

H-3 activity in any waste stream should not exceed the concentration as indicated in the primary coolant i

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lThe-activity for;each-waste stream'is determined by.using s.

direcc measurement"of radionuclides;or-gross:

radioactivity measurement.

Current practices are':

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' DAW, : Gross. radioactivity' measurement [in~ conjunction with C,

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hand. calculation-or' computer codes, forLexample:.RADMAN' d

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D' Filters:- Grossiradioactivity'measurementIin conjunction!

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'with: hand'. calculation or computer codes,:for.examplei n

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Soil - Direct measurementiof. radionuclides 1in conjbnctionu

- with hand calculation or computer codes.

All Other Waste: Streams - Direct. measurement of 4

radionuclidesLin' conjunction with' hand calculation;or-1

computer codes;

, 2.0 Waste-Classification Determination-of the NRC waste classification is-performed by. comparing the measured or. calculated ~

concentrations of significant radionuclides in the final waste. form'to those listed in 10 CFR 61'.55 and burial site' criteria.

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- Waste Packacinc 3.1; All disposal' liners are manufactured byLand. purchased from.QA. approved' vendors.

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All casks are manufactured'by,.l' eased,' rented or 3.2 purchased from'QA approved vendors.

3.3 All' services. purchased from QA approved' vendors.

3 '. 4 DOT. Specification 7A,. Type.A Packaging for'~ shipping and disposal are purchased to meet the requirements of.49 CFR 173.415.

3. 5 '

Strong Tight containers for shipping and disposalfare either purchased-.from a vendor or. constructed'in the

Plant, i

3.6 Each. cont'ainer of waste being shipped directly.to a disposal site.shall be clearly' labeled to identify'it asi 7

Class A waste, Class B waste'or Class'"C" waste in-accordance with 10 CFR 61.55.

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'its packaging are reduced to the(extent practicable to be.

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{less than or equal to.15 percent by volume or aEvariance-..

'isfobtained from1the-disposal; site.-

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Constituents [that may cause problems with cement

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. stabilization,2 filter breakEdown, anaerobic > activity,;or.

p generationLof mixed waste are excluded:from introduction d

into-the' waste streams.

4_. 2 Any new. constituents.that may be.directly.or-inadvertently introduced:into'any waste streamLwill be,

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evaluated for their effect prior to use.

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5 '.1 Radioactive material is'sent tx) a vendor'for volume Lj

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reduction processing.instead of directly'to a disposal-il site when~possible.

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5.2 Procedures implementing the PCP-specifyLthe' requirements

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for waste classification before radioactive material is' sent to vendor' facilities.

'5.3 Procedures implementing the PCP do not addressfthe requirements-for 10 CFR 61.56' Waste-Characteristics for-material sent.to intermediate processors since the, final treatment and packaging is performed at the vendor facility.

5.4 The types-of radioactive material sent to intermediate processors may include but is not-limited to the

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following:

i DAW Low Activity Bead Resin Low Activity Activated Charcoal-Contaminated Soil Contaminated metal 6.0 Solidification.' Stabilization, and'Encaosulation~

6.1 Solidification, stabilization, or encapsul tion is 9

performed in.accordance.with Ginna or~ vendor operati~ng.

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procedures and instructions.

The-use'of applicable testi

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data (for exampler Topical Reports)--may be used for

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Process Control Program qualification.

The test data

-must demonstrate'that the requirements given in Attachment IV are met.

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'LSolidified Class A waste,: separated from Class B'and C-waste, need 4nly demonstrate the product is a free

-standing monolith with no more.than 0.5 percent of-the

. volume as free liquid.

6.3-Solidified Class A waste not separated from Class B.

and/or Class C waste,. Class B.and Class C waste shall L_

meet the stability requirements of 10 CFR 61.56'(b). In order to ensure that Class'B'and/or Class C waste or its

. container will maintain its stability, the following c

conditions need to be met:

a)

The waste shall be a solid form or in a container or structure that provides stability after disposal.

c b)

The wastes shall not contain free standing..or corrosive liquids that-exceeds.1 percent by volume in containers designed to provide stability, or 0.5 percent by volume for solidified waste as measured using the method-in ANS 55.1.

c)

The waste or container should be' resistant to degradation caused by radiation effects.

d)

The waste or container should be resistant to biodegradation.

e)

The waste or' container should remain stable under the compressive loads inherent in the disposal environment.

f)

The waste or-container should remain stable if exposed to moisture or water after disposal.

g)

The as-generated waste should be compatible with the solidification media or container.

6.4 All waste must be stabilized if it contains isotopes with greater than 5 year half-lives and the total specific activity is greater than 1 microcurie / cubic centimeter.

This includes, but is not limited to, ion exchange resins, filter media, sludge, liquids, biological' waste and dry active waste.

Specific requests to bury DAW which exceeds the 1 microcurie / cubic centimeter limit which has not been stabilized may be considered by the disposal facility and NRC.

I

f.D ML.T Pro ~n Controli Program Page 11 7.0

'Dewaterina

-7.1 Wet radioactive material is dewatered by allowing water to' drain from the material completely.

As water is F

collected it is. removed by gravity drain or suction.

Material may be transferred to a vendor for further dewatering, volume-reduction or incineration.

Material prepared for shipment to_a burial facility will be dewatered to contain less than or~ equal to one percent I

y liquid by volume.

1 I

s 7.2 Dewatered resins with activities which will produce greater than 1 E+08 rads total accumulated dose over 300 years will not be shipped off-site.

This is usually i

verified by comparing the specific activity at time of shipment to the following concentration limits:

1 10 curies per cubic foot l

2E 350 micro curies per cubic centimeter-i 8.0 Radioactive Material Shioments 8.1 Procedures implementing the PCP address the requirements l

for waste classification.

8.2 Procedures implementing the PCP address the requirements for waste characteristics.

9.0 Ouality Control for Samolina'and Classification 9.1 The RADMAN computer code provides a mechanism for conducting a quality control program in accordance with waste classification requirements listed in 10 CFR 61.55.

All waste stream sample data changes are written to a computer data file for comparison review and future reference.

9.2 Audit frequency and management 1 review includes:

a)

Periodic audits which must include management

reviews, b)

Periodic management audits of the Ginna's sampling and classification progran to verify the adequacy of maintenance sampling and analysis.

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W riodicLaudits.are performed and documented by any?'

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.The-Plant' audit program is detailed;in'QA-1802 QA a

N Audit:and Scheduling.

9.3 General 1 requirements for vendor packagescare:

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Perform all inspection, handling and~ loading

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operations per= approved Ginna and/or vendor tj instructions and procedures.

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Store each container with.its designated closure assemblies to' prevent mismatching.

9.4

. General requirements for inspection prior to use include:

o a)

Ensuring all. containers are loaded-to meet the requirements of-test and' evaluation, for example:

WHO-EP-0558' Test and Evaluation' Document for. DOT Specification 7A Type A Packaging.

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Visually inspecting thread and seal areas-to verify they are free of foreign matter that could impair the thread or seal engagement.

c)

Visually inspecting the exterior' surfaces.for damage that may have occurred during transport or storage that could lessen the container integrity.

d)-

Visually: inspecting the lid.for sufficient closure.

IX-INTERIM STORAGE:

Waste is collected, packaged and stored at designated locations until shipment is arranged.

In the event that access to a disposal' facility is denied:

Implementing procedures will describe.the processing, packaging and storage of waste generated at the plant.

Implementing. procedures will describe the receipt and L

storage of processed waste returnea from a vendor h

following volume reduction.

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! DAW?willibe' packaged and stored.in thefUpper-Radwaste?

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Storage" Building 7 (URWSB);.

' Q, The waste;materialLremainingJfrom the"DAWLshipped to s

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vendorjfor.' processing 1and returned't'o'RG&E will.be' stored

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.j Low' activity: filter media'will'be packaged and'may.be secred either.in the URWSB or the HIC Open. Storage Area-7

- to be. constructed.

o The waste material remaining fromLlow activity filter media shipped to a vendor for processing land r.eturned.to-

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RG&E may'be stored either in the URWSB or the' HIC Open

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High activity filter media will be packaged and~ stored in 3-the HIC Open Storage Area.

4 The-' waste material remaining'from high activity filter media which is shipped to.a vendor;for processing and -

returned to RG&E'will be stored in the^ HIC Open. Storage

Area, ATTACIDENTS :

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Figure'1, Block diagram of typical waste processing-system

.Tigure 2, Block diagram of; typical dewatering system-Attachment l 1, - Ref erences ' Available for Radwaste -

Processing and' Shipments-

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ATTACHMENT l1>

REFERENCES'AVAILABLE FOR RADWASTE-PROCESSING AND SHIPMENTS-e t

'1. 0 FEDERAL" REGULATIONS' 1.~1 Code of Federal Regulations, Title 10,.Part 20

,1.2 Code of^ Federal Regulations, Title 10, Part 61

.1.3 Code of' Federal Regulations, Title 10, Part 70 1.4 Code of Federal Regulations, Title 10,'Part 71 1.5 Code of Federal Regulations, Title 29, Part 1900'.1200 P

1.6-Code of Federal Regulations, Title 40, Parts 240 Through 272 1.7 Code of Federal Regulations, Title 49, Parts 100 Through 180 1.8 Code of Federal Regulations, Title 49, Parts 350 Through 399

.i 2.O NRC INFORMATION NOTICES 2.1 NRC Information and Enforcement Bulletin 79-19: Packaging of Low-Level-Radioactive Waste for Transportation and Burial.

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2.2 NRC Information Notice 80-24: Low-Level Radioactive Waste Burial Criteria.

2.3 NRC Information Notice 80-32: Clarification ~of Certain Requirements for Exclusive-Use Shipments of radioactive Materials.

.2.4 NRC Information Notice 80-32, Rev 1: Clarification of

-Certain Requirements for Exclusive-Use Shipments of Radioactive Materials.

2.5 NRC Information Notice 82-47: Transportation of Type A Quantities of Non-Fissile Radioactive Material.

2.6 NRC Information Notice 83-05: Obtaining Approval for-

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Disposing of Very-Low-Level Radioactive Waste - 10'CFR Section 20.302.

2.7 NRC Information Notice 83-10: Clarification of Several Aspects Relating to Use of NRC-Certified Transport Packages.

2.8 NRC Information Notice 83-14: Dewatered Spent Ion i

Exchange Resin Susceptibility to Exothermic Chemical Reaction.

C

[ Proc::y ' Control Program.

Pag 3 17 w

t.*

Attachment I Page 2 of 9

' 2. 9 NRC Information Notice 83-33: Non-Representative Sampling of Contaminated 011.

2.10-NRC Information Notice 84-14: Highlights of Recent Transport Regulatory Revisions by DOT and NRC.

2.11 NRC Information Notice 84-50: Clarification of Scope of Quality Assurance Programs for Transport of Packages Pursuant to 10 CFR 50 Appendix B.

2.12 NRC Information Notice 84-72: Clarification of Conditions for Waste Shipments Subject to Hydrogen Gas Generation.

2.13 NRC Information Notice 85-92: Surveys of Wastes Before Disposal from Nuclear Reactor Facilities.

2.14 NRC Information Notice 86-20: Low-Level Radioactive Waste Scaling Factors, 10 CFR 61.

2.15 NRC Information Notice 86-90: Requests to Dispose of Very Low-Level Radioactive Waste Pursuant to 10 CFR 20.302.

2.16 NRC Information Notice 87-03: Segregation of Hazardous and Low-Level Radioactive Wastes.

2.17 NRC Information Notice 87-07: Quality Control of On-Site Dewatering / Solidification Operations by Outside Contractors.

2.18 NRC Information Notice'87-31: Blocking, Bracing, and Securing of Radioactive Materials Packages in Transportation.

2.19 NRC Information Notice 88-08: Chemical Reactions With Radioactive Waste Solidification Agents.

2.20 NRC Information Notice 88-16: Identifying Waste Generators in Shipments of Low-Level Waste to Land Disposal Facilities.

2.21 NRC Information Notice 88-62: Recent Findings Concerning Implementation of Quality Assurance Programs by Suppliers of Transport Packages.

2.22 NRC Information Notice 89-13: Alternative Waste Management Procedures in Case of Denial of Access to Low-Level Waste Disposal Sites.

2.23 NRC Information Notice 89-27: Limitations on the Use of Waste Forms and High Integrity Containers for the Disposal of Low-Level Radioactive waste.

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l l ' Proc: j Control Program Paga 18 y

Attachment I' Page 3.of 9 T

2.24 NRC Information Notice 90-09: Extended Interim Storage of Low-Level Radioactive waste by Fuel Cycle and Materials Licensees 2.25-NRC Information Notice 90-35: Transportation of Type A Quantities of Non-Fissile Radioactive Materials.

2.26 NRC Information Notice 90-50: Minimization of Methane Gas in Plant. Systems and Radwaste Shipping Containers.

2.27 NRC Information Notice 90-82: Requirements for Use of Nuclear Regulatory Commission Approved Transport Packages for Shipment of Type A Quantities of Radioactive Material.

2.28 NRC Information Notice 91-03: Management of Wastes Contaminated with Radioactive Katerials

(" Red Bag" Waste and Ordinary Trash).

2.29 NRC Information Notice 91-35: Labeting Requirements for Transporting Multi-Hazard Radioactive Materials.

2.30 NRC Information Notice 91-65: Emergency Access to Low-Level Radioactive Waste Disposal Facilities.

2.31 NRC Information Notice 92-62: Emergency Response Information Requirements for Radioactive Material Shipments.

1.32 NRC Information Notice 92-72: Employee Training and Shipper Registration Requirements for Transporting Radioactive Materials.

3.0 NRC REGULATORY GUIDES 3.1 Regulatory Guide 7.1: Administrative Guide for Packaging and Transporting Radioactive Material.

3.2 Regulatory Guide 7.2: Packaging and Transportation of Radio-actively Contaminated Biological Materials.

3.3 Regulatory Guide 7.4: Leakage Test on Packages for Shipment of Radioactive Materials.

3.4 Regulatory Guide 7.5: Administrative Guide for Obtaining Exemptions From Certain NRC Requirements Over Radioactive Material Shipments.

-~

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y% K.l ProcQaGl Control' Program iPaga'19e

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,.AttachmentLI-Page 4,of.9 s

"3.5:

RegulatoryfGuide 7.7:l Administrative Guide.for. Verifying' Compliance:With: Packaging. Requirements for ShipmentsLof j

' Radioactive' Materials.~

i i

3. 6-Regulatory Guide'7,.9, Rev 1: Standard Format and Content' of Part 71. Applications.for Approval of' Packaging of Type.

B,.Large Quantity and-Fissile' Radioactive. Material.

l 3.7

. Regulatory Guide 7.10,LRev 1: Establishing Quality-l Assurance Programs for Packaging =Used in the Transport-of Radioactive Material 4.0 NRC TECHNICAL POSITION

- 4.1 Final Waste Classification and Waste Form Technical' Position Papers, May 11, 1983.

4.2 Technical' Position on Waste Form, Rev.

1, January 1991.

L l

5.0 ANSI STANDARDS 5.1 ANSI /ANS-40.35-1991: Volume Reduction of. Low-Level Radioactive Waste or Mixed Waste.

i 5.2 ANSI /ANS-55.1-1979: American National Standard for. Solid Waste Processing System for Light Water..ooled Reactor' Plants.

5.3 ANSI N14.9.1-1976: Packaging ~for Transportation of Liquid.

Aqueous Radioactive Wastes From Nuclear Power Plants.

5.4 ANSI N679-1976: Guide for Writing Operating-Manuals for Radioactive Materials Packaging.

5.5 ANSI N14.7-1975: Guide to Design:and Use of Shipping-

~ Packages for Type A Quantities of Radioactive Materials.

6.0 R.E. GINNA TECHNICAL SPECIFICATIONS

-r 6.1, Section 6.16, Process Control Program-(PCP).

l 6.2 Section 6 17, Major Changes to Radioactive Waste Treatment Systems.

7.0 R.E.Ginna Updated Final Safety Analysis Report Section

'11.4,' Solid Waste Management. System.

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'ProcCw Control} Program Paga 20; rf i

4

' Attachment I' Page 5'of 9' l

'8.0 REPORTS-

~

t 8.1 '

EPRI, Interim On-Site Storage of: Low-Tevel Waste, Volume 4: Waste' Containers for Extended Storage,'. March 1992.

i 8.2 EPRI,'Radwaste Desk Reference, Volume 2:-TransportationL and' Disposal, June 1991.

8.3 EPRI, NP-4938,-Methodology-for Calculating 1 Combustible-Gas Concentration in Radwaste Containers, March 1987 8.4-EPRI, NP-5977, Radwaste Radiolytic Gas Generation L -

Literature Review, Spetember, 1988 8.5 NUMARC, A Technical Basis for Meeting the Waste Form Stability Requirements of.10 CFR 61.

8.6 WHC-EP-0558

Test and Evaluation Document for DOT Specification.7A Type A Packaging 9.0 INPO GOOD PRACTICES: Low Level Radioactive' Waste Management.

10.0 DISPOSAL SITE REQUIREMENTS 1

10.1 S20-AD-010: Barnwell Waste Management Facility Site

. Disposal Criteria.

10.2 Barnwell (South Carolina)' Disposal Site License.

11.O PLANT PROCEDURES r

11.1 A-101 Ginna Quality Assurance Program Implementation 11.2 A-805 Control of. Consumable Material at Ginna Station 11.3 QCIP-21 Inspection of Shipping Packages (Casks) for' Radioactive Material 11.4 QCIP-21.1 Inspection.of Shipping Packages (Casks) for Westinghouse Surveillance Capsule 11.5 QCIP-21.4 Radlock Inspection Procedure 11.'6 QCIP-21.6 Inspertion of Exclusive Radioactive Material Transport Vehicles t

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, a;; p : ?ProcjbOl Control Program Paga 21

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i SAttachment'I

,Page 6:ofc.9s

'j i

< 11'. 7

.QCIP-700 Quality. Control General Acceptance Criteria 11.8

-QCIP-701 Receipt Inspection Process i

11.9

-S-4.1.27. Chem Nuclear Waste System Operation, Monitor a

Tank A Recirc Thru Liquid; Waste Processing System._

i 4

11.10 S-4.1.30 Chem Nuclear Waste System O

Operation / Sampling / Isolation land Records-Chem Nuc 3

Technician Procedure

.a e

11.11 S-4.1.31' Transfer of.WHUT Thru Chem Nuclear Waste System.

l

~

to A Monitor Tank 11.12 S-4.4 Spent Resin Removal to Shipping Casks

.k 11.13 S-4.5 Sluicing Waste Condensate Polishing Demineralizer i

e Spent Resin to Shipping Cask 1

i 11.14.

S-4.5.1' Sluicing Waste Evaporator Distillate Demineralizer Spent Resin to'a Strong Tight Container' cj 11.15 RP-RW-PROC-CN120A/B, (RD-10.14) Handling, Loading and si Unloading of Chem-Nuclear 8-120 A or B (U) Transport Cask l

11.16 RP-RW-PROC-HIC, (RD-16.5)' Waste Solidification in Chem-Nuclear' Systems, Inc. Polyethylene High Integrity-Container t

11.17

'RP-RW-PROC-CN14 /195, - (RD-10.18) Handling,' Loading'and-Unloading of Chem-Nuclear CNSIl14-195H Transport Cask

.i 11.18 RP-RW-PROC-NP142,- (RD-10.19) Handling,. Loading and Unloading'of NUPAC Model 10-142 Transport Cask.

11.19 RPA-RW-SHIP-WSTE, (RD-10.21) Preparation and Shipment.of 4

Radioactive (Waste)' Material-

-11.20 RP-RW-PROC-CNFLTR120,.(RD-10.22) Transfer and Loading-of

,[

Proc 2ss Filters Using CNS 8-120A/B or 14-195H Transport Cask 11.21 RPA-RW-INV, (RD-10.23) Radwaste Inventory f

1 11.22 RP-RW-INV-SMPLG, (RD-10.24) Representative Sampling of Radioactive Material i

1 11.23-RP-RW-SHIP-VR, (RD-10.27) Preparation and Shipment of Radioactive Materials to a Volume Reduction Facility 1

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JAttachment'I:

Page:7 of.'9-a 11.24 RPA-RW-FLTR-INV,. (RD-10.28) Characterization'and.~,

Inventory. Tracking of Filter Assemblies Prior to' Shipment g

E 11.25 RPA-RW-TRN,, ' (RD-10. 31 ) Training and Responsibilities;of Individuals Involved in Radwaste(Group' Activities k

11.26 RP-PCP-DEWATER, (RD-16.3) Dewatering Wet Solid' Wastes

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11.27 RP-RW-PROC-GAS, (RD-16.4) Combustible Gas Detection-in or s Near Radioactive Waste Liners / Containers-t 12.O VENDOR PROCCURES, LETTERS AND NOTES NOTE The operational aspects of -vendor procedures are referenced or incorporated into site-specific procedures.

12.1 Pacific = Nuclear Systems Inc., Q.A. Manual, latest.

revision.

12.2' Chem-Nuclear Systems,.Inc., Q.A. Program' Document No.

QA-AD-001,. latest revision-

.12.3 Scientific. Ecology Group, Inc., Q.A. Program'No.

SEG/QA 100, latest revision 12.4 "RADMAN - A Computer. Code", Main Topical Report 12.5 NRC acceptance Letter: RADMAN Topical Report, July 25, 1983 12.6 WMG/P-045: Operating Procedures for RADMAN Software 12.7 WMG-9006: WMG Computer Program Dose-to-Curie Methodology verification and Validation 12.8 WMG/P-007: Operating Procedures for FILTRK Software

_,t 12.9 WMG/P-009: Operating Procedures for RAMSHP Software

[

12.10 WMG/P-010: Operating Procedures for TRASHP Software-12.'11 WMG-QA-011: WMG Quality Assurance Program 12.12 Chem-Nuclear Systems, Inc., Topical Report, Dewatering e

Control Process Containers, CNSI-DW-11118-01-NP-A' r

b S.

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%[&&'?Proddb6 Control [ Program; 1

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?AttachmentEIi PageI8 ofi9L (12.13 Chem-Nuclear Systems,'Inc., Topical Report,,Polyethylenei NE 4

PT

+

HighlInt'egrity.Containersi:,CNSI-HIC-14571-01-NP '

4,

-, -G 112.14. fTR-OP-030: Handling Procedure fori:CNSi Transport Cask!

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.. Number :14-170: Series IIIJ t

g 12.15- =TR-OP-022: Handling' Procedure for.CNSI Transport, Cask.;

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' Number CNS'14 170 Series II-1 a

J12.16 FO-OP-023EBead Resin / Activated Carbon Dewatering l

- ?

Procedure for CNSI Liners i

1 p

TR-OP-008: Operation and Maintenance' Manual for.CNS 112.17 14-195H and' Typical Trailers L

12.18' FO-AD-002: Operating Guidelines for;-Use of Polyethylene-High Int'egrity Containers

~

l 12.19 TR-MN-005:. Gasket / Seal /O-Ring Replacement Repair Procedure for CNSILCask Fleet

- i i

12 20' -SD-OP-048: Process Control. Program and. Operating; a

Procedure for Insitu Solidification of Suspended Objectsi a

'12.21 Nuclear Packaging,;Inc.,, Topical. Rep. ort:No..TP-02-NP-A,..

describes dewatering system.

1 12.22; OM 101:' Operation and Maintenance Manual.for NuPac Model!

.10-142 and Typical TIailers.

c

.12.23

.LT-29: Seal Integrity TestLof the NuPac'10-142 Transport Cask 12.24 H-18: Handling,. Shipping,-and Storage for theLNuPac t

~;

CL-200 Polyethylene High Integrity Container-12.25 H-19 Off-Loading ~for NuPac Cl-200 Crossed linked Polyethylene High Integrity Container l

12.26 OM-16: Users Guide for.the NuPac Crossed linked.

l Polyethylene'High Integrity Containers 12.27

.OM-43: Operating Procedure for' Resin Drying (Dawatering) l f

. System

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12.28 OM-46: Handling, Shipping and Storage for NuPac 14/190,-

~

and 14/210 14-Drum Casks Shielded' Shipping Container 12.29.Lt-04: General Procedure for Soap Bubble (Low' Pressure)-

{

Leak Test i

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12.30 OM-10; Installation and-Torquing of.NuPac Ratchet Binders 12.31 RSM-022: SEG Rad Services Manual.for 14-170 i

'12.32' RSM-021: SEG Rad Services Manual for LN-142 12.33 RSM-018: SEG Rad Services Manual for 14-215 12.34 RSM-006: SEG Rad Services Manual for 3-82B Shielded-Transportation Cask

'12.35 RSM-009: SEG Rad Services Manual 10-142' Shielded Transportation Cask, i

i 12.36 TR-OP-003: Handling Procedure ~for Chem-Nuclear System, Inc., Transport Cask 8-120A 12.37 TR-OP-035: Handline Procedure _for Chem-Nuclear System,-

Inc., Transport. Cask CNS 8-120B.

13.0 International Air Transport-Association, Dangerous Goods i

Regulations, January 1, 1993 i

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ATTACHMENT 2 Page 1'of 2' Tests for stability of solidified wastes to be 4

-demonstrated by vendor:

a):

. Waste specimens shall.be prepare'd'on the proposed waste-stream-to be solidified and based on-the. range'of waste stream chemistries expected.

b)

Solidified waste. specimens should have. compressive strengths of at least 50 psi when tested in accordance with ASTM C39 or ASTM D1074 when a bituminous product.

i l

c)

Waste specimens should be exposed to a minimum of E+8 Rads in a. gamma irradiator or equivalent.

The specimens shall have a minimum compressive strength of 50 psi t

following irradiation as tested in accordance with ASTM C39 or ASTM D1074.

' d) '

Specimens shall be tested for resistance to biodegradation in accordance with both ASTM G21 and 7

ASTMG22.

Following biodegradation testing, specimens shall'have compressive strengths greater than 50 psi as tested.using ASTM 39 or ASTM D1074 e)

Leach testing shall be performed for a minimum of 90 days in accordance with the procedure in ANS 16.1.

In addition, synthesized sea water leachant will be tested and radioactive tracers utilized in performing leach tests.

The leachability index, as calculated in accordance with ANS 16.1, shall be greater than 6.

<f)

Waste specimens chall have a compressive strength of 50 psi in accordance with ASTM 39 or ASTM'D1074, following immersion for a minimum of 90 days.

Immersion may be performed in conjunction with the leach testing.

g)

Waste specimens shall.be resistant to thermal degradation.

The heating and cooling chambers used for the thermal degradation testing shall conform to the-description given in ASTM B553, section 3.

Samples shall

'j be placed in the test chamber and a series of 30 thermal' cycles carried out in accordance with Section 5.4.1 through 5.4.4 of ASTM BS53.

The high temperature shall be 60C and the low temperature limit-40C.

Following testing the waste specimens shall have compressive strengths greater than 50 psi as tested in accordance j

~ ith ASTM 39 or ASTM D1074.

]

w f

Waste specimens shall have less than 0.5 percent by volume as j

h) free liquids as measured using the method _used in ANS 55.1.

Free liquids shall have a pH_between 4 and 11 i

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lProcxd ; Control' ' Program :j

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If small,. simulated laboratoryfsize(specimens-are.used for ths above' testing, testdatanfrom sections or cor'es'of-tha 4 ' '

p'

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anticipated. full-scale products should be.obtained to b y~ '

correlate the: characteristics of. actual-size products 1with thos'e'of. simulated ~1aboratory size-specimens. -The testing.

may be performed on non-radioactive specimens.. The full scale specimens shallcbe. fabricated _using actual or.

~;

comparable solidification' equipment.

Lj)

-Waste samples-from_ full-scale specimen.shall be-P

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' destructively analyzed-to ensure that the product-produced" a

is homogeneous to the' extent-that all regions ~in,the l

product can_ expect toLhave compressive strengths greater-than 50 psi.

Full-scalefspecimens-may be fabricated using

,l

. simulated non-radioactive products, but~shall-be fabricated using actual solidification equipment.

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