ML20056G098

From kanterella
Jump to navigation Jump to search
Rev 0 to Procedure RW-C-100, Solid Radwaste Sys Pcp. Procedure Supersedes RW-800 at LGS & RW-120 & RW-121 at PBAPS
ML20056G098
Person / Time
Site: Peach Bottom, Limerick  Constellation icon.png
Issue date: 12/28/1992
From:
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20056G090 List:
References
RW-C-100, NUDOCS 9309020049
Download: ML20056G098 (13)
v • d • e


Text

_

RW-C-100, Rev. O Page 1 of 13

)f } {g{)((

APPROVED COPY PHILADELPHIA ELECTRIC COMPANY V0'lD PREVIO DISTRIBUD0QSS g NUCLEAR GROUP  !

/ l

__b2

  • d 8- k SL ._ l Effective Date

~

.i RW-C-100 SOLID RADWASTE SYSTEM PROCESS CONTROL PROGRAM (I I

~

Note:

This procedure supersedes RW-800 at LGS and RW-120,and i

RW-121 at PBAPS.  :

1.0 PURPOSE j 1.1 This program provides guidance and boundary conditions ,

for. preparation of specific procedures for processing,  !

l sampling, analysis, packaging and shipment of solid  ;

requirements.

REFERENCES  :

I 2.0 '

l 2.1 SOURCE DOCUMENTS

.g

-j 2.1.1 Low level Waste Licensing Branch Technical Position on j

^2 Waste Form. 5 2.1.2 Low Level Waste Licensing Branch Technical Position on

['[ I fj ( 5m Waste Classification.

f 2.1.3 South Carolina Department of Health and Environmental l

  1. g d Control Radioactive Material License No. 097.  !

43 Barnwell Waste Management Facility Site' Disposal 2.1.4

.3 Criteria.

2.1.5 Limerick Generating Station Unit 1 and 2 Technical 6.8.1, 6.13.

M Specifications, 6.5.1.6, -

Nevada State Health Division Radioactive Material

    • 2.1.6 License No. 13-11-0043-02, (Beatty Site).

-t 2.1.7 Updated Final Safety Analysis Report Peach Bottom Atomic l Power Station Units 2 and 3.

4 4.8.F, 6.18.3.

T* 2.1.8 PBAPS Technical Specification 3.8.F, s

2.1.9 RW-C-106, Review Of Vendor Topical Report For Waste

+E .

Processing.

-; I

-.a .

2.1.10 State of Washington Radioactive Materials License. 1^

.m -

- p 2.2 CROSS REFERENCE i

49 CFR Parts 170 through 178.  !

$ d$b 2.2.1

}E3 J a T5S[ _

9309020049 930826 kU l pf . PDR ADOCK 05000277 hi}

R pop ig,  !

- - ~ . - - , . _ _ ,

i RW-C-100, Rev. 0 Page 2 of 13 lh l

! 2.2.2 10 CFR Parts, 20, 50, 61, and 71.

2.2.3 Standard Review Plan 11.4, including Branch Technical l Position ETSBll-3.

2.2.4 Facific Nuclear: NuPac Services Topical Report for

! Dewatering System TP-02-P-A.

2.2.5 General Criteria for High Integrity Containers (SCDHEC).

2.2.6 PCP Implementing Procedures.

NOTE: PCP Implementing Procedures are those listed above which apply directly to processing, packaging, sampling, analyzing, and shipping radwaste.

1. Limerick and Peach Bottom Radwaste Procedur.es (RW) or Applicable Common Procedure.
2. Limerick and Peach Bottom Surveillance Test Procedures (ST) and Routine Test Procedures (RT).
3. Limerick System (S) and Peach Bottom System

- Operating (SO) Procedures. ggg 2.2.7 Nuclear Quality Assurance Plan; Radwaste/ Material Section.

2.2.8 Chem Nuclear Systems Inc. Topical Report RDS-1000 Radioactive Waste Dewatering System RDS-25506-01-NP-A.

2.2.9 Stock Equipment Co. Topical Report Quick Dry Process for  :

Dewatering Bead Resin and Filter Sludge, SRS-003-P. l 2.2.10 Westinghouse-Hittman Nuclear, Inc. Topical Report STD-R-05-Oll-A, Mobile Incontainer Dewatering and Solidification System. J 2.2.11 Generic Letter 89-01 (Implementation of Programmatic Controls for Radiological Effluent Technical Specifications in the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of RETS to the Offsite Dose Calculation Manual or to the Process Control Program),

1/31/89.

2.2.12 Off Site Dose Calculation Manual.

2.2.13 Limerick and Peach Bottom Chemistry Procedures or a Applicable Common Procedures. W 2.2.14 Nuclear Quality Assurance Audit Section, Master Audit

RW-C-100, Rev. 0 Page 3 of 13 i

2.2.15 Safety Evaluation f or Oil Decontamination, MOD 1259A  ;

() (Peach Bottom only).

~

Radwaste Dewatering -'

i 2.2.16 Safety Evaluation for MOD 1750A, Facility Peach Bottom Atomic Power Station (Peach Bottom ~

only).

Inc. Mobil Cement Solidification 2.2.17 Chem-Nuclear Systems, l System Topical Report, CNSI-2 (4313-01354-01P-A).

2.2.18 Chem-Nuclear Systems, Inc. 10CFR61 Waste Form '

Certification --Cement (WF-C-01-NP).  ;

2.2.19 NRC Generic Letter 91-02 " Reporting Mishaps involving  ;

LLW Forms Prepared for Disposal" t

3.0 RESPONSIBILITY AND AUTHORITY NOTE:

The station operating organizataon is outlined in each

" station's UFSAR.

PORC is responsible for reviewing all revisions to the

~

3.1 J PCP.

The Plant Manager is responsible for approving all

" 3.2 revisions to the PCP.

[-j { y}jj 3.3 The Nuclear Quality Assurance Department performs ~ audits l q

to ensure compliance with the Nuclear Quality Assurance A Plan.

l 3.4 The Engineer-Radwaste is responsible for:

~

3.4.1 Compliance with this Process Control Program.

3.4.2 Record keeping and document control of shipping and processing data. i

~

3.4.3 Assuring the Radwaste personnel are appropriately trained and qualified.

3.4.4 Coordinating reviews and revisions to this document and corresponding implementing procedures.

3.4.5 Reviewing and revising this PCP and its implementing procedures.

~.

3.4.6 Submitting revisions to the PCP for inclusion in the

" Semi-Annual Radioactive Effluent Release Report.

n'

. l em m~m 1

.3' '

4 .y; '

~~ .

I

. _ _ _ _ _ _ ~

RW-C-100, Rev. O Page 4 of 13 3.5 The Superintendent-Operations is responsible for:

3.5.1 Providing trained personnel to operate appropriate permanent radwaste process equipment.

3.5.2 Defining those Operations positions which require training.

3.6 The Superintendent-Training is responsible for:

3.6.1 Development and implementation of performance-based training for designated personnel utilizing the Training  ;

Systems Development (TSD) model in accordance with Training Division procedures.

4.0 PREREQUISITES 4.1 Processing of solid radioactive waste Training shall be performed records

' by qualified and trained personnel.  ;

for operators of mobile vendor processing units shall be l maintained by the Engineer Radwaste while the vendor is active on-site.

4.2 Vendor services may be used for dewatering and

. solidification of radioactive vaste. processing provided ggg the services are governed by a Topical Report and

('

ggg referenced in this PCP. Processing of radioactive waste by on-site vendors shall be performed in accordance with applicable Topical Report, pr'ocedures and NRC guidance, the m

When providing solidification for stabilization, vendor shall have an NRC approved topical report. -

l 4.3 The Topical Reports of vendor supplied Radwaste )

Processing Systems shall undergo review by.the Engineer- '

Radwaste (or designee). The review shall ensure the l vendor supplied system will be compatible with plant j

operations. The review shall be performed in accordance l

with applicable RW-C-106. (See Ref. 2.1.9).

l l l

l 4.4 On-site processing of radioactive waste shall be i performed in accordance with approved station '

procedures.

~~

4.5 Quality Assurance shall be maintained as defined by the Nuclear Quality Assurance Plan. (See Ref. 2.2.8}.

.e

~

O a

M

IM-C- h ,

Page 5 of 13 l 5.0 PRECAUTIONS AND LIMITATIONS

( 5.1 Changes to the PCP shall be submitted to the Nuclear l Regulatory Commission infor thethe Semi-Annual period in Radioactive which the Effluent Release Report -

change was made. t 5.2 Changes to resin dewatering implementlng procedures or ,

systems'shall require verification that the freestanding w established regulatory limits.

Prior to revising or deleting a PCP implementing 5.3 procedure, the preparer shall review the procedure against the PCP to ensure that there is no compromise or l conflict.  !

5.4 Prior to a modification to an inplant liquid Radwaste  !

Processing System the individual responsible for the MOD shall review to ensure that it is not in conflict with or compromises the PCP. i meet disposal site and shipping l 5.5 When processing does not .

and transportation requirements, shipment shall be  !

suspended and the PCP should be reviewed for adequacy.  !

The implementing procedures and/or the Solid Waste  !

' System shall be corrected as necessary to prevent recurrence.

7 4

s rAJ a

6.0 APPARATUS None

.' 7.0 PROCEDURE .

^

7.1 ' PROCESS DESCRIPTIONS NOTE:

Vendor services may be used to process any radioactive J

waste stream provided the services are performed with an ~

acceptable Process Control Program.

sh

.4

.] ? .

'O ge

..a

'md I

_ .. ... __ _ .-~ . , _

l. . . .

RW-C-100, Rev. O Page 6 of 13 7.1.1 Waste Sources (For diagrams of the Solid Radwaste g Systems, see UFSAR 11.4 for LGS and 9.2 and 9.3 for PBAPS. Also refer to MOD 1750A for PBAPS).

1. Condensate Filter /Demineralizer Waste
a. Condensate Filter /Demineralizer Waste is the waste product generated by the backwash of the condensate filter /demineralizers consisting of contaminated powdered ion exchange resins at var'ying degrees of exhaustion, fibrous filter media, and smell concentrations of various solids and corrosion products.
b. A condensate filter /6er.ineralizer backwash consists of approximarfly 9,000 gallons of slurry.
c. Backwashes are collected andClarified settled inliquid a

Condensate Phase Separator.

is decanted until sufficient volume of settled spent resin and crud is obtained for a

processing.

d. Phase separator contents are recirculated prior to transfer to the Dewatering System. O tj, 5 e. Slurry input to the Dewatering System is transferred to the system from the phase separators via the sludge mixing pumps.

b 2. Condensate Deep Bed Demineralizer Waste (Limerick Only) 1 Condensate Deep EedeD mineralizer waste is the j

a.

waste product generated by the backwash of the condensate deep bed demineralizers consisting of contaminated ion exchange bead resins at

" var ying degrees of exhaustion and small concentrations of various solids and corrosion products.

b. Each condensate deep bed demineralizer backwash consists of approximately 2,800 gallons of slurry.
c. Each backwash contains 320 cubic feet of resin and is collected in an empty Spent Resin Receiver Tank.
d. During normal operations the Spent Resin gg}

Receiver Tank contents will be transferred to

,, _ , _ _ . the Floor and Equipment' Drain deep bed kt1 demineralizers for reuse.

9 a

RW-C-19@, U@TT~w f -

Page 7 of 13 l I.

i i

i e.

Resins that are determined unacceptable for ,

l. reuse or excess will be processed from the 1A  ;

l ]) Spent Resin Receiver Tank using vendor dewatering. - f f.

The 1A Spent Resin Receiver Tank Contents are ,

recirculated for a minimum of 25inminutes resulting a to mix .

contents of the vessel, l homogeneous resin slurry.

g.

The solids slurry is then fed to the External Processing Station for dewatering.

3.

Waste Sludge Tank Waste a.

Waste Sludge Tank Waste is the waste product ,

generated by the backwash of the liquid radwaste,and fuel pool filters and  ;

demineralizers consisting of contaminated l powdered ion exchange resins and bead resins fibrous filter at l varying media, degrees of exhaustion, carbon overlay material an

',i concentrations of various solids and corrosion l 8

products.

lizers,

b. . Backwashes from radwaste filter /demineraradwll filter /demineralizers are collected in the ,

5 .g1 Waste Sludge Tank.

a wuy

c. A backwash from a radwaste filter consistsorof

" ~t approximately 1,925 gallons of slurry (PB)

~j 1,500 gallons (LGS). .

'l d. A backwash from the radwaste deep bed -

( demineralizer consists of approximately 1,500

. .a gallons of slurry.

t At Peach Bottom, the Waste Sludge Tank contents e.

are transferred to a Condensate Phase Separator for processing. From the Condensate Phase Separators, waste is processed using a

  • Dewatering System.

f.

At LGS, Waste Sludge Tank contents may be  ;

processed directly to the Dewatering System orl processing.

ja

  1. ' g.

Tank contents are recirculated prior to transfer to the Dewatering System.

Y O. .

ee

~~1.',

P" .

G .

RW-C-100, Rev. O Page 8 of 13 Reactor Water Cleanup Waste 4.

Reactor Water Cleanup waste is the waste 9

a.

product generated by the backwash of the Reactor Water Cleanup filter demineralizers consisting of contaminated powdered ion exchange resins at varying degrees of

, exhaustion, fibrous filter media, and small concentrations of various solids and corrosion products.

b. A RWCU filter-demineralizer backwash consists of approximately 1,100 gallons of slurry.

Backwashes are collected and settled in a phase c.

separator. Clarified liquid is decanted until sufficient volume of settled spent resin and crud is obtained for processing.

d. Phase separator contents are recirculated prior to transfer to the Dewatering System. .
5. Oily Waste
a. Sludges and oils generated during operation and maintenance are collected in containers in g appropriate approved areas throughout the W plant. The filled and labeled containers are i

1 f "4%*" sealed and moved to available areas for temporary staging.

i

b. Sludges /cils may be decontaminated to below J station free release limits and p'rocessed as non-radioactive waste.
c. Sludges / oils may be shipped off-site for processing.
6. Miscellaneous Waste
a. Certain wet wastes may be allowed to dry and be treated as dry active waste or filters.

7.2 WASTE STREAM PROCESSING 7.2.1 Dewatering

1. Resin processing is normally performed using a Dewatering System.
a. The Dewatering System shall be operated in accordance with the system's Topical Report and applicable procedures. lll

. Ta' J

s

RW-C-100, Rev. O Page 9 of 13

b. The Dewatering System processes resin by using equipment 4escribed by the topical report to

({} remove free standing water.

c. Dewatered resin is packaged in appropriately ,j selected liners or High Integrity Containers based on waste classification.
d. Station to Dewatering System interfacing is addressed by an approved Safety Evaluation. ,

7.2.2 Solidification

1. Resins, sludges and oily wastes may be solidified by a Mobile Solidification System.
a. The Mobile Solidification System shall be operated in accordance with the system's i

L topical report and applicable procedures.

b. The Mobile Solidification System processes waste using equipment described by the topical report to remove free standing liquid.

Solidified waste is packaged in appropriately selected containers based upon waste

- classification.

c. Solidified waste is packaged in appropriately 3 selected containers based on waste -

classification. -

l' d. Station to Mobile Solidification system (a

~

interfacing shall be' addressed by an approved safety evaluation.

a 7.2.3 Decontamination

1. Decontamination of oil may be performed on-site using a vendor service. The service shall be performed in accordance with the applicable safety evaluation.

l L 7.3 PRODUCT CONTROL 7.3.1 Routine sampling is performed by one of two techniques:

Direct sample from each batch. These samples are

~

1. If
analyzed for activity and isotopic identity.

radionuclide distributions are shown to be consistent between similar batches, consideration may be given to decreasing the frequency of routine measurements. This constitutes routine sampling OR 1

45 NC' a ~

-e

R._: -_ _ - -

RW-C-100, Rev. O  ;

Page 10 of 13

2. Dose rate reading taken from a coatainer of waste, Dose rates are converted to activity and isotopic g

breakdown based on annual samples.

7.3.2 Scaling factors for nuclides which are hard to identify are established for waste by analysis through an off-site vendor. Frequency of sampling is on an annual basis as, a minimum.

to 7.3.3 Tests are performed on-site quarterly, as a minimum, verify scaling factors. If the tests indicate that the scaling factors obtained through annual samples have changed by more than a factor of ten, consideration shall be given to increased off-site analysis.

7.3.4 When plant parameters affecting waste stream isotopics are altered (ex. fuel failure), consideration shall be given to further waste stream sampling.

7.3.5 Administrative controls for preventing unsatisfactory waste forms from being released for shipment are described in applicable station procedures.

7.3.6 Liquid wastes or wastes containing liquids shall be converted to a form that contains as little free standing and non-corrosive liquid as is reasonably achievable. The liouid shall not exceed 1% of the i C2h volume of the waste,'.or 0.5% of the waste volume for solidified waste.

7.3.7 Processed resin is tested annually as a minimum to

" verify the free standing water content of the packaged In product is within applicable regulatory limits.

addition to the annual verification, the free standing water content is determined whenever process changes occur that may significantly alter system performance.

Tests are performed to verify operability and for ensuring the waste form is similar to that indicated in prequalification testing.

7.3.8 To prevent accumulation of radiolytically generated

" combustible gas in greater than Type A radioactive waste packages containing water and/or organic substances, one or more of the following measures are taken:

1. The contdiner is equipped with a vent to prevent
  • accumulation of such gas.

?'

2. A determination by calculation, test, or E~

measurement is performed to ensure that hydrogen j ;, generation is limited to a molar quantity that gg) would be no more than 5% by volume of the secondary J H.

-J container gas void at STP over a period of time '

4 Nb! that is twice the expected shipment time.

\

4 i

, RW-C-100, Rev. O l

Page 11 of 13 l

3 The cask cavity will be inerted.

l() 7.3.9 Sufficient analyses shall be performed to verify that the quality of waste forms prepared for disposal by vendor's on-site processing shall be similar to vendor's test results.

7.4 WASTE CHARACTERISTICS FOR LAND DISPOSAL (See i

The following are minimum requirements for all clas disposal site and provide protection of health and i

safety of personnel at the disposal site:

Waste shall not be packaged for disposal in cardboard or ,

7.4.1 fiberboard containers.

be readily capable of detonation or of Waste shall not l 7.4.2 reaction at normal pressures l j'

explosive decomposition orand temperatures, or of explosive reacti or be capable of generating, '

7.4.3 Waste shall not contain, vapors, or fumes harmful to  ;

quantities of toxic gases, persons transporting, handling, or dispo waste.

j Pyrophoric materials ,

f 7.4.4 Waste shall not be pyrophoric. contained in the vaste shall be t ,

l ij gu,wL packaged to be nonflammable.

-u r Waste containing hazardous, biological, pathogenic or

'I 7.4.5

  • infectiousextent maximum material shall bethe practicable treated potential to reduce h'azard to fromthethe -

l non-radiological materials.

Each waste shipment shall be accompanied by a shippingthe i

! a 7.4.6 giving a physical description of the waste, manifest the radionuclide identity and quantity, the l

' volume, h i al form, and l

,a

, total radioactivity, the principal c em c -

waste class.

7.5 WASTE STABILITY (See Ref. 2.1.1)

The following requirements are intended to provide

, stability and are applicable to Class B and Class C wastes:

4 7.5.1 Waste shall have structural stability which can be '

provided by the waste form itself, processing the waste to a stable form, or placing the waste in'a disposal

~

^~..

container or structure that provides stability.

d'i 7.5.2 void spaces within the waste and its package should be (h-- reduced to the extent practicable.

di W

t. <

W 4 9

= . . = ,,,amw,

RW-C-100, Rev. O Page 12 of 13 7.5.3 Waste requiring stabilization is normally packaged The HICsin are llh approved High Integrity Containers (HIC).

handled and stored in accordance with Upon the applicable arrival at I

(C of C).

Certificate of ConformanceClass B and C wastes are placed in the burial site, concrete o'rerpacks for structural stability.

7.6 SURVEILLANCE REQUIREMENTS FOR SOLIDIFICATION least 7.6.1 At least one representative test sp.ecimen from at (See every tenth batch of waste shall be solidified. l Ref. 2.2.12).

the 7.6.2 If any test specimen fails to verify solidification, snall be solidification of the batch under test suspended until additional test specimens can be obtained, alternative solidification parameters can be determined and a subsequent test verifies See Ref. 2,2.12. l solidification.

If the initial test specimen from a batch of waste fails 7.6.3 to verify solidification, representative test specimens least from consecutive batches specimens demonstrate shall be tested until at three consecutiveThe testsolidification process control o solidification.

program shall be modified as required to assureSee Ref. 2.2.12. ggg

". ~ " " solidification of subsequent batches.

.:.a 7.7 QUALITY ASSURANCE PROGRAM v.

7.7.1 Quality Assurance shall be maintained as defined by the a Nuclear OA Plan.

7.7.2 Audits by personnel independent of the activities are performed and reviewed by appropriate management personnel.

7.7.3 Administrative controls for preventing unsatisfactory i waste forms from being released for shipment are described in applicable station procedures.

7.7.4 Procedures are reviewed to ensure compliance with the requirements and process parameters of this PCP.

,.J 7.7.5 Radioactive wastes not inclusion described in within this this PCP document or in a

~~

shall be evaluated for vendor Process Control Program prior to processing.

LL 7.8 REVISIONS

'? 7.8.1 Revisions to the PCP shall be approved in accordance

~ with applicable station or Common Nuclear Group a

Procedures.

49 9.r*

k O

RW-C-100, Rev. O 1

Page 13 of 13 l I

Any changes to the Solid Radwaste process ControlPr 7.8.2 O

Radioactive Effluent Release Report. .

t 8.0 DOCUMENTATION 8.1 Records of all data, tests, analy ic results, and records of training, inspection, and audits are -

maintained ip accordance with applicable procedures. l 8.2 Waste classification records, waste form records, and .

other records required for the preparation of the  !

semiannual Radioactive Effluent Release Report shall be .

l prepared and retained in accordance with the49CFR170-178, and 10CFR71, requirements of 10CFR20, Station Technical Specifications.

8.3 Sufficient documentation shall be maintained to demonstrate compliance with this PCP.

. l 9.0 EXHIBITS ,

  • b One

.22 3

-} t i

4

.6 Me 4

e

'i.]

1l

,t r(>

= .

] .

M

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

Retrieved from "https://kanterella.com/w/index.php?title=ML20056G098&oldid=2594487"