ML20099F409

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Rev 0 to Administrative Procedure RW-1-210, Process Control Program
ML20099F409
Person / Time
Site: Waterford Entergy icon.png
Issue date: 11/09/1984
From:
LOUISIANA POWER & LIGHT CO.
To:
Shared Package
ML19274C314 List:
References
RW-1-210, NUDOCS 8411260409
Download: ML20099F409 (16)
v • d • e


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WATERFORD 3 SES

-g PLANT OPERATING MANUAL LoulSIANA M100LE SOUTH UTluTIES SYnTEM POM VOLUME 20 RW-1-210 POM SECTION 1 REVISION O LP&L W-3 RECORDS U'NCONTROLLED COPY DO NOT USE IN ANY SAFETY-RELATED TESTING, MAINTENANCE, OR OPERATIONAL ACTIVITY i

ADMINISTRATIVE PROCEDURE PROCESS CONTROL PROGRAM l

PORCMeetingh.i.j/T-//Y Reviewed:, M [ 2 b W PORC Chairman Approved: t W 'f Plant Manager-Nuclear Approval Date Effective Date 8411260409 841121 PDR ADOCK 05000

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?_mtC 117'"1"J l n o PORc has reviased .his 1:aa and decaraised that a safscy avsluation was perf:rned (as amplicabla), that an ungsviewed saf acy quescism Joes soe aziac (as applicabla) .

. hat a changs sa he T Wd-=1 Sp d'd-=ed e la sac requ1=ad, and that sucisar safsc7 i

is/was not adversely affassad.

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This 1:an la recommended for approval? @ TZ3 C 30 ,

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  • WATERFORD 3 SES ,

PLulT OPERATING MANUAL Check Block Below CHANGE / REVISION /DEIITION REQUEST l[lPOM ((lPORC-S/C Proced.tre No. R (d 2 iC Title Pro cess (oQ L ccd Ec ce, ret m Effective Data (if different from approval date)

Completa A, B and C A. Change No. I @Per==amat l[l Deviation Expiration Data i ~

B. Revision No. O C. Deletion l[ LYES @No DESCRIFfION OF CHAN E OR REVISION bhcoJCL Tu nach A Ie ed ecen c4 .6 re ereucr Sc4'io d ,

un hncrec% % doccoc<- r e Se reo ce_ 'n i SAdd M. l.1 P.ASON FOR CIANGE, RE7ISION, OR DEITION bhauc e_ -Fo oncrad , cal e reo rs 'i d ce. e.cecce S ec4. 6 G nas e% cec % ecoec reCece0cc ,'a SJeD s. 4. iJ.

4 4 REQUIRED SIGNATURES ORIGUATOR n ,a um 2 DATE // 19 ,,

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SAiTIT dE7IF3 Does this change, revision, or deletion:

1. Change the facility as described in the FSAR? TIS NO X _ _
2. Change the procedures as described in the TSAR 7 US NO X
3. Conduct tests / experiments not described in the FSAR7 YES _ NO X
4. Require a change to the Technical Specifications? TIS NO Y If the answer to any of the above is yes, completa and attach a 10CFR50.39SafepEvaluation .

SAFETT tu w a _ am DATE // /Q nCastCAL RErIEv %e DAR #b/N GROUP HEAD REVIZv $t#d=* #

DATE ////'1[8F TIMPORARY APPROVAL * (SRO) DATE IIMP',RARY APPS,07AL* DAIZ

  • Temporary approval aust be followed by Plant Manager /APM-N - Nuclear approval within 14 days. ,

1 DNT-1-003 Revision 8 43 Attach =mnt 6.7 (1 of 1)

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REVIEW COVER S m REVIEW OT:

RW-1-210 - Process Control Program (Rev. 0)

PORC REVIE*J The PORC has reviewed this item and deter =ined that a safety evaluatio: vas perfor:ed (as applicable), that an unreviewed safety questien does not exist (as applicable),

that a change to the Technical- Specifications is not required, and that nuclear safety is/was not adversely affected.

ORDER RECOMMENDED OF PORC MEMBER PORC MEMBER 70R APPROVAL DATI REVIE*4 SIGNATURE YES l NO Maintenance Superintendent /8c a -

//-Eh Operations Superintendent 4 W.A % ~

N'Er Radiation Protection '

Superintendent ,m *

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Plant Quality M =aga; /W@ 7

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Technical Support Superintendent

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~t.is ite: is rece== ended for approval? @ YES C NO git-M1 This ite: requires 4RtVN10 review prior to i=ple=entatica? - @ YIS C NO If yes, ensure docu=entation supporting review is attached. ,

This 1:e= requires QA review prior to i=ple=entation? C YES NO OA ?IVIr4

  • r Reviewed by ;4 / A. DA Z 14 / A Corporate QA' Manager Ptr
    V yx:AcER-m ctEAR APPROVA1. (.OFER T~o E V./.2./) g Co==ents: ,

1 Approved by M /A _ DATI M/A Plant Man'gdf-Nuclear

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9 WATERFORD 3 SES l PLANT OPERATI'TG MANUAL Check Block Below l go x NEW PROCEDURE llEQUEST QtlPOM l[lPORC-S/C PROCEDURE NO.MY-l- '.Y. O PROCEDURE TYPE ScLmM Skrd0e_

TITLE 7ecca. Nkd Pece, cam .

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AUTHOR L .2. 8 im o d EXPIRATION DATE (IF APPLICABLE)

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REASON FOR PROCEDURE N ocnie,O b O k. Laceoce.

3 AUTHORIZED BY EA h t N M DATE " /1 % 4 Pladt Manager-Nuclear (POM) i SAFEU REVIEW Does this procedure: Assist. Plant Manager-Nuclear (PORC-S/C)

1. Change ene facility as described in the FSAR7 YES NO t/
2. Change the procedures as described in the FSAR? YES NO t/
3. Conduct tests / experiments not described in the FSAR7 YES NO /
4. Require a change to the Technical Specifications? YES NO /

If any question 1 through 4 has been answered YES, complete and attach a 10CFR50.59 SAFETY EVALUATION.

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SAFEU REV n n cmo m // /Y fignature,' Xuthor

, I Date TECHNICAL REVIEW r 6%

Signature, Ted5iiiical Reviewer

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Signaturei Group Rirad Date l l

l Applicable Conditions (Temporary Procedures Only):

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UNT-1-003 Revision 8 Attachment 6.6 (1 of 1) 42.

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Administrative Procedure RW-1-210

' Proc.eos Control Program Revision 0

-TABLE OF CONTENTS 1.0. PURPOSE

2.0 REFERENCES

1 3.0 DEFINITIONS 4.0 RESPONSIBILITIES 5.0 PROCEDURE 5.1 Program Description 5.2 So'.idification Process Parameters 5.3 Administratise Controls 5.4 Waste C1caracterization and Classification 5.5 Quality Assurance 6.0 ATTACHMENTS LIST OF EFFECTIVE PAGES Title Revision 0 1-11 Revision 0 G A 03 e. 1 1, 3, t o 0. wa ug e 4. g 11 - 19 6A 4

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Administrative Procedure -RW-1-210 Process Control Program Revision 0 1.0 IURPOSE 1.1 The purpose of Waterford Steam Electric Station - Unit Number 3 (Weterford 3) Process Control Program (PCP) is to describe the program which prcvides reasonable assurance of the complete solidifi-ation of various radioactivs " wet wastes" including resin slurries and evaporator bottoms are accordance with applicable Department of Transportation (DOT), Nuclear Regulatory Commission (NRC), State and licensed burial facilities acceptance criteria for packaging and shipment to an approved burial site. Complianca with these criteria vill be achieved through implementation of the PCP and related Waterford 3 and vendor supplied procedures.

2.0 REFERENCES

2.1 Waterford 3 Documents 2.1.1 FSAR Chapter 16, Technical Specification 3/4 11.3 2.1.2 FSAR Chapter 16, Technical Specification 6.13.2 2.1.3 FSAR Chapter 11.4, Solid Waste Management System 2.1.4 FSAR Chapter 13.4. Review and Audit 2.1.5 FSAR Chapter 13.2. Training 2.1.6 FSAR Chapter 13.5, Plant Procedures 1

2.1.7 Nuclear Operations Quality Assurance Manual Section 2 Chapter 6 2

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u-inictr:tiva Procedura RW-1-210 Process Control Program Revision 0 2.2 Vendor Controlled Documents PS-53 o 378 C

  • 1" i 2.2.i f9=979=6999, NUS Process Services Corporation, Topical Report cfPd on Radwasta Solidification System, Rev.-0 33-lW 2.2.2 TR002, NUS Process Services Corporation. Topical Report on 10CFR61 Qualified Radioactive Waste Forms, May 1984 2.2.3 4313-01354-01P Chem-Nuclear Systems Inc., Topical Report on Mobile Cement Solidification System Rev. 2 2.2.4 CNSI-WF-C-01-NP, 10CFR61, Wasta Form Certification-Cement, Y Wet ar- $RS Chem-Wessese System Inc., November 30, 1983 ti. it . Gi cWSr.bw.ss u s-e t- P  %

2.2.5 N . Chem-Nuclear System, Inc., Dewatering M

9" 1 Topical, December 23, 1983 gg , g,gg

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2.2.6 HN-R1109. Westinghouse Hittman Nuclear, Inc., Topical Report on Radvasta Solidification System (Cement), Rev. 4 2.2.7 STD-R-05-005, Westinghouse Hittman Nucidar, I.c., Topical Report on Cement Solidified Wastes to Meet the Stability Requirements of 10CFR61, Rev. 0 2.2.8 STD-R-03-008 Westinghouse Hittman Nuclear, Inc., Topical Report for Hittman RADLOK High Integrity Containers, Rev. 0 2.2.9 FI-013, Process Control Program for Dewatering Liner with NUC l'SC Internals, NUS Process Services Corp.

2.2.10 STD-P-05-003, Hittman Nuclear Development Corp., Process Control Program for Incontainer Solidification of 10 of 14 Weight Percent Boric Acid, Rev. 1 3

EAdministrative Procedu're RW-1-210 iProcess Control Program Revision 0 2.2.11 STD-P-05-004,- Hittmac Nuclear Development Corp. , _ Process Control Program for Incontainer. Solidification of Bead Resin,

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'Rev. 1 2.2.12--Hittman Nuclear Development Corp.. STD-P-03-005, Hittman Nuclear Development' Corp., Dewatering Hittman Radlock Containers with Flexible Underdrains to Less Than 1% Drainable Liquid, Rev. 2

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2.2.13 STD-P-04-002, Dewatering Ion Exchange Resin and Activated-Charcoal Filter Media to 0.5% .

2.2.14 WMG 102-NP-A, Waste Management Group, RADMAN Tropical Report 2.3 Other Documents 2.3.1 10CFR61, Licensing Requirements for Land Disposal of Radio-active Waste t

2.3.2 10CFR20.311, Transfer for disposal and manifests 2.3.3 10CFR71.91, Records i I

3.0 LEFINITIONS l

NONE 4.0 RESPONS18ILITIES 4.1 Plant Manager-Nucleat i

i-l 4.1.1 The Plant Manager-Nuclear has overall administrative control responsibilities for the Process Control Program at Waterford-3.

He is responsible for ensuring the following:

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. Administrative Procedure RW-1-210 Process Control Program- Revision 0 4.1.1.1 The preparation, review and approval of the Process-Control Program proc'edures pertaining to-the process-ing and packaging, of' radioactive materials, and for-the operatien and maintenance of radwaste systems; 4.1.1.2 That plant personne1' adhere to the procedural require-ments of this program; 4.1.1.3 That plant interdepartmental responsibilities affect-ing the Process control Program are clearly established and accourliehed; 4.1.1.4 That personnel receive appropriate training and are ,

qualified for their respective duties; 4.1.1.5 ' Procurement of materials and supplies required for implementation and maintenance of the Process Control Program; 4.1.1.6 Operation and maintenance of radwaste systems; 4.1.1.7 Inspection of Radwaste activities; and 4.1.1. 8 Adequate staffing and sufficient resources for efficient and economic operation of the Process Control Program.

4.2 Radiation Protection Superintendent 4.2.1 The Radiation Protection Superintendent is responsible for the overall effective management of the plant Process Control Program. The Radiation Protection Superintendent ensures that changes are initiated to the Process Control Program procedures when necessary and that appropriate Health Physics support is provided.  ;

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Administrative Procedure RW-1-210 Process Control Program Revision 0 l

4.3 Plant Radwaste Engineer-Nuclear 4.3.1 The Plant Radwaste Engineer who reports to the' Radiation Protection Superintendent holds key. responsibilities for implementation of the Process Cont:cl Program such as:

4.3.1.1 Data collection, trend analysis, long-term planning, and problem solving for the plant Process Control Program; 4.3.1.2 Managing radwaste solidification dewatering and packaging; 4.3.1.3 Preparing procedures for solidification, dewatering and packaging; 4.3.1.4 Interfacing with other groups as necessary to analyze and resolve problems relating to the Process Control program such as the design of Radwaste Systems and Equipment; 4.3.1.5 Preparing periodic reports summarizing the Process Control Program.

4.4 Operations Superintendent 4.4.1 The Operations Superintendent is responsible for the ef fective

] operations of permanent plant radwaste systems ur.d will coordinate radwaste activities with the radwaste department.

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RW-1-210 Process Control Program -4 Revision 0 s

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4.5 Chemistrv Engineer-Nucles JI h

-- 4.5.1 The Chemistry Engineer-Nu: lear is responsibla for interfacing

.w ith the;Radwaffe' Mginee Koc. items or problems relating to

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-. , na ny ,/ radweste processes and chen* stry controls dr'chetical reactions

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, and' performing chemical and radiochemical anliyses of samples

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-of rad h,cctive vaste or materials.

-s 4.6 Plant Quality Manager M

4.6.1 The Plant Quality Manager is responsible for the review of plant Process Control Program procedures to ensure QA Program requirements are implemented and for the performance of activity sutye111ance.

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4.7 Nuclear Services Manager a  ?

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,. 4. 7. 1 The Nuclear Servics.s Maaager is' responsible for providing the following services: ,

4.7.1.1 State-of-the-art technical advise, support, and

\ assistance as required; 4.7.1.2 Liconsing and regulatory conpliance support; and 4 7.1.3 Appraisint the Waterford-3 Process Control Program l and reconneending improvem5nts.

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Process' Control Program Revision 0

'4.8 Corporate Quality' Assurance Manager-4.S.1 The Corporate Quality Assurance Managir is responsible for-assessing the implementation and effectiveness of the quality assurance aspecta of the Process Control Program th wsgh

> regalar audits and selective monitoring of activities. ,

5.0 PROCEDURE 5.1 Program Description

'5.1.1 Solidification System D,escription:

Waterford 3 utilizes vendor supplied portable solidification

equipment for radioactive waste solidification. References 2.2.1 through 2.2.13 provide a general description of respec-tive vendor solidification processes and process control ,

features; Reference 2.2.14 describes the method which will be utilized to classify wastes in accordance with 10CFR61; and Reference 2.1.1 through 2.1.7 are Waterford 3 documents which either implement or describe activities which provide reason-able assurance that wastes are solidified or dewatered in

. accordance with all applicable regulations and critatia.

1.1.2 Sources of Waterford 3 Solidification Feeds:

The solidification system will be used to process resins, evaporator bottoms and boric acid concentrates. During resin i solidification, vendor equipment will be connected to both the Resin waste Management System outlet and dewatering inlet to allow for the transfer of resin and the dewatering of the

liner. Vendor equipment will be connected to the Solid waste f Management Syst.es outlet when evaporator bottoms from the radwaste evaporator and boric acid concentrates from the Boron Management System evaporator are to be solidified.

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1 Administrative Procedure ,,- RW-1-210 1 Process' Control Program Revision 0 I

5.2 Solidification Process Parameters: )

5.2.1 Solidification formulas end. solidification process parameters are incorporated into the applicable vendor process control program. fNo exceptions or deviations from vendor supplied procedures or topical reports are anticipated. -The formulas are used to calculate the ratio of waste, cement, water and other reagents required to achieve an acceptable solidified

, product. Compatibility requirements of the waste stream with respect to the solidification media are described in the vendor process centrols program. Waste stream parameters are adjusted as necessary to meet these requirements.

5.2.2 Test solidifications aru performed on waste stress samples to verify vendor calculated solidification formulas. Plant procedures describe the frequency for performing test soli-difications and establish the acceptance criteria for the test solidifications in accordance with Technical Specification 3/4 11.3.

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l Administrative Procedure RW-1-210' Process Control Program Revision 0

. s 5.3 Administrative Controls 5.3.1 Administrative controls utilized to insure compliance with.

applicable state and federal regulations and burial site criteria are detailed in the radioactive vaste solidification surveillance procedure (s). These implementing document (s) for radiorctive wasta solidification and dowatering describes the requirements which must be met prior.co processing radio-active waste, as well as the condition of the solidified ,

J or dewatered waste. Test solidifications, full scale calcula-tions and operation of the solidification equipment are l performed by vendor personnel. Dewatering operations will be performed by vendor personnel or by qualified Plant staff.

Plant staff provides Health Physics and Quality Amaurance coverage, operates plant radioactive vaste systems.-collects

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waste stream aamples and performs isotopic analyses. Copies-of all referenced documents are available on site for use by personnel engaged in solidification activities, 5.3.2 Changes to this Process Control Program chall be described in the scui-annual Radioactive Effluent Release Report for the period in which the change is made, in accordan:e with Techni-cal Specification 6.13.2.

5.4 Waste Characterization and Classification i

l 5.4.1 Wasta Classification 5.4.1.1 Solidified wastes are classified in accordance with the requirements of 10CTR61.55, as implemented by ' Ch*9* 1 l reference 2.2.handplantvasteclassificationand EbET*

characterization procedure (s). il-d'E4 10

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Administrative Procedure RW-1-210 l

Process Control Frogram. Revision 0 l

5.1.4.2 Annual analysis will be performed on the waste streams to determine The isotopic abundance o'f gamma emmitting isotopes in the streams. Scaling factors for the acn-gamma emmitting and transuranic consti-tuents will be developed from this annual analysis.

The activity of each radioauclide in the solidified waste will be determined by a calculational method employing the percent abundance and scaling factors with a dose to curie conversion factor as described in reference 2.2.14.

5.4.2 Waste Characteristics 5.4.2.1 Solidified t<istes will meet the characteristics of 10CFR61.56(a) and (b). Waste containers will be labelled to identify the waste class.

5.4.2.2 The manifesting requirements of 10CFR20.311 are implemented and records are maintained in accordance with 10CPR71.91.

5.5 Quality Assurance 5.5.1 Quality Assurance related activities for the Radioactive Waste Program are implemented as described in the Nuclear Operations Quality Assurance Manual (Reference 2.1.7). These activities provide verification that the solidified wastes meet applicable state and federal regulations and burial site criteria.

6.0 ATTACHMEiTS NONE i

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