ML20082M278

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Rev 3 to Administrative Procedure RW-1-210, Process Control Program
ML20082M278
Person / Time
Site: Waterford Entergy icon.png
Issue date: 05/09/1989
From:
LOUISIANA POWER & LIGHT CO., NEW ORLEANS PUBLIC SERVICE CO.
To:
Shared Package
ML20082M216 List:
References
RW-1-210, NUDOCS 9109050117
Download: ML20082M278 (13)
v • d • e


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1 P0tt VOLUME RW-1-210 PON SECTION REVISION 3 i

ADMINISTRATIVE PROCEDUHE PROCESS CONTROL PROGRAM LP&L W-3 RECORDS MANAGEMENT CWRD_ E3 m(

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PORC tiesting No. M-6\

Reviewed d.on w _/, _ _ PF g itHC Chairman ' 'D41E Approve u ant :ianagst-duclear 4 / C 9 IY felE '

\J Effective Date 9109050117 910029 PDR ADOCl' 05000382 R POR

, s UNT-1-002 Revision 10 23 y flg.1 Atta ctmen t 6.3(1ofgr) 4/ (J,J,!'

PORC REVIEW COVCit SilEET )

t itEVIEW OP RW-1-210 - Proccan Control Program (Rev. 3) '

I'0!!C REVIEW 1

I, The FORC has reviewed this item and determined that a safety evaluation was performed (as applicable), that an unteviewed safety guention does not exist  !

(as appilcable), that a change to the Technical Specifications is not required, and that nuclear saf etypfwas not adversely af f ected. i i

tilli)ER OF PORC flE!! DER REC 0l!!!EllDED t ItEVIEW FORC llEll')ER TOR APPROVAL, l'A l E  !

lisintensuce SIGilAiURE Q3 gg-l

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Operations Superintendent

/ f hi 7' il Radiation Protection 7 Superintendent R

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Huelest-Qpoesttent Supps r t-s eri- As s es smetrt- s, i r

_ OpOEEII8tiskdlNINIdI3Nei Har e Plant Engineering Superintendent kh I i

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Assistant Pisat ,

flanager I L.

TORC Chairman ,

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se. ,w [ I FORC 11eeting flo. M-El Itmflo.h.- Date1 _b-S M This item is recommended for approval? O 11 0 1his item requires SRC/flRC review prior toKYES t enplemen t a t ien t o YES l If yes, ensure documentation supporting review is attached. Kilo ';

PLAllT llAllAur.R-il0CIIAR APPROVAL (REFER 10 5.4.12.1) L Cormnents :

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plant flanager-fluelear _ _ _ _ Date _ Q\b _

Ulit-1-004 Revision 8 I A t t a ciunen t 6.1 ( I o f 1)  ;

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UATERFORD 3 SES PLANT OPERATING MANUAL Check Block Below CHANGE / REVISION / DELETION REQUEST l@ POM l[lPORC-S/C Procedure No. StO-/ C/d _ Title [rcO M dmho/ /be rW7 ~

Effective Date (if different from approval date)

Complete A, B, and C A. Change No. A/A l[lPennanent l[lDeviation Expiration Date B. Revision No. 3 3 C. Deletion l[ LYES l$NO DESCRIPTION OF CHANGE OR REVISION A/I' fk Uhxlel h607katO k)4b (1if AtW l'n /h)$1 bG }' '2 (U!Yh

-lo wcu A&nelwc and fr/ gbrkt & R iWe4 Gd,ve,Jr (DF) h H&lA T!,o%3 A h I'i f to , Acll /?W A'? vbA /*f rd'$lWnt q lG*t-]l' t'/N d REASON FOR CRANCE, REVISION, OR DELETION N3 C /t?Utt i t]Ilif/1 th)Wlff ftYYYY(t tV) Rg (l.4/ O f gh)'ir- o.a'.3?

(Vnh ty?n%1 04 i)hnwr lLw. b tN,'c), Ox/ Sikh iMlhdb AtI (fl5fO'inM tom alf f/b A '

R'EQUIRED SIGNATURES ORIGINATOR M67M/M MN) DATE'*!f9/6C 7 SAFETY / COMMITMENT REVIEW Does this change, revision, or deletion:

1. Change the design, description, function and/or operation of a system structure or component described in the FSAR? YES NO >'
2. Change the procedures as described in the FSAR? YES NO /
3. Conduct tests / experiments not described in the FSAR? YES NO, '/'
4. Require a change to the Technical Specifications? YES NO %
5. Alter the implementation of any cocniements? YES N0 f If the answer to any of the above is Yes, complete and attach a 10CFR50.59 Safety Evaluation.

SAFETY /COMMITMENTREVIEWh')t'J!ty / //f /v'O DATE 3k// kS 1 TECHNICAL REVIEW M cu k h h# w i3 DATE 4 74rp GROUP HEAD REVIEW Q a ud //dM/-1c +?t7 DATE 4/2c7t'/

TEMPORARY APPROVAL"* (SRO) DATE _

TEMPORARY APPROVAL

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

UNT-1-003 Revision 10 Attachment 6.7 (1 of 1) 30

Administrative Procedure RW-1-210 Process Control Program Revision 3 i

TABLE OF CONTENTS i 1.0 PURPOSE

2.0 REFERENCES

i 3.0 DEFINITIONS  :

4.0 RESPONSIBILITIES t

5.0 PROCEDURE 5.1 Program Description- ,

5.2 Solidification Process Parameters '

t 5.3 -Administrative Controls ,

5.4 Waste Characterization and Classification ,.

5.5- Quality Assurance ,.

6.0 ATTACHMENTS i LIST OF EFFECTIVE PAGES Title Revision 3 1-10 Revision 3' I 9

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Adelnistrotive Procedure RW-1-210 Process control Program Revision 3 1.0 PURPOSE 1.1 The purpose of Waterford Steam Electric Station - Unit Number 3 (Waterford 3) Process Control Program (PCP) is to describe the program which provides reasonable assurance of the complete solidifi-ation of various radioactive " 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. Compliance with these criteria will 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 Technical Specification 3/4 11.3 2.1.2 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 2.1.7 Nuclear Operations Management Manual,Section VI, Chapter 5

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Administrative Procedure RW-1-210 I Process Control Program Revision 3

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2.2 Vendor Controlled Documents i e

2.2.1 LN Technologies Corporation, TR002, Topical Report on i 10CFR$1 Qualified Radioactive Waste Forms, May 1984 .

2.2.2 LN Technologies Corporation PI-013 Process Control Program  !

for Dewatering Liner with LN Technologies Corporation Internals,  !

LN Technologies Corporation i

2.2.3 LN Technologies Corporation, DW-002, Process Control Program for Dewatering Bead or Powdered Resin with Quick-Dry ,

Dewatering System No 8814.  !

2.2.4 LN Technologies Corporation, SS-005, Operating Procedure for LN Technologies Corporation Radwante Solidification System Numbhr 8908. .

2.2.5 LN Technologies Corporation, SS-001, Process control Program for Radwaste Solidification Service 2.2.6 WMG, Inc., 102-NP-A, RADMAN - A Computer Code Main Topical Report 6

2.2.7 WMG, Inc., 102P, RADMAN - A Computer Code Topical Report - '

Appendices  !

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-2.3 Other Documents 2.3.1 10CTR61, Licensing Requirements for Land Disposal of Radio-t l

active Waste- '

f 2.3.2 10CTR20.311 Transfer for disposal and manifests h

i 2.3.3 10CFR71.91, Records --

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Ad2inistrative Procedure RW-1-210 Process Control Program Revision 3 3.0 DEFINITIONS NONE 4.0 RESPONSIBILITIES 4.1 Plant Manager-Nuclear 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:

4.1.1.1 The preparation, review and approval of the Process

  • Control Program procedures pertaining to the process-ing and packaging, of radioactive materials, and for the operation and matntenance of radwaste systems; 4.1.1.2 That plant personnel adhere to the procedural require-ments of this program; 4.1.1.3 That plant inter:epartmental responsibilities affect-ing the' Process control Program are clearly established and accomplished; 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

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Administrative Procedure '

RW-1-210 Process Contrcl Program Revision 3 4.1.1.8 Adequate staffing and sufficient resources for efficient and economic operation of the Process Control Program, t

4.2 Radiation Protection Superintendent 4.2.1 The Radiation Protection Superintendent is responsible for the overall effective management of the plant Process Control j Program. The Radiation Protection Superintendent ensures that changes are initiated to the Process Control Program t

. procedures when necessary and-that appropriate !!ealth Physics support is provided.

4.3 Plant Radwaste Engineer-Nuclear

. . i 4.3.1 The Plant Radwaste Engineer who reports to the Radiation '

h Protection Superintendent holds key responsibilities for implementation of the Proces s Control 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 i packaging; 4.3.1.3 Preparing procedures for solidification, dewatering.

and packaging;

-1 4.3.1.4 Interfacing with rther groups as necessary to analyze '

and resolve problems relating to the Process Control I program such as the design of Radwaste Systems and [

Equipment, 4.3.1.5 Preparing periodic reports summarizing the Process i

Control Program, j

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Administrative Procedure RW-1-210 '

Process Control Program Revision 3 t'

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4.4 Operations Superintendent {

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4.4.1 The Operations Superintendent is responsible for the effective  ;

operations of permanent plant radwaste systems and will f coordinate radwaste activities with the radwaste department. {

i 4.5 Chemistry Engineer-Auclear I 4.5.1 The Chemistry Engineer-Nuclear is responsible for interfacing  !

with the Radwaste Engineer on items or problems relating to radwaste pracesses and chemistry controls or chemical reactions 1 and performing chemical and radiochemical analyses of samples f of radioactive waste or materials. I i

i 4.6 Operations Quality Assurance Manager '

t 4.6.1 The Operations Quality Assurance Manager is responsible for j providing the following services:

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4.6.1.1 Reviewing plant Process Control Program Procedures.  ;

i 4.6.1.2 Assessing the implementation and effectiveness of the quality assurance aspects of the Process Control I Program through regular audits and selective monitoring of activities.

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4 .' 7 Nuclear Services Manager 4.7.1 The Nuclear Services Manager is responsible for providing the following services:  !

4.7.1.1 State-of-the-art technical advise, support, and-assistance as required; )

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Administrative Procedure RW-1-210 Process Control Program Revision 3 4.7.1.2 Licensing and regulatory compliance support; and 4.7.1.3 Appraising the Waterford-3 Process Control Program and recommending improvements.

4.7.2 The Nuclear Services staff interfaces directly with the plant staff in providing these services.

5.0- PROCEDURE-5.1 Program Description 5.1.1 Solidification System

Description:

Waterford 3 utilizes vendor supplied portabic solidification

. equipment-for radioactive waste solidification. References 2.2.1, 2.2.4 and 2.2.5 provide a general description of respec-tive vendor solidification processes and process control features; References 2.2.6 and 2.2.7 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 reasonable-assurance'that wastes are solidified or dewatered in accordance with all applicable regulations and criteria.

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Administrativo Procedure RW-1-210 Process Control Program Revision 3 5.1.2 Sources of Waterford 3 Stabilization / Solidification reeds:

The Cement solidification will be used to stabilize resins.' l evaporator bottoms and boric acid concentrates. During resin stabilization, vendor equipment will be connected to the Resin Waste Management Fystem outlet to allow for the transfer of resin. Vendor equipment will be connected to the Solid waste Management System outlet when evaporator bottoms from the rad-waste evaporator and boric acid concentrates from the Boron Management System evaporator are to be stabilized. Solidi-g feation using Aquaset/Petroset media will be used to process resins. oil, water / acid, evaporator bottoms and boric acid cencentrates. This process will not be connected to any plant ,

waste systems and will be processed on a batch basis.

5.2 Solidification Process Parameters:

5.2.1 Solidification formulas and solidification process parameters are incorporated into the applicable vendor process control program. No exceptions or deviations from vendor supplied procedures or topical reports are anticipated for stabilized waste. The formulas are used to calculate the ratio of waste.

cement, water and other reagents required to a hieve an acceptable solidified product. Compatibility requirements of the waste stream with respect to the solidification media are described in the vendor process controls program. Vaste stream parameters are adjusted as necessary to meet these requirements.

5.2.2 Test solidifications are performed on vaste stream samples to verify vendor esiculated solidificttion formulas. Pinnt 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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Adainistrative Procedure RW-1-210 Process Control Program Revision 3 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 waste solidification surveillance procedure (s). These implementing document (s) for radioactive waste solidification and dewatering describes the requirements which must be met prior to processing radio-active waste, as well as the condition of the solidified or dewatered waste. Test solidifications, full scale calcula-tions and operation of the solidification equipment are performed by vendor personnel. Dewatering operations will be

-performed by vendor personnel or by qualified Plant staff.

Plant staff provides Health Physics and Quality Assurance coverage, operates plant radioactive waste systems, collects waste stream samples 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 shall be described in the semi-annual Radioactive Effluent Release Report-for the period in which the change is made, in accordance with Techni-cal Specification 6.13.2.

5.4 Waste Characterization and Classification 5.4.1 Waste Classification 5.4.1.1 Solidified wastes are classified in accordance with the requirements of 10CFR61.55, as implemented by references 2.2.6 and 2.2.7 and plant waste classification and characterization procedure (s).

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Administrative Procedure RW-1-210 Pr9eoss Control Program Revision 3 5.4.1.2 Annual analysis will be performed on the waste streams to determine the isotopic abundance of gamma emitting isotopes in the streams. Scaling factors for the non gamma emitting and transuranic consti-tuents will be developed from this annual analysis.

The activity of each radionuclide in the solidified waste will be determined by a core sample or a cal-culational method employing the percent abandance and scaling factors with a dose to curie conversion factor as described in reference 2.2.6. .

5.4.2 Waste Characteristics 5.4.2.3 Solidified wastes will meet the characteristics of 10CFR61.56(a) and (b). Vaste 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 10CFR71.91.

5.5 Quality Asqurance 5.5.1 Quality Assurance related activities for the Radioactive Waste Program are implemented as described in the Nuclear Operations Management Manual (Reference 2.1.7). These activities provide verification that the solidified wastes  !

meet applicable state and federal regulations and burial site criteria.

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6.0- ATTACHMENTS i

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