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{{#Wiki_filter:_     .    - ..          _            .    . . _      _ - _ _ - -
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f-PORC/PORC-SC l
!                                            PORC/PORC-SC l                                                                   RW-001-210 l                                                               REVISION               7 l                                                           EFFECTIVE DATE l
RW-001-210 l
REVISION 7
l EFFECTIVE DATE l
l l
l l
l l
l l
l l
l SAFETY-RELATED l
SAFETY-RELATED l
1
1 /
/
ADMINISTRATIVE PROCEDURE PROCESS CONTROL PROGRAM I
ADMINISTRATIVE PROCEDURE PROCESS CONTROL PROGRAM I
l   (1                   p la    i      h )} :.[. s           l COPY COPY No.               b/
l (1
UNT-001-002 Revision 13                                             Attachment 6.3 (1 of 2)
h )} :.
                                -t-9705010287 970429 PDR   ADOCK 05000302                         48 R                 PDR
. [ s p
la i
COPY COPY No. b/
UNT-001-002 Revision 13.3 (1 of 2) 9705010287 970429
-t-PDR ADOCK 05000302 48 R
PDR


l                                         PORC AND PORC - S/C REVIEW AND APPROVAL SHEET l
l PORC AND PORC - S/C REVIEW AND APPROVAL SHEET l
l     REVIEW 0F: RW-001-210 - Process Control Proaram             PORC                     E l     (Rev. 7)                                                     PORC - S/C               O i
l REVIEW 0F: RW-001-210 - Process Control Proaram PORC E
The PORC or PORC S/C has reviewed this item and determined that a Safety /
l (Rev. 7)
l     Commitment Review was performed (if applicable), that a Safety Evaluation was performed (if applicable), that an unreviewed safety question does i     not exist, and that nuclear safety is/was not adversely affected.
PORC - S/C O
!                  PORC                                           RECOMMENDED FOR APPROVAL MEMBER                 MEMBER SIGNATURE             YES               NO l
i The PORC or PORC S/C has reviewed this item and determined that a Safety /
u r n endent                         . //
l Commitment Review was performed (if applicable), that a Safety Evaluation was performed (if applicable), that an unreviewed safety question does i
Operations                                '/'//     N Superintendent            / {C 1 /' ,M-Radiation Protection Superintendent Quality Assurance           I t  /d
not exist, and that nuclear safety is/was not adversely affected.
: f.                 #                              '
PORC RECOMMENDED FOR APPROVAL l
Member                         c        1M'-
MEMBER MEMBER SIGNATURE YES NO u r n endent
Mgmt Knowledgeable                                                                           j in Engineering 1
. //
Manager Operations &
'/'//
Maintenance PORC-S/C Member PORC-S/C Member PORC-S/C Member Meeting No.       96-004           Item No.         VI-I     Date:       1/10/96 This item is recommended for approval? E YES               O N0 i         This item requires SRC/NRC review prior to implementation? O YES E NO If yes, ensure documentation supporting review is attached.
N
SIGNATURE         RECOMMENDED FOR APPROVAL YES         NO               DATE l         PORC-S/C Chairman         r   ,,
{C 1
PORC Chairman     ,Mh%       ,%               V                         / - / o #l/.   '
,M-Operations Superintendent
Comments:         U                     l m _ - _                   i Approved b N b                   'rh                     Date     i,/y /fc.
/
General Manager Plant Operations UNT-001-004 Revision 14                     23             Attachment 6.1 (1 of 1)
Radiation Protection
/'
Superintendent
/d t
Quality Assurance I
f.
Member 1M'-
c Mgmt Knowledgeable j
in Engineering Manager Operations &
Maintenance PORC-S/C Member PORC-S/C Member PORC-S/C Member Meeting No.
96-004 Item No.
VI-I Date:
1/10/96 This item is recommended for approval? E YES O N0 i
This item requires SRC/NRC review prior to implementation? O YES E NO If yes, ensure documentation supporting review is attached.
SIGNATURE RECOMMENDED FOR APPROVAL YES NO DATE l
PORC-S/C Chairman r
PORC Chairman
,Mh%,%
V
/ - / o #l/.
Comments:
U l
m _ - _
i Approved b N b
'rh Date i,/y /fc.
General Manager Plant Operations UNT-001-004 Revision 14 23.1 (1 of 1)


  . . . _ _ _ . _ _ _ _ _ . . _ -                    _ _ _ _ . . _ ~ _ . . _ - . . _ _ _ _ _ _ _ _ . _ _ _ . _ . - _ _ _ _
_ _ _ _.. _ ~ _.. _ -.. _ _ _ _ _ _ _ _. _ _ _. _. - _ _ _ _
i Check Block                                                                                       WATERFORD 3 SES TlPORC                                                                             PLANT OPERATING MANUAL                                                             l l           PORC-S/C-                                                                   REQUEST / APPROVAL PAGE
i Check Block WATERFORD 3 SES TlPORC PLANT OPERATING MANUAL l
                ~
l PORC-S/C-REQUEST / APPROVAL PAGE
~
DEPT.
DEPT.
Procedure No.:             RW-001-210
Procedure No.:
RW-001-210


==Title:==
==Title:==
PROCESS CONTROL PROGRAM
PROCESS CONTROL PROGRAM
      ~EffGctive Date:                   N/A                   (If different from approval date)
~EffGctive Date:
N/A (If different from approval date)
COMPLETE A. B. C. and D:
COMPLETE A. B. C. and D:
A. Change No.:               fd l A                       l         l Permanent                                     Deviation   Expiration Date:     N/A B. Revision No.:               7 l
A. Change No.:
C. Deletion:                                               l         l YES                                 X l NO D. Temporary Procedure:                                   l         l YES                               l X l NO                 Expiration Date:     N/A-                 >
fd l A l
DESCRIPTION OF CHANGE, REVISION, OR DELETION:                                                           1) ADDED STEP 3.3 "OUALIFIED SHIPPER" T0                             '
l Permanent Deviation Expiration Date:
l DEFlNATIONS. 2) REPLACED "RADWASTE FORMAN" WITH "OUALIFIED SHIPPER" IN RESPONSIBILITIES SECTION 4.2.           3) REFINED RESPONSIBILITIES OF THE CHEMISTRY AND OPERATIONS SUPERINTENDENTS.
N/A B. Revision No.:
7 l
C. Deletion:
l l YES X l NO D. Temporary Procedure:
l l YES l X l NO Expiration Date:
N/A-DESCRIPTION OF CHANGE, REVISION, OR DELETION:
: 1) ADDED STEP 3.3 "OUALIFIED SHIPPER" T0 l
DEFlNATIONS. 2) REPLACED "RADWASTE FORMAN" WITH "OUALIFIED SHIPPER" IN RESPONSIBILITIES SECTION 4.2.
: 3) REFINED RESPONSIBILITIES OF THE CHEMISTRY AND OPERATIONS SUPERINTENDENTS.
: 4) EXPANDED STEP 5.5.1.
: 4) EXPANDED STEP 5.5.1.
        ~
~
l REASON FOR CHANGE, REVISION, OR DELETION:                                                     1) OVALIFIED SHIPPER ADDED DUE TO DEPARTMENTAL ORGANIZATIONAL CHANGES. 2) RADWASTE FOREMAN REPLACED WITH OVALIFIED SHIPPER DUE TO DEPARTMENTAL ORGANIZATIONAL CHANGES. 3) RESPONSIBILITIES OF THE CHEMISTRY AND OPERATIONS SUPERINTENDENTS WERE POORLY WRITTEN. 4) STEP 5.5.1. WAS EXPANDED TO BETTER DEFINE THE QUALITY ASSURANCE PROGRAM MANUAL (SPECIAL SCOPE) CHAPTER 5 AS IT PERTAINS TO THE PCP.
l REASON FOR CHANGE, REVISION, OR DELETION:
AUTHOR \0RIGINATOR:                 STEVE LANDRY                         d Au                                                               DATE:   9-(&97 TECHNICAL REVIEW:                   J.P. WHITE                         h NT                                       7                         DATE:   ) - % "V, GRCUP HEAD REVIEW:                   Nd                                                   d                     7 A //, he /
: 1) OVALIFIED SHIPPER ADDED DUE TO DEPARTMENTAL ORGANIZATIONAL CHANGES. 2) RADWASTE FOREMAN REPLACED WITH OVALIFIED SHIPPER DUE TO DEPARTMENTAL ORGANIZATIONAL CHANGES. 3) RESPONSIBILITIES OF THE CHEMISTRY AND OPERATIONS SUPERINTENDENTS WERE POORLY WRITTEN. 4) STEP 5.5.1. WAS EXPANDED TO BETTER DEFINE THE QUALITY ASSURANCE PROGRAM MANUAL (SPECIAL SCOPE) CHAPTER 5 AS IT PERTAINS TO THE PCP.
v  .
AUTHOR \\0RIGINATOR:
DATE:   f[/J2 l         'O TEMPORARY APPROVAL (SRO):                                                                                                                   DATE:
STEVE LANDRY d Au DATE:
o TEMPORARY APPROVAL:                                                                                                                         DATE:
9-(&97 TECHNICAL REVIEW:
J.P. WHITE h NT 7
DATE:
) - % "V, GRCUP HEAD REVIEW:
Nd d
7 A //, he /
DATE:
f[/J2 v
l
'O TEMPORARY APPROVAL (SRO):
DATE:
o TEMPORARY APPROVAL:
DATE:
APPLICABLE CONDITIONS (Temporary procedures only):
APPLICABLE CONDITIONS (Temporary procedures only):
i i
i i
* Refer to paragraphs 3.2.18 and 3.2.19 for temporary approval requirements.
* Refer to paragraphs 3.2.18 and 3.2.19 for temporary approval requirements.
UNT 001 003 Revision 17                                                                                                       Attachment 6.5 (1 of 1)
UNT 001 003 Revision 17.5 (1 of 1)
 
kdministrativeProcedure                                            RW-001-210                    i Process Control Program                                            Revision 7 TABLE OF CONTENTS I
i  1.0  PURPOSE l


==2.0   REFERENCES==
kdministrativeProcedure RW-001-210 i
Process Control Program Revision 7 TABLE OF CONTENTS I
i 1.0 PURPOSE l


l 3.0   DEFINITIONS 4.0   RESPONSIBILITIES 5.0 PROCEDURE 5.1   -Program Description 5.2     Solidification Process Parameters 5.3     Administrative Controls 5.4     Waste Characterization and Classification 5.5     Quality Assurance 6.0 ATTACHMENTS LIST OF EFFECTIVE PAGES Title                   Revision 7                                   i 1-11                   Revision 7 l
==2.0 REFERENCES==
l 3.0 DEFINITIONS 4.0 RESPONSIBILITIES 5.0 PROCEDURE 5.1
-Program Description 5.2 Solidification Process Parameters 5.3 Administrative Controls 5.4 Waste Characterization and Classification 5.5 Quality Assurance 6.0 ATTACHMENTS LIST OF EFFECTIVE PAGES i
Title Revision 7 1-11 Revision 7 l
l l
l l
l l
1
1                                                       ,


NdministrativeProcedure                                                                                 RW-001-210 Process Control Program                                                                                 Revision 7 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 stabilization and/or solidification, as applicable of radioactive " wet waste" which may include resin slurries are in i                                   accordance with applicable Department of Transportation (DOT),
NdministrativeProcedure RW-001-210 Process Control Program Revision 7 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 stabilization and/or solidification, as applicable of radioactive " wet waste" which may include resin slurries are in i
l                                   Nuclear Regulatory Commission (NRC), State and licensed burial l                                   facilities acceptance criteria for packaging and shipment to an l                                   approved burial site. Compliance with these criteria will be achieved through implementation of the PCP and related Waterford 3 and vendor supplied procedures. Containers l                                   engineered and built to comply with the stability requirement may be used. Waterford 3 SES typically relies on Vendor supplied systems and/or services for stabilization and solidification services.
accordance with applicable Department of Transportation (DOT),
l Nuclear Regulatory Commission (NRC), State and licensed burial l
facilities acceptance criteria for packaging and shipment to an l
approved burial site. Compliance with these criteria will be achieved through implementation of the PCP and related Waterford 3 and vendor supplied procedures.
Containers l
engineered and built to comply with the stability requirement may be used. Waterford 3 SES typically relies on Vendor supplied systems and/or services for stabilization and solidification services.
l
l


==2.0   REFERENCES==
==2.0 REFERENCES==
 
l-2.1 Waterford 3 Documents i
l-                   2.1             Waterford 3 Documents i
2.1.1 FSAR Chapter 11.4, Solid Waste Management System 2.1.2 FSAR Chapter 13.4, Review and Audit i
2.1.1             FSAR Chapter 11.4, Solid Waste Management System 2.1.2             FSAR Chapter 13.4, Review and Audit i
2.1.3 FSAR Chapter 13.2, Training l
2.1.3             FSAR Chapter 13.2, Training l                                     2.1.4             FSAR Chapter 13.5, Plant Procedures l
2.1.4 FSAR Chapter 13.5, Plant Procedures l
(                                     2.1.5             Quality Assurance Program Manual (Special Scope)
(
Chapter 5
2.1.5 Quality Assurance Program Manual (Special Scope)
{
{
2.1.6           RW-002-401 Use of Radman Operating Program i
Chapter 5 2.1.6 RW-002-401 Use of Radman Operating Program i
2
2


hdministrativeProcedure                                                         RW-001-210 Process Control Program                                                         Revision 7 2.1.7             RW-002-411 Use of Radman Data Base Manager and Recover 2.1.8             RW-002-110 Waste Sample Collection and Isotope Evaluation l
hdministrativeProcedure RW-001-210 Process Control Program Revision 7 2.1.7 RW-002-411 Use of Radman Data Base Manager and Recover 2.1.8 RW-002-110 Waste Sample Collection and Isotope Evaluation l
l               2.2   Other Documents 2.2.1             10CFR61, Licensing Requirements for Land Disposal of Radioactive Waste l
l 2.2 Other Documents 2.2.1 10CFR61, Licensing Requirements for Land Disposal of Radioactive Waste l
l                     2.2.2             10CFR20.2006, Transfer for disposal and manifests 2.2.3               10CFR71.91, Records i
l 2.2.2 10CFR20.2006, Transfer for disposal and manifests 2.2.3 10CFR71.91, Records i
l l           3.0 DEFINITIONS 3.1   Stability means structural stability as per 10CFR61.2 3.2   Solidification means the immobilization of wet radioactive L
l l
3.0 DEFINITIONS 3.1 Stability means structural stability as per 10CFR61.2 3.2 Solidification means the immobilization of wet radioactive L
wastes such as spent resins, sludges, and reverse osmosis l
wastes such as spent resins, sludges, and reverse osmosis l
concentrates as a result of a process of mixing the waste type with a solidification agent (s) to meet the requirements of the                         j licensed disposal site and 10CFR61.
concentrates as a result of a process of mixing the waste type with a solidification agent (s) to meet the requirements of the j
i 3.3   Qualified Shipper means an individual qualified in the j                       classification, packaging and shipping of radioactive
licensed disposal site and 10CFR61.
[                       waste / material .
i 3.3 Qualified Shipper means an individual qualified in the j
classification, packaging and shipping of radioactive
[
waste / material.
l i
l i
3
3


Administrative Procedure                                           RW-001-210 Process Control Program                                             Revision 7 l
Administrative Procedure RW-001-210 Process Control Program Revision 7 l
l 4.0   RESPONSIBILITIES l
l 4.0 RESPONSIBILITIES l
l             4.1   Radiation Protection Superintendent 4.1.1     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.
l 4.1 Radiation Protection Superintendent 4.1.1 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.
4.2   Qualified Shipper 4.2.1     The Qualified Shipper (s) is responsible for ensuring radioactive material and radioactive waste is classified, packaged and shipped in accordance with appropriate procedures / regulations.
4.2 Qualified Shipper 4.2.1 The Qualified Shipper (s) is responsible for ensuring radioactive material and radioactive waste is classified, packaged and shipped in accordance with appropriate procedures / regulations.
4.3   Operations Superintendent 4.3.1     The Operations Superintendent is responsible for the effective operations of permanent plant radwaste systems.
4.3 Operations Superintendent 4.3.1 The Operations Superintendent is responsible for the effective operations of permanent plant radwaste systems.
4.4   Chemistry Superintendent 4.4.1     The Chemistry Superintendent is responsible for providing assistance on items or problems relating to radwaste processes and chemistry controls or chemical reactions and performing chemical and radiochemical analyses of samples of radioactive waste or materials.
4.4 Chemistry Superintendent 4.4.1 The Chemistry Superintendent is responsible for providing assistance on items or problems relating to radwaste processes and chemistry controls or chemical reactions and performing chemical and radiochemical analyses of samples of radioactive waste or materials.
4
4


dministrative Procedure                                                   RW-001-210 Process Control Program                                                     Revision 7 i
dministrative Procedure RW-001-210 Process Control Program Revision 7 i
l               4.5   Quality Assurance                                                               ;
l 4.5 Quality Assurance
                                                                                                        )
)
4.5.1   Quality Assurance is responsible for:                                   l I
4.5.1 Quality Assurance is responsible for:
f 4.5.1.1   Assessing the implementation and effectiveness of the quality assurance                       l aspects of the Process Control Program through regular audits and selective                         l monitoring of activities.                                   ;
f 4.5.1.1 Assessing the implementation and effectiveness of the quality assurance aspects of the Process Control Program through regular audits and selective monitoring of activities.
!                                                                                                      \
\\
l l
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I l
l' 5
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5


Administrative Procedure                                                                 RW-001-210   l
Administrative Procedure RW-001-210 Process Control Program Revision 7 i
;                Process Control Program                                                                   Revision 7   I i
4 l
4 l               5.0 PROCEDURE i
5.0 PROCEDURE i
5.1 Program Description
5.1 Program Description 5.1.1 Solidification System
>                                5.1.1                     Solidification System


== Description:==
== Description:==
Waterford 3 utilizes     )
Waterford 3 utilizes
f                                                           vendor supplied portable solidification equipment for radioactive waste solidification. All vendor                 l solidification process procedures will be approved as       l plant procedures by Plant Operating Review Sub-Committee.
)
f vendor supplied portable solidification equipment for radioactive waste solidification. All vendor solidification process procedures will be approved as l
plant procedures by Plant Operating Review Sub-Committee.
Reference 2.1.1 through 2.1.5 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.
Reference 2.1.1 through 2.1.5 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.
5~1.2 Sources of Waterford 3 Stabilization / Solidification Feeds:
5~1.2 Sources of Waterford 3 Stabilization / Solidification Feeds:
The Cement solidification will be used to stabilize resins, if needed. During resin stabilization, vendor equipment will be connected to the Resin Waste Management System outlet to allow for the transfer of resin. Solidification using Aquaset/Petroset media will be used to process resins, oil, and water / acid. This process will not be     l connected to any plant waste systems and will be processed on a batch basis.                                           1 4
The Cement solidification will be used to stabilize resins, if needed.
During resin stabilization, vendor equipment will be connected to the Resin Waste Management System outlet to allow for the transfer of resin.
Solidification using Aquaset/Petroset media will be used to process resins, oil, and water / acid. This process will not be connected to any plant waste systems and will be processed on a batch basis.
1 4
6
6


Administrative Procedure                                               RW-001-210 Process Control Program                                               Revision 7 5.2   Solidification Process Parameters:
Administrative Procedure RW-001-210 Process Control Program Revision 7 5.2 Solidification Process Parameters:
5.2.1     Solidification formulas and solidification process parameters are incorporated into the applicable vendor l                             process control program. No exceptions or deviations l
5.2.1 Solidification formulas and solidification process parameters are incorporated into the applicable vendor l
l                             from vendor supplied procedures 'or topical reports are l                             anticipated for stabilized waste. The formulas are used to calculate the ratio of waste, cement, water and
process control program.
,                              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 controls program.
No exceptions or deviations l
Waste stream parameters are adjusted as necessary to l
l from vendor supplied procedures 'or topical reports are l
i meet these requirements.
anticipated for stabilized waste. The formulas are used to calculate the ratio of waste, cement, water and other reagents required to achieve an acceptable solidified product.
l 5.2.2     Test solidifications are performed on waste stream samples to verify vendor calculated solidification formulas.
Compatibility requirements of the waste stream with respect to the solidification media are described in the vendor process controls program.
l NOTE i       Vendor PCP along with applicable procedures will be approved as plant l       procedures prior to use.
l Waste stream parameters are adjusted as necessary to i
5.2.3     Radioactive wastes shall be solidified or dewatered in accordance with the process control program to meet shipping and transportation requirements during transit, and disposal site requirements when received at the disposal site.
meet these requirements.
l 5.2.2 Test solidifications are performed on waste stream samples to verify vendor calculated solidification formulas.
l NOTE i
Vendor PCP along with applicable procedures will be approved as plant l
procedures prior to use.
5.2.3 Radioactive wastes shall be solidified or dewatered in accordance with the process control program to meet shipping and transportation requirements during transit, and disposal site requirements when received at the disposal site.
7 l
7 l


                    ' Administrative Procedure                                                           RW-001-210           !
' Administrative Procedure RW-001-210 Process Control Program Revision 7 i
Process Control Program                                                             Revision 7 i
L i
L                                                                                                                             i l                                                                                                                             !
l 5.2.4 With solidification or dewatering not meeting disposal l
5.2.4         With solidification or dewatering not meeting disposal l                                                 site and shipping and transportation requirements,                         .
site and shipping and transportation requirements, suspend shipment of the inadequately processed wastes l
suspend shipment of the inadequately processed wastes                       !
and correct the process control program, the C
l                                                  and correct the process control program, the C
procedures, and/or the solid waste system as necessary to prevent recurrehce.
procedures, and/or the solid waste system as necessary                       ;
t 5.2.5 With solidification or dewatering not performed in L
to prevent recurrehce.                                                     t 5.2.5         With solidification or dewatering not performed in                           !
accordance with the process control program, test the improperly processed waste in each container to ensure that it meets burial ground and shipping requirements and perform appropriate corrective action if required.
L                                                  accordance with the process control program, test the                       :
i 5.2.6 Solidification of at least one representative test i
;                                                  improperly processed waste in each container to ensure that it meets burial ground and shipping requirements
j specimen from at least every tenth batch of each type L
!                                                  and perform appropriate corrective action if required.
of wet radioactive wastes (e.g., filter sludges, spent resins), shall be verified in accordance with the vendor's process control program.
i 5.2.6           Solidification of at least one representative test                         i j                                                 specimen from at least every tenth batch of each type                       ;
l 5.2.7 If the initial test specimen from a batch of waste
L                                                  of wet radioactive wastes (e.g., filter sludges, spent resins), shall be verified in accordance with the vendor's process control program.
)
l                                 5.2.7           If the initial test specimen from a batch of waste                         )
fails to verify solidification, the process control l
fails to verify solidification, the process control l                                                 program shall provide for the coFection and testing of representative test specimens from each consecutive batch of the same type of wet waste until at least three consecutive initial test specimens demonstrate solidification. The process control program may be l                                                 modified if practical to assure solidification of subsequent batches of waste.
program shall provide for the coFection and testing of representative test specimens from each consecutive batch of the same type of wet waste until at least three consecutive initial test specimens demonstrate solidification. The process control program may be l
modified if practical to assure solidification of subsequent batches of waste.
l l
l l
l l                                                                                                           2
l l
    ~
2
~
8
8


Administrative Procedure                                                             RW-001-210 Process Control Program                                                             Revision 7                       ,
Administrative Procedure RW-001-210 Process Control Program Revision 7 i
i 5.2.8   If any test specimen fails to verify solidification,                               i the solidification of the batch under test shall be                                 !
5.2.8 If any test specimen fails to verify solidification, i
suspended until such time as additional test specimens                             ,
the solidification of the batch under test shall be suspended until such time as additional test specimens can be obtained, alternative solidification parameters can be determined in accordance with the vendors process control program, and a subsequent test verifies i
can be obtained, alternative solidification parameters can be determined in accordance with the vendors process control program, and a subsequent test verifies i                                                         solidification. Solidification of the batch may then be resumed using the alternative solidification parameters determined by the process control program.                                         j l
solidification. Solidification of the batch may then be resumed using the alternative solidification parameters determined by the process control program.
5.3         Administrative Controls                                                                     ,
j l
5.3.1   Administrative controls utilized to insure compliance with applicable state and federal regulations and                                   [
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 l
burial site criteria are detailed in the radioactive waste solidification surveillance procedure (s). These implementing document (s) for radioactive waste l
solidification and dewatering describes the requirements which must be met prior to processing
solidification and dewatering describes the requirements which must be met prior to processing radioactive waste, as well as the condition of the i
!                                                          radioactive waste, as well as the condition of the                                 i
. solidified or dewatered waste. Test solidifications, full scale calculations and operation of the solidification equipment are performed by vendor i
                                                          . solidified or dewatered waste. Test solidifications,                               !
personnel. Dewatering operations will be performed by vendor personnel or by qualified Plant staff. Plant staff provides Health Physics and Quality Assurance l
full scale calculations and operation of the solidification equipment are performed by vendor i                                                         personnel. Dewatering operations will be performed by vendor personnel or by qualified Plant staff. Plant staff provides Health Physics and Quality Assurance l                                                           coverace, 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 j                                                           solidification activities.
coverace, 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 j
l 9
solidification activities.
9


  ' Administrative Procedure                                           RW-001-210 l   Process Centrol Program                                           Revision 7           ,
' Administrative Procedure RW-001-210 l
l                                                                                          i l                                                                                           l l               5.3.2   Changes to this Process Control Program shall be l                       described in the semi-annual Radioactive Effluent Release Report for the period in which the change is               l l                        made, i
Process Centrol Program Revision 7 l
o 5.4   Waste Characterization and Classification l
i l
5.4.1   Waste Classification                                               i i
l 5.3.2 Changes to this Process Control Program shall be l
5.4.1.1     Solidified wastes are classified in
described in the semi-annual Radioactive Effluent Release Report for the period in which the change is l
;                                    accordance with the requirements of 10CFR61.55, as implemented by reference 2.1.6 and plant waste classification and characterization procedure (s).
: made, i
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 as described in Reference 2.1.8.
o 5.4 Waste Characterization and Classification l
Scaling factors for the non-gamma emitting and transuranic constituents will be                   i developed from this annual analysis using References 2.1.6 and 2.1.7. The activity of each radionuclide in the solidified waste will be determined by a core sample or a calculational method employing the percent abundance and scaling factors with a dose to curie conversion factor as described in               j Reference 2.1.6.
5.4.1 Waste Classification i
i 5.4.1.1 Solidified wastes are classified in accordance with the requirements of 10CFR61.55, as implemented by reference 2.1.6 and plant waste classification and characterization procedure (s).
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 as described in Reference 2.1.8.
Scaling factors for the non-gamma emitting and transuranic constituents will be developed from this annual analysis using References 2.1.6 and 2.1.7.
The activity of each radionuclide in the solidified waste will be determined by a core sample or a calculational method employing the percent abundance and scaling factors with a dose to curie conversion factor as described in j
Reference 2.1.6.
l l
l l
l l
l l
l 10
10


Administrative Procedure                                                                       RW-001-210 Process Control Program                                                                       Revision 7 5.4.2           Waste Characteristics                                                                       ,
Administrative Procedure RW-001-210 Process Control Program Revision 7 5.4.2 Waste Characteristics 5.4.2.1 Solidified wastes will meet the characteristics of 10CFR61.56(a).
5.4.2.1                       Solidified wastes will meet the characteristics of 10CFR61.56(a).                             r Stabilized wastes will meet the characteristics of 10CFR61.56(b). Waste                       ,
r Stabilized wastes will meet the characteristics of 10CFR61.56(b). Waste containers will be labeled to identify the waste class.
containers will be labeled to identify the waste class.
5.4.2.2 The manifesting requirements of 10CFR20.2006 are implemented and records are maintained in accordance with 10CFR71.91.
5.4.2.2                       The manifesting requirements of 10CFR20.2006 are implemented and records are maintained in accordance with 10CFR71.91.
5.5 Quality Assurance 5.5.1 The Process Control Program shall meet the requirements specified in Quality Assurance Program Manual (Special l
5.5   Quality Assurance 5.5.1           The Process Control Program shall meet the requirements specified in Quality Assurance Program Manual (Special l                                                       Scope) Chapter 5.
Scope) Chapter 5.
6.0   ATTACHMENTS i
6.0 ATTACHMENTS i
l                               NONE L
l NONE L
l l
l l
I l
I l
i
i i.
: i.                                                                                                                                                   -
11
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Latest revision as of 19:47, 11 December 2024

Rev 7 to RW-001-210, Process Control Program
ML20138D889
Person / Time
Site: Waterford Entergy icon.png
Issue date: 01/11/1996
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20138D697 List:
References
RW-001-210, RW-1-210, NUDOCS 9705010287
Download: ML20138D889 (14)


Text

_

f-PORC/PORC-SC l

RW-001-210 l

REVISION 7

l EFFECTIVE DATE l

l l

l l

l SAFETY-RELATED l

1

/

ADMINISTRATIVE PROCEDURE PROCESS CONTROL PROGRAM I

l (1

h )} :.

. [ s p

la i

COPY COPY No. b/

UNT-001-002 Revision 13.3 (1 of 2) 9705010287 970429

-t-PDR ADOCK 05000302 48 R

PDR

l PORC AND PORC - S/C REVIEW AND APPROVAL SHEET l

l REVIEW 0F: RW-001-210 - Process Control Proaram PORC E

l (Rev. 7)

PORC - S/C O

i The PORC or PORC S/C has reviewed this item and determined that a Safety /

l Commitment Review was performed (if applicable), that a Safety Evaluation was performed (if applicable), that an unreviewed safety question does i

not exist, and that nuclear safety is/was not adversely affected.

PORC RECOMMENDED FOR APPROVAL l

MEMBER MEMBER SIGNATURE YES NO u r n endent

. //

'/'//

N

{C 1

,M-Operations Superintendent

/

Radiation Protection

/'

Superintendent

/d t

Quality Assurance I

f.

Member 1M'-

c Mgmt Knowledgeable j

in Engineering Manager Operations &

Maintenance PORC-S/C Member PORC-S/C Member PORC-S/C Member Meeting No.96-004 Item No.

VI-I Date:

1/10/96 This item is recommended for approval? E YES O N0 i

This item requires SRC/NRC review prior to implementation? O YES E NO If yes, ensure documentation supporting review is attached.

SIGNATURE RECOMMENDED FOR APPROVAL YES NO DATE l

PORC-S/C Chairman r

PORC Chairman

,Mh%,%

V

/ - / o #l/.

Comments:

U l

m _ - _

i Approved b N b

'rh Date i,/y /fc.

General Manager Plant Operations UNT-001-004 Revision 14 23.1 (1 of 1)

_ _ _ _.. _ ~ _.. _ -.. _ _ _ _ _ _ _ _. _ _ _. _. - _ _ _ _

i Check Block WATERFORD 3 SES TlPORC PLANT OPERATING MANUAL l

l PORC-S/C-REQUEST / APPROVAL PAGE

~

DEPT.

Procedure No.:

RW-001-210

Title:

PROCESS CONTROL PROGRAM

~EffGctive Date:

N/A (If different from approval date)

COMPLETE A. B. C. and D:

A. Change No.:

fd l A l

l Permanent Deviation Expiration Date:

N/A B. Revision No.:

7 l

C. Deletion:

l l YES X l NO D. Temporary Procedure:

l l YES l X l NO Expiration Date:

N/A-DESCRIPTION OF CHANGE, REVISION, OR DELETION:

1) ADDED STEP 3.3 "OUALIFIED SHIPPER" T0 l

DEFlNATIONS. 2) REPLACED "RADWASTE FORMAN" WITH "OUALIFIED SHIPPER" IN RESPONSIBILITIES SECTION 4.2.

3) REFINED RESPONSIBILITIES OF THE CHEMISTRY AND OPERATIONS SUPERINTENDENTS.
4) EXPANDED STEP 5.5.1.

~

l REASON FOR CHANGE, REVISION, OR DELETION:

1) OVALIFIED SHIPPER ADDED DUE TO DEPARTMENTAL ORGANIZATIONAL CHANGES. 2) RADWASTE FOREMAN REPLACED WITH OVALIFIED SHIPPER DUE TO DEPARTMENTAL ORGANIZATIONAL CHANGES. 3) RESPONSIBILITIES OF THE CHEMISTRY AND OPERATIONS SUPERINTENDENTS WERE POORLY WRITTEN. 4) STEP 5.5.1. WAS EXPANDED TO BETTER DEFINE THE QUALITY ASSURANCE PROGRAM MANUAL (SPECIAL SCOPE) CHAPTER 5 AS IT PERTAINS TO THE PCP.

AUTHOR \\0RIGINATOR:

STEVE LANDRY d Au DATE:

9-(&97 TECHNICAL REVIEW:

J.P. WHITE h NT 7

DATE:

) - % "V, GRCUP HEAD REVIEW:

Nd d

7 A //, he /

DATE:

f[/J2 v

l

'O TEMPORARY APPROVAL (SRO):

DATE:

o TEMPORARY APPROVAL:

DATE:

APPLICABLE CONDITIONS (Temporary procedures only):

i i

  • Refer to paragraphs 3.2.18 and 3.2.19 for temporary approval requirements.

UNT 001 003 Revision 17.5 (1 of 1)

kdministrativeProcedure RW-001-210 i

Process Control Program Revision 7 TABLE OF CONTENTS I

i 1.0 PURPOSE l

2.0 REFERENCES

l 3.0 DEFINITIONS 4.0 RESPONSIBILITIES 5.0 PROCEDURE 5.1

-Program Description 5.2 Solidification Process Parameters 5.3 Administrative Controls 5.4 Waste Characterization and Classification 5.5 Quality Assurance 6.0 ATTACHMENTS LIST OF EFFECTIVE PAGES i

Title Revision 7 1-11 Revision 7 l

l l

1

NdministrativeProcedure RW-001-210 Process Control Program Revision 7 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 stabilization and/or solidification, as applicable of radioactive " wet waste" which may include resin slurries are in i

accordance with applicable Department of Transportation (DOT),

l Nuclear Regulatory Commission (NRC), State and licensed burial l

facilities acceptance criteria for packaging and shipment to an l

approved burial site. Compliance with these criteria will be achieved through implementation of the PCP and related Waterford 3 and vendor supplied procedures.

Containers l

engineered and built to comply with the stability requirement may be used. Waterford 3 SES typically relies on Vendor supplied systems and/or services for stabilization and solidification services.

l

2.0 REFERENCES

l-2.1 Waterford 3 Documents i

2.1.1 FSAR Chapter 11.4, Solid Waste Management System 2.1.2 FSAR Chapter 13.4, Review and Audit i

2.1.3 FSAR Chapter 13.2, Training l

2.1.4 FSAR Chapter 13.5, Plant Procedures l

(

2.1.5 Quality Assurance Program Manual (Special Scope)

{

Chapter 5 2.1.6 RW-002-401 Use of Radman Operating Program i

2

hdministrativeProcedure RW-001-210 Process Control Program Revision 7 2.1.7 RW-002-411 Use of Radman Data Base Manager and Recover 2.1.8 RW-002-110 Waste Sample Collection and Isotope Evaluation l

l 2.2 Other Documents 2.2.1 10CFR61, Licensing Requirements for Land Disposal of Radioactive Waste l

l 2.2.2 10CFR20.2006, Transfer for disposal and manifests 2.2.3 10CFR71.91, Records i

l l

3.0 DEFINITIONS 3.1 Stability means structural stability as per 10CFR61.2 3.2 Solidification means the immobilization of wet radioactive L

wastes such as spent resins, sludges, and reverse osmosis l

concentrates as a result of a process of mixing the waste type with a solidification agent (s) to meet the requirements of the j

licensed disposal site and 10CFR61.

i 3.3 Qualified Shipper means an individual qualified in the j

classification, packaging and shipping of radioactive

[

waste / material.

l i

3

Administrative Procedure RW-001-210 Process Control Program Revision 7 l

l 4.0 RESPONSIBILITIES l

l 4.1 Radiation Protection Superintendent 4.1.1 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.

4.2 Qualified Shipper 4.2.1 The Qualified Shipper (s) is responsible for ensuring radioactive material and radioactive waste is classified, packaged and shipped in accordance with appropriate procedures / regulations.

4.3 Operations Superintendent 4.3.1 The Operations Superintendent is responsible for the effective operations of permanent plant radwaste systems.

4.4 Chemistry Superintendent 4.4.1 The Chemistry Superintendent is responsible for providing assistance on items or problems relating to radwaste processes and chemistry controls or chemical reactions and performing chemical and radiochemical analyses of samples of radioactive waste or materials.

4

dministrative Procedure RW-001-210 Process Control Program Revision 7 i

l 4.5 Quality Assurance

)

4.5.1 Quality Assurance is responsible for:

f 4.5.1.1 Assessing the implementation and effectiveness of the quality assurance aspects of the Process Control Program through regular audits and selective monitoring of activities.

\\

l l

l' 5

Administrative Procedure RW-001-210 Process Control Program Revision 7 i

4 l

5.0 PROCEDURE i

5.1 Program Description 5.1.1 Solidification System

Description:

Waterford 3 utilizes

)

f vendor supplied portable solidification equipment for radioactive waste solidification. All vendor solidification process procedures will be approved as l

plant procedures by Plant Operating Review Sub-Committee.

Reference 2.1.1 through 2.1.5 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.

5~1.2 Sources of Waterford 3 Stabilization / Solidification Feeds:

The Cement solidification will be used to stabilize resins, if needed.

During resin stabilization, vendor equipment will be connected to the Resin Waste Management System outlet to allow for the transfer of resin.

Solidification using Aquaset/Petroset media will be used to process resins, oil, and water / acid. This process will not be connected to any plant waste systems and will be processed on a batch basis.

1 4

6

Administrative Procedure RW-001-210 Process Control Program Revision 7 5.2 Solidification Process Parameters:

5.2.1 Solidification formulas and solidification process parameters are incorporated into the applicable vendor l

process control program.

No exceptions or deviations l

l from vendor supplied procedures 'or topical reports are l

anticipated for stabilized waste. 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 controls program.

l Waste stream parameters are adjusted as necessary to i

meet these requirements.

l 5.2.2 Test solidifications are performed on waste stream samples to verify vendor calculated solidification formulas.

l NOTE i

Vendor PCP along with applicable procedures will be approved as plant l

procedures prior to use.

5.2.3 Radioactive wastes shall be solidified or dewatered in accordance with the process control program to meet shipping and transportation requirements during transit, and disposal site requirements when received at the disposal site.

7 l

' Administrative Procedure RW-001-210 Process Control Program Revision 7 i

L i

l 5.2.4 With solidification or dewatering not meeting disposal l

site and shipping and transportation requirements, suspend shipment of the inadequately processed wastes l

and correct the process control program, the C

procedures, and/or the solid waste system as necessary to prevent recurrehce.

t 5.2.5 With solidification or dewatering not performed in L

accordance with the process control program, test the improperly processed waste in each container to ensure that it meets burial ground and shipping requirements and perform appropriate corrective action if required.

i 5.2.6 Solidification of at least one representative test i

j specimen from at least every tenth batch of each type L

of wet radioactive wastes (e.g., filter sludges, spent resins), shall be verified in accordance with the vendor's process control program.

l 5.2.7 If the initial test specimen from a batch of waste

)

fails to verify solidification, the process control l

program shall provide for the coFection and testing of representative test specimens from each consecutive batch of the same type of wet waste until at least three consecutive initial test specimens demonstrate solidification. The process control program may be l

modified if practical to assure solidification of subsequent batches of waste.

l l

l l

2

~

8

Administrative Procedure RW-001-210 Process Control Program Revision 7 i

5.2.8 If any test specimen fails to verify solidification, i

the solidification of the batch under test shall be suspended until such time as additional test specimens can be obtained, alternative solidification parameters can be determined in accordance with the vendors process control program, and a subsequent test verifies i

solidification. Solidification of the batch may then be resumed using the alternative solidification parameters determined by the process control program.

j l

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 l

solidification and dewatering describes the requirements which must be met prior to processing radioactive waste, as well as the condition of the i

. solidified or dewatered waste. Test solidifications, full scale calculations and operation of the solidification equipment are performed by vendor i

personnel. Dewatering operations will be performed by vendor personnel or by qualified Plant staff. Plant staff provides Health Physics and Quality Assurance l

coverace, 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 j

solidification activities.

9

' Administrative Procedure RW-001-210 l

Process Centrol Program Revision 7 l

i l

l 5.3.2 Changes to this Process Control Program shall be l

described in the semi-annual Radioactive Effluent Release Report for the period in which the change is l

made, i

o 5.4 Waste Characterization and Classification l

5.4.1 Waste Classification i

i 5.4.1.1 Solidified wastes are classified in accordance with the requirements of 10CFR61.55, as implemented by reference 2.1.6 and plant waste classification and characterization procedure (s).

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 as described in Reference 2.1.8.

Scaling factors for the non-gamma emitting and transuranic constituents will be developed from this annual analysis using References 2.1.6 and 2.1.7.

The activity of each radionuclide in the solidified waste will be determined by a core sample or a calculational method employing the percent abundance and scaling factors with a dose to curie conversion factor as described in j

Reference 2.1.6.

l l

l l

10

Administrative Procedure RW-001-210 Process Control Program Revision 7 5.4.2 Waste Characteristics 5.4.2.1 Solidified wastes will meet the characteristics of 10CFR61.56(a).

r Stabilized wastes will meet the characteristics of 10CFR61.56(b). Waste containers will be labeled to identify the waste class.

5.4.2.2 The manifesting requirements of 10CFR20.2006 are implemented and records are maintained in accordance with 10CFR71.91.

5.5 Quality Assurance 5.5.1 The Process Control Program shall meet the requirements specified in Quality Assurance Program Manual (Special l

Scope) Chapter 5.

6.0 ATTACHMENTS i

l NONE L

l l

I l

i i.

11

_