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DATE: /2/l-!f$C1 e a r General Office Review Station Review BY: - | DATE: /2/l-!f$C1 e a r General Office Review Station Review BY: - | ||
OM/ b . 4)27 t-- BY: M I[M[ | OM/ b . 4)27 t-- BY: M I[M[ | ||
(( TITLE: Mtu c hhb fmgtweop TITLE: /I' red /g/ <L viox DATE: /2 /4/ f SC) DATE: A#/S/89 i | |||
This revision is approved for use at ficGuire Nuclear Station. t | This revision is approved for use at ficGuire Nuclear Station. t | ||
. f Sechnical System Manager 8.CbL/AA k k.AA FicGui re . Te'cfinical Services Superintendent DATE: /Z- d DATE: /L - J : .P f | . f Sechnical System Manager 8.CbL/AA k k.AA FicGui re . Te'cfinical Services Superintendent DATE: /Z- d DATE: /L - J : .P f | ||
Latest revision as of 09:36, 15 March 2020
| ML20012A369 | |
| Person / Time | |
|---|---|
| Site: | McGuire, 05000000, Mcguire |
| Issue date: | 12/05/1989 |
| From: | Carpenter C, Ekechukwu O, Mcconnell T DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML15217A104 | List: |
| References | |
| PROC-891205, NUDOCS 9003090332 | |
| Download: ML20012A369 (54) | |
Text
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DUKE POWER COMPANY l N' ) PCP REVISION. APPROVAL j l l Revised PCP Sectiont ;
)
Corporate PCP, Rev . ONS PCP, Rev l MNS PCP, Rev 8 l CNS'PCP, Rev' This revision has been reviewed against Technical Specifications and applicable NRC guidance documents and found to be acceptable. ; PREPARED BY: O. E. Ekochukwu - Nuclear Production Engineer TITLE: DATE: I 2 /L-l 59 l General Office Review Station Review BY: !OM/b,b -_, BY: M Mdwd ! f) TITLE: 7tu o htybulue h,ynop. "'ITLE: /djd#grgf viu
.DATE: ,j@ 4 M , , , , _
DATE: _J /6-Mp -
"his revision is approved f or use at jicGuire_____ Ninclear Station.
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/ \Cechnical System Manager
_,3 irs s a n w .7 ,rr __ McGuire Te'cfinfcal Services Superintendent DATE: /2 DATE: /4 - J - f f (
/
W u W )A'?Ih1 Ate lf Y l' $tation Manap6r / DATE: /2!5 9
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MCGUIRE NUCLEAR STATION I { PROCESS CONTROL PROGRAM ' l 1.0 PURPOSE i The purpose of the McGuire Nuclear Station Process Control ! Program is to insure all requirements of the DPC Corporate ! Process Control Program have been met for each container of ! solidified or dewatered radioactive waste shipped for burial i at a licensed burial facility. The PCP is applicable only : to the solifification or dewatering of liquid or wet solid ; radioactive waste. j 2.0 COMPOSITION ' 2.1- The McGuire Nuclear Statien PROCESS CONTROL PROGRAM ; shall consist of: 2.1.1 The Duke Power Company Process Control Manual . Introduction (Section 1). 2.1.2 The Duke Power Company Corporate Process (} Cor. trol Program. 2.1.3 A list of all sthtion-soecific procedures that implement the requirements of tho ; Ccrporate Process Control Program, ' 2.1.4 McGuire Nuclcar Station diagrams or drawings or drawing numbers showing a]l connections between CNS radwaste nystems and solidi-L fications and dewatering equipment. 2.1.5 Cocunentation of NRC approval of the initial McGuire Nuclear Station Process Control Program. \ 2.1.6 Documentation of Technical System Manager p Nuclear Chemistry, MNS Technickl Services Superintendent and MNS Station Manager approval of the changes *,o the Corporate Process Control Program. ! 2.1.7 Documentation that all changes to the L Corporate and/or CNS Process Control Program were sent to the NRC in the Semi-Annual Radioactive Effluent Report:,
%)
M-1 Rev. 8 E- - - - _ . - -
, j i
j'T 2.1.8 Relevant sections and subsections of !
\_) Process Control Program-related definitions i transferred from Section 1 of McGuire t
}' Nuclear Station Technical Specifications. . 2.1.9 Relevant sections and subsections of Process ! Control Program-related limiting conditions for operation, bases and surveillance , requirements transferred from Sections 3/4 ! of the McGuire Nuclear Station Technical Sepcifications. 3.0 EXCEPTIONS 3.1 The McGuire Nuclear Station Process Control Program takes the following exceptions with DPC Corporate : Process Control Programs i
- 3.1.1 For Corporate PCP Section 2.1.2, station review and station Technical Services Superintendent approval are not required.
Corporate review and approval of vendor solidification services are sufficient. 3.1.2 For Corporate PCP Section 3.1.2, station FN review and station Technical Services Superintendent approval are not required. 5-) Corporate review and approval of vendor dewatering services are sufficient. ' l [ M-2 Rev 8
l' . l . 4 o i L
^
U DUKE POWER COMPANY k-) PROCESS CONTROL PROGRAM i SECTION 2.1.3 IMPLEMENTING PROCEDURE CP/0/B/8300/20 "Radwaste Chemistry Procedure for Handling of Laboratory Quantities of Spent Resin" , CP/0/B/8600/ll "Radwaste Chemistry Procedure for Sampling ' Evaporator Concentrates and Resin (Isolock Sampler)" HP/0/B/1004/04 " Preparation and Shipment of' Mechanical Radwaste Materials" HP/0/B/1004/09 " Preparation and Shipment of Processed ! Radwaste Materials" HP/0/B/1004/12 " Utilization of Polyethylene High Integrity Overpacks" HP/0/B/1004/14 " Preparation and Shipment of Dewatered Resins" OP/0/B/6200/32 "Radwaste Procedure for the Nuclear Solid Waste (WS) Disposal System Operation" OP/0/B/6200/37 "Radwaste Procedure for Conteninated Oil Storage Tank Operation" OP/0/B/6200/53 "Radwaste Chemistry Procedure for Transfer, Solidification and Preparation for Shipment" OP/0/B/6200/64 "Raawaste Chemistry Procedure for Transfer, Dewater3ng and Shipment of Bead Resin" , OP/0/B/6200/65 "Radwasce chemistry Procedure for Transfer, Devatnring and Shipment of Powdex Resin" ; OP/0/B/6200/66 "Radwaste Chemistry Procedure for Dewatering and Shipment of Vendor Demineralizers and Filters" OP/0/B/6200/67 " Process Control Program for CNSI-Acid Solidification" OP/0/B/6200/68 " Process Control Program for CNSI Cement Solidification Units" (FOP /0/B/6200/69 " Process Control Program for Cement / Oil Solidification" M-3 Rev. 8
7, e I . . ; i
/~'s OP/0/B/ 6200/70 " Operating Procedure for the CNSI Mobile U Solidification Unit for 55-gallon drums l
.(MSU-Drum-C-3)" i OP/0/B/6250/09 " Condensate Polishing Domineralizer i operation" i I
OP/0/B/6200/77 " Babcock and Wilcox Aquaset/Petroset i Solidification Process" \ l l I I c i i s- , O%/ M-4 Rev. 8
'4 '
i MCGUIRE NUCLEAR STATION l d('- PROCESS CONTROL PROGRAM j SECTION 2.1.4 DI< AWING INDEX ) Plant Interfaces: MC-110 '. -01. 0 2 MC-1423-19.32-02 < MC-1566-1.0 l MC-1566-1.1 MC-1566-2.0 : MC-1566-3.0 MC-1590-1.3 i MC-1604-1.1 '
. All portable system interfaces are shown on diagrams in the '
applicable station procedure.
,Q U 1 i
i
+
f i k O M-5 Rev. 8
. j McGUIRE NUCLEAR STATION l L (_) PROCESS CONTROL PROGRAM H
SECTION 2.1.8 l DEFINITIONS ' 1 l.0 DEFINITIONS The defined terms of this section appear in capitalized type : l cnd are applicable throughout this' PROCESS CONTROL PROGRAM. Note: This section is transferred directly from pre-1989- ! Technical Specifications per NRC Generic Letter GL 89-01. OPERABLE - OPERABILITY A 1.18 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing
- its specified function (s), and when all necessary attendant
-instrumentation, controls, electrical power, cooling or seal !
water, lubrication or other auxiliary equipment that are ' required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support functions (s). PROCESS CONTROL PROGRAM (PCP) 1.22 The. PROCESS CONTROL PROGRAM shall contain the provisions to assure that the SOLIDIFICATION of wet radioactive wastes results in a waste form with properties that meet the require- , ments of-10 CFn part 61 and of low level radioactive waste disposal sites. The.PCP shall identify process parameters i influencing SOLIDIF1 CATION such as pH, oil content, H0 3 esntent, solids. content, ratio of solidificatin1 agent to waste and/or nocassary additivites for each type of anticipated ; waste, and the acceptable boundary conditiens for the process
- parameters shall be identified for each waste type, based on
- laboratory scale and full scale testing or experience. The PCP >
chall also include an identification of conditions that must be catisfied, based on full scale testing, to assure that dewatering of bead resins, powdered resins, and filter sludges will result in volumes of free water, at the time of disposal, ' within the limits of 10CFR Part 61 and of low level radioactive , waste disposal sites. SOLIDIFICATION 1,32 SOLIDIFICATION shall be the immobolization of wet radioactive wastes such as evaporator bottoms, spent resins, sludges and reverse osmosis. concentrates as a result of a O process,of thoroughtly mixing the waste type with a SOLIDIFICATION agent (s) to form a free standing monolith with chemical and physical characteristics specified in the PROCESS CONTROL PROGRAM (PCP). - M-6 Rev. 8
F .. , L l MCGUIRE NUCLEAR STATION I (Q> > PROCESS CONTROL PROGRAM SECTION 2.1.9 LIMITING C04]ITIOtS FOR OPERATIONS. BASES AND S JtVEILJ.,ANCE REQUIR z riLiis l l RADIOACTIVE EFFLUENTS 3/4.11.3 SOLID RADIOACTIVE WASTES LIMITING CONDITION FOR OPERATION 3.11.3 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. APPLICABILITY: At all times. ACTION: -
- a. With SOLIDIFICATION or dewatering not meeting dis-posal site and shipping and transportation requirements, suspend shipment of the inadequately processed wastes and correct the PROCESS CONTROL PROGRAM, the procedures and/or the Solid Radwaste
(} System as necessary to prevent recurrence,
- b. With SOLIDIFICATION or dewatering not performed in accordance with the PROCESS CONTROL PROGRAM, test the improperly processed wasta in each container to ensure that it meets burial ground and shipping requirements and take appropriate administrative j action to prevent recurrence.
l
- c. The provisions of specification 3.0.3 are not applicable, ,
SURVEILM ECE REQURIEMENTS 4.11.3 SOLIDIFICATION of at least one representative test specimen from at least'every tenth batch of each type of wet radioactive wastes (e.q., filter sludges, spent resins, evaporator bottoms, boric acid solutions and sodium sulfate solutions) shall be verified in accordance with the PROCESS CONTROL PROGRAM:
- a. If any test specimen fails to verify SOLIDIFICATION, 4 the SOLIDIFICATION, of the batch under test shall be suspended until such time as additional test specimens can be obtained, alternative SOLIDI-FICATION parameters can be determined in accordance O
with the PROCESS CONTROL PROGRAM, and a subsequent test verifies SOLIDIFICATION. SOLIDIFICATION of the batch may then be resumed using the alternative
. De51
. p
(~TSOLIDIFICATION parameters determined by the PROCESS : s CONTROL PROGRAN; l
- b. If the initial test specimen from a batch of waste 1 fails to verify SOLIDIFICATION, the PROCESS CONTROL 1 PROGRAM shall provide for the collection and testing of representative test specimens from each con- ,
secutive batch of the same type of wet waste until at j least three consecutive initial test specimens : demonstrate SOLIDIFICATION. The PROCESS CONTROL PROGRAM shall be modified as required, as provided in Specification 6.13, to assure Solidification of , subsequent batches i of waster and I
- c. With the installed equipment incapable of meeting l Specification 3.11.3 or declared inoperable, restore ;
the equipment to OPERABLE status or provide for 1 contract capability to process wastes as necessary to satisfy all applicable transportation and disposal j requirements. BASES i 3/4.11.3 SOLID RADIOACTIVE WASTES ' (' This specification implements the requirements of 10 CFR 50.36a ' 1 Cnd General Design Criterion 60 of Appendix A to 10 CFR Part 50. The process parameters included in establishing the Process 1 Control Program may include, but are not limited to waste type, waste pH, waste / liquid / SOLIDIFICATION agent / catalyst ratios, l waste oil content, waste principal chemical constituents, and 1
-mixing and curing times. '
l l l 1 O M-8 Rev. 8 i
O & i
/ l DUKE POWER COMPANY
'd PCP REVISION APPROVAL L Revised PCP Section:
Corporate PCP, Rev ONS PCP, Rev MNS PCP, Rev 8 CNS PCP, Rev This revision has been reviewed against Technical Specifications and applicable NRC guidance documents and found to be acceptable. PREPARED BY: 0. E. Ekechukwu Nuclear Production Engineer TITLE: ; DATE: I ~d /4-l f 59 General Office Review Station Review i BY: W b, b t BY: Ma M[p[ h TITLE: Mtu et.chtv0LulvAvImgucog,. TITLE: /d@ M v gm4w DATE: /2/41f$9 DATE: A2/6~/M This revision is approved for use at McGuire Nuclear Station. l l _ f d'L/A ,/ A & K W
/\TechnicalSystemManager McGuire Tetfini~ cal Services '
Superintendent DATE: /2/4 '. DATE: /4 - J~- P f { l n
/ / l fl(
$tation Mana%r / l DATE: /2 1
- , ,9 1 1
l
L .. e DUKE POWER COMPANY L 7)s (~ . MCGUIRE NUCLEAR STATION PROCESS CONTROL PROGRAM 1.0 PURPOSE The purpose of the McGuire Nuclear Station Process Control Program is to insure all requirements of the DPC Corporate Process control Program have been met for each container of solidified or dewatered radioactive waste shipped-for burial at a licenned burial facility. The PCP is applicable only to the solifification or dewatering of liquid or wet solid radioactive waste. 2.0 COMPOSITION 2.1 The McGuire Nuclear Station PROCESS CONTROL PROGRAM shall consist of: 2.1.1 The Duke Power Company Process Control Manual Introduction (Section 1). 2.1.2 The Duke Power Company Corporate Process Control Program. (m) v 2.1. 3 - A list of all station-specific procedures that implement the requirements of the Corporate Process Control Program. 2.1.4 McGuire Nuclear Station diagrams or drawings or drawing numbers showing all connections between*gNS radwaste systems and solidi-fications and dewatering equipment. 2.1.5 Documentation of NRC approval of the initial McGuire Nuclear Station Process Control Program. 2.1.6 Documentation of Technical System Manager Nuclear Chemistry, MNS Technical Services Superintendent and MNS Station Manager approval of the changes to the Corporate Process Control Program. 2.1.7 Documentation that all changes to the Corporate and/or CNS Process Control Program were sent to the NRC in the Semi-Annual Radioactive Effluent Report. M-1 Rev. 8 L _. .
V' , f-i ! 2.1.8 Relevant sections and subsections of () p .. s Process Control Program-related definitions , transferred from Section 1 of McGuire l Nuclear Station Technical Specifications. . 2.1.9 Relevant sections and subsections of Process Control Program-related limiting conditions for operation,-bases and surveillance ' requirements transferred from Sections 3/4 of the McGuire Nuclear Station Technical ' Sepcifications. 3.0 EXCEPTIONS 3.1 The McGuire Nuclear Station Process Control Program I takes the following exceptions with DPC Corporate Process Control Program: ; [ 3.1.1 For Corporate PCP Section 2.1.2, station ! review and station Technical Services ' Superint.endent approval are not required. Corporate review and approval of vendor ; solidification services are sufficient. ' t 3.1.2 For Corporate PCP Section 3.1.2, station : review and st?. tion Technical Services : f
^
s Superintendent approval are not required. ,
\ corporate review and approval of vendor l
-dewatering services are sufficient.
i
. r'
( M-2 Rev. 8
?
-' s DUKE POWER COMPANY
(_) PROCESS CONTROL PROGRAM ! SECTION 2.1.3 l IMPLEMENTING PROCEDURE ! CP/0/B/8300/20 "Radwaste Chemistry Procedure for Handling l of Laboratory Quantities of Spent Resin" l t CP/0/B/8600/ll "Radwaste Chemistry Procedure for Sampling Evaporator Concentrates and Resin (Isolock l Sampler)" l HP/0/B/1004/04 " Preparation and Shipment of Mechanical !
~
Radwaste Materials" HP/0/B/1004/09 " Preparation and Shipment of Processed Radwaste Materials" , i HP/0/B/1004/12 " Utilization of Polyethylene High Integrity i overpacks" t HP/0/B/1004/14 " Preparation and Shipment of Dewatered Resins" , r~T dt/ OP/0/B/6200/32 "Radwaste Procedure for the Nuclear Solid Waste (WS) Dicposal System Operation" OP/0/B/6200/37 "Radwaste Procedure for Contaminated Oil ! Storage Tank Operation" OP/0/B/6200/53 "Radwaste Chemistry Procedure for Transfer, Solidification and Preparation for Shipment" OP/0/B/6200/64 "Radwaste Chemistry Procedure for Iransfer, , Dewatering and Shipment of Dead Resin" l OP/0/B/6200/65 "Radwaste Chemistry Procedure for Transfer, Dewatering and Shipment of Powdex Resin" OP/0/B/6200/66 "Radwaste Chemistry Procedure for Dewatering and Shipment of Vendor Demineralizers and . Filters" OP/0/B/6200/67 " Process Control Program for CNSI-Acid Solidification" OP/0/B/6200/68 " Process Control Program for CNSI Cement solidification Units" () OP/0/B/6200/69 " Process Control Program for Cement / Oil Solidification" M-3 Rev. 8
- m.
( r. + ~
'N i i' ;i ,
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.r 4. - OP/0/3/6200/70 " Operating Procedure for the CNSI-Mobile
'(): _.
Solidification Unit for 55-gallon drums (MSU-Drum-C-3)" l I i i :- l
+ OP/0/B/6250/09- " Condensate Polishing Domineralizer
- Operation" .
x, OP/0/B/6200/77 " Babcock and.Wilcox Aquaset/Petroset
,,' solidification Process" r ., j i
;r.. -
'l ~
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MCGUIRE NUCLEAR STATION k~- PROCESS CONTROL PROGRAM SECTION 2.1.4 DRAWING-INDEX
~ Plant Interfaces: .MC-1100-01.02 MC-1423-19.32-02 MC-1566-1.0 MC-1566-1.1 MC-1566-2.0 MC-1566-3.0 MC-1590-1.3
.MC-1604-1.1
-1 All portable system interf aces are shown-on-diagrams in the applicable station procedure. ,p de sev ,h[
.gp -t< [ ,O,
'e '
1.' A , ag ', , . .n , ?
~
't c
h M-5 Rev. 8 1
1 L . . y i r , i < McGUIRE NUCLEAR STATION i 3s,)s PROCESS CONTROL PROGRAM l 1 SECTION 2.1.8 L DEFINITIONS j 1.0 DEFINITIONS The' defined terms of this section appear in capitalized type i and are applicable throughout this PROCESS CONTROL PROGRAM. i i Note: This section is transferred directly from pre-1989 , Technical Specifications per NRC Generic Letter GL 89-01. , OPERABLE - OPERABILITY 1.18 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing ! its specified function (s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support functions (s). ,
,PROCE_SS CONTROL PROGRAM yCP) le22 ihe PROCESS CONTROL PROGR\M shall contain the provisions to ascure that the SOLIDIFICATION of wet radioactive w;stes '
results in a waste form with properties that meet the require-Inents of 10 CFR part (1 and of low level radioactive war.te ; disposkl. sites. The PCP shall identify process parameteru influencing SOLIDIFICATION such as pH, oil content, H,0 ; content, solids content, ratio of solidification agent to waste and/or necessary additivites for each type of anticipated . waste, and the acceptable boundary conditions for the process ' parameters shall be identified for each waste type, based on laboratory scale and full scale testing or experience. The PCP shall also include an identification of conditions that must be
-satisfied, based on full scale testing, to assure that dewatering of bead resins, powdered resins, and filter sludges will result in volumes of free water, at the time of disposal, within the limits of 10CFR Part 61 and of low level radioactive waste disposal sites.
SOLIDIFICATION l.32 SOLIDIFICATION shall be the immobolization of wet radioactive wastes such as evaporator bottoms, spent resins, sludges, and reverse osmosis concentrates as a result of a p). (_ process of thoroughtly mixing the waste type with a SOLIDIFICATION agent (s) to form a free standing monolith with chemical and physical characteristics specified in the PROCESS CONTROL PROGRAM (PCP). M-6 Rev. 8
e-F , f~ l t a MCGUIRE NUCLEAR STATION I ' . (_), PROCESS CONTROL PROGRAM SECTION 2.1.9 i l L T.TMTTTNG FONDTTIONC FOR nDERATTOMS, i BASES AN_D_ SURVEILLANCE REQUIREMENTS, j RADI0 ACTIVE EFFLUENTS ! 3/4.11.3 SOLID RADIOACTIVE WASTES LIMITING CONDITION FOR OPERATION , .) 3.11.3 ~ Radioactive wastes shall be solidified or dewatered I in accordance with the PROCESS CONTROL PROGRAM to meet shipping ) and transportation requirements during transit, and disposal 1
- site requirements when received at the disposal site.
]
APPLICABILITY: At all times. ) ACTION:
- a. With SOLIDIFICATION or dewatering not meeting dis- ,
posal site and shipping and transportation i requirements, suspend shipment of the inadequately I processed wastes and correct the PROCESS CONTROL J PROGRAM, the procedures and/or the Solid Radwaste j L ('s System as necessary to prevent recurrence. Q
- b. W.4.th SOLIDIFICATION or dewatering not performed in accordance with the PROCESS CONTROL PROGRAM, test ;
the improperly processed waste in each contair.cr to , ensure that it meets burial ground end shipping requirements and take apptopt*iata administre.tive ' action to prvvent recurrence..
- c. The provisions of Specification 3.0.3 are not '
npplicable. SURVEILLANCE REQURIEMENTS 4.11.3 SOLIDIFICATION of at least one representative test specimen from at least every tenth batch of each type of wet radioactive wastes (e.g., filter sludges, spent resins, evaporator bottoms, boric acid solutions and sodium sulfate solutions) shall be verified in accordance with the PROCESS CONTROL PROGRAM:
- a. If any test specimen fails to verify SOLIDIFICATION, the SOLIDIFICATION, nf the batch under test shall be suspended until such time as additional test specimens can be obtained, alternative SOLIDI-3 FICATION parameters can be determined in accordance ,
(g-) . with the PROCESS CONTROL PROGRAM, and a subsequent test verifies SOLIDIFICATION. SOLIDIFICATION of the L batch may then be resumed using the alternative M-7 ,
..Rev.,.8 _ _
,.; l
~__yp cx SOLIDIFICATION parameters determined by the PROCESS l
-()
CONTROL PROGRAM; l b.. If the initial test specimen from a batch of waste : fails to verify SOLIDIFICATION. the PROCESS CONTROL PROGRAM shall provide for the collection and testing ; of representative test specimens from each con- ' secutive batch of the same type of wet waste until at , least three consecutive initial test specimens demonstrate SOLIDIFICATION. The PROCESS CONTROL " PROGRAM shall be modified as required, as provided in Specification 6.13, to assure Solidification of subsequent batches i of waste; and
- c. With the installed equipment incapable of meeting Specification 3.11.3 or declared inoperable, restore ;
the equipment to OPERABLE status or provide for contract capability to process wastes as necessary to satisfy.all applicable transportation and disposal . requirements. t i BASES 3/4.11.3 SOLID RADIOACTIVE WASTES i r'y This specification implements the requirements of-10 CFR 50.36a (/ and General Design Criterion 60 of Appendix A to'10 CFR Part 50. . The. process parameters included in establishing the Process ' Control Program may include, but are not limited to waste type, waste pH, waste / liquid / SOLIDIFICATION agent / catalyst ratios, waste oil content, waste principal chemical constituents, and ! mixing and curing times. t M-8 Rev. 8
C ,, ZT ' i 9 ( DUKE POWER COMPANY V) PCP REVISION APPROVAL - Revised PCP Section: - Corporate PCP, Rev ONS PCP, Rev MNS PCP, Rev 8 CNS PCP, Rev This revision has been reviewed against Technical Specifications and applicable NRC guidance documents and found to be acceptable. 1 PREPARED BY: 0. E. Ekechukwu Nuclear Production Engineer l TITLEt DATEt l))t-)l$Q General Office Review St.ation Review , BYs 'TlGUI S bhiib' :_- , Dit ANIO d'&&kl~ __, () TITLZ: 'j(Lu dyJ_wdiy fwgtmerap TITLE: gw.hkpAwier _dgd-/F9 DATE: /Q/'/ /31___ DATE: This revision is approved for use at licGuire Nuclear Station. jf<k/A./ k D.hM
' i
/ 5Sechnical System Manager McGuire Te'cfinFcal Services i Superintendent -
DATE: / 7, d DATE: /L - J - # '9 ( ( ( ; WuW)$$lhtntlf Y
$tation Mana%r /
DATE: /2!$, 7,9 0 V l l
4 vx DUKE POWER COMPANY U MCGUIRE NUCLEAR STATION PROCESS CONTROL PROGRAM 1.0 PURPOSE The purpose of the McGuire Nuclear Station Process Control Program is to insure all requirements of the DPC Corporate ' Process Control Program have been met for each container of solidified or dewatered radioactive waste shipped for burial at a licensed burial facility. The PCP is applicable only to the solifification or dewatering of liquid or wet solid radioactive waste. 2.0 COMPOSITION 2.1 The McGuire Nuclear Station PROCESS CONTROL PROGRAM shall consist of: 2.1.1 The Duke Power Company Process Control Manual Introduction (Section 1). 2.1.2 The Duke Power Company Corporate Process (~j Control Program.
\.m/ f 2.1.3 A list of all station-specific procedures :
that implement the requirements of the Corporato Process Control Program, i 2.1.4 McGuire Nuclear Station diagrams or drawings or drawing numbers showing all connections betweenM%S re.dwaste systems and solidi-fications and dewatering equipment. 2.1.5 Documentation of NRC approval of the initial McGuire Nuclear Station Process Control Program. 2.1.6 Documentation of Technical System Manager Nuclear Chemistry, MNS Technical Services Superintendent and MNS Station Manager approval of the changes to the Corporate Process Control Program. 2.1.7 Documentation that all changes to the Corporate and/or CNS Process Control Program were sent to the NRC in the Semi-Annual Radioactive Effluent Report. Ov M-1 Rev. 8
I " h
, -s 2.1.8 Relevant sections and subsections of
, (_) Process Control Program-related definitions i~ transferred from Section 1 Of McGuire Nuclear Station Technical Specifications. 2.1.9 Relevant sections and subsections of Process Control Program-related limiting conditions for operation, bases and surveillance requirements transferred from Sections 3/4 of the McGuire Nuclear Station Technical Sepcifications. L 3.0 EXCEPTIONS E 3.1 The McGuire Nuclear Station Process Control Program takes the following exceptions with DPC Corporate l Process Control Program: , 3.1.1 For Corporate PCP Section 2.1.2, station review and Station Technical Services Superin:endent approval are not required. Co:perat e ::eoiew snd approva.1 of vende,r solidiilc&tica services arc s%ificient. 1 3.1.2 For Corporate PCP Section 3.1.2 station revj ew and station Technical Services Superintendent. approval are not required.
'r-)s
% Corporate review and approval of vendor dewatering services are sufficient.
E fl As - l M-2 Rev. 8
1 ,>. { 9, i l DUKE POWER COMPANY 7) (_j PROCESS CONTROL PROGRAM 1 i SECTION 2.1.3 1 I!4PLEMENTING PROCEDURE CP/0/B/8300/20 "Radwaste Chemistry Procedure for Handling ' of Laboratory Quantities of Spent Resin" CP/0/B/8600/ll "Radwaste Chemistry Procedure for Sampling
- Evaporator Concentrates and Resin (Isolock Sampler)"
HP/0/B/1004/04 " Preparation and Shipment of Mechanical i Radwaste Materials" , HP/0/B/1004/09 " Preparation and Shipment of Processed - Radwaste Materials" HP/0/B/1004/12 " Utilization of Polyethylene High Integrity i overpacks" HP/0/B/1004/14 " Preparation and Shipment of Dewatered -y- Resins" 3 7 r; OP/0/B/6200/32 "Radwaste l>roceduro for the Nucleer Solid - Wasto (WS) Disposal System Operhtlon"- 4 OP/0/B/6200/37 "Radwaste Procedure for Contaminated Oil Storage Tank Operation" , OP/0/B/6200/53 "Radwaste Chemistry Procedure for Transfer, Solidification and Preparation for Shipment" OP/0/B/6200/64 "Radwaste Chemistry Procedure for Transfer, Dewatering and Shipment of Bead Resin" OP/0/B/6200/65 "Radwaste Chemistry Procedure for Transfer, Dewatering and Ehipment of Powdex Resin" OP/0/B/6200/66 "Radwaste Chemistry Procedure for Dewatering and Shipment of Vendor Demineralizers and Filters" , OP/0/B/6200/67 " Process Control Program for CNSI-Acid Solidification" OP/O/B/6200/68 " Process Control Program for CNSI Cement Solidification Units" (m_) OP/0/B/6200/69 " Process Control Program for Cement / Oil Solidification" M-3 Rev. 8
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Plant Interfaces MC-1100-01.02 : MC-1423-19.32-02 ' MC-1566-1.0 : MC-1566-1.1 p MC-1566-2.0 ; MC-1566-3.0 r MC-1590-1.3 MC-1604-1.1 *
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/ MCGUIRE NUCLEAR STATION < (_)s PROCESS CONTROL PROGRAM SECTION 2.1.8 DEFINITIONS ,
1.0 DEFINITIONS The defined terms of this section appear in capitalized type and are applicable throughout this PROCESS CONTROL PROGRAM. Note: This section is transferred directly from pre-1989 Technical Specifications per NRC Generic Letter GL 89-01. OPERABLE - OPERABILITY; 1.18 A system, subsystein, train, component or devica shall ha OPERABLE or have OP2XALILITY when it is capable of performing its specified function (s), and when all necessary attendant instrumentation, controlu, electrical power, cooling or snal water, lubrication er other auxiliary equipment.that are i required fer tihe ryttcM, snboystem, truin, component, or device to perform its functients) are also capable of performing their related supy'rt functione(s).
's- PROCESS CONTROL PROGRAM (PCP) 1.22 The PROCESS CONTROL PROGRAM shall contain the provisions to assure that the SOLIDIFICATION of wet radioactive wastes-results in a waste form with properties that meet the require- '
ments of 10 CFR part 61 and of low level radioactive waste- ' disposal sites. The PCP shall identify process parameters influencing SOLIDIFICATION such as pH, oil content, H 90 < content, solids content, ratio of solidification agent to waste and/or necessary additivites for each type of anticipated ; waste, and the acceptable boundary conditions for the process parameters shall be identified for each. waste type, based on l laboratory scale and full scale testing or experience. The PCP ' shall also include an identification of conditions that must be satisfied, based on full scale testing, to assure that dewatering of bead resins, powdered resins, and filter sludges will result in volumes of free water, at the time of disposal, within the limits of 10CFR Part 61 and of low level radioactive
- i. waste disposal sites.
1 SOLIDIFICATION 1.32 SOLIDIFICATION shall be the immobolization of wet radioactive wastes such as evaporator bottoms, spent resins, f~ sludges, and reverse osmosis concentrates as a result of a
=s '
process of thoroughtly mixing the waste type with a SOLIDIFICATION agent (s) to form a free standing monolith with chemical and physical characteristics specified in the PROCESS CONTROL PROGRAM (PCP). M-6 Rev. 8
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LTMTTTNG'CONDITTONS FOR'ODERATTONA, BASES AND SURVEILLANCE REQUIREMENTS ~
-RADIOACTIVE EFFLUENTS !
I 3/4.11.3 SOLID RADIOACTIVE WASTES L C LIMITING CONDITION FOR OPERATION 3.11.3 -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.- .
a APPLICABILITY: At all times. ACTION:. >
- a. With SOLIDIFICATION or dewatering not meeting dis-- .
l posal site and shipping and transportation requirements,Lsuspend. shipment of the inadequately , processed wastes and cc rect the PROCESS' CONTROL PROGRAM,.the procedu: .nd/or the Solid Padwaste System as necessary ?Jevent recurrence.
][
~b. With SOLIDIFICATION or dewatering not performed in accordance with the PROCESS CONTROL PROGRAM, test the improperly processed waste in each container to censure that it meets burial ground and shipping requirements and:take appropriate administrative action-to prevent recurrence.
~
c.- The provisions of Specification-3.0.3 are not' applicable.
< SURVEILLANCE REQURIEMENTS 4.11.3 SOLIDIFICATION of.at least one representative test specimen from at least every tenth batch of each type of wet radioactive wastes /(e.g., filter sludges, spent resins, evaporator bottoms, boric acid solutions and sodium sulfate solutions) shall be verified in accordance with the PROCESS -'
CONTROL PROGRAM:
- a. If any test specimen fails to verify SOLIDIFICATION, the: SOLIDIFICATION, of the batch under test shall be' suspended until such time as additional test specimens can be obtained, alternative SOLIDI-
,/<1 FICATION parameters can be determined in accordance 3 : with the PROCESS CONTROL PROGRAM, and a subsequent test verifies SOLIDIFICATION. SOLIDIFICATION of the batch may then be resumed using the alternative t
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, s-F' r . _.h L rw SOLIDIFICATION parameters determined by the PROCESS h i_,b . CONTROL PROGRAM; L b. If the initial test specimen from a batch ofiwaste g- = fails to-verify SOLIDIFICATION, the PROCESS CONTROL P . PROGRAM shall provide for.the collection and-testing of representative test specimens from each con-E secutive batch of the'same type'of wet waste until at least-three consecutive initial test specimens
' demonstrate 1 SOLIDIFICATION. The PROCESS CONTROL PROGRAM shall be modified as required, as provided-in-Specification 6.13, to assure solidification of subsequent batches of wastes:and
- c. With the installed equipment incapable of meeting Specification 3.11.3 or declared inoperable, restore the equipment to OPERABLE status or provide for ,
j e contract' capability to process wastes as necessary to satisfy.all applicable transportation and disposal i
. requirements. ,
-BASES !
~
3/4.11.3 SOLID RADIOACTIVE WASTES y^% This specification implements the requirements.of 10 CFR 50.36a (-) and, General Design Criterion 60 of Appendix A to 10 CFR Part 50. l The' process parameters included in establishing the Process Control Program may include, but are not limited to waste type, L waste pH, waste / liquid / SOLIDIFICATION agent / catalyst ratios, waste oil content, waste principal chemical constituents, and d l mixing and curing times. 1; i L !
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- /7 DUKE POWER COMPANY 2
PCP REVISION APPROVAL , Revised.PCP Section: :
-Corporate PCP, Rev ONS PCP, Rev i
MNS PCP, Rev 8 CNS PCP, Rev This revision has been reviewed against Technical Specifications , and applicable NRC guidance documents and found to be acceptable. ' PREPARED BY:. O. E. Ekechukwu Nuclear Production Engineer TITLE: DATE: /2/l-!f$C1 e a r General Office Review Station Review BY: - OM/ b . 4)27 t-- BY: M I[M[ (( TITLE: Mtu c hhb fmgtweop TITLE: /I' red /g/ <L viox DATE: /2 /4/ f SC) DATE: A#/S/89 i This revision is approved for use at ficGuire Nuclear Station. t
. f Sechnical System Manager 8.CbL/AA k k.AA FicGui re . Te'cfinical Services Superintendent DATE: /Z- d DATE: /L - J : .P f
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MCGUIRE NUCLEAR STATION PROCESS CONTROL PROGRAM
'l.0 PURPOSE The purpose of the McGuire Nuclear Station Process Control Program is to insure all requirements of the DPC Corporate '
Process Control Program have been met for each container of
- solidified or dewatered radioactive waste shipped for burial at a licensed burial facility. The PCP is applicable only
- to the solifification or dewatering of liquid or wet-solid ,
radioactive waste. 2.0 COMPOSITION 2.1 The McGuire Nuclear Station PROCESS CONTROL PROGRAM , shall consist of: 2.1.1 The Duke Power Company Process Control Manual ' Introduction (Section 1). 2.1.2 The Duke Power Company Corporate Process
=
Control Program. . 2.1.3 A list of all station-specific procedures that implement the requirements of the i n Corporate Process Control Program. 2.1.4 McGuire Nuclear Station diagrams or drawings or drawing numbers showing all connections betweenM $S radwaste systems and solidi-fications and dewatering equipment. 2.1.5 Documentation of NRC approval of-the initial McGuire Nuclear Station Process Control [ Program. 2.1.6 Documentation of Technical System Manager Nuclear Chemistry, MNS Technical Services
~
Superintendent and MNS Station Manager' approval of the changes to the Corporate Process Control Program. ! 2.1.7 Documentation that all changes to the Corporate and/or CNS Process Control Program were sent to the NRC in the Semi-Annual Radioactive Effluent Report.
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s i i V^) . 2.1.8 Relevant sections and subsections of
- \,,/'
Process Control Program-related definitions transferred from Section 1 of McGuire
. Nuclear Station Technical Specifications.
- 2 .1 ~. 9 Relevant' sections and subsections of1 Process
' Control Program-related. limiting conditions' for operation, bases and surveillance requirements transferred from sections 3/4 of the McGuire Nuclear Station Technical Sepcifications.
3.0 EXCEPTIONS 3.1 ~The McGuire Nuclear Station Process Control Program takes the following exceptions with DPC Corporate Process Control Program: 3.1.1 For Corporate PCP Section 2.1.2, station-review and station Technical Services Superintendent approval are not required.
. Corporate review and approval of vendor solidification services are sufficient.
i 3.1.2 For Corporate PCP Section 3.1.2, station review and station Techntcal Services Superintendent approval are'not required. r'} bv- Corporate review and approval of vendor dewatering services are sufficient.
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of Laboratory Quantities of Spent ~ Resin" CP/0/B/8600/11 "Radwaste Chemistry Procedure for-Sampling Evaporator Concentrates and Resin (Isolock . Sampler)" HP/0/B/1004/04 " Preparation and Shipment of Mechanical-Radwaste Materials" HP/0/B/1004/09 " Preparation and Shipment of Processed Radwaste Materials" HP/0/B/1004/12 " Utilization of Polyethylene High Integrity overpacks" HP/0/B/1004/14 " Preparation and Shipment of Dewatered Reains"
/"_)N OP/0/B/6200/32
( "Radwaste Procedure for the Nuclear-Solid Waste (WS) Disposal System Operation" OP/0/B/6200/37. "Radwaste Procedure for Contaminated Oil Storage Tank Operation" ; OP/0/B/6200/53 "Radwaste Chemistry Procedure for Transfer, Solidification and Preparation for Shipment" OP/0/B/6200/64 "Radwaste Chemistry Procedure for Transfer, Dewatering and Shipment of Bead Resin"
^
OP/0/B/6200/65 "Radwaste Chemistry Procedure for Transfer, , Dewatering and Shipment of Powdex Resin" OP/0/B/6200/66 "Radwaste Chemistry Procedure for Dewatering and Shipment of Vendor Demineralizers and l Filters" OP/0/B/6200/67 " Process Control Program for CNSI-Acid Solidification" OP/0/B/6200/68 " Process Control Program for CNSI Cement Soliditication Units"
.(') OP/0/B/6200/69 " Process Control Program for Cement / Oil Solidification" M-3 Rev. 8
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-All portable system interfaces are shown-on-diagrams in the i applicable station procedure, yp d cscv . E'O _
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, SECTION 2.1.8 DEFINITIONS ,
1.0 DEFINITIONS ) 1
.The defined terms of this section appear in capitalized type .1 and are applicable throughout this PROCESS CONTROL PROGRAM.
Note: This section is transferred directly from-pre-1989 Technical Specifications per NRC Generic Letter GL 89-01. ., OPERABLE - OPERABILITY -
- 1.18 A system, subsystem, train, component or device shall be '
OPERABLE or have OPERABILITY when it is capable of performing its :specified' function (s) , and when all necessary attendant
-instrumentation, controls, electrical power, cooling or seal water,-lubrication or other auxiliary equipment that are required for the system,. subsystem, train, component, or device to perform its function (s) are also capable of performing their s related support functions (s).
A U ' PROCESS CONTROL' PROGRAM (PC,P_1
.l.22.The PROCESS CONTROL PROGRAM shall contain the provisions
~
L .to assure that the SOLIDIFICATION.of wet radioactive wastes results in a waste form with properties thit meet the require-
~ments of 10 CFR part 61 and..of low level 7.adioactive waste disposal sites. The PCP shall identify process parameters influencing. SOLIDIFICATION such as pH, oil content, H9 0 content,; solids content, ratio of solidification agent to waste L and/or necessary additivites for each type of anticipated l waste,-and the acceptable boundary conditions for the process parameters shall be identified for each waste type, based on L laboratory scale and full scale testing or experience. The PCP shall also include an identification of conditions that must be y satisfied, based on full scale testing, to assure that l = dewatering of bead resins, powdered resins,,and filter sludges y
.will result in volumes of free water, at the time of disposal, within-the limits of 10CFR Part 61 and of low level radioactive waste disposal sites.
SOLIDIFICATION , ~1.32 SOLIDIFICATION shall be the immobolization of wet B radioactive wastes such as evaporator bottoms, spent resins, L sludges, and reverse osmosis concentrates as a result of a L :(j-)z process'of thoroughtly mixing the waste type with a , I- SOLIDIFICATION agent (s) to form a free standing monolith with L chemical and physical characteristics specified in the PROCESS L CONTROL PROGRAM'(PCP). 4 L L M-6 Rev. 8
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' ^f() PROCESS CONTROL PROGRAM f SECTION 2.1.9 3
.LTMTTING CONDTTTONS TOR OPEPATTONS,
; BASES _AND SURVEILLANCE REQUIREMENTS RADIOACTIVE EFFLUENTS 3/4.11.3 SOLID RADIOACTIVE WASTES '
LIMITING CONDITION FOR~ OPERATION 3.11.3 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. APPLICABILITY: At all times. ACTION:
- a. With SOLIDIFICATION or dewatering not meeting dis-posal site and shipping and transportation requirements, suspend. shipment of the inadequately processed wastes and correct the-PROCESS CONTROL PROGRAM, the procedures and/or the Solid Radwaste r' System as necessary to prevent recurrence, k.)Y -
- b. 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 I
requirements and'take appropriate-administrative action to prevent recurrence.
- c. The' provisions of Specification 3.0.3 are not applicable.
L . SURVEILLANCE REQURIEMENTS l i 4.11.3 SOLIDIFICATION of at least one representative test l specimen from at least every tenth batch of each type of wet P < radioactive wastes (e.g., filter sludges, spent resins, L evaporator bottoms, boric acid solutions and sodium sulfate-solutions) shall be verified in accordance-with the PROCESS CONTROL PROGRAM:
- a. If any test specimen fails to verify SOLIDIFICATION,
_ t}ua SOLTDIFICATION, of the batch under test shall
-be suspended until such time as additional test l specimens can be obtained, alternative SOLIDI-FICATION parameters can be determined in accordance
() with the PROCESS CONTROL PROGRAM, and a subsequent test verifies SOLIDIFICATION. SOLIDIFICATION of the batch may then be resumed using the alternative 1 3 l-
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l*Y _ l r~y SOLIDIFICATION parameters-determined by the PROCESS i U CONTROL PROGRAM; () l
- b. Ithe f initial test specimen from a batch of waste fails to verify SOLIDIFICATION,.the PROCESS CONTROL
' ' PROGRAM shall provide for the collection and; testing of-representative-test specimens from each con-secutive' batch of the same type of wet waste until at.
.least three consecutive initial test specimens demonstrate SOLIDIFICATION. The PROCESS CONTROL
-PROGRAM shall be modified as required, as provided_in Specification 6.13, to assure solidification of subsequent batches of waste; and c.- With the installed equipment incapable of meeting Specification 3.11.3 or declared inoperable, restore the equipment to OPERABLE-status or provide for contract capability to process wastes as necessary to satisfy all. applicable transportation and disposal requirements.
, BASES 3/4.11.3-SOLID RADIOACTIVE WASTES
" em,
.This specification implements the requirements of 10 CFR 50.36a
, T) s -and General. Design Criterion 60 of Appendix A to 10 CFR Part 50.
-The process parameters included in establishing the Process Control Program may include, but are not limited to waste type, waste pH, waste / liquid / SOLIDIFICATION. agent / catalyst ratios,-
waste oil content, waste. principal chemical constituents, and mixing'and' curing times. t M-8 Rev 8
30 + x.: a .y (
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J DUKE POWER COMPANY PCP REVISION APPROVAL v
- Revised PCP Sections.
L Corporate PCP, Rev ONS PCP, Rev MNS PCP, Rev 8 b CNS PCP, Rev
~ ThisLrevision has been reviewed against Technical Specifications and applicable NRC guidance documents and found to be acceptable.
PREPARED BY: 0. E. Ekechukwu Nuclear Production Engineer TITLE: DATE: f
/ 2 /t-l f SC General Office Review Station Review I BY: 0.U/ b , h 6- BY: M M[y[
TITLE: b c hyduv fetcowepy TITLE: /2# m Jrku Q w vior DATE: /2 /4/
~ DATE: /J/6~/F7
' This= revision is approved for use at licGuire Nuclear Station, i
/ 2.CdL6LA k & J A
- /_\TechnicalSystemManager NicGuire Te'cfinical Services Superintendent DATE: /E 4
( DATE: ./ A - J ,P 7 ( l
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DATE: /2 89
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f DUKE POWER COMPANY U . MCGUIRE NUCLEAR STATION PROCESS CONTROL PROGRAM , 1.0 PURPOSE The_ purpose of the McGuire Nuclear Station Process Control Program is to insure all requirements of the DPC Corporate Process Control Program have been met for each container of solidified or dewatered radioactive waste shipped for burial at a licensed burial facility. The PCP is applicable only to the solifification or dewatering of liquid or wet solid radioactive waste. . 2.0 COMPOSITION 2.1 The McGuire Nuclear Station PROCESS CONTROL PROGRAM shall consist of: 2.1.1 The Duke Power Company Process Control Manual Introduction (Section 1). 2.1.2 The Duke Power Company Corporate Process Control Program. 2.1.3 A list of all station-specific procedures that implement the requirements of the Corporate Process Control Program. 2.1.4 McGuire Nuclear Station diagrams or drawings or drawing numbers showing all connections between CNS radwaste systems and solidi-fications and dewatering equipment. 2.1.5 Documentation of NRC approval of the in :ial McGuire Nuclear Station Process Control Program. 2.1.6 Documentation of Technical System Manager Nuclear Chemistry, MNS Technical Services Superintendent and MNS Station Manager approval of the changes to the Corporate Process Control Program. 2.1.7 Documentation that all changes to the Corporate and/or CNS Process Control Program were sent to the NRC in the Semi-Annual Radioactive Effluent Report. l /~T ,. V M-1 Rev 8
._ ~
7-( 2.1.8 Relevant sections and subsections of ' jsJc
Process Control Program-related definitions transferred'from section 1 of McGuire Nuclear Station Technical Specifications. :,
2.1.9 Relevant sections and subsections of Process Control Program-related limiting conditions a for operation, bases and surveillance f requirements transferred from sections 3/4 of the McGuire Nuclear Station Technical Sepcifications. 3.0 EXCEPTIONS 3 .1 - The McGuire Nuclear Station Process Control Program takes the following exceptions with DPC Corporate Process Control Programs t 3.1.1 For Corporate PCP Section 2.1.2, station review and station Technical Services Superintendent approval are not required. Corporate review and approval of vendor solidification services are sufficient. 3.1.2 For Corporate PCP Section 3.1.2, station review and station Technical Services a (~' Superintendent approval are not required. ,, Corporate review and approval of vendor dewatering services are sufficient. l I p d. M-2 Rev. 8 l
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~ DUKE POWER COMPANY h PROCESS CONTROL PROGRAM SECTION 2.1'.3
. IMPLEMENTING PROCEDURE CP/0/B/8300/20 "Radwaste Chemistry Procedure for Handling ,
of Laboratory Quantities of Spent Resin" CP/0/B/8600/ll "Radwaste Chemistry Procedure for Sampling ' Evaporator Concentrates-and Resin (Isolock Sampler)" o l .
.~HP/0/B/1004/04 " Preparation and Shipment of Mechanical Radwaste Materials" HP/0/B/1004/09 " Preparation and Shipment of Processed ,
Radwaste Materials" . HP/0/B/1004/12 " Utilization of Polyethylene High Integrity overpacks" HP/O/B/1004/14 " Preparation and Shipment of Dewatered Resins" OP/0/B/6200/32 "Radwaste Procedure for the Nuclear Solid Waste (WS) Disposal System Operation" OP/0/B/6200/37 "Radwaste Procedure for Contaminated Oil Storage Tank Operation" OP/0/B/6200/53 "Radwaste Chemistry Procedure for Transfer, Solidification and Preparation for Shipment" OP/O/B/6200/64 "Radwaste Chemistry Procedure for Transfer, U Dewatering and Shipment of Bead Resin" OP/0/B/6200/65 "Radwaste Chemistry Procedure'for Transfer, Dewatering and Shipment of'Powdex Resin" OP/0/B/6200/66 "Radwaste Chemistry Procedure for Dewatering and Shipment of Vendor Demineralizers and Filters" OP/0/B/6200/67 " Process Control Program for CNSI-Acid Solidification"
-OP/0/B/6200/68 " Process Control Program for CNSI Cement Solidification Units" h I )-OP/0/B/6200/69 " Process Control Program for Cement / Oil L Solidification" l
M-3 Rev. 8 1.
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-Solidification Process" 2
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X_/ . PROCESS CONTROL PROGRAM r SECTION-2.1.4 DRAWING INDEX
- Plant Interfaces - .MC-1100-01.02 -
MC-1423-19.32-02 ' MC-1566-1.0 ' MC-1566-1.1 MC-1566-2.0 MC-1566-3.0 MC-1590-1.3 k MC-1604-1.1 All portable system interfaces are shown on diagrams in the I applicable station procedure. O L s O M-5 Rev. 8
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I fy .McGUIRE-NUCLEAR STATION
-Q PROCESS CONTROL PROGRAM i
i SECTION'2.1.8 I DEFINITIONS 1 1.0l DEFINITIONS The defined terms of-this section appear in capitalized type
'and are cpplicable throughout this PROCESS CONTROL PROGRAM.
Note: This section is transferred directly from pre-1989 Technical Specifications per NRC Generic Letter GL 89-01. _l OPERABLE - OPERABILITY l 1.18~A system, subsystem, train, component or-device shall be j l OPERABLE-or have OPERABILITY when it is-capable of performing Lits specified function (s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal ' i water, lubrication or other-auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its. function (s).are also capable of performing their related support functions (s). PROCESS CONTROL PROGRAM (PCP) l 1.22 The' PROCESS CONTROL PROGRAM shall contain the provisions to assure'that the SOLIDIFICATION of wet radioactive wastes
-results'in a wasteiform with properties'that meet the require-ments of'10 CFR part.61 and of, low-level radioactive waste 1 disposal sites. -The PCP shall identify process parameters !
influencing SOLIDIFICATION such as pH, oil content, H 0
. content, solids content,' ratio of solidification agent3 to waste o 1
l and/or necessary additivites for each typeLof anticipated ' waste, and'the acceptable boundary conditions forLthe process H . parameters shall be identified for each' waste type, based on i laboratory-scale and full scale testing or experience. The PCP H chall also include an identification of conditions that must be l t icatisfied,-based on full scale testing, to assure that ' dewatering'of bead resins, powdered resins, and filter sludges will result in volumes of free water, at the time of disposal, within the limits of 10CFR Part 61 and of low level radioactive waste disposal sites. [ SOLIDIFICATION 1.32' SOLIDIFICATION shall be the immobolization of wet radioactive wastes such as evaporator bottoms, spent resins, 7 $ aludges, and reverse osmosis concentrates as a result of a l g_/ process of thoroughtly mixing the waste type with a l SOLIDIFICATION agent (s) to form a free standing monolith with chemical and physical characteristics specified in the PROCESS
- r. ' CONTROL PROGRAM (PCP).
L K M-6 Rev. 8
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W MCGUIRE NUCLEAR STATION Q PROCESS CONTROL PROGRAM' '
,. SECTION 2.1.9:
LIMITING CONDITIONS FOR OPERATIONS.
- BASES AND SURVEILLANCE REQUIREMEN"S
, RADIOACTIVE EFFLUENTS 3
3/4.11.3 SOLID RADIOACTIVE WASTES LIMITING CONDYTION-FOR OPERATION _ t 3.11.3- ~ Radioactive wastes shall be; solidified or dewatered i in accordance with the PROCESS CONTROL PROGRAM to meet. shipping and transportation requirements during transit, and disposal I site' requirements when received at the disposal site. APPLICABILITY: At all times. 4
. ACTION.
'a. With SOLIDIFICATION or dewatering not meeting dis-posal site and shipping and transportation l requirements, suspend shipment of the inadequately I processed wastes and correct the PROCESS CONTROL l PROGRAM, the-procedures and/or the Solid'Radwaste System as necessary.to prevent recurrence.
L .b. 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 L ' requirements and take appropriate administrative action to prevent recurrence..
- c. The provisions of Specification 3.0.3 are not applicable. ,
SURVEILLANCE REQURIEMENTS L 4.11.3 SOLIDIFICATION of at least one representative test E specimen ~from at least every tenth batch of each type of wet ! radioactive wastes (e.g., filter sludges, spent resins, evaporator bottoms, boric acid solutions and sodium-sulfate E solutions) shall be verified in accordance with the PROCESS i CONTROL PROGRAM: a .' If any test specimen fails to verify SOLIDIFICATION, t the SOLIDIFICATION, of the batch under test shall be suspended until such time as additional test specimens can be obtained, alternative SOLIDI-FICATION parameters can be determined in accordance
.O with the PROCESS CONTRot PROGRAa, and a subsequent test verifies SOLIDIFICATION. SOLIDIFICATION of the batch may then be resumed using the alternative L
l l W-9 - . sca . e.
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- 6 SOLIDIFICATION parameters determined by the PROCESS
... V CONTROL PROGRAM; b.
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If the initial test specimen from a batch of waste fails ~to verify SOLIDIFICATION, the PROCESS CONTROL PROGRAM shall provide for the' collection and testing '} of representative test specimens from each con-secutive batch of the same type of wet waste until at least three consecutive initial test specimens. i demonstrate SOLIDIFICATION. The PROCESS CONTROL _ PROGRAM shall:be modified as required, as provided in r Specification 6.13, to-assure Solidification of _ subsequent batches-of-waste; and ;
- c. With the installed equipment incapable of meeting Specification 3.11.3 or declared inoperable, restore the equipment to OPERABLE status or provide for' contract capability to process wastes as necessary to satisfy all applicable transportation and disposal requirements.
BASES 3/4.11.3 SOLID RADIOACTIVE WASTES A This specification implements the requirements of 10 CFR 50.36a l
- V &nd General: Design Criterion 60~of Appendix A to 10 CFR Part-50.
The process parameters included in establishing the Process Control Program may include, but are not limited to waste type, waste'pH, waste / liquid / SOLIDIFICATION agent / catalyst ratios, zwaste oil content, waste principal chemical constituents,.and
- mixing-and curing times.
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3I s, t (3 - DUKE POWER COMPANY PCP REVISION APPROVAL Revised.PCP Section: Corporate PCP, Rev , 1 ONS PCP, Rev MNS PCP, Rev 8 CNS PCP, Rev This revision has been reviewed against Technical Specifications and applicable NRC guidance documents and found to be acceptable.
. PREPARED BY: 0. E. Ekechukwu Nuclear Production Engineer TITLE:
DATE:. I d lLI 5'l
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General Office Review Station Review BY: OM/ b , b t BY: AM M[p[ TITLE: YL c M4vhl2 A> Imgrwco g- TITLE: /Imj7kv <Dmdo# [ .; DATE: /d Alf$9 DATE: /J /6~/ M This revision is approved for use at McGuire Nuclear Station. 8.Ch.HJ k & M
- / \ Technical System Manager McGuire TetfinTcal Services Superintendent DATE: /2 4 DATE: /L - J- ,P f
( t WiW)W!bWalclf$tation Manapr / Y DATE: /2!f 9
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a . , a + y DUKE POWER COMPANY
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MCGUIRE NUCLEAR STATION PROCESS CONTROL PROGRAM 1.O PURPOSE , The purpose of the McGuire Nuclear Station Process Control Program is to insure all requirements of the DPC Corporate Process-Control-Program have been met for each container of solidified or dewatered' radioactive waste shipped for burial at'a licensed burial facility. The PCP is applicable only ' to the solifification or dewatering of liquid.or wet solid radioactive waste. . 2.0 COMPOSITION
,2 .1 The McGuire Nuclear Station PROCESS CONTROL PROGRAM shall consist of:
2.1.1 The-Duke Power Company Process Control Manual - Introduction (Section 1). 2.1.2 The Duke Power Company Corporate Process Control Program. [} 2.1.3 Alistofallstation-specilicprocedures
.that implement the requirements of the Corporate Process Control Program.- ,
l 2.1.4 McGuire Nuclear Station diagrams or drawings or drawing numbers showing all connections between CNS'radwaste systems and solidi-fications and dewatering equipment. 2.1.5 Documentation of NRC approval'of the initial l McGuire Nuclear Station Process Control Program. 2.1.6 Documentation of Technical System Manager Nuclear Chemistry, MNS Technical Services Superintendent and MNS Station Manager ~ approval of the changes to the Corporate Process Control Program. l ' 2.1.7 Documentation that all changes to the Corporate and/or CNS Process Control Program were sent to the NRC in the Semi-Annual Radioactive Effluent Report. . ()' l l M-1 Rev. 8 __- __ _ ___9 --__ _ _ __
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5 7'y 2.1. 8- Relevant sections and' subsections of (>E -Process Control Program-related definitions transferred from Section 1 of McGuire a Nuclear Station Technical Specifications. I 2.1.9. Relevant sections and subsections of Process control Program-related limiting conditions for operation, bases and surveillance requirements transferred from Sections 3/4 of the McGuire Nuclear Station Technical l Sepcifications. i 3.0 EXCEPTIONS t 3.1 The McGuire Nuclear Station Process-Control Program takes the following exceptions with DPC Corporate
' Process Control Programs l 3.1.1 For Corporate PCP Section 2.1.2, station review and station Technical Services Superintendent approval are-not required.
Corporate review and approval of vendor solidification services are sufficient. 3.1.2 For Corporate PCP Section 3.1.2, station l review and station Technical Services Superintendent approval are not required.
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Corporate review and approval of vendor j dewatering services are-sufficient, i 1 l
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_ PROCESS CONTROL PROGRAM SECTION 2.1.3 l IMPLEMENTING PROCEDURE l CP/0/B/8300/20- "Radwaste Chemistry Procedure for Handling of Laboratory Quantities of' Spent Resin" CP/0/B/8600/ll. "Radwaste. Chemistry Procedure for Sampling Evaporator Concentrates and Resin (Isolock Sampler)" HP/0/B/1004/04 " Preparation and Shipment of Mechanical Radwaste Materials" HP/0/B/1004/09 " Preparation and Shipment of Processed '
,Radwaste Materials" HP/0/B/1004/12 " Utilization _of Polyethylene High' Integrity overpacks" HP/0/B/1004/14'
" Preparation and Shipment of Dewatered Resins" OP/0/B/6200/32 "Radwaste Procedure for the, Nuclear Solid Waste (WS) Disposal System Operation" OP/0/B/6200/37 "Radwaste Procedure for Contaminated Oil Storage Tank Operation" OP/0/B/6200/53_
Radwaste Chemistry Procedure for Transfer, Solidification and Preparation for Shipment" OP/0/B/6200/64 ~"Radwaste Chemistry Procedure for Transfer, Dewatering and Shipment of Bead Resin" OP/0/B/6200/65 "Radwaste Chemistry Procedure for Transfer, Dewatering and Shipment ~of Powdex Resin"
'OP/0/B/6200/66 "Radwaste Chemistry Procedure for Dewatering and shipment of Vendor Demineralizers and ,
Filters" OP/0/B/6200/67 " Process Control Program for CNSI-Acid Solidification" OP/0/B/6200/68 " Process Control Program for CNSI Cement Solidification Units"
'k)'OP/0/B/6200/69 " Process Control Program for Cement / Oil Solidification" M-3 Rev. 8
.:t . .
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-gOP/0/B/6200/70-- " Operating Procedure for the CNSI Mobile:-
3 Solidification Unit for 55-gallon drums (MSU-Drum-C-3)"
-OP/0/B/6250/091
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" Condensate Polishing Demineralizer-
', Operation" s
OP/0/B/6200/7.7 " Babcock and Wilcox Aquaset/Petroset Solidification Process" 9 M-4 Rev. 8
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= MCGUIRE NUCLEAR STATION !
i L PROCESS CONTROL PROGRAM ' SECTION 2.1.4 e DRAWING INDEX Plant Interfaces:. MC-1100-01.02 I MC-1423-19.32-02 '
- MC-1566-1.0 MC-1566-1,1-MC-1566-2.0 'i MC-1566-3.0 i MC-1590-1,3 MC-1604-1.1 ,
All portable system interfaces are shown on diagrams in the '
. applicable station procedure.
t i LO . O M-5 Rev. 8
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v.. 1 t 9 r: .; McGUIRE NUCLEAR STATION PROCESS CONTROL PROGRAM , SECTION 2.1.8 DEFINITIONS d 1.0 DEFINITIONS
- The defined terms-of this section appear in capitalized type and are applicable.throughout this PROCESS CONTROL PROGRAM.-
Notes This section is transferred directly from pre-1989
' Technical Specifications per-NRC Generic Letter GL 89-01.
~ OPERABLE - OPERABILITY
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u 4:
'l.18 A system, subsystem, train, component or device shall be
--OPERABLE or have OPERABILITY when_it is capable of performing its specified function (s),~and when all necessary attendant' '
instrumentation, controls, electrical power, cooling or seal water, lubrication-or other auxiliary equipment that are t i required for the system,1 subsystem, train, component, or device. I 'to perform its function (s) are also capable of performing their-L. .related support functions (s). ' PROCESS CONTROL PROGRAM (PCP) E. , . . f .l.22 The< PROCESS CONTROL PROGRAM shall contain-.the provisions
-to' assure that the SOLIDIFICATION of wet radioactive wastes
.results in a-waste, form with properties that meet the require- '
ments of 10 C110 part.61 and of low level radioactive waste disposal sites. .The PCP.shall identify process parameters influencing SOLIDIFICATION such as pH, oil content, H,0 ' content, solids content,' ratio of solidification' agent to waste
>cnd/or necessary additivites for each type ofLanticipated '
waste,'and the' acceptable boundary conditions for the process parameters shalltbe identified for each waste type, based on j L - laboratory scale and' full scale testing or' experience. The PCP ! chall also-include an identification of conditions that must be ; catisfied', based on full scale testing, to assure that E dewatering of bead resins,-powdered resins, and filter sludges - L
- will result in volumes of free water, at the-time of disposal,
' within theilimits1of 10CFR Part 61 and of low level radioactive waste disposal sites.
1
. SOLIDIFICATION 1.32 SOLIDIFICATION shall be the immobolization of wet i radioactive wastes such as evaporator bottoms, spent resins, i t
l r sludges, and reverse osmosis concentrates as a result of a t-i ' process of thoroughtly mixing the waste type with a SOLIDIFICATION agent (s) to form a free standing monolith with L chemical ~and' physical characteristics specified in the PROCESS , CONTROL PROGRAM (PCP). } M-6 Rev. 8
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MCGUIRE NUCLEAR STATION dd PROCESS: CONTROL PROGRAM.. l SECTION:2.1.9 LIMITING CONDIT::ONS FOR OPERATIONS, BJSES AND SURVE::LLANCE REQUIREMENTS
' RADIOACTIVE-EFFLUENTS-3/4.11.3 SOLID RADIOACTIVE WASTES
. LIMITING CONDITION FOR OPERATION 3.11.3 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.
-APPLICABILITY: At all times'. 3 ACTION: -
- a. 'With SOLIDIFICATION or dewatering not meeting dis-posal site and shipping and transportation requirements,-suspend 1 shipment of the inadequately
. processed wastes and-correct the PROCESS CONTROL
' PROGRAM, the procedures >and/or the. Solid Radwaste
.1~l 1
System as necessary to prevent recurrence.
- v. H
.b. With SOLIDIFICATION or dewatering not performed in !
accordance withLthe PROCESS CONTROL PROGRAM,' test- l the improperly. processed waste in each container to ensure.that it meets burial ground and shipping requirements and.take appropriate administrative l action to. prevent recurrence. .! ~
- c. The provisions of Specification 3.0.3 are not <
applicable. , l SURVEILLANCE-REQURIEMENTS f 14=.11.3 SOLIDIFICATION of at least one representative test
- specimen from-at least'every tenth batch of each type of wet l L
radioactive wastes (e.g., filter sludges, spent resins, j
. evaporator bottoms, boric acid solutions and sodium sulfate i solutions) shall be verified in accordance with'the PROCESS
- -CONTROL PROGRAM:
[ a.. If any test specimen fails to verify SOLIDIFICATION, l l the SOLIDIFICATION, of the batch under test shall l be suspended until such time as additional test specimens can be obtained, alternative SOLIDI-f a FICATION parameters can be determined in accordance l
' with the PROCESS CONTROL PROGRAM, and a subsequent l l test verifies SOLIDIFICATION. SOLIDIFICATION of the l l
r 1 batch may then be resumed using the alternative l i 1 1 i . _ %5L - C - -
g OLIDIFICATION parameters determined by the PROCESS W CONTROL PROGRAM:
- b. If the initial test specimen from a batch of waste fails to verify SOLIDIFICATION, the PROCESS CONTROL PROGRAM shall provide for the collection and testing of representative test specimens from each con-secutive batch of the same type of wet waste until at least three consecutive initial test specimens demonstrate SOLIDIFICATION. The PROCESS CONTROL PROGRAM shall be modified as required, as provided in Specification 6.13, to assure solidification of subsequent batches uf waster and
- c. With the installed equipment incapable of meeting Specification 3.11.3 or declared inoperable, restore the equipment to OPERABLE status or provide for contract capability to process wastes as necessary to satisfy all applicable transportation and disposal requirements.
BASES 3/4.11.3 SOLID RADIOACTIVE WASTES This specification implements the requirements of 10 CFR 50.36a and General Design criterion 60 of Appendix A to 10 CFR Part 50. The process parameters included in establishing the Process Control Program may include, but are not limited to waste type, waste pH, waste / liquid / SOLIDIFICATION agent! catalyst ratios, waste oil content, waste principal chemical constituents, and mixing and curing times. e I M-8 Rev. 8
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