ML20148B662
| ML20148B662 | |
| Person / Time | |
|---|---|
| Site: | Oconee, Mcguire, Catawba, McGuire, 05000000 |
| Issue date: | 02/16/1988 |
| From: | Cline D, Semmler D, Tucker H DUKE POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| PROC-880216, NUDOCS 8803220078 | |
| Download: ML20148B662 (21) | |
Text
_ _.,
O DUKE POWER COMPANY CORPORATE q
PROCESS CONTROL PROGRAM TABLE OF CONTENTS
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1.0 PURPOSE
~2.0 SOLIDIFICATION 2.1 Vendor Requirements 2.2 Program Requirements 3.0 DEWATERING 3.1 Vendor Requirements 3.2 Program Requirements 4.0 WASTE OIL 5.0 INTERIM STORAGE 6.0 10 CFR PART 61 COMPLIANCE 6.1 Vendor Requirements 6.2 Program Requirements 7.0 TRANSPORTATION 7.1 Program Requirements 8.0 REVIEWS 9.0 AUDITS An(
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1.0 -PURPOSE 1.1 The. purpose of the Duke Power Company Corporate Process Control Program is-to establish a set of requirements that shall be met at all nuclear stations to insure that all solidification and dewatering activities are conducted'in a manner and produce a final product that complies with all applicable Federal and State regulations and licensed burial site criteria.
1.2 The Duke Power Company Process Control Program shall be used to control and direct all solidification and dewatering activities for liquids (e.g., evaporator concentrates) and "wet solids" (e.g.,
resin slurries, filter backwash slurries, cartridge filters) at the Oconee Nuclear Station.
Units 1, 2 and 3, the.McGuire Nuclear Station, Units 1 and 2, and the Catawba Nuclear Station, Units 1 and 2.
1.3 Station - specific procedures shall be developed to
(-_s) implement the requirements of this corporate PCP.
1.4 This Process Control Program and implementing procedures shall assure that all solidification and dewatering activities are in compliance with 10CFR20, 50, 61, 71, and 49 CFR and licensed burial site. criteria.
1.5 If this Process Control Program is not followed, each vessel of processed (i.e.,
solidified or dewatered) waste shall be physically tested to verify the absence of free standing liquids.
2.0 SOLIDIFICATION 2.1 Vendor Requirements 2.1.1 Any vendor utilized for solidification services by Duke Power Company shall have a Topical Report that is either under NRC review or has NRC approval, or shall supply to Duke Power sufficient documentation of the process and results for review to demonstrate an l
acceptable product will be produced using the described solidification process.
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2.1.2 Any vendor solidification services utilized by Duke
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Power Company shall be approved by the Corporate Radwaste Engineer and station (s) Technical Services
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Superintendent prior to operation.
2.1.2.1 Technical review shall be performed by corporate and station radwaste staffs of all vendor documents and j
procedures to insure they meet the requirements of the Duke Power Company PCP outlined below.
2.1.3 Chem-Nuclear Systems, Inc. has been reviewed and approved to provide solidification services to the Oconee, McGuire, and Catawba Nuclear Stations as described in:
Mobile Cement Solidification System, Topical Report CNSI-2 (4313-01354-0IP-A).
Approved waste forms for solidification are:
boric acid evaporator concentrates, spent bead resin, spent powdered resin, filters, filter backwash slurry, and resin regenerative chemical wastes.
2.1.4 Babcock and Wilcox has been reviewed and approved to provide solidification services to McGuire Nuclear Station for Class A unstable waste as described in B & W's supporting documents.
Approved waste forms for solidification are:
oil, oil and water mixtures, organics and sludges.
D 2.2 Program Requirements 2 2.1 The vendor topical report or documentation supplied to the Company shall include a detailed system description giving all vendor interfaces with company equipment.
Drawings or diagrams shall be included detailing all solidification system interfaces with plant radwaste systems and equipment.
2.2.2 The vendor topical report or documentation supplied to the Company shall include a statement that the design, construction, operation and quality assurance provisions are in accordance with NRC ETSB Branch Technical Position 11-3 and Regulatory Guide 1.143.
2.2.3 Duke Power Company permanent or portable solidification systems shall have a detailed system description giving all solidification equipment interfaces with other company equipment.
Drawings or diagrams shall be included detailing all solidification system interfaces with other plant radwaste equipment and systems.
NOTE:
This information may be included as part of a Topical Report furnished by the equipment manufacturer or supplier or as part of the plant specific Final
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Safety Analysis Report.
G-3 Rev. 2
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-2.2.4 Duke Power Company permanent or portable solidification
('_s) systems shall be designed, constructed, operated per
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and meet all quality assurance provisions of NRC ETSB Branch Technical Position 11-3 and Regulatory Guide 1.143.
2.2.5 Station procedures shall be established to assure the j
following requirements are met:
2.2.5.1 A representative sample shall be taken from at least every tenth batch of each waste type to verify solidification.
2.2.5.2 If the initial sample fails to verify solidification, a representative sample shall be taken from each consecutive batch of the same type waste until three consecutive samples demonstrate solidification.
2.2.5.3 A representative sample shall meet all the following conditions:
(a)
The contents of the container to be sampled shall be recirculated a minimum of three volume turnovers or adequately mixed to achieve a homogeneous mixture.
NOTE:
Adequately mixed shall be defined as:
mixing via
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agitative or recirculative flow which exceeds a specified (m/
minimum rate which has been documented to provide a representative sample for the vessel.
(b)
For final samples prior to initiating solidification, no additional waste shall be introduced into the container after recirculation or mixing has begun.
Vessel level readings or input isolation shall be documented at the time of mixing initiation, sampling, and process initiation.
(c)
Recirculation or mixing time and/or volume must be uninterrupted from initiation until completion of sample collection.
2.2.5.4 During the recirculation and sampling period, the vessel shall not be placed in a transfer mode.
2.2.5.5 Sample ana.1.ysis shall be performed as outlined in site-specific procedures for each waste form and solidification media.
These should include such analysis as:
(a)' Waste pH.
(b)
Waste density.
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(c)
Waste boron concentration.
((_j (d)
Waste oil content.
2.2.5.6 Test solidification shall be performed to establish boundary conditions for all process parameters.
J NOTE:
"Process parameters' shall be defined as, "these conditions critical to insure complete solidification".
NOTE:
"Boundary conditions" shall be defined as, "acceptable numerical values for process parameters as established by a test solidification".
i 2.2.5.7 Process parameters should include any of the following which are required to assure solidification:
(a)
Waste form.
(b)
Waste to solidification agent ratio.
(c)
Amount of each solidification additive.
(d)
Waste pH.
(e)
Waste boron concentration.
(f)
Waste _ density.
(g)
Waste oil content.
(h)
Mixer speed.
(i)
Mixing time.
(j)
Curing time.
(k)
Specific activity.
2.2.5.8 Vendor shall submit sample analysis, test solidification results and prescribed boundary conditions to Station Chemistry Supervision.
2.2.5.9 Station Chemistry Supervision shall review the data l
outlined in Step 2.2.5.8 and shall authorize solidification prior to initiation.
(a). Difficultics and/or disagreements between vendor and station personnel should be resolved through direct interaction between vendor and station.
Corporate Radwaste Engineering staff should be contacted if resolution cannot be reached at the station level.
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G-5 Rev. 2
l 2.2.5.10- Solidification for disposal shall not be performed
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unless the test solidification is acceptable.
2.2.5.11 All system operation shall be controlled by station procedures to assure that the solidification system is operated within the boundary conditions established in Step 2.2.5.7.
1 (a)
Vendor procedures shall be incorporated as attachments to station procedures.
Vendor format may be retained as a DPC enclosure if desired or the procedure may be rewritten into DPC format.
2.2.5.12 The absence of free standing liquids (FSL) shall be verified for each vessel of solidified waste prior to disposal.
Verification shall be performed by either confirmation that the Process Control Program was followed or by physical testing.
(a)
Physical testing shall be required for each vessel if the Process Control Program was not followed or if any off-normal condition existed during processing.
(a.1)
Physical testing shall consist of visual inspection and probe penetrate tests.
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(b)
A vessel shall have less than 0.5% free standing liquid by N-waste volume.
(c)
If a High Integrity Container is utilized, the vessel shall have less than 1% free standing liquid.
2.2.5.13 Any solidification vessel that does not pass the tests specified in Step 2.2.5.12 shall not be shipped to a burial site until reprocessing or repackaging has resulted in an acceptable product.
2.2.5.14 Records shall be maintained by Duke Power Company on each vessel of solidified wastes.
These records shall be maintained for six (6) years (per the Administrative Policy Manual).
('a)
These records shall include:
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(a.1)
Representative sampling documentation (per Step 2.2.5.3).
(a.2)
Sample analysis results (per Step 2.2.5.5).
(a.3)
Reference test solidification results and boundary conditions (per Steps 2.2.5.6 and 2.2.5.7).
('T (a.4) station Radwaste Supervision authorization for solidification per (Step 2.2.5.9).
1 G-6 Rev. 2 l
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4 (a.5)
System operation data to insure all boundary conditions
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were met-(per Step 2.2.5.11).
(a.6)
FSL Verification (per Step 2.2.5.12).
3.0 DEWATERING 1
3.1 - Vendor Requirements 3.1.1 Any vendor utilized by Duke Power Company to' provide dewatering services shall have a Topical Report that is either under NRC review or has NRC approval, or.shall supply to Duke Power sufficient documentation of process and results for review to demonstrate adequate dewatering is accomplished using the described process.
3.1.2 Any vendor dewatering services utilized by Duke Power Company shall be approved by the. Corporate Radwaste Engineer and station (s) Technical Services Superintendent prior to operation.
3.1.2.1 Technical review shall be performed by corporate and station radwaste staffs of all vendor documents and procedures to insure they meet all requirements of the Duke Power Company PCP outlined below.
O 3.1.3 Chem-Nuclear Systems, Inc. has been reviewed and approved to provide dewatering services to Oconee, McGuire, and Catawba Nuclear Stations as described in Topical Report CNSI-DW-11118-01.
3.2 Program Requirements 3.2.1 The vendor topical report or documentation supplied to the Company shall include a detailed system description giving all vendor interfaces with company equipment.
Drawings or diagrams shall be included detailing all dewatering system interfaces with plant radwaste systems and equipment.
3.2.2 The vendor topical report or documentation supplied to the company shall include a statement that the design, construction, operation and quality assurance provisions are in accordance with Regulatory Guide 1.143.
3.2.3 All vendor supplied portable demineralizers shall meet all requirements of Steps 3.2.1 and 3.2.2.
3.2.4 Duke Power Company permanent or portable dewatering systems shall have a detailed system description giving all dewatering equipment interfaces with other company
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equipment.
Drawings or diagrams shall be included l
Rev. 2 G-7
4 detailing all dewatering system interfaces with other
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plant radwaste equipment and systems.
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NOTE:
This information may be included as part of a Topical Report furnished by the equipment manufacturer or supplier or as part of the plant specific Final Safety Analysis Report.
3.2.5 Duke Power company permanent or portable dewatering systems shall be designed, constructed, operated per and meet all quality assurance provisions of NRC Branch Technical Position 11-3 and Regulatory Guide 1.143.
3.2.6 Station procedures shall be established to assure the following requirements are met:
3.2.6.1 Boundary conditions shall be established for all process parameters.
NOTE:
Process parameters shall be defined as, "those conditions critical to insure complete dewatering".
NOTE:
"Boundary conditions" shall be defined as, unacceptable numerical values for process parameters".
3.2.6.2 Process parameters shall be identified in site-specific (s) procedures.
Typical parameters are:
(a)
Waste form.
(b)
Settling time.
T (c)
Drain (or pump) time.
(d)
Drying time.
3.2.6.3 Sample analysis and boundary conditions shall be submitted to the Station Radwaste Supervisor.
(a)
For filter dewatering, data shall be submitted to the Station Health Physics Supervisor.
3.2.6.4 Station Supervisor shall review the data outlined in Step 3.2.6.3 and shall authorize dewatering prior to initiation.
(a)
Difficulties and/or disagreements between vendor and station personnel should be resolved through direct interaction between vendor and station.
Corporate Radwaste Engineering staff should be contacted if resolution cannot be reached at the station level.
G-8 Rev. 2
3.2.6.5 All operations-shall be controlled by station
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procedures to assure that all boundary conditions As/ _
established in Step 3.2.6.1 are met.
(a)
Vendor procedures shall be incorporated as attachments to station procedures.
Vendor format may be retained as a DPC enclosure if desired or the procedure may be rewritten into DPC format.
3.2.6.6 The absence of free standing liquids (FSL) shall be verified for each vessel of dewatered waste prior to disposal.
Verification shall be performed by either confirmation that the Process Control Program was followed or by physical testing.
(a)
Physical testing shall be required for each vessel if the Process Control Program was not followed or if any off-normal condition existed during processing.
(b)
A vessel shall have less than 0.5% free liquids by waste volume.
(c)
A High Integrity container shall have less than 1% free liquids by waste volume.
3.2.6.7 Any dewatered vessel containing excess free liquids, as I\\
defined in Step 3.2.6.6, shall not be shipped to a
\\l burial site until reprocessing or repackaging has resulted in an acceptable product.
3.2.6.8 Records shall be maintained by Duke Power Company on each vessel of dewatered wastes.
These records shall be maintained for six (6) years (per the Administrative Policy Manual).
These records shall include:
(a)
Sample analysis and boundary conditions (per Step 3.2.6.3).
(b)
Station supervisor authorization for dewatering (per Step 3.2.6.4).
(c)
Equipment operation data to insure all boundary conditions were met (per Step 3.2.6.5).
(d)
FSL Verification (per Step 3.2.6.6).
4.0 WASTE OIL 4.1 Incidental levels of waste oil may be solidified using the system described in Section 2.2.
4.1.1 "Incidental" shall be defined as less than 1% oil.
O 4.2 If larger volumes of waste oil are to be solidified a special procedure shall be used.
G-9 Rev. 2
4.2.1 The oil-specific procedure shall include all
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requirements in Section 2.0.
N 4.3 Solidified waste oil shall not be shipped to the licensed burial site at Barnwell, S.C.,
for disposal, except as defined in Step 4.1.
5.0 INTERIM STORAGE 5.1 Program Re.quirements 5.1.1 Station procedures shall be established to assure the following requirements are met:
5.1.1.1 Any processed (i.e., solidified or dewatered) waste that is stored for an interim period in a disposal container shall be packaged such that there is no interaction between the waste and its container.
5.1.1.2 If applicable, certificates of Compliance shall be maintained at each station for all waste disposal containers used for interim storage.
5.1.1.3 Vendor supplied handling and storage procedures shall be maintained at each station.
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5.1.1.4 Each container and waste shall be checked against
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information given in Steps 5.1.1.2 and 5.1.1.3 to insure all chemical compatibility requirements are met.
5.1.1.5 Station Chemistry or Health Physics supervision shall I
review the information in Step 5.1.1.4 and shall certify chemical compatibility and authorize storage.
5.1.1.6 Records shall be maintained by Duke Power Company for each container.
These records shall be maintained for six (6) years (per the Administrative Policy Manual).
These records shall include:
(a)
Chemical compatibility certification (per Step 5.1.1.5).
(b)
Station supervision authorization to store waste (per Step 5.1.1.5).
l 6.0 10CbR61 COMPLIANCE i
6.1 Vendor Requirements l
l 6.1.1 The vendor (s) described in Section 2.1 for solidification shall have a NRC approved report documenting compliance with waste form requirements in the final solidified product, or shall supply Duke f)i Power sufficient documentation to demonstrate waste s-form compliance.
l G-10 Rev. 2 l
6.1.2 The vendor (s) described in Section 3.1 for dewatering
[x shall have a NRC approved report documenting compliance N-j with waste form requirements in the final dewatered product, or shall supply Duke Power sufficient documentation to demonstrate waste form compliance.
6.'1.3 Any vendor providing High Integrity Containers to Duke Power Company shall have a NRC approved report documenting compliance with waste form requirements, or shall supply Duke Power sufficient documentation to demonstrate waste form compliance.
6.1.4 All vendor reports (per Steps 6.1.1, 6.1.2, and-6.1.3) shall contain a statement that the final product conforms to the appropriate waste form for either Class A,
B, or C waste.
6.2 Program Requirements 6.2.1 Station procedures shall be established to assure the following requirements are met:
6.2.1.1 Each container of processed (i.e., solidified or dewatered) waste shall be classified as either Class A, B, or C waste using the Duke Power Company "10 CFR Part 61 Waste Classification and Waste Form Implementation 7.-
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Program".
6.2.1.2 Each container of processed waste shall be certified to the appropriate waste form for either Class A, B or C waste.
(a)
Waste form certification shall be contingent upon the documents referenced in Section 6.1.
6.2.1.3 Records shall be maintained for each container of processed waste to assure ccmpliance with the requirements of Steps 6.2.1.1 and 6.2.1.2.
These records shall be maintained for six (6) years (per the Administrative Policy Manual).
7.0 TRANSPORTATION 7.1 Program Requirements l
7.1.1 All shipping casks used to transport processed waste l
for burial shall have a NRC issued Certificate of Compliance.
I 7.1.2 Station procedures shall be established to insure all requirements of the certificate of Compliance are met.
O 7.1.2.1 Vendor procedures shall be incorporated into station procedures prior to use.
Vendor format may be l
G-11 Rev. 2
<^'s retained, if desired, or the procedure may be rewritten h
into DPC format.
7.1.3 Station procedures shall be established to insure all applicable Federal and State regulations and burial site criteria are met for each container of processed waste.
7.1.4 Records shall be maintained for each container and
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shipment of processed waste.
These records shall be maintained for six (6) years (per the Administrative Policy Manual).
These records shall include:
7.1.4.1 Documentation of a valid Certificate of Compliance for each cask (per Step 7.1.1).
Maintained for six (6) years.
7.1.4.2 Documentation that all requirements of the Certificate of Compliance were met (per Step 7.1.2).
Maintained for six (6) years.
7.1.4.3 Documentation that all shipping regulations were met (per Step 7.1.3).
Maintained for life of plant.
8.0 REVIEWS
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8.1 Program Requirements 8.1.1 Changes to the Corporate Process Control Program shall be reviewed by the Corporate Radwaste Engineering staff and each station's Radwaste and Health Physics staffs prior to implementation._ Proposed revisions shall be reviewed against Technical Specifications and all applicable NRC guidance to assure all requirements of a Process Control Program have been addressed.
Review documents shall include:
8.1.1.1 NUREG-0133.
8.1.1.2 NUREG-0472.
8.1.1.3 NUREG-0800.
8.1.1.4 Branch Technical Position - ETBS 11-3.
8.1.1.5 Appendix aa.4-A, "Design Guidance for Temporary Storage...".
8.1.1.6 NRC Review Criteria for Solid Waste Management Systems.
8.1.1.7 Site-specific Technical Specifications.
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8.1.2 Changes to the Corporate Process Control Program shall be approved by the System Radwaste Engineer and each G-12 Rev. 2
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station's Technical Services Superintendent prior to O-implementation.
8.1.3 Each Station Manager shall document that any changes to the Corporate Process Control Program have been reviewed and approved (per Steps 8.1.1 and 8.1.2).
8.1.4 The Nuclear Safety Review Board shall review the activities of the Station Man ~ger detailed in Step a
8.1.3.
8.1.5 A record of the review (per Step 8.1.4) shall be sent to the Vice President, Nuclear Production and the Executive Vice President, Power Operations within fourteen (14) days following completion of the review.
8.1.6 All changes to the Corporate PCP shall be sent to the NRC in each station's Semi-annual Radioactive Effluent Report.for the period in which the changes were implemented.
8.1.7 Changes to all implementing procedures shall be reviewed by station radwaste or health physics staff and approved by the station's Technical Services, Operating, OR Maintenance Superintendent, or Station Manager, prior to implementation.
8.1.7.1 Changes to implementing procedures shall be reviewed by the Technical Services, Operating, OR Maintenance Superintendent, or Station Manager, to assure they de not conflict with the Corporate Process Control Program.
8.1.8 Records shall be maintained documenting the approvals required by Section 8.1.
Records shall be maintained for six (6) years (per the Administrative Policy Manual).
9.0 AUDITS 9.1 Program Requirements 9.1.1 The Corporate Process Control Program and station implementing procedures shall be audited at least once per twenty-four months at each station.
9.1.2 This audit shall be performed under the cognizance of the NSRB.
9.1.3 Audit reports shall be forwarded to the Vice President, Nuclear Production; Executive Vice President, Power Operations; and Station Manager within thirty (30) days of completion of the audit.
G-13 Rev. 2
..f DUKE POWER COMPANY
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STATION PROCESS CONTROL PROGRAM 1.0 PURPOSE _
The purpose of the Duke Power Company-Station Process control Program shall be to insure all requirements of the DPC Corporate Process Control Program have been met for each container of solidified or dewatered radi~oactive waste shipped for burial at a licensed burial facility.
2.0 COMPOSITION 2.1 The Duke Power Company Station Process Control Program shall consist of:
2.1.1 The Duke Power Company Process Control Manual Introduction (Section I).
2.1.2 The Duke Power Company Corporate Process Con' trol Program.
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2.1.3 A list of all station-specific procedures that implement the_ requirements of the Corporate Process Control Program.
2.1.4 Diagrams or drawings or drawing numbers showing all connections between plant radwaste systems and solidification and dewatering equipment.
2.1.5 Documentation of NRC approval of the initial station Process Control Program.
2.1.6 Documentation of System Radwaste Engineer, station Technical Services Superintendent, and Station Manager approval of all changes to the Corporate Process Control Program.
2.1.7 Documentation that all changes to the Corporate and/or Station Process Control Program were sent to the NRC in the Semi-Annual Radioactive Effluent Report.
3.0 EXCEPTIONS l
3.1 The Station Process Control Program takes the following exceptions with the Corporate Process Control Program:
10 G-14 Rev. 2
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v DUKE POWER GOMPANY P.O. BOX 33189 I
citARLOTrE, N.C. 28242
!!AL B. TUCKER reLzenoxz m a rarsioews (704) 373 4531 stusam rnoottrios March 16,'1988 U. S. Nuclear Regulatory Comunission Attention: Document Control Desk Washington, D. C. 20555
Subject:
Catawba Nuclear Station Docket Nes. 50-413 and -414 McGuire Nuclear Station Docket Nos. 50-369 and -370 Oconee Nuclear Station Docket Nos. 50-269, -270, and -287 Corporate Process Control Program
Dear Sir:
Attached are Control Copy Numbers 26 through 31 of Duke Power Company's Process Control Program (PCP). By copy of this letter, Control Copy Number 22 of the PCP is being forwarded to Region II.
Very truly yours, w9S
)d;nw Hal B. Tucker SAG /11001/sbn i
Attachment xc:
(W/ Attachment)
Dr. J. Nelson Grace, Regional Administrator U. S. Nuclear Regulatory Comunission Region II 101 Marietta Street, NW, Suite 2900 g",d g Atlanta, Georgia 30323 s/ lk' ALCD ASf TiAA13 I
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U..S. Nuclear Rigulatery Commi=sion
' March 16, 1988
.Page Two xc:
(W/0 Attachment)
Mr..Darl Hood Office of Nuclear Reactor Regulations U. S. Nuclear Regulatory Commission Washington, D..C.
20555 Dr. K. Jabbour.
Office of' Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Ms. Helen Pastis Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Mr. P. K. Van Doorn NRC Resident Inspector Catawba Nuclear Station Mr. P. H. Skinner NRC Resident Inspector Oconee Nuclear Station Mr. W. T. O'rders NRC Resident Inspector McGuire Nuclear Station l
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U..S. Nuclear R;gulatory Commission March 16, 1988 Page Three bxc:
W.- P. Deal. CNS J. W. Foster R. L.-Gill
-P. F. Guill N. A. Rutherford D. B. Seamler.
R..O. Sharpe C. T. Yongue-File:
CN-801.01 File: MC-801.01 File: 0S-801.01 l
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.# 2(o DUKE POWER COMPANY PCP REVISION APPROVAL Revised PCP Section:
Corporate PCP, Rev 2
ONS PCP, Rev MNS PCP, Rev CNS PCP, Rev This revision has been reviewed against Technical Specifications and applicable NRC guidance documents and found to be acceptable.
PREPARED BY: 2cht bmmler TITLE:
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General Office Review Station Review BY:
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System Radwaste Engineer Technical Services Superin endent
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DATE:
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DUKE POWER COMPANY PCP REVISION APPROVAL Revised PCP Section:
J Corporate PCP, Rev 2
ONS PCP, Rev MNS PCP, Rev CNS PCP, Rev This revision has been reviewed against Technical Specifications and applicable NRC guidance documents and found to be acceptable.
PREP,ARED BY: 2cht bmmier TITLE:
Assislont [noinEee If 2/o/ff DATE:
General Office Review Station Review BY:
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TITLE:
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This revision is approved for use at ALL Nuclear Station.
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V DUKE POWER COMPANY PCP REVISION APPROVAL Revised PCP Section:
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ONS PCP, Rev MNS PCP, Rev CNS PCP, Rev This revision has been reviewed against Technical Specifications and applicable NRC guidance documents and found to be acceptable.
PREPARED BY: 2ehm bmmler-TITLE:
Assisletnf [noineer If 2(ofW DATE:
General Office Review Station Review BY:
M h BY:
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TITLE:
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DATE:
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DATE:
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DUKE POWER COMPANY PCP REVISION APPROVAL Revised PCP Section:
J Corporate PCP, Rev 2
ONS PCP, Rev MNS PCP, Rev CNS PCP, Rev This revision has been reviewed against Technical Specifications and applicable NRC guidance documents and found to be acceptable.
PREPARED BY: 2ehm bmmler TITLE:
Mssislont [noineer-DATE:
_i 2(o fff' General Office Review Station Review BY:
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TITLE:
1" TITLE:
DATE:
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u This revision is approved for use at ATAW SA Nuclear Station.
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Syst.em Radwaste Engineer Technical Services
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Superintendent l
DATE:
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