ML20137X578

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Revised Vol 1 to Process Control Program, Sections I-V. Sections VI-IX Withheld
ML20137X578
Person / Time
Site: Oconee, Mcguire, Catawba, McGuire, 05000000
Issue date: 03/01/1985
From:
DUKE POWER CO.
To:
Shared Package
ML20099J651 List:
References
PROC-850301, NUDOCS 8510040542
Download: ML20137X578 (46)
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Text

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DUKE POWER COMPANY l l

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PROCESS CONTROL .

PROGRAM I

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This is a Process Control Program Manual. This manual includes two types of documents - 1) the actual Process Control Program for each nuclear station and, 2) supporting documents and forms which are not part of the PCP proper.

The actual Process Control Program as required by Technical Specification consists solely and exclusively of manual sections:

I. Introduction II. Corporate PCP, end

/3 III, IV, or V. Station PCP

\_.] Revisions to these sections shall be governed by Section 6 of the applicable station's Technical Specifications.

T ual Sections VI through IX consist of documents and forms use in Nuclear Production technical review of proposed revisions t.a the PCP or its implementing procedures. Thece documents are not part of the Proce. 3s Control Program, arf __nst required by Technical Specification, and revisions are not governed by Section 6.0 buitk kell' ,

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A ,l DUKE POWER COMPANY PROCESS CONTROL PROGRAM MANUAL TABLE OF CONTENTS I. INTRODUCTION AND BACKGROUND II. CORPORATE PROCESS CONTROL PROGRAM n j III. OCONEE NUCLEAR STATION PROCESS CONTROL PROGRAM i

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IV. MCGUIRE NUCLEAR STATION PROCESS CONTROL PROGRAM V. CATAWBA NUCLEAR STATION PROCESS CONTROL PROGRAft VI. NRIDEVELOPMENTDOCUMENTS-NPDINTERNALUSEONLY VII. DOCUMENT REQUIREMENT INDEX - NPD INTERNAL USE ONLY VIII. NPD PROGRAM REVIEW

SUMMARY

- NPD INTERNAL USE ONLY IX. VENDOR SUPPORT DOCUMENTS - NPD INTERNAL USE ONLY A. CHEM-NUCLEAR SYSTEMS hii+k kolk Rev. 0,,,

O DUKE POWER COMPANY PROCESS CONTROL PROGRAM INTRODUCTION AND BACKGROUND Technical Specifications 3/4.11.3 for McGuire and Catawba Nuclear Stations and 3.11 for Oconee Nuclear Station define the operation of the Solid Radioactive Waste System (WS). This specification requires that the WS System be operated in accordance with a ' Process Control Program", such that the final product of solidification or dewatering meet all shipping and transportation requirements during transit and meet disposal site requirements when received at the disposal site. These " Process Control Program" requirements are applicable to liquid or wet solid wastes only.

While Technical Specifications require a " Process Control Program", they do not provide sufficient guidance on the totality of the requirements that must be addressed in an acceptable program. These requirements can be found in several i documents developed by the NRC to provide guidance on a " Process Control Program". These documents include:

1. NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants"
2. NUREG-0452," Standard Technical Specifications for Westinghouse PWR's"
3. NUREG-0800, " Standard Review Plan for Solid Waste Management Systems"
4. Branch Technical Position - ETSB 11-3, " Design Guidance of Solid Radioactive Management Systems"
5. Appendix 11.4-A, " Design Guidance for Temporary Onsite Storage of Low Level Radioactive Waste"
6. NRC Review Criteria for Solid Waste Management Systems
7. Site-specific Technical Specifications.

These documents, except for site Technical Specifications, can be found in Section VI of this manual.

A listing of the requirements specified or referenced by each document can be found in Section VII. These requirements can be generally summarized as follows:

1. A PCP shall be used to control all solidification and dewatering activities.
2. A PCP shall assure compliance with applicable federal regulations: 10CFR Parts 20, 50, 61, and 71 and 49 CFR (173-179).
3. A PCP shall be approved by the NRC prior to implementation. ,

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O 4. Changes to the PCP shall be submitted to the NRC in the Semiannual Radioactive Effluent Report.

5. A PCP shall consist of the processing steps and processing parameters that must be followed to assure satisfactory solidification and/or dewatering products.
6. A PCP shall establish a sampling or testing schedule for verification of solidification.
7. A PCP shall establish a set of records that must be maintained for each solidification and dewatering performed for disposal.
3. A PCP shall specifically address methods for radioactive waste oil disposal.
5. A PCP shall address chemical compatibility of waste and disposal container during interim storage.
10. A PCP shall be implemented in station operating procedures.

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11. A PCP shall establish a system of technical and management review and approval for all changes to itself or its implementing procedures.
12. A PCP shall establish a system of performance audits for itself and its implementing procedures.

This manual outlines Duke Power Company's program for complying with the NRC requirements for a Process Control Program for the Oconee, McGuire and Catawba Nuclear Stations. The Corporate Process Control Program is the list of the specific requirements that must be met to assure a final solidification or dewatering product meets all federal and state regulations. The Station Process Control Program is a list of the operating procedures that implement the requirements of the Corporate PCP and a station specific drawing reference for system interfaces.

As the Nuclear Regulatory Commission further defines their requirements for a PCP and as federal or state regulations change, this manual will be revised to meet these changes.

SOLIDIFICATION General System Description Solidification is accomplished at all Duke Power Nuclear Stations by mix:ng measured amounts of waste, binder, and required additives and allowing sufficient cure time to insure a solid free-standing monolith.

A measured amount of waste is transferred from company-owned and controlled containers (e.g., waste storage tanks, tankers, drums) through company- or vendor-supplied isolation valves to the solidification vessel.

! Measured amounts of binding agent and additives (as required) are transferred

! from storage containers through transfer lines to the solidification vessel.

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O The waste and binder are mixed using company- or vendor-supplied equipment and allowed to cure for a predetermined time. At the end of the curing period, the absence of free liquids is verified either by confirmation that the PCP was followed or by physical testing.

The solidification system ventilation discharge is routed through company- or vendor-supplied piping to the plant's Auxiliary Building or Radwaste facility ventilation system prior to discharge to the environment. If the solidification system has filtered ventilation, exhaust need not be routed back to building ventilation.

Any decanted liquids (e.g., excess sluice liquid) are routed back to plant storage tanks through company- or vendor-supplied piping.

Solidification equipment and processing may be provided by vendor, by permanent Duke Power systems, or by portable Duke Power systems. Any process used shall be verified by station and corporate Radwaste staffs as meeting all requirements outlined in the Corporate PCP. Verification and approval by station and corporate Radwaste supervision are required prior to placing any system in service for the purpose of producing solidified waste for disposal as radioactive waste.

DEWATERING General System Description Dewatering is accomplished by removing all free liquids from " wet solids" such that the final product meets all regulatory and burial site criteria for disposal (i.e., less than 0.5% free standing liquid by waste volume per container or less than 1% free standing liquid if a high integrity container is utilized).

All wastes to be dewatered are degassed prior to the dewatering process.

Therefore special ventilation requirements are not necessary.

Liner Dewatering:

Vendor- or company-supplied liners are used to dewater large volumes of wet solids, usually resin slurries. The wet solids are transferred from company owned and controlled storage containers (e.g., tanks 3 temporary liners) through company- cr vendor-supplied isolation valves to the disposal liner. All free liquid is pumped out of the liner and returned to the company storage containers using company or vendor pumps and piping.

Demineralizer Dewatering:

Vendor-supplied portable demineralizers are dewatered by using company or vendor pumps to remove all free liquids from the vessel. The dewatering liquid is returned to company storage containers for sampling prior to reuse or processing.

(N Filter Dewatering:

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Filters are dewatered by draining and drip drying prior to shipment. Packing material may be placed within the vessel to maintain position of contents

} during shipment. Filters may also be dewatered in liners.

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. Filter Slurry Dawatering:

Filter backwash slurry may be dewatered similar to resin liner dewatering or i solidified. '

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Y DUKE POWER COMPANY CORPORATE PROCESS CONTROL PROGRAM TABLE OF CONTENTS 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 b

V 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

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O v DUKE POWER COMPANY CORPORATE PROCESS CONTROL PROGRAM 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 implement the requirements of this corporate PCP.

V 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, 49 CFR and licensed burial site criteria.

1. 5 If this Process Control Program is not followed each vessel of processed 3

(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 solidification services utilized by Duke Power Company shall have a NRC approved Topical Report.

2.1.2 Any vendor solidification services utilized by Duke Power Company shall be approved by the Corporate Radwaste Engineer and station (s)

Technical Services Superintendent prior to operation.

2.1.2.1 Technical review shall be performed by corporate and station radwaste staffs of all vendor documents and 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

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V 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). Appr3ved waste forms for G-2 Rev. O

solidification are:ooric acid evaporator concentrates, spent bead resin, spend powdered resin, filters, filter backwash slurry, and resin regenerative chemical wastes.

2.2 Program Requirements 2.2.1 The vendor topical report 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 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 plar.t 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 Safety Analysis Report.

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V ) 2.2.4 Duke Power Ccmpany permanent or portable solidification systems shall be designed, constructed, operated per 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 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:

2.2.5.3.1 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 agitative or recirculative flow which Q

V exceeds a specified minimum rate which has been documented to provide a representative sample for the vessel.

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2.2.5.3.2 For final samples prior to initiating solidification, no additional waste shall be introduced into the con-tainer after recirculation or mixing has begun.

Vessel level readings or input isolation shall be documented at the time of mixing initiation, and process initiation.

2.2.5.3.3 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 analysis shall be performed as outlined in site-specific procedures for each waste form and solidification media. These should include such analysis as:

2.2.5.5.1 Waste pH 2.2.5.5.2 Waste density 2.2.5.5.3 Waste boron concentration 2.2.5.5.4 Waste oil content

, ( ) 2.2.5.6 Test solidification shall be performed to establish boundary conditions for all process parameters.

NOTE: " Process parameters" shall be defined as, "those 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".

2.2.5.7 Process parameters should include any of the following which are required to assure solidification:

2.2.5.7.1 Waste form.

2.2.5.7.2 Waste to solidification agent ratio.

2.2.5.7.3 Amount of each solidification additive.

2.2.5.7.4 Waste pH.

2.2.5.7.5 Waste boron concentration.

2.2.5.7.6 Waste density.

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' 2.2.5.7.7 Waste oil content.

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D1 2.2.5.7.8 Mixer speed.

2.2.5.7.9 Mixing time.

2.2.5.7.10 Curing time.

2.2.5.7.11 Specific activity.

2.2.5.8 Vendor shall submit sample analysis, test solidification results and prescribed boundary conditions to Station Radwaste Supervision.

2.2.5.9 Station Radwaste Supervision shall review the data outlined in Step 2.2.5.8 and shall authorize solidification prior to initiation.

2.2.5.9.1 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 can not be reached at the station level.

2.2.5.10 Solidification for disposal shall not be performed unless the test solidification is acceptable.

2.2.5.11 All system operation shall be controlled by station proce-d dures to assure that the solidification system is operated within the boundary conditions established in Step 2.2.5.7.

2.2.5.11.1 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 liquids 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.

2.2.5.12.1 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.

2.2.5.12.1.1 Physical testing shall consist of visual inspection and probe penetrate tests.

2.2.5.12.2 A vessel shall have less than 0.5% free standing liquid by waste volume.

2.2.5.12.3 If a High Integrity Container is utilized, the vessel shall have less than 1% free standing liquid.

A h 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 G-S Rev. 0

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l 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).

2.2.5.14.1 These records shall include:

2.2.5.14.1.1 Representative sampling documentation (per Step 2.2.5.3).

2.2.5.14.1.2 Sample analysis results (per Step 2.2.5.5).

2.2.5.14.1.3 Reference test solidification results and boundary conditions (per Steps 2.2.5.6 and 2.2.5.7) 2.2.5.14.1.4 Station Radwaste Supervision authorization for solidification per (Step 2.2.5.9).

2.2.5.14.1.5 System operation data to insure all boundary conditions were met (per Step O 2.2.5.11).

2.2.5.14.1.6 FSL Verification (per Step 2.2.5.12).

3.0 DEWATERING 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.

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.

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.

i q 3.2 Program Requirements b 3.2.1 The vendor topical report shall include a detailed system descrip-tion giving all vendor interfaces with company equipment. Drawings i

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\ or diagrams shall be included detailing all dewatering system interfaces with plant radwaste systems and equipment.

3.2.2 The vendor topical report 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 be covered by a topical report that meets 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 equipment. Drawings or diagrams shall be included detailing all dewatering system interfaces with other plant radwa,te 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 Safety Analysis Report.

3.2.5 Duke Power Company permanent or portable dewatering systems shall be designed, constructed, operated per and meet all quality assur- '

ance provisions of NRC Branch Technical Position 11-3 and Regulato-ry 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, " acceptable numerical values for process parameters".

3.2.6.2 Process parameters shall be identified in site-specific procedurs. Typical parameters are:

3.2.6.2.1 Waste form.

3.2.6.2.2 Settling time.

3.2.6.2.3 Drain (or pump) time 3.2.6.2.4 Drying time.

3.2.6.3 Sample analysis and boundary conditions shall be submitted to the Station Radwaste Supervisor, p

( 3.2.6.3.1 For filter dewatering, data shall be submitted to the

' Station Health Physics Supervisor.

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v 3.2.6.4 Station Supervisor shall review the data outlined in Step 3.2.6.3 and shall authorize dewatering prior to initiation.

3.2.6.4.1 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 can not be reached at the station level.

3.2.6.5 All operations shall be controlled by station procedures to assure that all boundary conditions established in Step 3.2.6.1 are met.

3.2.6.5.1 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 liquids 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.

3.2.6.6.1 Physical testing shall be required for each vessel if the Process Control Program was not followed or if any p

J off normal condition existed during processing.

3.2.6.6.2 A vessel shall have less than 0.5% free liquids by waste volume.

3.2.6.6.3 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 defined in Step 3.2.6.6, shall not be shipped to a 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:

3.2.6.8.1. Sample analysis and boundary conditions (per Step 3.2.6.3).

3.2.6.8.2 Station supervisor authorization for dewatering (per Step 3.2.6.4).

3.2.6.8.3 Equipment operation data to insure all boundary conditions were met (per Step 3.2.6.5).

O y) 3.2.6.8.4 FSL Verification (per Steo 3.2.6.6).

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O D 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.

4.2 If larger volumes of waste oil are to be solidified a special procedure shall be used.

4.2.1 The oil-specific procedure shall include all requirements in Section 2.0.

4.3 Solidified waste oil shall not be shipped to the licensed burial site at i Barnwell, S.C. for disposal, except as defined in Step 4.1.

5.0 INTERIM STORAGE 5.1 Program Requirements 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.

1 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.

5.1.1.4 Each container and waste.shall be checked against 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 Radwaste or Health Physics supervision shall review the information in Step 5.1.1.4 and shall certify chemical compatibility and authorize storage.

i 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:

5.1.1.6.1 Chemical compatibility certification (per Step 5.1.1.0).

5.1.1.6.2 Station supervision authorization to store waste (per Step 5.1.1.5).

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O 6.0 10 CFR 61 COMPLIANCE 6.1 Vendor Requirements 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.

6.1.2 The vendor (s) described in Section 3.1 for dewatering shall have a NRC approved report documenting compliance with waste form require-ments in the final dewatered product.

6.1.3 Any vendor providing High Integrity Containers to Duke Power Company shall have a NRC approved report accumenting compliance with waste form requirements.

1 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 appro-priate 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)

O.. waste shall be classified as either Class A, B or C waste using the Duke Power Company "10 CFR Part 61 Waste Classifi-cation and Waste Form Implementation 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.

6.2.1.2.1 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 compliance 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 7.1.1 All shipping casks used to transport processed waste for burial shall have a NRC issued Certificate of Compliance.

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 proce-dures prior to use. Vendor format may be retained if desired or the procedure may be :ewritten into DPC format.

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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 shipment of processed waste. These records shall be maintained for six (6) years or life of station per the Adninistrative Policy Manual).

These records shall include:

4 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 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.

4 O Proposed revisions shall be reviewed against Technical Specifica-tions 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-0452 8.1.1. 3 NUREG-0800.

4 8.1.1.4 Branch Technical Position - ETBS 11-3.

8.1.1. 5 Appendix 11.4-A, " Design Guidance for Temporary Storage...".

8.1.1.6 NRC Review Criteria for Solid Waste Management Systems.

i 8.1.1.7 Site-specific Technical Specifications.

8.1.2 Changes to the Corporate Process Control Program shall be approved by the System Radwaste Engineer and each station's Technical Services Superintendent prior to implementation.

3.1.3 Each Station Manager shall document that any changes to the Corpo-rate Prncess Control Program have been reviewed and approved (per Ster'; 8.1.1 and 8.1.2).

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O 8.1.4 The Nuclear Safety Review Board shall review the activities of the Station Manager detailed in Step 8.1.3.

8. i. 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 Superintendent prior to implementation.

8.1.7.1 Changes to implementing procedures shall be reviewed by the Technical Services Superintendent to assure they do not

,l conflict with the Corporate Process Control Program.

i l 8.1.8 Records shall be maintained documenting the requirements of 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.

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a DUKE POWER COMPANY STATION PROCESS CONTROL ri(0GRAi?

! 1.0 PURPOSE f The purpose of the Duke Power Compan) Station Process Control Program j shall be to insure all requirements tf the DPC Corporate Process Control

Program have been meet for each container of solidified or dewatered j radioactive waste shipped for burial et a licensed burial facility.

2.0 COMPOSITION i

2.1 The Duke Power Company Station Process Control Program shall consist of

! 2.1.1 A list of all station-specific procedures that implement the requirements of the Corporate Process Control Program.

2.1.2 Diagrams or drawings or drawing numbers showing all connections batween plant radwaste systems and solidification and dewatering

equipment.

l 2.1.3 Documentation of NRC approval of the initial station Process

! Control Program.

l 2.1.4 Documentation of System Radwaste Engineer and station Technical Services Superintendent approval of all changes to the Corporate Process Control Program.

2.1.5 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 3.1 The Station Process Control Program takes the following exceptions with the Corporate Process Control Program:

i O

1 G-13 Rev. 1

O DUKE POWER COMPANY PCP VENDOR APPROVAL VENDOR:

TOPICAL REPORT NO:

SERVICES:

This vendor's topical report and support documents have been O reviewed against the Duke Power Company Corporate Process Control Program and found to be acceptable.

General Office Review Station Review By: By:

Title:

Title:

Date: Date:

i This vendor is approved to provide services to

, Nuclear St.stion.

i l System Radwaste Engineer Technical Services Superintendent Date: Date:

O

i O

DUKE POWER COMPANY PCP REVISION APPROVAL Revised PCP Section: '

Corporate PCP, Rev 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.

General Office Review Station Review By: By:

Title:

Title:

Date: Date:

This revision is approved for use at Nuclear Station.

System Radwaste Engineer Technical Services Superintendent Dates Date:

Station Manager Date:

O

DUKE POWER COMPANY OCONEE NUCLEAR STATION PROCESS CONTROL PROGRAM 1.0 PURPOSE The purpose of the Oconee 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. This PCP is applicable only to the solidification or dewatering of liquid or wet solid radioactive waste.

2.0 COMPOSITION 2.1 The Oconee Nuclear Station Process Control Program shall consist of:

2.1.1 A list of all station-specific procedures that implement the requirements of the Ccrporate Process Control Program.

2.1.2 Oconee Nuclear Station diagrams or drawings or drawing numbers showing all connections between ONS radwaste systems and d solidifications and dewatering equipment.

2.1.3 Documentation of NRC approval of the initial Oconee Nuclear Station Process Control Program.

2.1.4 Documentation of System Radwaste Engineer and ONS Technical Service! Superintendent approval of all changes to the Corporate Process Control Program.

2.1.5 Documentation that all changes to the Corporate and/or ONS Process Control Program were sent to the NRC in the Semi-Annual Radioactive Effluent Report.

3.0 EXCEPTIONS 3.1 The Oconee Nuclear Station Process Control Program takes the following exceptions with the 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.

3.1.2 For Corporate PCP section 3.1.2, station review and station Technical Services Superintendent approval are not required.

('] Corporate review and approval of vender dewatering services are V sufficient.

Rev. O 0-1

. . -_ . _ _ _ _._ . . _ . _ ._m _ _ _ _ . ._

l 4

SECTION 2.1.1 Implementing Procedures CP/0/B/5002/04 "Ecodex Precoat/Powdex/Diatomedus Earth Transfer From the Powdex Backwash Tank to Disposable Cask Liners" CP/0/B/5002/10 " Bead Dewatering Procedure for CNSI 14-195 or Smaller I i

Liners" CP/0/B/5002/11 " Operating Guidelines for the use of CNSI High Integrity Containers" '

CP/0/B/5002/12 " Handling Procedure for CNSI High Integrity Overpack Containers CP/0/B/5006/07 " Dewatering Procedure for CNSI 24" Diameter Vessels Containing Activated Carbon and Ion Exchange Resins" CP/0/B/5008/06A " Concentrate Storage Tank Recirculation and Transfer to

,, the 121 Mobile Solidification Unit" CP/1&2/B/5009/03 " Unit 1 and 2 Spent Resin Storage Tank (SRST) Resin

-. Transfer to Disposable Liners"

, CP/0/B/5010/04 " Operating Procedure for the Mobile Solidification Unit 4 # 121" i

j CP/0/B/5010/04A " Assembly and Disassembly Procedure for the Mobile Solidification Unit # 121" l

CP/0/B/5010/04B "PCP Required Records for Solidified Concentrates" l CP/0/B/5010/05 "PCP for CNSI Solidification Unit" i

CP/0/B/5010/07 "PCP for CNSI Acid Solidification"

i. .

CP/0/B/5010/08 "PCP for CNSI Cement /0il Solidification" HP/0/B/1006/01/A " Procedure for the Preparation and Shipment of

Radioactive Waste" a

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0-2 Rev. O i

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l t i SECTION 2.1.2 .

I f Drawing Index  !

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f t l All system interfaces are shown on diagrams in the applicable station procedure i

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t 0 -3 Rev. 0

V DUKE POWER COMPANY ~

PCP REVISION APPROVAL Revised PCP Section:

Corporate PCP, Rev 0 ONS PCP, Rev 0 MNS PCP, Rev CNS PCP, Rev -

This revision has been reviewed against Technical Specifications and applicable NRC guidance documents and found to be acceptable.

General Office Review Station Review By: N d- Wh'%- ' By: 1L kN bQk

/

Title:

[bMbA bb

Title:

4 E., Am/Td SwlM Os Date: /2 ' 80 ~ 8h Date:

J f 1-1-35[o l - M - Ni

/

This revision is approved for use at oconee Nuclear Station.

$lld b SW System Radwaste Engineer Uconee Technical Services I Superintendenlt Date:

, , Date: 1  %}9s W

Oconee Station Manager Date: I 5 0

,,.,,,,,_-.-+~-.v-,,g e. --vv+ -e---+-"~*-17'---'* ~ " " - ' * ' " ~ ' ' ' " '

  • O DUKE POWER COMPANY PCP VENDOR APPROVAL i

VENDOR: Chem-Nuclear TOPICAL REPORT NO: CNSI-DW-1118-01 SERVICES: Dewatering 4

1 This vendor's topical report and support documents have been reviewed against the Duke Power Company Corporate Process Control Program and found to be acceptable.

General Office Rev4ew By: Al d/o e O'(Lmtt>m

Title:

O.44]Af N. b Date: AbC 81 ; / 9BM This vendor is approved to provide dewatering services to Oconee Nuclear Station.

b System R(dwaste Engineer Date: /2lJ/,lW 4

O i DUKE POWER COMPANY PCP VENDOR APPROVAL VENDOR: Chem-Nuclear TOPICAL REPORT NO: 4313-01354-01D-A SERVICES: Cement Solidification 4

This vendor's topical report and support documents have been reviewed against the Duke Power Company Corporate Process Control Program and found to be acceptable.

General Office Jeview.

i By: Al J ucavum

Title:

O AS ;M N. P

! Date: L02 c sl ,. 19sg i

I l

This vendor is approved to provide solidification services to
Oconee Nuclear Station.

I W

System hadwaste Engineer

  • Date: /Lf 3/' PV

. O '

i DUKE POWER COMPANY PCP VENDOR APPROVAL VENDOR: Chem-Nuclear Systems TOPICAL REPORT NO: WF-C-01-ND SERVICES: Part 61 Compliance (Solidification)

O This vendor's topical report and support documents have been reviewed against the Duke Power Company Corporate Process Control Program and found to be acceptable.

General Office Eeview By: H. J . da. muse

Title:

dedici . N. P.

Date: hC. El. I4RN ,

This vendor is approved to provide _Part 61 Certifi- services to Oconee Nuclear Station. cation 9.A u W System'Raddaste Engineer Date: /A!J/!N

< i

(

DUKE POWER COMPANY 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. This PCP is applicable only to the solidification 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 A list of all station-specific procedures that implement the requirements of the Corporate Process Control Program.

, 2.1.2 McGuire Nuclear Station diagrams or drawings or drawing numbers x showing all connections between radwaste systems and solidifica-

] tions and dewatering equipment.

2.1.3 Documentation of NRC approval of the initial McGuire Nuclear Station Process Control Program.

2.1.4 Documentation of System Radwaste Engineer and MNS Technical Services Superintendent approval of all changes to the Corporate Process Control Program.

2.1.5 Documentation that all changes to the Corporate and/or MNS Process Control Program were sent to the NRC in the Semi-Annual Radioactive Effluent Report.

V) i l

3 M-1 Rev.

T-SECTION 2.1.1 Implementing Procedures CP/0/B/8300/20 "Radwaste Chemistry Procedure for Handling of Laboratory Quantities of Spent Resin"

~~

CP/0/B/8400/31 "Radwaste Chemistry Procedure for Addition of Chemicals to the ECST and the ECBT" CP/0/B/8600/11 "Chec21stry Procedure for Sampling with the Isolok Sampler"

~

HP/0/B/1004/04 " Preparation a'nd Shipment of Mechanical Radwaste Filter Media" iip /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" 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 Binder 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 Transier, Dewatering and Shipment of Powdex Resin"

, OP/0/B/6200/66 "Radwaste Chemistry Procedure for Dewatering Vendor Demineralizers" i

OP/0/B/6250/09' " Condensate Polishing Demineralizer Operation" 0

1 C%)

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i M-2 Rev. 3 ,

I 3, te.

1 nt ,e

SECTION 2.1.2 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

)

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1 DUKE POWER COMPANY PCP REVISION APPROVAL Revised PCP Sections (Circle One)

Corporate PCP, Rev 0 ONS PCP, Rev MNS PCP, Rev 3 CNS PCP, Rev This revision has been reviewed against Technical Specifications and applicable NRC guidance documents and found to be acceptable.

General Office Review Station Review By: IJ.J.h sy, hr

Title:

bl b

Title:

A b Date: bEC 09, I$0Y Date: 12~ 2 2 - E Y I

This revision is approved for use at McGuire Nuclear Station.

flfn W A / ~ .?. /T h r J Sysfem Atadwaste sngineer McGuire Technical Services Date: hm2Y /9fl Superintendent Date: M lJ/lM

' /

/ // l l

McGuire W

Station Manager Date: / I/ M

/ /

O

G

Subject:

McGuire Nuclear Station Process Control Progra.T Please find attached copy / copies No. 28 of Revision 2 ,.

of the subject manual. Only affected pages should be changed in accordance with the List of Effective Pages. Note that this document contains proprietary information.

Revision 2 of this manual has been approved as indicated below.

O 1II 3 Approval Date: A /JF[f6 Approval Date:

/ /

kky$bd $b$

M. D. McIntosh, Manager

M. L. Birch i

System Radwaste Engineer McGuire Nuclear Station J

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DUKE POWEn COMPANY P.O. ISOX W)lHD CALAHLOTTE. KC. 2H242 nALu.TrCKER Te ternomt

== m pen 8MS, (704l DF F4&):

= = = - ~ ~ March 11, 1983 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Atten tion: Ms. E. G. Adensam, Chief Licensing Branch No. 4 Re: McGuire Nuclear Station Docket Nos. 50-369, 50-370 Process Control Program

Dear Mr. Denton:

Please find enclosed 20 copies of Revision 2 of the Process Control Program.

This revision is submitted as a result of the revised McGuire Nuclear Station Technical Specifications which require additional information on the Dewatering Process. Determination was made that this change does not reduce the overall conformance of the solidified waste product to existing criteria for solid

< wastes. This revision has been reviewed and approved by the station manager as indicated on the following cover sheet.

According to Technical Specification requirements, revisions to the Process Control Program are to be submitted in the semi-annual Radioactive Effluent Release Report. As a matter of convenience, we are submitting this revision prior to submittal of the semi-annual Radioactive Effluent Release report for the period January-June 1983. Please advise if there are any questions concerning this matter.

Very truly yours, fb b'hg Hal B. Tucker WHH/php Attachment cc: (w/o attachment)

Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303

('~)

(_ / Mr. W. T. Orders NRC Senior Resident Inspector I

McGuire Nuclear Station

ODuxz POWER COMPANY Powsm Buttnixo y 422 Socra Cavacu Srazer, CaAntortz. N. C. asa4a ,

wi w a o. w ata. x August 22, 1980 WCE #ets.0t=T ItkE *==O= t; Anta 7Ca Seca= Peoowcwon 373-40s3 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Mr. B. J. Youngblood, Chief Licensing Projects Branch No. 1 Re: McGuire Nuclear Station, Units 1 and 2 Docket Nos. 50-369, 50-370 4

Dear Mr. Denton:

At requested by Mr. Robert L. Tedesco's letters of July 29, 1980 and July 31, y 1980, please find attached additional infornation on the discussion in the McGuire Final Safety Analysis Report on the Radwaste Management System at McGuire Nuclear Station, the Radiological Effluent Technical Specifications, j the Offsite Dose Calculation Manual, and the Process Control Progran.

Revision 1 of the Process Control Program has been reviewed and approved. Our

'i response includes 20 copies of a nonproprietary Process Control Program, Revision 1, and 20 copies of the proprietary Process Control Program, Rev!sion 1.

Revision 1 of the McGuire Offsite Doce Calculation Manual has been reviewed and approved. Ten copies of this document are attached.

Also note that a response has been provided to your infor=al request for infor-mation telecopied to us on August 5, 1980.

Please advise us if you have any questions on this material.

Very truly yours, O T 4

William O. Parker, Jr.

LJB:ses Attachments

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3 l August 19, 1980 b

i

Subject:

McGuire Nuclear Station Process Control Program Please find attached copy / copies No. of Revision 1 of the subject manual. As this revision constitutes a complete reprint of the manual, 1 please discard all present manuals. Subsequent revisions will be issued as i required and only affected pages will be changed. Note that this document contains proprietary information.

Revision 1 of this manual has been approved as indicated below.

I Approval Date: N O Approval Date: k $ /~ ' O YkA Lionel Lewis System Health Physicist

)40KilW!

M. D. McIntosh, Manager McGuire Nuclear Station 1

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p c u co -

,_ LN~~

UNITED STATES

,7 ] E\)s,((k'j NUCLEAR REGULATORY COMMISSION *

(_, '  ! WASHINGTON, D. C. 20555

{.Igf,/

\%4 ,

  • .*** JUL 3 : Isso Docket Nos.: 50-369 and 50-370 Mr. William 0. Parker, Jr.

Vice President - Steam Production Duke Power Company Post Office Box 33189 422 South Church Street Charlotte, North Carolina 28242

Dear Mr. Parker:

Subject:

Process Control Program (McGuire 11uclear Station, Units 1 & 2)

(  ; By letter dated July 8,1980, you provided a proprietary report " Process L- Control Program for CNSI Moble Solidification Units Using the Dow Process"

( SD-0P-005) . We have reviewed the material based on the requirements and criteria of 10 CFR 2.790 and have determined that the document sought to be withheld contains trade secrets or confidential or privileged commercial or financial information.

In order for us to complete our review and evaluation we request that you provide a non-proprietary PCP considering the non-proprietary Dow report D'1S-RSS-001-NP and the non-proprietary CNSI information in order that we can accept the PCP for review. We will need the revised non-proprietary PCP for solidification and the packaging of wet solid radioactive waste by August 15, 1980, in order to evaluate and complete our review before licer. sing.

Sincerely, Robert L. Tedesco, Assistant Director for Licensing Division of Licensing

(.

\  !

DUKE POWER COMPANY

' PCP VENDOR APPROVAL VENDOR: O DI-NUCLEAR SYSTBIS TOPICAL REPORT NO: CNSI-DK-11118-01 SERVICES: DEWATERING l

This vendor's topical report and support documents have been O reviewed against the Duke Power Company Corporate Process Control Program and found to be acceptable.

B / N B --

Title:

M N b-

Title:

M dverd MJn<vm Dates 12-2 7- 8 & Date /2-20-fY i

j This vendor is approved to provide dewaterinc services to McGuire Nuclear Station.

h/% Y M System R/ adwaste Engineer ow o?, flNY McGuiW Technical Services Superintendent Date: 1AN/ SV Date: /dl4lN i /

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DUKE POWER COMPANY PCP VENDOR APPROVAL VENDOR: OD!-NUCIEAR SYSTD!S TOPICAL REPORT NO: 4313-01354-01P-A SERVICES: CBIENT SOLIDIFICATION i

4 a

p)

(

This vendor's topical report and support documents have been reviewed against the Duke Power Company Corporate Process Control Program and found to be acceptable.

B . ru__ B / ma t

Titles d4&21I M.[.

Title:

[M,ed $44*e iiu -z,'

Date: /A-a?- RW Date /2*20-PY This vendor is approved to provide solidification services to McGuire Nuclear Station.

l

. N?nAh System Rddwaste Engineer

% ./M M McGuke Technical Services l

Superintendent I

Date: /

.W lJ'V Date: / J/lN

\

t

O DUKE POWER COMPANY PCP VENDOR APPROVAL t

VENDOR: O D!-NUCLEAR SYSTB!S TOPICAL REPORT NO: h7-C-01-NP SERVICES: PART 61 C0f@LIANCE (SOLIDIFICA1DN AND DEWATER.)

i 1

This vendor's topical report and support documents have been reviewed against the Duke Power Company Corporate Process Control Program and found to be acceptable.

"""'*J'J.'c W * '*"1t%%

Title:

Mk

Title:

[M*M I</+wezrv Date: /.2-2A"SY Date /2-X-!Y This vendor is approved to provide Part 61 Certifi- services to McGuire Nuclear Station. cation AM  % d8 System Ragwast'e Engineer McGuirF Technical Services Superintendent Date: l) 3l Date: lY)/ N

~ - - _ -

DUKE POWER COMPANY

, CATAWBA NUCLEAR STATION PROCESS CONTROL PROGRAM 1.0 PURPOSE i The purpose of the Catawba 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. This PCP is applicable only to the solidification or dewatering of liquid or wet solid radioactive waste.

2.0 COMPOSITION 3 2.1 The Catawba Nuclear Station Process Control Program shall consist of:

2.1.1 A list of all station-specific procedures that implement the requirements of the Corporate Process Control Program.

2.1.2 Catawba Nuclear Station diagrams or drawings or drawing numbers showing all connections between CNS radwaste systems and 1 solidifications and dewatering equipment.

! 2.1. 3 Documentation of NRC approval of the initial Catawba Nuclear i Station Process Control Program.

i 2.1.4 Documentation of System Radwaste Engineer and CNS Technical 4

Services Superintendent approval of all changes to the Corporate Process Control Prcgram.

2.1.5 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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O f C-1 Rev. 0 l

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SECTION 2.1.1 l <

Implementing Procedures i

HP/0/8/1006/09 " Shipment of Radioactive Filters and Filter

( Media" HP/0/B/1006/10 " Shipment of Solidified Radwaste" HP/0/8/1006/12 " Shipment of Dewatered Resins"

]

HP/0/8/1006/13 " Determination of the Waste Classification for  !

i Radioactive Waste Offered for Shallow Land l Burial" l OP/0/8/6500/13 " Operating Procedure for the Nuclear Solid Waste l

(WS) Disposal System" 4

OP/0/B/6500/46 "Radwaste Operating Procedure for Solidification j and Dewatering of Radioactive Waste" i

OP/0/B/6500/49 "Radwaste Chemistry Operating Procedure for i

SamplingtheECHT,ECBT,andRBTUsingIn-line i Samples

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j SECTION 2.1.2 s

i Drawing Index i

l Plant Interfaces: CN-1566-1.6 i

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DUKE POWER COMPANY PCP REVISION APPROVAL T

Revised PCP Section: (Circle One)

Corporate PCP, Rev 0 ONS PCP, Rev MNS PCP, Rev i

CNS PCP, Rev,._Q_

This revision has b[en reviewed against Technical Specifications i and applicable NRC guidance documents and found to be acceptable.

General Office Review Station Review i By: M.J.d w m u ay, ud5:M/dM-4;4 Titles - N b- Ti e : // 6c*'*'/k "A

  • Date: Lh(' c7 7 /9 B M Date: l2 -3 k -W P

This revision is approved for use at Catawba Nuclear Station.

i A>> 4 A- NA I

System "

jadwaste Engineer Cataw a Technical Services i

^ Super,intendent I Date: > hjI /fM Date: I /T/ XI

/ /

~

/

Catawba fitatdon Manager Date: / ~ )~

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4

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  • DUKE Poweit Goni>m '

/

l'.O. ISOX 3 31110

( HAI. D. R*CKER "-

CIIAHLOTTE. N.C. Oll242

.J".'..","'"" November 29, 1984 tra EP380ME Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C. 20555 4' f/

, kv, Attention: Ms. E. G. Adensam, Chief "

Licensing Branch No. 4 Re: Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-413 and 50-414 MEE Process Control Program (EC 101984 d

Dear Mr. Denton:

In response to your letter dated September 14, 1984 requestin l *fM' information regarding Catawba's Process Control Program (PCP)g , and asadditional ,

comitted specific PCP.to in my October 3,1984 letter please find attached the Catawba Very truly yours, C, h / ecc Hal B. Tucker RWO: sib Attachment ec: Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission NRC Resident Inspector Region II Catawba Nuclear Station 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. Jesse L. Riley Carolina Environmental Study Group 854 Henley Place Charlotte, North Carolina 28207 Palmetto Alliance 21351 Devine Street Columbia, South Carolina 29205 Robert Guild, Esq.

.O)

V P. O. Box 12097 Charleston, South Carolina 29412

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