ML20210R769

Forwards Proposed Rev 23 to PGE-8010, Trojan Nuclear QAP, in Response to NRC 990708 RAI Re Relocation of TS ACs to Qap.Revised QAP Will Be Made Effective Concurrently with Implementation of License Change Application Lca 245

ML20210R769
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	08/11/1999
From:	Quennoz S PORTLAND GENERAL ELECTRIC CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
VPN-067-99, NUDOCS 9908170209
Download: ML20210R769 (64)

Text

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'Dvjan Nuclear Plant 7276 Cd"'"I RW Hu'j Rainier OR 97048 August i1,1999 (503) 556-3713 VPN-067-99 Trojan Nuclear Plant Docket 50-344 License NPF-1 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Dear Sir:

Response to Request for Additional Information Regarding Relocation of Technical Specification Administrative Controls to the Quality Assurance Program (TAC NO. MA3635)

This letter responds to Nuclear Regulatory Commission (NRC) letter dated July 8,1999,

" Request for Additional Information [RAI] Regarding Relocation of Technical Specification Administrative Controls to the Quality Assurance Program (TAC NO. MA3635)." The NRC's RAI encompassed three questions related to the relocation of certain administrative requirements from Section 5.0 of the Trojan Technical Specifications to the Trojan Nuclear Quality Assurance Program, PGE-8010. The relocation of Trojan Technical Specification administrative controls to PGE-8010 was proposed as part of Portland General Electric Company (PGE) License Change Application (LCA) 245, which was forwarded by PGE letter VPN-034-98, dated August 27,1998, i

To assist the NRC in its review of this RAI response, Enclosure I to this letter provides a proposed Revision 23 to PGE-8010," Trojan Nuclear Quality Assurance Program," that incorporates the administrative controls that will be relocated from the Trojan Technical Specifications. The relocated text has been incorporated into a new Appendix C to PGE-8010, Revision 23. Other changes to the current PGE-8010, Revision 22, have also been incorporated into the enclosed Revision 23 to reflect modifications related to the new Appendix C. A description of each change incorporated into Revision 23 of the Trojan Nuclear Quality Assurance Program, PGE-8010, is provided as Enclosure II to this letter.

The enclosed PGE-8010, Revision 23, will be made effective concurrently with implementation of LCA 245 in accordance with the schedule consideration included in LCA 245. In the event that PGE-8010 is revised prior to the enclosed Revision 23 being made effective, editorial and/or administrative changes will be made to the enclosed PGE-8010 revision as necessary to reflect the next sequential revision number and to incorporate changes made effective since Revision 22.

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9908170209 990811 \ I PDR ADOCK 05000344 W PDR  % (

Connecting People, Power and Possibilities O' u J

VPN-067-99 '

. August i1,1999 Page 2 of 4 Enclosure III to this letter provides Table A, Revision 1, which supersedes Table A of Attachment I to PGE's August 27,1998, submittal. As requested in the NRC's RAI Question 2, the revised Table A incorporates clarifications to the descriptions of each technical specification to be relocated to the quality assurance program. For ease of review, an additional column has been added to Table A, Revision 1, to indicate for each technical specification to be relocated the

. corresponding section number in the enclosed PGE-8010, " Trojan Nuclear Quality Assurance Program," Appendix C.

The NRC's three RAI questions and PGE's response to each question are provided below.

RA11 tem 1 Technical Specification (TS) 5.5.1.1.2 states that "The Chairman ofthe Independent Review and Audit Committee shall designate Independent Safety Reviewers in writing. " Theproposed amendment eliminates this committee. Describe the revisedprocessfor designating independent reviewers and revise the relocated text accordingly.

PGE Response to RAIItem 1 Upon elimination of the Independent Review and Audit Committee, the Plant General Manager or his designee shall designate Independent Safety Reviewers in writing. The relocated Trojan Technical Specification 5.5.1.1.2 text has been revised to reflect this

- change, and is included in Enclosure I to this letter as Appendix C, Section 1.3.1.1.2, to the proposed PGE-8010, Revision 23.

RA11 tem 2 Table A ofAttachment Ito the August 27,1998, submittal describes each technical specification to be relocated to the quality assurance program. Several ofthe descriptions state that "the applicable requirements ofthis section " are being relocated. The affected relocations include TS 5.1.1, TS 5.2.1, TS 5.5.1, TS 5.5.3, TS 5. 7.1, [and] TS 5. 7.2. The descriptions should be clarified to either (1) confirm that the requirements will be relocated verbatim (by deleting,for instance, the word " applicable "), or (2) identifying the specific requirements to be relocated and changes thereto.

PGE Response to RAIItem 2 The revised Table A provided in Enclosure III to this letter incorporates clarifications to the descriptions of each technical specification to be relocated to the quality assurance program, including Trojan Technical Specifications 5.1.1,5.2.1,5.3.1,5.5.3,5.7.1, and

VPN-067-99 August 11,1999 Page 3 of 4 i

5.7.2. The clarifications are designed to either confirm that the requirements will be relocated verbatim, or identify the specific requirements to be relocated and changes thereto. The relocated text, as proposed to be incorporated into the new Appendix C to PGE-8010, Revision 23, may be reviewed in Enclosure I to this letter. To assist in this review, an additional column has been added to Table A, Revision 1, to indicate for each relocated technical specification the corresponding section number in the enclosed PGE-8010, Appendix C.

RAIItem 3 TS 5.10 (Iligh Radiation Arca) should not be relocated to the QA Program.

PGE Response to RAI Item 3 Trojan Technical Specification 5.10, High Radiation Area, will remain in Section 5 of the Trojan Technical Specifications. Section 5.10.2 will be revised to reflect the elimination of the Shift Manager position, which is encompassed by the deletion of Trojan Technical Specification Section 5.2.2 and Table 5.2.2-1 as proposed in LCA 245.

Attachment Il to PGE letter VPN-034-99, dated August 27,1998, transmitted to the NRC a copy of the Appendix A, Technical Specification, pages with proposed changes annotated, as well as a copy of the revised pages without annotations. Submitted in part to reflect the relocation of Trojan Technical Specification Section 5 to the QA Program, these annotated and revised pages previously provided to the NRC have been updated to reflect the fact that Section 5.10 will remain in the Trojan Technical Specifications. The updated annotated and revised Trojan Technical Specification pages provided in Enclosure IV to this letter supersede the corresponding annotated and revised pages previously submitted to the NRC by PGE letter VPN-034-99 on August 27,1998.

This letter is submitted under oath and affirmation as required by 10 CFR 50.30(b). If you have any questions regarding this correspondence, please contact Mr. Lanny Dusek of my staff at (503) 556-7409.

Sincerely,

.;dEj H ='M _

Stephen M. Quennoz Vice President Nuclear and Thermal Operations

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VPN-067-99

. . August 11,1999 Page 4 of 4 Enclosures c: L. H. Thonus, NRC, NRR J. B. Hickman, NRC, NRR K. C. Heck, NRC, NRR Director, NMS,NRC Region IV D. Stewart-Smith, OOE' A. Bless, OOE i

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i STATE OF OREGON, )

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) I COUNTY OF COLUMBIA )

I, S. M. Quennoz, being duly sworn, subscribe to and say that I am the Vice President Nuclear and Thermal Operations for Portland General Electric Company, the licensee herein; that I have )

full authority to execute this oath; that I have reviewed the foregoing; and that to the best of my . !

knowledge, information, and belief the statements made in it are true.

4 Date h%7 t i ,1999 l

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'S. M. Quennoz, V Vice President Nuclear and Thermal Operations j Portland General Electric Company l On this day personally appeared before me, S. M. Quennoz; to me known to be the individual who executed the foregoing instrument, and acknowledged that he signed the same as his free act.

GIVEN under my hand and seal this I t- day of Au c,rREr ,1999.

9 OFFCM SFAL CillWE.CASCAATS w m Nota $bhc in and for the State of Oregon Residing atdocums Ahe My commission expires >l.x7Mece, f

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r UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION i

In the Matter of )

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PORTLAND GENERAL ELECTRIC COMPANY ) Docket 50-344 THE CITY OF EUGENE, OREGON, AND ) License NPF-1 PACIFIC POWER & LIGHT COMPANY )

(TROJAN NUCLEAR PLANT) )

CERTIFICATE OF SERVICE 1 hereby certify that copies of the Trojan Nuclear Plant response to the Nuclear Regulatory Commission's Request for Additional Information Regarding Relocation of Technical Specification Administrative Controls to the Quality Assurance Program, dated August 11,1999, have been served on the following by hand delivery or by deposit in the United States Mail, first class, this 1Ith day of August 1999:

State of Oregon-Attn: David Stewart-Smith Oregon Office of Energy 625 Marion Street NE Salem, Oregon 97301-3742 Chairman of County Commissioners Columbia County Courthouse St. Helens, Oregon 97051 A r/

Lansin[Dusek Manager, Nuclear Regulatory Affairs On this day personally appeared before me Lansing G. Dusek, to me known to be the individual who executed the foregoing instrument, and acknowledged that he signed the same as his free act.

GIVEN under my hand and seal this 1Ith day of August 1999.

ct, v Notary P b m and for the State of Oregon e,m OmCIAL SEAL ClelM L CASCRAfD NOTARY PUBUC-OREGON cMSON Residing ato.em6f A GeueTM My commission expires 7 lan ).wo.5

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ENCLOSURE I TO VPN-067-99 PROPOSED REVISION 23 TO PGE-8010," TROJAN NUCLEAR QUALITY ASSURANCE PROGRAM" i I

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PGE-8010 PORTLAND GENERAL ELECTRIC (PGE)

NUCLEAR QUALITY ASSURANCE PROGRAM FOR TROJAN NUCLEAR PLANT l

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Revision 23 Portland General Electric Company 121 SW Salmon Street Portland, Oregon 97204 i

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I PGE-8010 PGC NUCLEAR QUALITY ASSURANCE PROGRAM FOR TROJAN NUCLEAR PLANT j 1

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Approval:

General Manager, Nuclear Oversight Date l

I Approval:

Trojan Site Executive and Plant General Manager Date 1

i Portland General Electric Company 121 SW Salmon Street Portland, Oregon 97204

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TABLE OF CONTENTS t

Pace TITLE PAGE , . . . . . . . . . . . . . . . . . . . . . . . . . . . . i APPROVAL PAGE . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 TABLE OF CONTENTS . . . . . . . . . . . . . . . . . . . . . . . . . iii j POLICY STATEMENT . . . . . . . . . . . . . . . . . . . . . . . . . iv

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LIST OF EFFECTIVE PAGES . . . . . . . . . . . . . . . . . . . . . . . Y l i

1 PROGRAM I I

1.0 ORGANIZATION . . . . . . . . . . . . . . . . . . . . 1 1-5 l 1

2.0 QUALITY ASSURANCE PROGRAM . . . . . . . . . . . . . . 2 2-2 3.0 DESIGN CONTROL . . . . . . . . . . . . . . . . . . . 3 3-2 ,

4.O PROCUREMENT DOCUMENT CONTROL . . . . . . . . . . . . . . . 4-1 5.0 INSTRUCTIONS, PROCEDURES, AND DRAWINGS . . . . . . . . . . 5-1 6.0 DOCUMENT CONTROL , . . . . . . . . . . . . . . . . . 6 6-2 7.0 CONTROL OF PURCHASED MATERIAL, EQUIPMENT AND SERVICES 7 7-2 8.0 IDENTIFICATION AND CONTRCL OF MATERIAL, PARTS, . . . . . . 8-1 AND COMPONENTS 9.0 CONTROL OF SPECIAL PROCESSES . . . . . . . . . . . . . . . 9-1 10.0 INSPECTION . . . . . . . . . . . . . . . . . . . . . . . . 10-1 11.0 TEST CONTROL . . . . . . . . . . . . . . . . . . . . . . . 11-1 12.0 CONTROL OF MEASURING AND TEST EQUIPMENT MD . . . . 12 12-2 INSTALLED INSTRUMENTATION 13.0 HANDLING, STORAGE', AND SHIPPING . . . . . . . . . . . . . . 13-1 14.0 INSPECTION, TEST, AND OPERATING STATUS . . . . . . . . . . 14-1 15.0 NONCONFORMING MATERIAL, PARTS, OR COMPONENTS . . . 15 15-2 16.0 CORRECTIVE ACTION . . . . . . . . . . . . . . . . . . . . . 16-1 17.0 QUALITY ASSURANCE RECORDS . . . . . . . . . . . . . . . . . 17-1 18.0 AUDITS . . . . . . . . . . . . . . . . . . . . . . . . . . 18-1 APPENDIX A - QUALITY ASSURANCE AND ADMINISTRATIVE . . . . A A-4 CONTROLS FOR PACKAGING RADIOACTIVE MATERIAL FOR TRANSPORT APPENDIX B - QUALITY ASSURANCE AND ADMINISTRATIVE . . . . B B-4 CONTROLS FOR THE INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)

APPENDIX C --ADDITIONAL ADMINISTRATIVE CONTROLS FOR TROJAN NUCLEAR PLANT 10 CFR 50 LICENSED ACTIVITIES . . C C-11 GLOSSARY , . . . . . . . . . . . . . . . . . . . . . . Gl Gl-5

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PORTLAND GENERAL ELECTRIC COMPANY NUCLEAR QUALITY ASSURANCE PROGRAM POLICY STATEMENT Portland General Electric Company implements a Quality Assurance (QA)

Program which directs quality-related activities at the Trojan Nuclear Plant.

This QA Program complies with Title 10, Code of. Federal Regulations, Part 50, Appendix B, " Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants."

In addition to 10 CFR 50 activities, this QA Program applies to activities covered by 10 CFR 71, Subpart H, " Quality Assurance for Packaging and Transportation of Radioactive Material," and 10 CFR 72, Subpart G, " Quality Assurance for Independent Storage of Spent Nuclear i Fuel and High-Level. Radioactive Waste." l The approval of this document commits the Portland General Electric )

Company to the requirements of the QA Program described herein and its ]

successful implementation. Portland General Electric Company personnel '

who perform quality-related functions are responsible for complying with the requirements of this QA Program.

l Changes to the QA Program must be documented and approved by the General Manager, Nuclear Oversight and the Trojan Site Executive and Plant General Manager.

Trojan Site Executive and Plant-General Manager Portland General Electric Company (Date)

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NUCLEAR QUALITY ASSURANCE PROGRAM i l

l List of Effective Paces Pace Revision i (title page) 23 11 and lii 23 iv 20 l v 23 1-1 and 1-2 23 1-3 21 1-4 and 1-5 23 2-1 19 2-2 23 3-1 and 3-2 16 j 4-1 21 5-1 16 6-1 and 6-2 16 7-1 23 7-2 16 8-1 16 9-1 16 l 10-1 16 11-1 16 12-1 and 12-2 16 13-1 16 14-1 16 15-1 and 15-2 16 16-1 16 17-1 16 18-1 23 A-1 16 A-2 and A-3 17 A-4 23 B-1 19 B-2 21 B-3 23 B-4 21 C-1 through C-11 23 Gl-1 21 Gl-2 16 Gl-3 through Gl-5 23

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1.0 ORGANIZATION 1.1 PURPOSE The Portland' General Electric Company (PGE or Company) executive management is responsible for the safety of the Trojan Nuclear Plant (TNP) and the Trojan Independent Spent Fuel Storage Installation (ISFSI). The Nuclear Quality Assurance Program (hereafter referred to as the QA Program) deals specifically with management of quality-related activities pertaining to the operation, maintenance, design, modification, and decommissioning of the TNP (until the 10 CFR 50 license is terminated) and the design, fabrication, construction, testing, operation, modification, and decommissioning of the ISFSI.

This chapter describes the functions, authorities, responsibilities, and interfaces of the PGE management organizations involved with the TNP and the ISFSI.

1.2 ORGANIZATION The onsite management organization (General Manager and above) for control of the TNP and the ISFSI is shown in Figure 1.0-1.

1.2.1 Troian Site Executive and Plant General Manaaer The Trojan Site Executive and Plant General Manager, hereafter referred to as the Plant General Manager reports to a corporate executive with responsibility for nuclear activities. The Plant General Manager has overall authority and responsibility for operations, maintenance, radiation protection, and for execution of this QA Program to ensure safety.

The Manager, Operations; Manager, Maintenance; Manager, Personnel / Radiation Protection, and Manager, ISFSI, report to the Plant General Manager. In addition, the General Manager, Nuclear Oversight; 1-1 Revision 23

the General Manager, Engineering / Decommissioning; and the General Manager, Plant Support and Technical Functions report to the Plant General Manager and their responsibilities are addressed in the following subsections. The Plant General Manager has delegated to the Nuclear Division managers responsibility for implementation of this QA Program.

The ISFSI Safety Review Committee (ISRC) reports to him, and he is responsible for evaluating recommendations of the ISRC and assuring that responsible management acts on recommendations which are to be implemented.

1.2.2 ISRC The ISRC performs review functions required by the ISFSI Safety Analysis Report. Additionally, the ISRC is responsible for conducting a biennial audit of the Nuclear Oversight Department.

The results of the biennial audit of the Nuclear Oversight Department I

and audits of the ISRC are forwarded to the Plant General Manager.  !

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1.2.2.1 Nuclear Oversicht Denartment The Nuclear Oversight Department is under the direction of the General

' Manager, Nuclear Oversight. This department is independent of other departments performing quality-related activities.

To control deviations from QA Program requirements, the Nuclear oversight Department has the authority and responsibility to initiate j stop work orders, as necessary, for any condition adverse to quality i that has occurred or is developing.

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l 1.2.2.1.1 General Manacer. Nuclear Oversicht The General Manager, Nuclear Oversight, together with the Plant General Manager, is responsible for approving revisions to the QA Program. The General Manager, Nuclear Oversight, has the authority and independence to identify quality problems; initiate, recommend, or provide solutions to quality problems through designated channels; and verify implementation of solutions to quality problems. The General Manager, ,

1 Nuclear Oversight, directs the Nuclear Oversight staff in the implementation of the overall QA Program, including contractor QA involvement.

1.2.2.1.2 Oualification Recuirements for the General Manaaer. Nuclear Oversicht The General Manager, Nuclear Oversight must be knowledgeable of the QA Program and 10 CFR 50, Appendix B, and maintain up-to-date knowledge of applicable regulatory guides, codes, and standards related to quality assurance.

The General Manager, Nuclear Oversight, must meet the following qualifications:

Eight years of experience in the field of quality assurance or equivalent number of years of nuclear plant experience in a supervisory position or a combination of the two. Graduation from a four-year accredited engineering or science college or university may be substituted for four years of this experience. At least one year of this experience shall be nuclear power plant experience in the implementation of the quality assurance program.

1.2.2.2 General Manaaer. Encineerina/Decommissionino The General Manager, Engineering / Decommissioning, has primary responsibility for direction and coordination of decommissioning, design i i

engineering, and for design control to ensure safety and reliability.

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1.2.2.3 General Manaaer. Plant Sunnert and Technical Functions The General Manager, Plant Support and Technical Functions, has been l delegated responsibility for the direction and coordination of nuclear regulation and for training, purchasing, and the overall administration and maintenance of records.

1.2.2.4 Plant Staff The plant organization described in procedures details the functional areas and responsibilities, qualifications, and training required for personnel performing quality-related activities.

1.2.3 Cornorate Executives Resnonsible for Sunnort Orcanizations Corporate executives with responsibility for nuclear support activities shall assure that.their assigned managers implement the QA Program, as applicable.

1.2.3.1 Manacers of Nuclear Sunnort Oraanizations l

Managers of nuclear support organizations that perform quality-related ,

activities, such as records control services, are responsible for ensuring that procedures that implement the applicable portions of the OA Program are established, implemented, and maintained.

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TROJAN SITE EXECUTIVE AND PLANT GENERAL MANAGER I

ISFSl SAFETY REVIEW COMMITTEE i

GENERAL MANAGER GENERAL MANAGER GENERAL MANAGER NUCLEAR OVERSIGHT PLANT SUPPORT AND ENGINEERING /

TECHNICAL FUNCTIONS DECOMMISSIONING l

Figure 1.0-1 Trojan On-Site Management Organization l

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2.0 QUALITY ASSURANCE PROGRAM 2.1 PURPOSE This chapter describes the QA Program for the TNP and the ISFSI, and defines the applicability of the QA Program including training necessary to assure its proper implementation and effectiveness.

2.2 OUALITY ASSURANCE PROGRAM 2.2.1 General This QA Program is app 34 cable to quality-related items as defined in the Glossary of this program.

Safety-related structures, systems, and components are described in a ,

i controlled document.

Generally, the action indicated in the text is applicable to l

safety-related items and activities and will be applied to the other j quality-related areas, as necessary, to assure an appropriate level of quality, in relation to the complexity of work to be performed, the importance to safety and the environment, and the importance of an item's usage.

The portions of this 10 CFR 50, Appendix B, QA Program which are applicable to Packaging Radioactive Material for Transport are described in Appendix A and those applicable to the ISFSI are described in Appendix B of this program. The portions of this QA Program which are applicable to the remaining nonsafety-related, but quality-related areas, are described in a controlled document. I The QA Program provides requirements for obtaining objective evidence that all quality-related components, systems, and structures are in conformance with the design specifications, test specifications, and  !

criteria established for the plant and its components. j 2-1 Revision 19

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2.2.2 Oualitv-Related Procedures Procedures cover quality-related aspects of administration and control.

The procedures document the policies and instructiors necessary to fulfill the intent of the QA Program. They also include standard forms, lists, and checkoffs used in documenting the audits, QA surveillances, inspections, certifications, and reviews.

Where appropriate, the procedures assure that activities affecting quality are performed under suitably controlled conditions. Controlled conditions include the use of appropriate equipment, suitable environmental conditions for performing the activity, and adequate cleanliness, handling, and storage to assure that required prerequisites for the given activity have been satisfied.

2.2.3 Trainino The' training program provides for indoctrination and training of personnel performing quality-related activities as necessary to assure that suitable proficiency is achieved and maintained.

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3.O DESIGN CONTROL 3.1 PURPOSE This chapter describes controls to assure that design requirements affecting quality-related items are correctly translated into design documents.

3.2 GENERAL The' design control functions are defined in written and approved procedures that delineate authority and responsibility of personnel involved in the preparation, review, and approval of design documents.

These procedures identify and control design interfaces and coordinate design activities among participating design organizations.

3.3 DESIGN PROCESS Quality standards are included or referenced in design documents. Any exceptions and/or deviations from specified design quality standards are documented and controlled.

Design documents are based upon the appropriate design bases, safety analysis, design regulations, codes and standards, and licensing documents.

The materials, parts, equipment, and processes relected and specified by design documents are reviewed to assure that they are suitable for the intended application.

3.4 DESIGN VERIFICATION Design control measures shall provide for verifying or checking the adequacy of design.

The verifying or checking process shall be performed by individuals or groups other than those who performed the original design, but who may be from the same organization.

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Where a test program is used to verify the adequacy of a specific design feature in lieu of other. verifying or checking processes, it shall include suitable qualification' testing of a prototype unit under the most. adverse design conditions.

3.5 CHANGE CONTROL Design changes, including field changes, shall be subject to design control measures commensurate with those applied to the original design and shall be approved by Engineering.

Procedures provide for notification of personnel of design changes and/or modifications which may affect the performance of their duties ~ .

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4.O PROCUREMENT DOCUMENT CONTROL 4.1 ' PURPOSE l This chapter. describes the preparation, review, approval, and control of procurement documents pertaining to quality-related items and services to assure the inclusion of applicable quality assurance requirements.

4.2 PROctinEMENT DOCUMENT CONTROL PROGRAM Applicable procurement requirements for quality-related items and services are specified or referenced in procurement documents.

Procurement requisitions and supplements thereto are reviewed for adequacy by independent personnel knowledgeable of QA practices and concepts.  ;

Procurement.documtats are reviewed and approved by a manager or his designee.  !

I Approved procurement documents are submitted to the purchasing manager or designee for procurement.

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5.0 INSTRUCTIONS,. PROCEDURES, AND DRAWINGS 5.1 PURPOSE This chapter describes measures which will assure that activities affecting quality-related items and services are delineated, controlled, implemented, and accomplished through utilization of approved and documented instructions, procedures, or drawings.

5.2 INSTRUCTIONS. PRocRnURES. AND DRAWINGS Activities affecting quality shall be accomplished in accordance with approved and documented instructions, procedures, or drawings.

Instructions and procedures that describe activities affecting quality j include the necessary' limits and tolerances on material, equipment, l processes, and specifications for activities associated with quality-related items and services. Instructions and procedures also prescribe special controls, processes, test equipment, tools'and skills to attain the required quality, and requirements for documentation and/or verification of quality by inspection and test. Also included are appropriate qualitative-and quantitative acceptance criteria for determining that important activities have been satisfactorily l accomplished.

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l 6.O DOCUMENT CONTROL 6.1 PURPOSE This chapter describes methods for review, approval, distribution, and j control of documents and changes thereto which affect quality-related  ;

items.

6.2 DOCUMENT CONTROL PROGRAM Written procedures are available which provide for the preparation, review, and approval of documents requiring control.

These procedures identify the appropriate qualified individuals or groups responsible for determining that appropriate quantitative and qualitative criteria are included in documents describing quality-related activities and for verifying that these criteria have been satisfactorily met. Procedures also require that documents are approved for implementation by appropriate levels of management and changes to the documents are reviewed and approved by the same organizations as the original unless another responsible organization is designated by the governing procedure. Approved changes are included in controlled documents prior to implementation of the change.

Procedures shall ensure that documents are distributed in a timely manner to appropriate locations and are available for use by personnel performing prescribed activities.

Master lists or equivalent document control systems are established to l identify the current revision of controlled documents. These lists are available for use by cognizant personnel to preclude the use of superseded documents, procedures dealing with corrective action shall be reviewed by the Nuclear Oversight Department. Other quality-related procedures, including contractor procedures to be used onsite for quality-related work, are reviewed by personnel knowledgeable of OA practices and concepts.

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Temporary changes to quality-related documents may be made and implemented if a procedural method has been established to control the review and approval of the temporary changes.

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r 7.0 CONTROL OF PURCHASED MATERIAL, EQUIPMENT, AND SERVICES 7.1 PURPOSE This chapter describes the measures for selection and evaluation of procurement sources for quality-related items and services and for verification activities to assure that specified requirements are met.

7.2 OUALITY ASSURANCE PROGRAM EVALUATION PGE purchase orders / contracts for quality-related items or services are placed with contractors, suppliers, and service organizations who have been evaluated by the Nuclear Oversight Department for the applicable quality system level. Procedures govern the selection of procurement sources.

The effectiveness of the control of quality by contractors and suppliers shall be assessed at intervals consistent with the importance, complexity, and quantity of the product or service.

Quality-related items and services procured from a contractor, supplier, or service organization for which a quality assurance program is required but has not been reviewed or accepted may be utilized by PGE with the specific written approval of the Nuclear Oversight Department.

Appropriate additional controls such as source inspection, special receipt instructions, QA surveillance, and testing are imposed when this option is utilized.

7.2.1 Source Insnection. Survev. and Audit of Contractors and Sunoliers of Qualitv-Related Items l

The Nuclear Oversight Department is responsible for assuring source inspections, surveys, or audits are performed as necessary.

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7.3 RECEIPT INSPECTION 1

Receipt inspection of quality-related items is performed to assure that the. requirements of the procurement documents have been met.

Accepted items are appropriately marked, removed from the inspection area, and located in a controlled storage area or issued for use.

Documentary evidence that items conform to the procurement document requirements shall be available at the plant prior to installation or use.

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r 8.0 IDENTIFICATION AND CONTROL OF MATERIAL, PARTS, AND COMPONENTS B'1

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This chapter describes measures for the identification and control of quality-related items to assure they can be traced to associated documents and to prevent the use of incorrect or defective material,

' parts,.and components.

s.2 newunAL Quality-related~ items and subassemblies are identified (on the item or on records traceable to the item) in such a manner as to allow traceability to the appropriate quality documentation. The location and method of identification are selected to prevent affecting the function or quality of the item.

When an item is subdivided, required identification markings will be transferred to each part or reflected in the records.

When several parts are joined in fabrication, a list of parts and corresponding identification documents will accompany the assembly, as necessary. This documentation'will include, as applicable, heat, lot, serial or part numbers, material certifications, weld or braze qualifications, test reports, NDE records,' fabric 3 tion travelers, and other. documentation to provide the bases for determining the acceptability of the assembly and its component parts.

Proper identification of materials, parts, and components is verified and documented at receipt inspection or prior to release for fabrication, assembly, shipping, or installatien.

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h l-9.0 CONTROL OF SPECIAL PROCESSES 9.1 PURPOSE 1

'This chapter describes t'he nethods for the control of special processes relative to quality-related items.

9,2 SPECIAL PROPERE CONTROL PROGRAM Cognizant managers are responsible for ensuring:

a. Procedures,_ equipment, and personnel connected with special Processes are qualified in'accordance with applicable codes, standards, and specifications,

b. Special processes are performed by qualified personnel and accomplished and documented in accordance with the approved procedure.

c. Qualification records of procedures, equipment, and personnel associated with special processes are prepared and retained.

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10.0 INSPECTION r.

10.1 PURDOSE i

This chapter establishes and describes the methods for the inspection of quality-related items and activities to assure their acceptability.

10.2 GENERAL l

Inspections are performed in accordance with written, approved inspection plans and/or-inspection procedures, to verify that quality-related items and processes conform to predetermined quality requirements.

Inspection programs are implemented through procedures which provide for

! preparation, review, and approval of inspection plans and procedures and provide for establishing mandatory hold points for witness by inspection. These procedures also define the minimum requirements for inspection plans. Inspection plans are approved by the responsible

. plant supervisor.

Inspections shall be performed by individuals other than those who l performed or directly'aupervised the activity being inspected.

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If direct inspection of items is impossible-or disadvantageous, indirect control by monitoring processing methods, equipment, and personnel shall be provided. Both inspection and process monitoring shall be provided when control is inadequate without both.

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11.0 TEST CONTROL l l

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-11.1 PURPOSE This chapter describes the controls for testing required to demonstrate satisfactory performance of quality-related items. Tests within the

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scope of this chapter. include periodic operational,-instrumentation, and engineering tests' as well as tests required by modifications,

-maintenance, or significant changes in operating procedures.

These tests are performed to verify that an item will perform satisfactorily in service.

11.2 ' TEST CONTROL PROGRAM 11.2.1 General The work package for maintenance or modifications to quality-related items identify those installation checks or tests necessary to demonstrate satisfactory performance of the affected equipment.

Installation checks are performed during the installation process to j verify that items have been correctly installed and will-function properly.

Each test procedure is prepared and reviewed in accordance with applicable design documents,. codes, and specifications. l The procedures shall include provisions for assuring that all prerequisites for the given test have been met, that adequate test j l

instrumentation is available and used, and that the test is performed i under suitable environmental conditions.

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11.2.2 Test Documentation Test results are documented, evaluated, and their acceptability determined by qualified personnel, 11-1 Revision 16

F 12.0 CONTROL OF MEASURING AND TEST EQUIPMENT AND INSTALLED INSTRUMENTATION l

l 12.1 PURPOSE This chapter describes the provisions for the control of portable measuring and testing equipment and installed plant instrumentation utilized in the inspection, testing, and monitoring of quality-related items.

12.2 MEASURING AND TEST EQUIPMENT AND INSTATTrn INSTRUMENTATION CONTROL PROGRAM 12.2.1 General The control of portable measuring and test equipment and installed instrumentation is implemented by specific procedures which describe accuracy requirements, calibration techniques, recall frequency requirements,.and calibration control.

Instruments, tools, gages, fixtures, and standards used in quantitative measurement are uniquely identified, indicate calibration status, appear

'l on a controlled list, are issued for use through a controlled issuance program, and are included in the calibration program.

12.2.2 Calibration Standards and Traceability Comparison stendards used for calibrations and adjustment are traceable to nationally recognized standards wherever possible. If not possible, the basis for calibration is documented.

Instruments used as standards are sent to approved calibration facilities for calibration at intervals consistent with the instrument manufacturer's guaranteed repeatability and the user's experience.

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12.2.3 Defective or Out-of-Calibration Measurina and Test Eculoment and Installed Inntrumentation When portable measuring or test equipment or installed instrumentation is found to be out of calibration or when its repair or replacement is required, an investigation is conducted and documented to determine the validity of previous inspection or test results and to determine the acceptability of those items previously inspected or tested, I

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13.0 HANDLING, STORAGE, AND SHIPPING

'13.1 PURPOSE This' chapter describes measures for the control of the handling, storage, shipping, cleaning, and preservation of quality-related items to preclude' damage, loss, or deterioration.

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13.2' HANDf.TNG . STORAGE. SHIPPING, r'T.E ANING . AND pnyc ERVATION PROGRAM 13.2.1 General On receipt of quality-related items, compliance with special requirements for protective environments is verified and documented by receipt inspection personnel. )

I-Items are stored in a manner to protect against damage, degradation, or misuse.

Quality-related items are handled, stored, preserved, or protected in j accordance with'specified codes and standards.  !

I 13.2.2 unndlina of Oualitv-Related Items

, Procedures'or instructions will be used to ensure that handling equipment, cranes, and rigging are examined and tested prior to  ;

performing critical lifts of quality-related items.

13.2.3 Mandlina. Storace, and Shinnina of Radioactive Materials Radiation protection personnel are responsible for establishing administrative controls and requirements for handling, storing, and I shipping radioactive materials. These requirements are established in plant procedures.

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14.0 INSPECTION, TEST, AND OPERATING STATUS 14.1 PURPOSE l This chapter provides measures for the identification of the inspection,

. test, and operating status of quality-related items to preclude bypassing of requirements and i'tadvertent operation.

14.2 TNEPECTION. TEST. AND OPERATING STATUS PROGRAM 14.2.1 Insnection and Test Status j l

Procedures are established to indicate the status of inspections and tests performed on quality-related items.

Operations personnel are responsible for maintaining sufficient I knowledge of tests or inspections in progress to control plant activities.

If a required test, inspection, or other critical operation is to be bypassed, it is documented to provide appropriate controls in accordance with procedures.

14.2.2 Oneratino Status The operating status of systems, structures, and components undergoing maintenance, modification, or which have nonconformances, is identified using tags, if appropriate, under the direction of operations personnel to prevent inadvertent operation. Prior to the removal from service of operating equipment or system, permission to change status is given and documented in accordance with procedures to assure.that the removal will not have an adverse effect on plant safety.

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f 15.0 NONCONFORMING MATERIAL, PARTS, OR COMPONENTS

>1E.1 PURPOSE l

This chapter describes measures'for documentation, control, and disposition of nonconforming quality-related items to prevent their inadvertent use or installation.

l l 15.2 NONCONFORMING MATERIAL CONTROL PROGRAM i

15'.2.1 General' Items that deviate from approved specifications, codes, drawings, or-other applicable ~ documents are considered as nonconforming.

Procedures govern the use of nonconformance reports for identification, control, disposition'of nonconforming items, and notification of affected organizations.

Unless such controls are not feasible, nonconforming items are-identified with appropriate tago and segregated to indicate their unacceptable status until the nonconformance is properly dispositioned.

If this is not feasible, other methods are established to identify and

. control the nonconforming items.

15.2.2 Work Packmae

'A work package may be used in lieu of a nonconformance report in accordance with plant procedures when nonconforming items are identified which can be restored to the original design requirements under a

" rework" disposition.

15.2.3 Nonconformance Renort Management reviews and approves nonconformance report dispositions.

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"Use as is" or a modify" dispositions require the review and approval of .

1 Engineering.

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i Tags associated with a nonconformance report are removed only by authorized personnel.

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l 16.0 CORRECTIVE ACTION 16.1 PURPOSE This chapter describes the corrective action measures to assure that conditions adverse to quality are identified, evaluated, and corrected.

For significant conditions adverse to quality, corrective action is taken to preclude repetition.

16.2 CORRECTIVE ACTION PROGRAM Procedures govern the use of nonconformance reports to assure that conditions adverse to quality are identified and corrected in a timely 1 1

manner.

Any individual has the authority and responsibility to report a condition adverse to quality to their manager or supervisor who will assure that it is or has been documented on a nonconformance report.

Nonconformance reports documenting significant conditions adverse to quality require determination of cause and corrective actions taken to preclude repetition.

Copies of nonconformance reports which identify significant conditions j adverse to quality are distributed to appropriate levels of management for information and review.

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17.0 QUALITY ASSURANCE RECORDS 17.1 PURPOSE This chapter describes measures for the identification, retention, and retrievability'of records which' furnish documentary evidence of the quality of items or activities affecting quality.

17.2 OUALITY ASSURANCE RECORDS CONTROL PROGRAM i

Records should be_ identifiable to specific systems, structures, and components, when applicable.  !

l Documents which are designated as quality assurance records shall be legible, accurate, and completed as appropriate for the work l accomplished. l l

Records are indexed, including as a minimum retention times and location i

of the records within the record system, to provide for retrieval ]

1 without undue delay. '

Quality assurance records are ultimately filed and maintained at a Permanent Records Storage Facility. )

Prior to final. transmittal of quality assurance records to permanent storage, the originating organization will be responsible for maintaining quality assurance record controls.

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r 18.0 AUDITS l

18.1 PURPOSE l

l This chapter describes the audit program utilized to verify the implementation, adequacy, and effectiveness of the QA Program.

18.2 AUDIT / SURVEILLANCE PROGRAM 18.2.1 General The Nuclear Oversight Department has overall responsibility for performing planned and periodic internal and external audits. In addition, the Nuclear Oversight Department performs QA surveillances of selected quality-related activities.

Audit schedules are established to meet applicable regulatory requirements and are based on the safety importance of the activities to be auditad.

Audits shall be performed in accordance with written procedures using a check list or an annotated procedure which details the areas to be evaluated.

Audit results shall be documented. These results shall be reviewed by management having responsibility in the area audited.

Followup action, including reaudit of deficient areas, chall be taken where indicated.

18.2.2 Audit Personnel Auditors are appropriately trained to assure competence for performing the required audits. Audit team personnel shall be independent of the activities being audited.

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APPENDIX A ]

QUALITY ASSURANCE AND ADMINISTRATIVE CONTROLS FOR PACKAGING RADIOACTIVE MATERIAL FOR TRANSPORT i

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e APPENDIX A l

QUALITY ASSURANCE AND ADMINISTRATIVE CONTROLS FOR PACKAGING RADIOACTIVE MATERIAL FOR TRANSPORT The Nuclear Quality Assurance Program (QA Program) assures that the requirements for packaging of radioactive material for transport as specified in 10 CFR 71 and the quality assurance criteria for shipping packages for radioactive material are satisfied. The QA Program will assure that waste materials intended for disposal at a land disposal facility are properly classified, identified, and documented as required by 10 CFR 20 and 10 CFR 61.55,'61.56, and 61.57. Activities involving the receipt and shipment of Type A packages under the requirements of 49 CFR 172-173 are prescribed in written procedures, instructions, or drawings.

Implementation of the QA Program elements applicable to the design, fabrication, and use of packaging _for radioactive material is under the management control of the General Manager, Trojan Plant.

Procedures implement the QA Program elements applicable to the design, fabrication, and use of packaging for radioactive material.

The chapters of the QA Program applicable to Packaging Radioactive Materials for Transport activities are described and modified below.

chanter (s) 1.0 and 2.0 Fully applies in' addition to Section a. of this appendix.

3.0 Fully applies.

4.0 Fully applies in addition to Section b. of this appendix.

5.0 Fully applies.

6.0 Fully applies.

7.0 Fully applies.

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chanter (s) 0.0 Fully applies.

9.0 Fully applies.

10.0 Fully applies.

11.0 Fully applies.

12.0 Fully applies.

13.0 Fully applies.

14.0 Fully applies.

15.0 Fully applies.

16.0 Fully applies.

17.0 Fully applies in addition to Section c. of this appendix.

18.0 Fully applies.

a. OA Program l

Controls are established over activities affecting the quality of materials and components as necessary to ensure conformance to the approved design of each individual package used for the shipment of I l

radioactive material. QA requirements and procedures are based on the following considerations concerning the complexity and proposed use of the package and its components.

(1) The impact of malfunction or failure of the item to safety; A-3 Revision 17 .

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(2) The design and fabrication complexity or uniqueness of the item; (3) The need for special controls and QA surveillance over processes j and equipment; (4) The degree to which functional compliance can be demonstrated by inspection or test; and l

(5) The quality history and degree of standardization of the item.

b. Procurement Document control - Measures are established to assure that the applicable requirements of 10 CFR 71 are included or referenced in l 1

documents for procurement of materials, equipment, and services for the design, fabrication, and use of packaging for radioactive material, and that packages and procedures for use of these packages have been authorized by the NRC and documented in the NRC Certificate of Compliance. l l

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c. OA Records '

In addition to the records required by the definition of Quality Assurance Records in the Glossary of this QA Program, the records must include the instructions, procedures, and drawings required by 10 CFR 71.111 and must include closely related records such as required j qualifications of personnel, procedures, and equipment. The records must include the procedures which establish the records retention program. These records shall be retained for three years beyond the date when PGE last engages in packaging and shipping radioactive materials controlled by this appendix. If any portion of the written procedures or instructions is superseded, PGE shall retain the superseded material for three years after it is superseded.

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APPENDIX B-QUALITY ASSURANCE AND ADMINISTRATIVE CONTROLS FOR THE INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI) l i

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APPENDIX B QUALITY ASSURANCE AND ADMINISTRATIVE CONTROLS FOR THE INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)

The Nuclear Quality Assurance Program (QA Program) assures that the quality assurance requirements for the Trojan ISFSI as specified in 10 CFR 72 are satisfied. The requirements of this appendix apply to the design, fabrication, construction, testing, operation,-modification, and decommissioning of the structures, systems, and components of the ISFSI that are important to safety. These requirements also apply to the I managerial and administrative controls used to ensure safe operation of the ISFSI.

Implementation of the QA Program elements applicable to the'ISFSI is under the management control of the General Manager, Trojan Plant.

The chapters of the QA Program applicable to the ISFSI are described and modified below, chanter (s) 1.0- Applies in addition to Sections a. and b. of this appendix.

2.0 Fully applies in addition to Section a. of this appendix.

3.0 Fully applies in addition to Section c. of this appendix.

-4.0 Fully applies in addition to Section d. of this appendix. 1 5.0 Fully applies.

6.0 Fully applies, j 7.0 Fully applies.

8.0 Fully applies.

9.0 Fully applies.

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11.0 Fully applies in addition to Section e. of this appendix. i 12.0 ' Fully applies, i 13.0 Fully applies.

14.0 Fully applies.

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16.0 Fully applies.

17.0'  ; Fully applies in addition to Section f of this appendix.

18.0 Fully applies.

a. -QA Proaram - Controls are established over activities affecting the quality of materials and components as necessary to ensure conformance to the approved design of the ISFSI. QA requirements and procedures are based on the following considerations concerning the complexity'and proposed use of the ISFSI structures, systems, and components.

(1) The impact of malfunction or failure of the item on safety; (2) The design and fabrication complexity or uniqueness of the item; (3) The need for speciali controls and QA surveillance over processes and equipment; (4) The degree-to which functional compliance can be demonstrated by inspection or test; and (5) The quality history and degree of standardization of the item.

b. Organization - The ISFSI Safety Review Committee (ISRC) assesses the i adequacy of the QA Program's implementation biennially.

- c. Desion control - Measures are established to assure that proposed design changes are evaluated to determine if a change to the ISFSI license.is required. Changes to conditions specified in the ISFSI license require NRC approval,

d. Procurement Document control - Measures are established to assure that, to the extent necessary, contractors or subcontractors provide a quality assurance program consistent with the applicable provisions of~10 CFR 72, Subpart G.

e. Igst control - Measures are established to assure that test procedures incorporate the applicable requirements of 10 CFR 72 and the acceptance limits contained in the ISFSI license, i

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, f. OA Records - In addition to the records required by the definition of Quality Assurance Records in the Glossary of this QA Program, ISFSI ,

, records required by 10 CFR 72.30, 72.48, 72.72, 72.80, 72.154, and j l

72.174 shall be maintained. ISFSI records pertaining to the design, j fabrication, erection, testing, maintenance, and use of structures, i systems, and components important to safety shall be maintained by or under the control of PGE until the NRC terminates the 10 CFR 72 license.

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APPENDIX C ADDITIONAL ADMINISTRATIVE CONTROLS FOR TROJAN NUCLEAR PLANT 10 CFR 50 LICENSED ACTIVITIES l

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APPENDIX C ADDITIONAL ADMINISTRATIVE CONTROLS FOR l TROJAN NUCLEAR PLANT (TNP) 10 CFR 50 LICENSED ACTIVITIES l

This Appendix C contains additional Administrative Controls which are applicable to TNP activities until the 10 CFR 50 License is terminated.

It is noted that other portions of this 10 CFR 50 QA Program are applicable to the 10 CFR 72 Licensed ISFSI. When the 10 CFR 50 License is terminated, this QA Program, Appendix C, shall become null and void and may be removed from this QA Program as a change that does not reduce the commitments in the QA Program description previously accepted by the NRC.

These administrative controls were initially relocated from the TNP Technical Specifications, Appendix A, Section 5.0, and from TNP License condition 2.C (8) into this QA Program following removal of all of the spent fuel from the Spent Fuel Pool and its placement in the ISFSI. As a result of this, these Additional Administrative Controls apply, in some cases, to both quality-related and non-quality-related activities.

During the remaining duration of the TNP 10 CFR 50 License, changes to this OA Program, Appendix C, shall be processed in accordance with 10 CFR 50.54(a) requirements.

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i 1.0 ADDITIONAL ADMINISTRATIVE CONTROLS FOR TNP 10 CFR 50 LICENSED ACTIVITIES 1.1 Responsibility The Trojan Site Executive and Plant General Manager (hereafter called the Plant General Manager), shall have overall responsibility for the facility and shall delegate in writing the succession to this responsibility during his absence.

1.2 General Organizational Requirements Facility and corporate organizations shall be established for the facility staff and corporate management, respectively.

a. Lines of authority, responsibility, and communication shall be ,

defined and established throughout highest management levels, intermediate levels, and all operating organization positions.

These relationships shall be documented and updated, as appropriate, in organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation;

b. The individuals who carry out radiation protection functions or perform quality assurance functions may report to the appropriate line manager; however, these individuals shall have sufficient organizational freedom to ensure the ability to perform their assigned functions.

1.3 Reviews and Audits 1.3.1 Indeoendent safety Review Independent Safety Reviews shall be a thorough review by a qualified Independent Safety Reviewer. Persons performing these reviews shall be knowledgeable in the subject area being reviewed.

These independent Safety Reviews are completed prior to implementation of proposed activities.

1.3.1.1 Composition 1.3.1.1.1 Reviewers Independent safety reviewers shall be an individual not having ,

direct responsibility for the performance of the activities under review, but who may be from the same functionally cognizant organization as the individual or group performing the original work.

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i 1.3.1.1.2 Qualifications The Independent Safety Reviewers shall have five years of professional level experience and either a Bachelor's Degree in Engineering or the Physical Sciences or equivalent in accordance with ANSI /ANS-3.1-1981.

The Plant General Manager or designee shall designate the Independent Safety Reviewers in writing.

1.3.1.1.3 Responsibilities The following subjects shall be independently reviewed by a qualified Independent Safety Reviewer: j l

a. Safety evaluations for changes in the facility as described j in the Safety Analysis Report, changes in procedures as '

described in the Safety Analysis Report, and tests or experiments not described in the Safety Analysis Report to .

verify that such actions do not involve a change to the  !

Technical Specifications or constitute an unreviewed safety question as defined in 10 CFR 50.59. j

b. Proposed changes to the programs required by Section 1.4.2, l

'to verify such changes do not involve a change to the l Technical Specifications and will not constitute an unreviewed safety question as defined in 10 CFR 50.59.

1.3.2 Records Written records of reviews and audits shall be maintained. As a minimum these records shall include: i

a. Results of the activities conducted under the provisions of Section 1.3.1;

b. Recommendations to the management of the organization being audited; and

c. Documentation of the reviews conducted per Section 1.3.1.1.3.

1.4 Procedures, Programs, and Manuals 1

1.4.1 Procedures 1.4.1.1 Scope Written procedures shall be established, implemented, and maintained covering the following activities:

a. Quality assurance for radiological effluent and environmental monitoring;

b. Fire protection program implementation; and

c. All programs specified in Section 1.4.2.

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1.4.1.2 Review and Approval ,

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Each procedure of Section 1.4.1.1, and changes thereto, shall I be independently reviewed in accordance with established  !

administrative procedures and approved by the Plant General l Manager or his designee prior to implementation.

1.4.1.3 Temporary Changes Temporary changes to procedures of Section 1.4.1.1 may be made provided:

a. The intent of the existing procedure is not altered; l

b. The change is approved by two members of the facility i management staff; and I

c. The change is documented, reviewed and approved by the responsible manager, in accordance with approved '

administrative procedures within 14 days of implementation.

1.4.2 Proarams and Manuals  !

The following programs shall be established, implemented, and maintained.

1.4.2.1 Radiation Protection Program Frocedures for personnel radiation protection shall be prepared .

consistent with the requirements of 10 CFR 20 and shall be I approved, maintained, and adhered to for all operations involving personnel radiation exposure, l.4.2.2 Process Control Program (PCP)

The PCP shall contain the current formulas, sampling, analyses, tests, and determinations to be made to ensure that processing and packaging of solid radioactive wastes will be accomplished to ensure compliance with 10 CFR 20, 10 CFR 61, and 10 CFR 71; state regulations; burial ground requirements; and other requirements governing the disposal of solid radioactive waste.

Licensee initiated changes to the PCP:

a. Shall be documented and records of reviews performed shall be retained. This documentation shall contain:

1. sufficient information to support the change (s) and appropriate analyses or evaluations justifying the change (s ) ; and

2. a determination that the change (s) maintain the overall conformance of the solidified waste product to the existing requirements of Federal, State, or other applicable regulations.

b. Shall be effective after review and approval by an Independent Safety Reviewer and the approval of the Plant General Manager or designee.

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J 1.4.2.3 Offsite Dose Calculation Manual (ODCM) 1.4.2.3.1 Content j a. The ODCM shall contain the methodology and parameters used )

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in the calculation of off-site doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the Radiological Environmental Monitoring Program; and

b. The ODCM shall also contain the Radioactive Effluent Controls Program and the Radiological Environmental Monitoring Program required by Sections 1.4.2.4 and 1.4.2.5 respectively, and descriptions of the information that should be included in the Annual Radiological Environmental Monitoring Report required by Section 1.5.1.2.

1.4.2.3.2 Licensee initiated changes to the ODCM:

a. Shall be documented and records of reviews performed shall be retained. This documentation shall contain:

1. sufficient information to support the change (s) j together with the appropriate analyses or evaluations i justifying the change (s); and l

2. a determination that the change (s) maintain the levels of radioactive effluent control required by 10 CFR 20.1302, and 40 CFR 190, and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations;

b. Shall become effective after review and approval by an Independent Safety Reviewer and the approval of the Plant General Manager or designee; and

c. Shall be submitted to the NRC in the form of a complete, ,

legible copy of the entire ODCM as a part of or concurrent i with the Radiological Environmental Monitoring Report for l the period of the report in which any change in the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i .e. , month and year) the change was implemented.

1.4.2.4 Radioactive Effluent Controls Program This program provides controls for radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable. The program shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:  ;

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a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM;

b. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areau, conforming to 10 CFR 20, Appendix B;

c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM;

d. Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least quarterly;

e. Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the site boundary conforming to the dose associated with 10 CFR 20, Appendix B;

f. Limitations on the annual dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190;

g. Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released to unrestricted areas conforming to 10 CFR 50, Appendix I;

h. Limitations on the operability and use of eff.?uent treatment systems to ensure appropriate portions of these systems are used to reduce releases when the projected doses in a 31 day period would exceed 2 percent of the guidelines for the annual dose or dose commitment ,

conforming to 10 CFR 50, Appendix I; and

i. Limitations on the annual and quarterly doses to a member of the public from tritium and radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas beyond the site boundary conforming to Appendix I to 10 CFR Part 50.

1.4.2.5 Radiological Environmental Monitoring Program This program is for monitoring the radiation and radionuclides in the environs of the facility. The program shall provide representative measurements of radioactivity in the highest potential exposure pathways and verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall be contained in the ODCM and shall include the following:

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a. Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM; and

b. Participation in an Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

1.4.2.6 Storage Tank Radioactivity Monitoring Program j l

I A surveillance program to ensure that the quantity of radioactivity contained in all outdoor liquid radwaste tanks that are not surrounded by liners, dikes, or walls, capable of i.

holding the tanks' contents and that do not have tank overflows l

and surrounding area drains connected to the liquid radwaste l treatment system is less than limits of 10 CFR 20, Appendix B l at the nearest potable water supply and the nearest surface l water supply in an unrestricted area, in the event of an I

uncontrolled release of the tanks' contents. For temporary l storage tanks a limit of 10 curies, excluding tritium and dissolved or entrained noble gasses, may be used in lieu of the above criteria.

The following provisions are applicable to the Storage Tank Radioactivity Monitoring Program Surveillance Requirement (SR) frequencies:

a. The specified Frequency for each SR is met if the Surveillance is performed within 1.25 times the interval l specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.  !

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b. If it is discovered that a Surveillance was not performed I within its specified Frequency, then declaring the Requirement not met may be delayed, from the time of  !

discovery, up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the ,

specified Frequency, whichever is less. This delay period is permitted to allow performance of the Surveillance.

If the Surveillance is not performed within the delay period, the Requirement must immediately be declared not met.

When the Surveillance is performed within the delay period and the Surveillance is not met, the Requirement must immediately be declared not met.

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1.4.2.7 Fire Protection Program l This program provides controls to ensure that appropriate fire l protection measures are maintained to protect the facility from j fires which could release radioactive materials.

I A fire protection program will be implemented and maintained to meet the requirements of 10 CFR 50.48. Changes may be made to this program, without prior NRC approval, provided those changes would not adversely increase the likelihood of an I

offsite release of radioactive material due to a fire.

1.5 Reporting Requirements 1.5.1 Routine Reoorts The following reports shall be submitted in accordance with 10 CFR 50.4.

1.5.1.1 Occupational Radiation Exposure Report An Occupational Radiation Exposure Report covering the activities of the facility as described below for the previous calendar year shall be submitted by March 31 of each year.

Occupational Radiation Exposure Report shall include a tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures > 100 mrem /yr and their associated man-rem exposure according to work and job functions (e.g., fuel handling, surveillance, maintenance and waste processing). This tabulation supplements the requirements of 10 CFR 20.2206. The I dose assignments to various duty functions may be estimated I based on pocket dosimeter, thermoluminescent dosimeter (TLD),

or film badge measurements. Small exposures totaling < 20% of the individual total dose need not be accounted for. In the aggregate, at leart 80% of the total whole body dose received from external sor.rces should be assigned to specific major work functions.

1.5.1.2 Annual Radiological Environmental Monitoring Report The Annual Radiological Environmental Monitoring Report covering the activities during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM).

The Annual Radiological Environmental Monitoring Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements. In the event that some individual results are not available for inclusion with the report, the report shall C-9 Revision 23

i.

be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.

The Annual Radiological Environmental Monitoring Report shall include licensee initiated changes to the ODCM during the period of the report as described in Section 1.4.2.3.2, or these changes shall be submitted concurrently.

1.5.1.3 ' Annual Radioactive Effluent Release Report The Annual Radioactive Effluent Release Report covering the activities of the unit shall be submitted in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program.

1.6 Record Retention 1.6.1 The following records shall be retained for at least 3 years:

a. All Licensee Event Reports required by 10 CFR 50.73; 1

l

b. Records of changes made to the procedures required by '

Sectica 1.4.1.1.

1.6.2 The following records shall be retained for at least 5 years:

a. Records and logs of activities related to the safe storage of irradiated fuel; l

b. Records and logs of principal maintenance activities, inspections, repair, and replacement of principal items of equipment related to safe storage of irradiated fuel;

! c. Records of surveillance activities, inspections, and l calibrations required by the Technical Specifications (TS); j

d. Records of sealed source and fission detector leak tests and ,

results; and )

e. Records of annual physical inventory of all sealed source material of record.

1.6.3 The following records shall be retained for the duration of the Possession Only License:

a. Records and drawing changes reflecting design modifications made to structures, systems and components needed for the safe storage of irradiated fuel as described in the Safety Analysis Report;

b. Records of irradiated fuel inventory, fuel transfers, and i assembly burnup histories; 1

l c. Records of radiation exposure for all individuals entering l

radiation control areas; C-10 Revision 23 l

l

i

d. Records of gaseous and liquid radioactive material released to the environs; I

e. Records of radioactive waste disposal in accordance with 10 CFR 20.2108;

f. Records of training and qualification for members of the facility staff; l 1

g. Records of quality assurance activities required by the Trojan Nuclear Quality Assurance (QA) Program and which are classified as permanent records by, applicable regulations, codes, and standards;

h. Records of reviews performed for changes made to procedures, equipment, or reviews of tests and experiments pursuant to 10 CFR 50.59;

i. Records of the reviews and audits required by Section 1.3.1;

j. Records of analyses required by the Radiological Environmental Monitoring Program that would permit evaluation of the accuracy of the analysis at a later date (these records should include procedures effective at specified times and records showing that these procedures were followed); and

k. Records of reviews performed for changes made to the Offsite Dose Calculation Manual and the Process Control Program.

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C-11 Revision 23 L i

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GLOSSARY Audit. An activity which determines through investigation, review, and objective evidence, the adequacy of, and adherence to, established procedures, instructions, specifications, codes, standards, or other applicable contractual and licensing requirements, and the effectiveness of implementation.

calibration: The process by which measuring or test equipment is checked against standards of equal or higher accuracy and adjusted as necessary l to assure its compliance with designated specifications.

conditions Adverse to Ouality: Departures from specified quality-related requirements, such as failures, malfunctions, deficiencies, deviations, defective material or equipment, and nonconformances.

Corrective Action: Action taken to correct conditions adverse to quality and to preclude repetition of significant conditions adverse to quality.

Desian: The technical and management processes which commence with the identification of design inputs and which lead to and include the issuance of design output documents such as drawings, specifications, and other documents defining the technical and physical requirements of systems, structures, and components.

Desian chance: A change or alteration to the technical or physical requirements of an item.

Desian Documents: Specifications, drawings, calculations, and analyses associated with design changes and modifications that define technical requirements.

I Desian verification: The process of reviewing, confirming, or ,

substantiating the design by one or more methods to provide assurance i that the design meets the specified design requirements. This may be accomplished by the performance of design reviews, use of alternate or simplified calculational methods, or by performance of a suitable testing program.

Documents Recuirina control: Documents requiring control contain written or pictorial information describing, defining, specifying, reporting, or certifying activities, requirements, procedures, or results. As a minimum, these include design specifications; procurement documents; drawings; QA Program; procedures; Defueled Safety Analysis Report; ISFSI Safety Analysis Report; manufacturing, inspection, maintenance, modification, design change and testing instructions; nonconformance reports; as-built packages; and other documentation affecting quality-related items.

Examination: An element of inspection consisting of investigation of materials, components, supplies, and services to determine conformance to those specified requirements which can be determined by such investigation. Examination is usually nondestructive and includes simple physical manipulation, gauging, and measurement.

G1-1 Revision 21

g Identification: A msans by which material, equipment, or parts can be

, traced to their associated quality' documentation through the use of heat number, lot number, serial number, part number, purchase order number, or L :other appropriate means.

l Tnanection: An element of quality control which by meano of examination, observation, or measurement determines the conformance of materials, supplies, components, parts, appurtenances, systems, processes, or structures to predetermined quality requirements.

Tnatallation chackm: Those measurements, verifications,'and comparisons performed following maintenance or modification to determine satisfactory condition, accuracy, safety, or performance. Installation checks do not include tests or NDE inspections. Installation checks include but are not limited to

a. Pipe hangers, seismic anchors, and restraints are properly installed; l

b. Pumps seals and packing are properly installed;

c. Valve glands and packing are installed;

d. Valve stroking, actuation, and settings are proper;

.e. Rotation of prime movers is correct; f-. Electrical circuits, controls, and relay settings are correct;

g. Phasing of electrical buses is correct;

h. Instrumentation is calibrated and in service as required;

1. Limit switches, interlocks, and stops are properly adjusted and set.

Measurino and Test Eauinmant: Devices or systems used to calibrate, measure, gauge, test, or inspect in order to control or acquire data to verify conformance to specified requirements. Measuring and Test Equipment does not include permanently installed plant instrumentation nor does it include test equipment used for preliminary checks where data obtained will

-not be used to determine acceptability or verify conformance to established 4

criteria.

Modification: A planned change in plant design or operation accomplished in accordance with the requirements and limitations of applicable codes,  !

standards, procedures, specifications, licenses, and predetermined safety restrictions.

Modifv (termed "renair" in ANSI N45.2.10): The disposition applied to nonconforming items which are restored to a condition such that the capability of an item to function reliably and safety is unimpaired, even though that-item still may not conform to the original requirement.

Nonconformance: A deficiency in characteristic, documentation, or procedure which renders the quality of an item or activity unacceptable or

. indeterminate.

G1-2 Revision 16

b l

i Permanent Records Storace Facility: A Parmantnt Rrcords Storaga Facility is '

an environmentally controlled room or vault with controlled access which j

provides protection of quality assurance records from fire, theft, flood, and deterioration, l

l Plant: The word " plant," as used in this QA Program, includes both the Trojan Nuclear Plant (TNP) and the Independent Spent Fuel Storage Installation (ISFSI) facility. The term "TNP" refers to that portion of the Plant licensed under 20 CFR 50.

Procedure: A document that specifies or describes how an activity is to be performed. It may include methods to be employed, equipment or materials to be used, and sequence of operation.

Procurement Documents: Those purchase requisitions, stock purchase repeating requisitions, term purchase order renewals, release letters, letters of intent, bid specifications, contracts, purchase orders, specifications, or other documents which provide contractual basis for procurement actions. They identify and define the requirements which items or services must meet in order to be acceptable to the Purchaser.

Purchased Services: Purchased services are services procured by PGE to support quality-related items. Examples include design analysis, evaluations, reviews, audits, calibration, and data reduction.

Quality Assurance f oA) : All those planned and systematic actions necessary to provide adequate confidence that an item or facility will perform satisfactorily in service.

OA Surveillance: A documented QA observation or review of an activity for the purpose of verifying conformance with specified requirements or evaluating their adequacy and effectiveness.

Quality Assurance Records: Those records which provide documentary evidence of the quality of items and/or activities affecting quality. A document is considered a QA record when the document is complete, valid, legible, and adequately identifiable to the item or activity involved. Documents shall be considered valid records only if stamped, initialed, signed, or otherwise authenticated and dated by authorized personnel. A record is completed when the final review signature or other authentication is placed on the document or on a documentation package containing multiple documents. QA records include operating logs and the result of reviews, inspections, tests, audits, monitoring of work performance, and material analyses. QA records also include closely related data such as qualifications of personnel, procedures, and equipment. TNP and ISFSI decommissioning records will be dispositioned in accordance with 10 CFR 50.75 and 10 CFR 72.30 respectively.

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G1-3 Revision 23

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Oualitv-Related: Ths tenn "qunlity-ralated" cncompassas thoma items and activities which are safety-related or are associated with:

• Radiological-Environmental and Effluent Monitoring.

• Fire Protection equipment protecting areas containing safety-related equipment.

• Radiation Protection.

• Packaging Radioactive Material for Transport.

• Radioactive Waste Management Systems.

• ISFSI equipment classified as important to safety.

Quality Recuirements: Quality requirements include, but are not limited to, such items as test, inspection, and acceptance criteria and any special instructions and prerequisites for such activities as designing, identification, fabrication, cleaning, erecting, packaging, handling, shipping, and extended storage.

j Radiation Protection: Radiological controls applied to radiation areas, radiation services, or radiation-producing machines consistent with the requirements of 10 CFR 19, 10 CFR 20, and 10 CFR 50, Appendix I.

Reiect: The disposition applied to nonconforming items which are unsuitable for their intended purpose but which may be feasible to return to the supplier as salvage for replacement or credit, or feasible to scrap.

Rework: The disposition applied to nonconforming items which are made to l conform to a prior specified requirement by completion, remachining, reassembly, or other corrective means.

Sionificant condition Adverse to cuality: A departure from specified requirements is considered to be a significant condition adverse to quality  !

if the condition appears to be an event (1) which requires reporting in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or less in accordance with the TNP License, ISFSI License, j 10 CFR 20, or 10 CFR 50.72; (2) which requires reporting in accordance with 10 CFR 21; or (3) which involves a significant breakdown in the QA Program implementation.

Soecial Process: A process or operation performed on an item in such a manner that conformance to specified requirements and verification of all essential characteristics may not be determined solely by inspection, test, or examination; assurance that all steps of the process were properly carried out depends in part on the skill of the operator, use of specified equipment, and adherence to the qualified process procedures and control.

Special processes include, but are not limited to: welding, heat treating, metal spraying, and nondestructive testing.

Ston Work: The authority that permits immediate stoppage of quality-related activities such as design, procurement, fabrication, inspection, testing, or removal.

l G1-4 Revision 23 L _ .

Testino: Tha dstormination or vsrification of the capability of en item to meet specified requirements by subjecting the item to a set of physical, chei,.ical, environmental, or operating conditions.

Use As In: A disposition applied to nonconforming items which do not meet all specified requirements but do safely and reliably meet their intended purpose.

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G1-5 Revision 23

y ENCLOSURE II TO VPN-067-99 DESCRIPTION OF CHANGES INCORPORATED INTO PROPOSED REVISION 23 TO PGE-8010," TROJAN NUCLEAR QUALITY ASSURANCE PROGRAM" 4

Enclosure II VPN-067-99 August i1,1999 1

Page1 of2 I

Description Of Changes l Incorporated Into Proposed Revision 23 to PGE-8010," Trojan Nuclear Quality Assurance Program" l

The following table provides a' description of the changes proposed to be incorporated into Revision 23 to PGE-8010," Trojan Nuclear Quality Assurance Program." The changes

incorporated into PGE-8010, Revision 23, are those related to the relocation of many of the administrative controls currently contained in Trojan Technical Specifications, Section 5, to the j Trojan Nuclear Quality Assurance (QA) Program, PGE-8010. The proposed PGE-8010, Revision 23, will be made effective concurrently with implementation of and in accordance with the schedule considerations of the approved License Change Application (LCA) 245," Post Fuel Movement License Amendment." j 010 Description of and Reason for Change Table of Contents, These sections are revised to reflect page numbering and page listing l Page iii; changes due to addition of new Appendix C," Additional Administrative List of Effective Controls for Trojan Nuclear Plant 10 CFR 50 Licensed Activities," which Pages,Pagev incorporates the text relocated from the Trojan Technical Specifications.

1.1 Additional text clarifies that this QA Program is applicable to 10 CFR 50 ,

licensed activities at the Trojan Nuclear Plant until the 10 CFR 50 license is terminated. This text clarification is made to be consistent with the introductory page of Appendix C, Page C-2, which states that Appendix C may be removed from the QA Program upon termination of the 10 CFR 50 license.

1.2.1 This change removes " emergency planning" from a list ofitems for which the Plant General Manager has overall authority and responsibility. This i change reflects the fact that implementation of PGE-8010, Revision 23, will be coincident with implementation of LCA 244, which deletes Emergency Plan requirements from the 10 CFR 50 license following fuel movement to l the ISFSI. Additional details regarding implementation schedule are 1 provided in LCA 245, forwarded by PGE letter VPN-034-98, dated August 27,1998.

1.2.1; These sections and the figure are revised to reflect the elimination of the 1.2.2; and Independent Review and Audit Committee (IRAC) as proposed by Figure 1.0-1 LCA 245. The basis for the proposed elimination of the IRAC is provided in Enclosure III to VPN-067-99, under the Table A, Revision 1, entry for Trojan Technical Specification 5.5.2.

Enclosure II VPN-067-99 August 11,1999 Page 2 of 2 PGE-8010 g ;9 Description of and Reason for Change 1.2.2.3 This change removes " security" from a list ofitems for which the General Manager, Plant Support and Technical Functions, has been delegated responsibility. This change reflects the fact that implementation of PGE-8010, Revision 23, will be coincident with implementation of LCA 243, which deletes Security Plan requirements from the 10 CFR 50 license following fuel movement to the ISFSI. Additional details regarding implementation schedule are provided in LCA 245, forwarded by PGE letter VPN-034-98, dated August 27,1998.

2.2.2; These sections are revised to change any specific references to the term 7.2; " surveillance" to the newly termed "QA surveillance." This change is 18.2.1; necessary Jue to the incorporation of the new Appendix C, which contains Appendix A, reference to " surveillance" as a verification of systems and equipment Section a (3); configuration, as opposed to " surveillance" as it exists in PGE-8010, Appendix B, Revision 22, as a documented observation of activities for evaluation of Section a (3); and adequacy. This latu : usage is proposed to be changed to "QA surveillance."

Glossary, Pages GI-3 and Gl-4 Glossary, The definition of" quality-related" is changed by the removal of" Installed Page GI-4 monitoring equipment used to satisfy TNP Technical Specifications, Appendix A, surveillance requirements." This change reflects the elimination of Technical Specification surveillance requirements as proposed in LCA 245.

Appendix C This new appendix contains the text relocated from the Trojan Technical Specifications, as proposed in LCA 245, and as supplemented by PGE letter VPN-067-99 and its enclosures.

ENCLOSURE III TO VPN-067-99 REVISION 1 TO TABLE A (Supersedes Table A of Attachment I to PGE Letter VPN-034-98," License Change Application (LCA) 245 -

Post Fuel Movement License Amendment," dated August 27,1998)

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ENCLOSURE IV TO PGE-067-99 REPLACEMENT ANNOTATED TROJAN TECHNICAL SPECIFICATION PAGES 5-1,5-26, AND 5-27 ,

I REPLACEMENT REVISED TROJAN TECHNICAL SPECIFICATION PAGES 5-1 AND 5-2 l (Replacement pages supersede corresponding pages previously submitted to NRC by PGE Letter VPN-034-98,

" License Change Application (LCA) 245 - Post Fuel Movement License Amendment," dated August 27,1998) ,

4

Responsibility 5.1 5.0 ADMINISTRATIVE CONTROLS E 4 n _ _ _ _ ! L f f !i. ,

V3 5 Dweyvi rstwissty 5.1 through 5.9 Sections 5.1 through 5.9 have been intentionally deleted. See Quality Assurance Program (PGE-8010) for administrative controls requirements.

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TROJAN UNIT 1 5-1 AMENDMENT NO.195

High Rndiation Arca 5.10 5.0 ADMINISTRATIVE CONTROLS 5.10 High Radiation Area 5.10.1 Pursuant to 10 CFR 20, paragraph 20.1601, in lieu of the requirements of 10 CFR 20.1601, each high radiation area, as defined in 10 CFR 20, in which the intensity of radiation is > 100 mrem /hr but < 1000 mrem /hr, shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP). Individuals qualified in radiation protection procedures or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas with exposure rates < 1000 mrem /hr, provided they are otherwise following facility radiation protection procedures for entry into such high radiation areas.

Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a. A radiation monitoring device that continuously indicates the radiation dose rate in the area.

b. A radiation monitoring device that continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel are aware of them.

c. An individual qualified in radiation protection procedures with a ,

radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and l shall perform periodic radiation surveillance at the frequency specified by the Radiation Protection Manager in the RWP.

)

(continued)

TROJAN UNIT 1 5-26 AMENDMENT #194

]

High Radiation Area 5.10 i

5.10. High Radiation Area (continued) l 5.10.2 in addition to the requirements of Specification 5.10.1, areas with radiation levels > 1000 mrem /hr shall be provided with locked or continuously guarded doors to prevent unauthorized entry and the keys i shall be maintained under the administrative control of the Chl't '/;r,ager en duty or health physics supervision. Doors shall remain locked except ,

during periods of access by personnel under an approved RWP that shall specify the dose rate levels in the immediate work areas and the maximum allowable stay times for individuals in those areas. In lieu of i the stay time specification of the RWP, direct or remote (such as closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities being performed within the area.

5.10.3 For individual high radiation areas with radiation levels of > 1000 mrem /hr, accessible to personnel, that are located within large areas  ;

such as reactor _ containment, where no enclosure exists for purposes of locking, or that cannot be continuously guarded, and where no enclosure can be reasonably constructed around the individual area, that individual area shall be barricaded and conspicuously posted, and a flashing light shall be activated as a warning device.

TROJAN UNIT 1 5-27 AMENDMENT #194

Rasponsibility 5.1 5.0 ADMINISTRATIVE CONTROLS f-5.1 through 5.9 Sections 5.1 through 5.9 have been intentionally deleted. See l Quality Assurance Program (PGE-8010) for administrative controls l requirements.

Revised l 5.10 High Radiation Area by !

CA-245 5.10.1 Pursuant to 10 CFR 20, paragraph 20.1601, in lieu of the requirementsS gpm' 10 CFR 20.1601, each high radiation area, as defined in 10 CFR 20, in Dat which the intensity of radiation is > 100 mrem /hr but < 1000 mrem /hr, shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a 8/11/ 9 Radiation Work Permit (RWP). Individuals qualified in radiation protection procedures or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas with exposure rates 51000 mrem /hr, provided they are otherwise following facility radiation protection procedures for entry into such high radiation areas.

l Any Individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a. , A radiation monitoring device that continuously indicates the .

radiation dose rate in the area. 1

b. A radiation monitoring device that continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate levels in the i area have been established and personnel are aware of them.

c. An individual qualified in radiation protection procedures with a I radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the Radiation Protection Manager in the RWP.

(continued)

TROJAN UNIT 1 5-1 AMENDMENT XXX l

)

High Radiation Area 5.10 5.10 High Radiation Area (continued) 5.10.2 in addition to the requirements of Specification 5.10.1, areas with radiation levels > 1000 mrem /hr shall be provided with locked or.  !

continuously guarded doors to prevent unauthorized entry and the keys shall be maintained under the administrative control of health ' l

- physics supervision. Docrs shall remain locked except during periods I of access by personnel under an approved RWP that shall specify the Revised dose rate levels in the immediate work areas and the maximum by allowable stay times for individuals in those areas. In lieu of the stay LCA-245 time specification of the RWP, direct or remote (such as closed circuit Submittals TV cameras) continuous surveillance may be made by personnel Dated .

qualified in radiation protection procedures to provide positive 8/27/98 exposure control over the activities being performed within the area. and 8/11/99 5.10.3 For individual high radiation areas with radiation levels of > 1000 mrem /hr, accessible to personnel, that are located within large areas such as reactor containment, where no enclosure exists for purposes of locking, or that cannot be continuously guarded, and where no enclosure can be reasonably constructed around the individual area, that individual area shall be barricaded and conspicuously posted, and a flashing light shall be activated as a warning device.

TROJAN UNIT 1 5-2 AMENDMENT XXX l