ML20147F933
| ML20147F933 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek, 05000000, Crane |
| Issue date: | 08/25/1987 |
| From: | Phyllis Clark GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20147F919 | List: |
| References | |
| 1000-ADM-1291.0, NUDOCS 8803080075 | |
| Download: ML20147F933 (46) | |
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l Nuclear i
GPU "; clear Corporate l Number policy and procedure Manual i 1000-ADM-1291.01 l
l Title Procedure for Nuclear Safety and Environmental Review and Approval of Documents Impact i Revision No.
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Applicab111ty/5 cope l
l Responsible Office Nuclear Safety Reviews and Approvals at THI-1 and Oyster Creek l NSAD-6300 1
This document is within QA plan scope x Yes No l Ef fective Date Safety Reviews Required x Yes No l
l October 1, 1987 List of Effective Pages Page Revision Page Revision Page Revision 1.0 3
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NUCI68r lI GPU Nuclear Corporate l Number Policy and Procedure Manual l 1000-ADM-1291.01 1
1 Title Procedure for Nuclear Safety and Environmental Impact i Revision No.
Review and Approval of Documents l
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TABLE OF CONTENTS 1.0 PURPOSE 2.0 APPLICABILITY / SCOPE 3.0 DEFINITIONS 3.1 Concurrence 3.2 Cross-Disciplinary Review 3.3 50.59 Consideration 3.4 Potenti61 Environmental Impact 3.5 Implementing Approval 3.6 Important to Safety l
3.7 Independent Safety Review l
3.8 Independent Safety Reviewer 3.9 Licensing Basis Document i
3.10 Originator l
3.11 Responsible Technical Reviewer 3.12 Safety Determination 3.13 Safety Evaluation 3.14 Safety Related l
3.15 Technical Review 3.16 Technical Specifications 3.17 Unreviewed Safety Question I
4.0 PROCEDURE 4.1 Summary of Review and Approval Treatment 4.2 Safety Determination 4.3 Safety Evaluation 4.4 Preparation 4.5 Technical Review 4.6 Independent Safety Review 4.7 Implementing Approval 4.8 Certification of Individuals 4.8.1 Qualifications 4.8.2 Training 4.9 Selection of Individuals 4.10 Review and Approval Matrices 2.0 1520K
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policy and Procedure Manual l 1000-ADM-1291.01 I
l Title Procedure for Nuclear Safety and Environmental Impact l Revision No.
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TABLE OF CONTENTS (CONTINUED) 4.11 Review and Approval of Temporary Changes Permitted by the Technical Specifications 4.12 Independent On Site Safety Review Group 4.13 Changes to This Procedure 4.14 Unreviewed Safety Questions / Technical Specification Change Required 4.15 Division Safety Review Coordinator l
4.16 Records and Reports 5.0 RESPONSIBILITIES
6.0 REFERENCES
7.0 ATTACHMENTS i
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1.0 PURPOSE To establish a procedure to inplement and control the GPU Nuclear Saf ety Review and Approval Process by:
1.1 Identifying the parties and responsibilities for the preparation, review, and approval of specific documents or types of documents.
1.2 Establishing the requirements for the certification of Responsible Technical Reviewers and Independent Safety Reviewers.
1.3 Specifying the procedure for processing changes to the Review and Approval Matrices.
1.4 Establishing the requirement for and responsibilities of Division Safety Review Coordinators.
1.5 Establishing the requirements for the development and retention of records associated with the review and approval process.
2.0 APPLICABILITY / SCOPE 2.1 This procedure applies to each Division of GPU Nuclear that prepares, reviews, or approves documents (as defined in 2.2 below) that pertain to TMI-l or Oyster Creek nuclear facilities.
2.2 Documents and substantive revisions of documents, which are within QA Plan scope, shall be prepared, reviewed and approved ja accordance with this procedure if:
2.2.1 they are listed on the Review and Approval Matrices, (Exhibits 1 and 2 of this procedure) and 2.2.2 they have the potential to adversely affect nuclear saf ety or safe plant operations, or 2.2.3 they involve a 50.59 Consideration, or 2.2.4 they involve an Unreviewed Safety Question, or 2.2.5 they involve a change to the Technical Specifications or any other Licensing Basis Document, or 2.2.6 they have any Potential Environmental Impact, or 2.2.7 the Technical Specifications or other corporate requirements so specify.
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2.3 This procedure applies only to substantive revisions of documents.
Non-substantive revisions are those which do not affect the activities associated with the document or the document's meaning or intent.
Examples of non-substantive changes are:
2.3.1 Correcting spelling.
2.3.2 Adding (but not deletipg) sign-off spaces.
2.3.3 Blocking in notes, cautions, etc.
2.3.4 Changes in corporate and personnel titles which do not reassign responsibilities and which are not referred to in the Technical Specifications.
2.3.5 Changes in nomenclature or editorial changes which clearly do not change function, meaning, or intent.
3.0
_EFINITIONS 0
3.1 CONCURRENCE - Written agreement that the provisions in a document for which review has been requested are acceptable for implementation within, or from the standpoint of, the signer's area of responsibility.
3.2 CROSS-0!SCIPLINARY REVIEW - A review performed by one or more individuals representing more than one specialty area or perspective.
3.3 50.59 CONSIDERATION (Reference 6.8)-
3.3.1 A change to the facility as described in the safety analysis report.
3.3.2 A change in the prc:edures as described in the safety analysis report.
3.3.3 The performance of a test or experiment not described in the safety analysis report.
3.4 POTENTIAL ENVIRONMENTAL IMPACT Any proposed activity, change, facility expanston, production increase, prQcess modification, test or experiment which could result in any of the following:
3.4.1 A release or potential release of non-radioactive material (gas or 11guld) to the environment.
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3.4.2 A change in any systems, components, or actions which affect the control or monitoring of actual or potential releases of non-radioactive materials to the environment.
3.4.3 A physical or chemical change in the characteristics of plant discharges, effluents, withdrawals, or other plant interfaces with the environment.
3.?.4 Disposition or storage for disposition of any non-radioactive waste material.
3.5 IMPLEMENTING APPROVAL - The signature of a Manager (or person with a higher title) which indicates that the document has been properly prepared and reviewed and is thereby released for implementation.
3.6 IMPORTANT TO SAFETY (ITS) (Reference 6.9) - A special classifi-cation or category of those structures, systems, components and activities that provide reasonable assurance that the facility can be operated without undue risk to the health and safety of the public.
It encompasses the. broad class of plant features covered (not necessarily explicitly) in the General Design Criteria, (10CFR50 Appendix A),that contribute in important ways to the safe operation and protection of the public in all phases and aspects of facility operation (i.e., normal opera-tion, transient control, and accident mitigation).
It includes Safety-Related as a subset. For software, this classification has been replaced by the terms QA Plan Scope and Safety Review Required (Reference 6.1).
3.7 INDEPENDENT SAFETY REVIEW - An independent verification of a document to the extent necessary to verify safety adequacy.
It should include:
3.7.1 Review of technical aspects.
3.7.2 Review of any associated Safety Evaluation.
3.7.3 Review of reportable events, including the results of any investigations made, and the recommendations resulting from such investigations, to prevent or reduce the probability of recurrence of the event.
3.7.4 Other subjects as required by Technical Specification Section 6.5.2.5.
3.8 INDEPENDENT SAFETY REVIEWER (ISR) - An individual who performs an Independent Safety Review.
If the Independent Safety Review is accomplished by more than one person, the individual whose signature attests the review shall be the Independent Safety Reviewer.
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' 1000-ADM-1291.01 l
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3.9 LICENSING BASIS 00CUMENT (LSD) - Any document which is part of the licensing basis of the plant.
Examples of Licensing Basis Documents include: FSAR, Technical Specifications Emergency Plan, Offsite Dose Calculation Manual, Security Plan, Fire Protection Plan, In-Service Inspection Plan, Radiation Protection Plan, Quality Assurance Plan, and Process Control Program.
3.10 ORIGINATOR - The person who is responsible for the development of items such as Policies, Plans, Procedures or other documents. Also referred to as the preparer.
3.11 RESPONSIBLE TECHNICAL REVIEWER (RTR) - An individual who performs a Technical Review.
If the Technical Review is accomplished by more than one person, the individual whose signature attests the review shall be the Responsible Technical Reviewer.
3.12 SAFETY DETERMINATION (Exhibit 7) - A determination of whether a document:
3.12.1 Has any potential impact on nuclear safety or safe plant operations and, as a result, should have a written safety evaluation, and/or 3.12.2 Involves a change to the Technical Specifications, FSAR, or other Licensing Basis Document, and/or 3.12.3 Involves an Unreviewed Safety Question, and/or 3.12.4 Involves any potential environmental impact.
3.13 SAFETY EVALUATION (Exhibit 8) - An assessment of a document which provides the written basis for determining:
3.13.1 Whether an Unreviewed Safety Question is involved, (Refer to Definition 3.17) and/or 3.13.2 Whether the margin of safety, as defined in Licensing Basis Documents other than the Technical Specification, is reduced and/or 3.13.3 Whether the document can be implemented without adversely affecting nuclear safety.
3.14 SAFETY RELATED - (Reference 6.8) A term which refers to those structures, systems, or components necessary to assure:
3.14.1 The integrity of the reactor coolant pressure boundary, or 7.0 1520K
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3.14.2 The capability to shut down the reactor and maintain it in a safe shutdown condition, or 3.14.3 The capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposures comparable to the guideline exposures of 10 CFR 100.
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3.15 TECHNICAL REVIEW - A verif' cation of the technical and safety adequacy of a document.
It is a thorough review from a technical standpoint, and will include applicable items I,
delineated in Definition 3.7.
t 3.16 TECHNICAL SPECIFICATIONS - The part of the opera' ting license of each unit which governs operating limits and administrative requirements for the power plant.
3.17 UNREVIEWED SAFETY QUESTION - Any proposed action which:
3.17.1 May increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report; or 3.17.2 May create a possibility for an accident or malfunction of a different type than any evaluated previously in i
the safety analysis report; or 3.17.3 Reduces the margin of safety as defined in the basis l
l for any Technical Specification.
4.0 PROCEDURE 4.1
SUMMARY
OF REVIEW AND APPROVAL TREATMENT 4.1.1 Exhibit 3 outlines steps to follow to decide if this procedure applies to a document.
Other reviews and approvals of documents may be required by procedures or agreements outside the scope of this procedure.
The Originator initially decides if the review and approval process of this procedure applies to a particular document.
If this procedure applies, the resulting process will be as described in 4.1.2, 4.1.3, or 4.1.4. (also see Exhibit 4).
If this procedure applies, the Originator will indicate that a Safety Review is required by checking the appropriate "Yes" block on the document cover page.
If this procedure does not apply, the "Safety Review Required" block will be checked "No" (Reference 6.1).
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4.1.2 Matrix Section I and II Documents When this procedure applies, matrix Section I and II type documents shall always have a Safety Determination (Ref. Section 4.2), and shall always be given a Technical Review.
If the Originator and RTR agree that the Safety Determination is negative, the document is submitted for Implementing Approval.
If the Safety Determination has the appropriate "yes" answers, a written Safety Evaluation must also be prepared by the Originator.
The document package is then given a Technical Review.
If the Originator and RTR agree that an Unreviewed Safety Question (USQ) or Technical Specification Change (TSC) is not involved, the document may be submitted for Irnplementing Approval.
(Refer to Section 4.14 if the Originator and RTR agree that an USQ cr TSC is involved).
An Independent Safety Review of an affirmative Safety Determination and its associated Safety Evaluation is always required, but need not be done before Implementing Approval unless an USQ or TSC is involved.
Exhibit 5 sumarizes the process for Matrix Section I and II documents.
4.1.3 Matrix Section III Documents This procedure always applies to Matrix Section III type documents.
A Safety Determination is not required.
A written Safety Evaluation is required far Technical Specification / License change requests.
The required content of Licensee Event Reports is sufficiently detailed so that, for LERS, a separate, written Safety Evaluation is not required.
Exhibit 6 summarizes the process for Ntrix Section III documents.
4.1.4 Matrix Section IV DocumentsSection IV of the Matrices is a miscellany of document types which should be reviewed for potential safety 9.0 1520K
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significance to determine if the requirements of Technical Specification Section 6.5.2.5 apply.
The requirements for review and approval of these documents shall be covered by Division level procedures.
When Technical Review, Independent Safety Review, and/or Implementing Approval is required, they shall be performed in accordance with this procedure.
4.1.5 It is not anticipated that this procedure will be considered applicable to any document of a type not listed on the appropriate Matrix.
However, the requirements of Section 2 notwithstanding, should an Originator and the document's approver decide that this procedure should apply, the document shall be processed in accordance with Section I.A.1 of the appropriate Matrix, with cross-disciplinary input or specialist assistance obtained as required. This procedure's Originator should be notified so that a revision to the Matrices can be considered.
Exhibit 3 identifies some considerations that may be reviewed to confirm that this procedure is not applicable to a document of a type not on the Matrices.
4.1.6 Calculations and analyses which provide the basis for establishing or changing an operating parameter, which can have an effect on nuclear safety, such as trip points and alarm points, need to be design verified.
The criteria for detemining the need for design verification is contained in Technical Functions Division procedure 5000-ADM-7311.01.
The method for performing design verification is contained in Technical Functions Division procedure 5000-ADM-7311.02. All Divisions shall utilize these procedures or approved equivalent procedures.
4.2 SAFETY DETERMINATION (Exhibit 7)
The purpose of a Safety Determination is to detemine if documents, document changes, or facility changes, tests, and experiments have any potential environmental impact or have potential safety significance.
Safety Deteminations shall be documented on the Safety / Environmental Detemination and 50.59 Review form, Exhibit 7, or on other forms which include the basic elements of Exhibit 7 unless Safety Deteminations that differ in content are specified in Division implementing procedures.
Safety Determination variations are pemitted to provide better guidance in detemining the potential safety significance of particular documents than may be provided by Exhibit 7.
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Safety Determinations that differ in content from Exhibit 7, if used, shall be:
a) formally established by Division implementing procedure ( s),
b) structured so that "yes" answers to the questions asked will require that a written Safety Evaluation be prepared, and c) in full compliance with Technical Specifications and other Regulatory requirements.
Question No. 3 on Exhibit 7 addresses the potential adverse affects on nuclear safety or safe plant operations.
In answering this question, consideration should be given to the potential interaction with safety related items (i.e., systems, structures, or components) which may result from the proposed change. For example, scaffolding which is erected in the plant should be evaluated with respect to its potential to adversely affect safety related items by falling or by preventing the performance of an intended safety related function (e.g.,
blocking a valve closure).
4.3 SAFETY EVALUATION (Exhibit 8)
The purpose of the Safety Evaluation is to determine if documents, document changes, tests and experiments will result in an Unreviewed Safety Question or a Technical Specification Change, or will impact on nuclear safety.
A Safety Evaluation, as defined in this procedure, is broader than the Safety Evaluation required by 10 CFR 50.59. This enables the GPUN safety review and approval process to encompass documents that do not clearly involve a 50.59 Consideration but which still may present safety concerns.
Unless otherwise specified in Division implementing procedures, Safety Evaluations shall be documented on the Safety Evaluation form, Exhibit 8, or on other foms which include the basic elements of Exhibit 8.
When Safety Detemination forms other than Exhibit 7 are used, as permitted in section 4.2, Safety Evaluation forms different than Exhibit 8 are permitted.
If used, these alternative forms shall be:
a) formally established by Division implementing procedures, b) consistent with the Safety Determination form used, and c) in full compliance with Technical Specifications and Regulatory requirements.
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Safety Evaluations which consist only of a simple statement or conclusion are not sufficient.
The scope of a Safety Evaluation must be commensurate with the potential safety significance of the document, and the depth sufficient to determine that the document adequately addresses related safety concerns.
4.4 PREPARATION 4.4.1 The Originator's responsibilities include:
4.4.1.1 Preparing a document which adequately considers pertinent technical and safety concerns.
4.4.1.2 Preparing a document which complies with applicable regulatory and procedural requirements.
4.4.1.3 Determining the need for and obtaining cross-disciplinary inputs or specialist assistance, as required.
4.4.1.4 Determining the extent of applicability of this procedure by performing the Safety / Environmental Determination and 50.59 Review.
For Safety Determinations which do not require written Safety Evaluations; that is, for those instances in which the answers to questions 3, 4, 5, and 6 on Exhibit 7 are all dNo", the Originator is required to provide written justification.
4.4.1.5 Identifying any additional reviews required by this procedure or by division policies, practices, or agreements, e.g., Rad Con, Environmental, QA, etc.
4.4.1.6 When required by the Safety / Environmental Determination and 50.59 Review, preparing a written Safety Evaluation.
4.4.1.7 Resolving comments received during the review and approval process.
4.4.2 If the Originator determines that a written safety evaluation is not required for a document type or for a change to a document type that is listed on the Matrices, that determination and written justification shall be reviewed and concurred with by the Originator's management.
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individual is not an RTR, then the detemination shall also be reviewed and concurred with by an RTR.
4.4.3 The Originator shall be responsible for the resolution of comments made during the review and approval process.
Disagreements regarding the incorporation of comments, which cannot be resolved by the Originator, shall be referred to successively higher levels of authority.
If agreement cannot be reached, final resolution shall be as determined by the parties designated to approve in the applicable matrix.
4.5 TECHNICAL REVIEW 4.5.1 The Responsible Technical Reviewer is responsible for:
- 4. 5.1.1 Perfoming a thorough review to ensure that:
a) Activities performed in accordance with the documents being reviewed will be technically correct and concordant with safe operations, and, b) Temporary, interim, or permanent configuration changes to structures, systems, and components as a result of the documents being reviewed are technically correct and concordant with safe operations.
4.5.1.2 Detemining the need for and obtaining cross-disciplinary inputs or specialist assistance to perform the Technical Review.
4.5.2 If a Safety / Environmental Determination and 50.59 Review concludes that a written Safety Evaluation is not required, the signature of the Responsible Technical Reviewer signifies concurrence with the Determination and that an Unreviewed Safety Question does not exist and a Technical Specification change is not required.
The signature of the Responsible Technical Reviewer signifies concurrence that technical and safety considerations have been properly addressed, that any associated Safety Determinations and Safety Evaluations are accurate and complete, and that cross-disciplinary reviews associated with the Technical Review were acceptably perfomed by appropriate individuals.
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This signature also indicates that the RTR was appropriately independent of the Originator and releases the document for further processing in accordance with this procedure.
4.5.3 Cross-disciplinary review or technical input from individuals who are not qualified as RTRs may be accepted by the Responsible Technical Reviewer.
4.6 INDEPENDENT SAFETY REVIEW 4.6.1 The Independent Safety Reviewer is responsible for 4.6.1.1 Performing a thorough review to confirm that:
a)
The safety significant aspects of the document have been properly addressed, b)
The Safety Evaluation, if required, is complete and accurate.
4.6.1.2 Determining the need for and obtaining cross-disciplinary inputs or specialist assistance to perform the Independent Safety Review.
4.6.2 The signature of the Independent Safety Reviewer signifies concurrence that safety considerations have been adequately evaluated and are properly addressed in any associated Safety Determination or Safety Evaluation.
This signature also indicates that cross-disciplinary tasks associated with the Independent Safety Review were acceptably performed by appropriate individuals, and that the Reviewer was appropriately independent of the Originator and the RTR.
4.6.3 The Independent Safety Review of documents that do not involve an Unreviewed Safety Question or a Technical Specification Change may be performed after Implementing Approval.
For documents which invoivst an Unreviewed Safety Question or a Technical Specification Change, refer to Section 4.14.
4.7 IMPLEMENTING APPROVAL 4.7.1 Documents shall be approved for imple mentation by the individual (s) designated in the appl cable Matrix, or their designees.
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4.7.2 The signature of the Implementing Approver on the document signifies that the document has been properly prepared and reviewed, that concurrence signatures, if required, have been obtained, and that the document is released for implementation.
4.8 CERTIFICATION OF INDIVIDUALS Certifiers shall be GPUNC employees.
Formal certification of Originators is not required.
Responsible Technical Reviewers (RTRs) and Independent Safety Reviewers (ISRs) shall be certified by their respective division based on meeting the minimum qualification and training requirements specified in this procedure.
Transferred employees shall be recertified by their new department.
Such recertification may be based solely on the training and experience documented by the previous certification.
Certification of RTRs and ISRs shall be documented using a form equivalent to Exhibit 9.
This certification shall be by the individual's imediate supervisor or a higher management position in the reporting chain, or as designated in division procedures.
A list of currently certified reviewers shall be maintained for each Division by its respective Safety Review Coordinator.
(Refer to Section 4.15).
Consultants / contractors may be certified as RTRs or ISRs by the responsible Division Director only.
Certification shall be based on meeting the Qualification and Training requirements specified in 4.8.1 and 4.8.2 below.
4.8.1 Qualifications l
l 4.8.1.1 Preparers shall be sufficiently knowledgeable l
in the subject areas so that, with appropriate task supervision, the document being prepared will be technically correct and adequate from the standpoint of plant safety.
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4.8.1.2 RTRs in the areas of Reactor Engineering, Instrumentation and Control, Chemistry and Radiochemistry, Radiation Protection, and Quality Assurance shall meet or exceed the qualifications of ANSI /ANS - 3.1 - 1978 Section 4.4, or else shall have seven years of appropriate experience in their specialty.
Reviewers in other areas (e.g. Nelding.
Operations, Maintenance) shall have a Bachelor's Degree in Engineering or the Physical Sciences and three years nuclear power experience, or else shall have seven years of appropriate experience in their specialty.
Reviewers may be competent in more than one specialty.
Experience in different specialties may have been acquired simultaneously.
4.8.1.3 ISRs shall have either a Bachelor's Degree in Engineering or the Physical Sciences and five years of professional-level experience in the area being reviewed, or else shall have nine years of appropriate experience in their specialty.
4.8.1.4 Reviewers may be qualified to perform reviews in more than one specialty.
Experience in different specialties may have been acquired simultaneously.
Credit toward experience will be given for advanced degrees on a one-for-one basis up to a maximum of two years.
4.8.2 Training 4.8.2.1 RTRs and ISRs shall complete an initial training program prior to certification.
4.8.2.2 RTRs and ISRs shall complete an approved refresher training program approximately every two years following initial certification.
If refresher training is not completed within two years, six months, fresher training is certification shall be suspended until re completed.
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4.8.2.3 The Safety Review initial and refresher training program shall be approved by the Manager, Corporate Training.
4.9 SELECTION OF INDIVIDUALS 4.9.1 The individual who assigns a task to an Originator, RTR, or ISR is responsible for ensuring that the individual selected has the knowledge and experience needed to perfonn the task, or to determine when cross-disciplinary or specialist assistance is required.
4.9.2 The RTR must be knowledgeable and experienced in the area of the review.
The RTR cannot be the Originator or Independent Safety Reviewer.
The RTR may be from the same organization as the Preparer, and may be the supervisor or manager who approves the document.
4.9.3 The ISR must be knowledgeable and experienced in the area of the review.
The ISR cannot be the Originator, RTR, Implementing Approver or an individual having direct responsibility for performance of the activities under review.
The ISR may be from the same functional organization as the Preparer and RTR.
4.10 REVIEW AND APPROVAL MATRICES 4.10.1 The Review and Approval Matrices snow which position or group shall prepare, review, and approve various kinds of documents that may apply to TMI-l or Oyster Creek facilities (see Exhibits 1 and 2).
The "Subject" column of each Matrix lists those categories of documents which may require reviews in accordance with this procedure. The other columns indicate the division, group, or position (e.g.,
Preparer) responsible for the specified function.
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4.11.1 In accordance with each plant's Technical Specifications (Section 6.8.3 for both) temporary changes may be made to procedures provided that:
4.11.1.1 The intent of the original procedure is not altered, and 4.11.1.2 The temporary change is approved by two members of GPUNC Management Staff who are certified Responsible Technical Reviewers and are knowledgeable in the area affected by the procedure.
For changes which may affect the operational status of unit systems or equipment, at least one of these individuals shall be a member of unit management or supervision holding a Senior Reactor Operator's license on the unit, and 4.11.l.3 The temporary change is documented, reviewed, and approved within 14 days of implementation.
4.11.1.4 Temporary changes can only be made if the affected organization has procedures detailing how these changes will be made.
Such procedures shall as a minimum reflect the Technical Specification requirements for Safety Review and Approval. Modified or additional review and approval requirements may be specified in such procedures as agreed to by the parties involved.
4.12 INDEPENDENT ONSITE SAFETY REVIEW GROUP 4.12.1 The Independent Onsite Safety Review Group (IOSRG) may perform supplemental reviews of any documents from the Review and Approval Matrices.
4.12.2 10SRG shall review documents on a selective basis, with a de,eth and scope corvaensurate with the actual or potential safety concern.
These reviews may include assessments of the actual activities governed by the document.
4.12.3 The Manager Nuclear Safety shall direct 10SRG reviews of documents and associated activities.
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4.12.4 The Manager, Nuclear Safety shall approve reports of 10SRG evaluations and assessments, and shall submit these reports to the NSA Director, Planning and Nuclear Safety Division Director, and other Division Directors and management positions who are responsible for the area reviewed.
4.12.5 10SRG members shall have either:
4.12.5.1 A Bachelor's Degree in Engineering or appropriate Physical Science and three years of professional level experience in the nuclear power field which may include technical supporting functions or 4.12.5.2 Eight years of appropriate experience in nuclear power plant operations and/or technology.
4.12.5.3 Credit toward experience will be given for advanced degrees on a one-for-one basis up to a maximum of two years.
4.13 CHANGES TO THIS PROCEDURE 4.13.1 Changes to the Matrices 4.13.1.1 Changes to the matricer may be required as a result of an amendment to the Technical Specification, regulatory agency change notice, or at the request of a Division.
A change to a Matrix is initiated by a request from Licensing or the Director of the Division proposing the change, to the Nuclear Safety Assessment Director. A copy shall be sent to the Directors of the Divisions affected by the change.
The request shall include the reason for the change, and the required date, if any.
4.13.1.2 The Nuclear Safety Assessment Department (NSAD) shall review the requested change, prepare a draf t revision to the Matrix, and complete the Responsible Technical Review.
NSAD will submit the draf t revision to GPUN Licensing and to the Directors of the Divi? ions af fected by the change for concurrence.
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4.13.1.3 Licensing shall perfonn an Independent Safety Review of the proposed revision.
If it is determined that an Unreviewed Safety Quastion (USQ) or Technical Specification Change (TSC) is involved, the proposed revision shall be processed in accordance with the applicable procedures. Otherwise, l
Licensing shall complete the Independent Safety Review, and return the revision package to NSAD.
4.13.1.4 NSAD shall distribute the proposed revision to the affected Division Directors and shall coordinate the resolution of all consnents on the proposed revision. Those comments which cannot be resolved by NSAD shall be referred to the appropriate Division Directors for resolution.
4.13.1.5 Written concurrence from Division Directors affected by the proposed revision is requi red.
4.13.1.6 Af ter obtaining the required concurrence signatures, NSAD shall forward the revision to Information Management for formal incorporation into the procedure.
Information Management shall obtain the implementing approval from the Office of the President.
4.13.1.7 The approved revision shall be distributed in accordance with GPU Nuclear Procedure 1000-ADM-1218.01.
4.13.2 Other Changes 4.13.2.1 All other changes to this procedure shall be processed in accordance with GPU Nuclear Procedure 1000-ADM-1218.02 Changes to the matrices, that occur at the same time as other changes, shall also be processed in accordance with 1000-ADM-1218.02 In either case, an Independent Safety Review shall be performed by Licensing.
4.14 UNREVIEWED SAFETY QUESTIONS / TECHNICAL SPECIFICATION CHANGES 20.0 1520K
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Title Procedure for Nuclear Safety and Environmental Impact i Revision No.
Review and Approval of Documents l
1 l
4.14.1 Documents that involve an Unreviewed Safety Question or Technical Specification Change must receive an Independent Safety Review before submittal to the Nof.
A review of the Technical Specification Change and/or Unreviewed Safety Question by the Independent Onsite Safety Review Group (IOSRG) is also required before implementation of the amendment authorizing the change. This review may be performed concurrently with the Independent Safety Review.
Documents that involve an Unreviewed Safety Question or Technical Specification Change require NRC approval before being submitted for Implementing Approval.
4.15 DIVISION SAFETY REVIEW COORDINATOR 4.15.1 Each Division shall designate a primary Safety Review Coordinator.
This individual shall serve as the Division's representative for intradivisional, interdivisioral, and corporate level matters concerning this procsdure and its implementation, and other related activities or issues such as Safety Review Process training.
4.15.2 Additional responsibilities, which may be delegated to other designated individuals within a Division, include:
4.15.2.1 Coordinating the development, implementation, and presentation of appropriate training modules for use in initial and refresher Safety Revient Process training progros within each Division as required by the cognizant Division Director.
4.15.2.2 Coordinating the perfomance of Safety Reviews requested of the Coordinator's department or division by another l
organization.
This includes detemining the need far cross-disciplinary reviews, assigning Safety Reviews and tracking the documents within the Coordinator's organization.
4.15.2.3 Transmitting and tracking documents developed within the Coordinator's group which require Safety Review by other l
organizations, f
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4.15.2.4 Preparing reports of Independent Safety Reviews per each plant's Technical Specification (Section 6.5.2.7 for both) and transmitting this report to the cognizant Division Director at least annually.
(See 4.15.1.3below.)
4.15.2.5 Ensuring the retention of records of all Safety Evaluations and Independent Safety Reviews associated with documencs originating within the Coordinator's division.
4.15.2.6 Ensuring the retention of RTR and ISR certification records.
4.15.2.7 Maintaining records and listings of all currently certified RTRs and ISRs within the Coordinator's division, and publishing a list of certified RTRs and ISRs at least annually.
4.15.2.8 Providing or obtaining guidance or interpretations regarding the iglementation of this procedure.
4.15.2.9 Performing an annual review of the Review and Approval Matrices.
4.16 RECORDS AND REPORTS 4.16.1 The following records will be developed and muintained as noted:
4.16.1.1 Records of certification of Responsible Technical Reviewers, Independent Safety Reviewers and 10SRG members shall be developed by appropriate Divisions and shall be maintained for the duration of the operating license.
4.16.1.2 Records of Independent Safety Reviews shall be maintained for the duration of the operating license.
4.16.1.3 Reports of all Technical Reviews, and Independent Safety Reviews shall be prepared and transmitted, at least annualln to the responsible Division Director. They shall be maintained for the duration of the operating license.
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Review and Approval of Documents L
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4.16.1.4 Reports of evaluations and assessments by 10SRG shall be maintained for the duration of the operating license.
4.16.1.5 Records of changes to operating procedures which are within QA Plan Scope shall be retained for 5 years.
4.16.1.6 All records required in 4.16 will be forwarded to, and maintained by, the document control groups.
5.0 RESPONSIBILITIES 5.1 0FFICE OF THE PRESIDENT - Responsible for approving this Procedure and its revisions.
5.2 OlVISION DIRECTORS - Responsible for' 5.2.1 Developing and implementing Divisional procedures as required to implement the requirements of this Procedure.
5.2.2 Concurring with this Procedure and any Divisional procedures which address interdivisional responsibilities.
5.2.3 Assuring that adequate, qualif ted, Responsible Technical Reviewers and Independent Safety Reviewers are provided to carry out their reiponsibilities.
5.3 NUCLEAR SAFElf ASSESSMENT DIRECTOR - Responsible for this Procedure and changes to it.
6.0 REFERENCES
6.1 GPUN PROCEDURE,1000-ADM-1218.01, "GPU Nuclear Policy, Plan, and Procedure System."
6.2 GPUN PROCEDURE,1000-ADM-1218.02, "Document Change Request Procedure."
6.3 GPUN POLICY,1000-POL-1291.00, "GPUN Nuclear and Radiation Safety Policy."
6.4 GPUN PROCEDURE 1000-ADH-1291.02, "GPU Nuclear Safety Review and Approval Procedure for THI-2."
6.5 TMI-1 and Oyster Creek Technical Specifications Saction 6.
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I Title Procedure for Nuclear Safety and Environmental Impact i Revision No.
Review and Approval of Documents 3
6.6 ANSI /ANS - 3.1 - 1978, "Standard For Selection and Training of Nuclear Power Plant Personnel."
6.7 Regulatory Guide 1.33, Rev. 2 - 1978. Quality Assurance Program Requirements (Operations).
6.8 Code of Federal Regulations Title 10 Part 50.59 and Part 100, Appendix A.
6.9 GPU Nuclear Operational Quality Assurance Plans for Three Mile Island Unit 1 and Oyster Creek Nuclear Stations, Appendix D.
6.10 GPUN PROCEDURE 5000-ADM-7311.01 (EP-006), "Calculations."
C 11 GPUN PROCEDURE, 5000-ADM-7311.02 (EP-009), "Design Verification "
7.0 ATTACHMENTS 7.1 EXHIBIT 1 - GPU Nuclear Safety Review and Approval Matrix, THI-l 7.2 EXHIBIT 2 - GPU Nuclear Safety Review and Approval Matrix, Oyster Creek 7.3 EXHIBIT 3 - Detennination of the Extent of Applicability of 1000- ADM-1291. 01 7.4 FXHIBIT 4 - Sumary of Safety Review Process Alternatives 7.5 EXHIBIT 5 - Flow Chart for Matrix Sections I and II Documents 7.6 EXHIDIT 6 - Flow Chart for Matrix section III Documents 7.7 EXHIBIT 7 - Safety / Environmental Determination and 50.59 Review Form 7.8 EXHIBIT 8 - Safety Evaluation Form 7.9 EXHIBIT 9 - ISR and RTR Initial Certification Form 24.0 1520K
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- 0. C. Di v.
- w Dir./ Deputy. 0.C.
5 NS
,o '
c3 5.
Equipment Control 0.C. Div.0 0.C. Div.
Df v.Dir./ Deputy. 0.C.
80 3
l N en 6.
Shift Relief and Turnover 0.C. Div.0
- 0. C. Di v.
Div.Dir./ Deputy. 0.C.
Q E
o sa 7.
Log Entries, Record Retention & Rev. Proc.
0.C. Div.0 0.C. Di v.
Div.Dir./ Deputy. 0.C.
- o e
Z 8.
Bypss of Safety Functions & Jtsmper S
Contal 0.C. Div.0
- 0. C. Di v.
Div.Dir./ Deputy. 0.C.
m
{
9.
Main. of Minimum Shift Composition and Call In 0.C. Div.0 0.C. Div.
Div.Dir./ Deputy. 0.C.
10.
Communication System Procedures
- 0. C. Di v.0 0.C. Di v.
Dt v.Dir./ Deputy. 0.C.
O 11.
Plant Administratie Procedures that
~~ ~~~
either Assign Responsibilities to 2
--* Z Indtviduals/Depts. or Specify General 8$
Requirements of Work Performance O.C. Di v.0
- 0. C. Di v.
Df v.Dir./ Deputy. 0.C.
>=O, O
I - See Procedure 1000-ADM-1218.01 for review, concurrence and approval requirements Y
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OYSTER CREEK REVIEW AND APPROVAL MATRIX Q$
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INDEPENDENT a
S. '
TECHNICAL SAFETY IMPLEMENTING SUBJECI REVIEW REVIEW APPROVAt 32 9
8.
GENERAL PLANT OPERATING u,
V, :r ---
1.
Operating (SU/Cooldown) 0.C. Di v.
Tech Functions Div.Dir./ Deputy. 0.C.
g O_
oc or 0.C.
2.
System Operating 0.C. Div.
Tech Functions D1 v.Dir./ Deputy. 0.C.
m*
or 0.C.
o,.
,g 3.
Abnormal Operating 0.C. Div.
Tech Functions Di v.Dir./ Deputy. 0.C.
oo ay
- ' C
or 0.C.
4.
Emergency Operating
- 0. C. Di v.
Tech Functions Div.Dir./ Deputy. 0.C.
MC o%
nx or 0.C.
m 5 Alarm Responses
- 0. C. Di v.
0.C. or + Tech Di v.Dir./ Deputy. 0.C.
y gx m
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ag s
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co so ci m
6.
Special Temporary
- 0. C. Di v.
0.C. or + Tech Di v.Di r. / Deputy. 0.C.
U O
ro oo Functfons
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7.
Fueling / Refueling 0.C. Div.
Tech Functions Div.Dir./ Deputy. 0.C.
]
y ct o C
or 0.C.
8 Cheafstry
- 0. C. Di v.
Tech Functions Div.Dir./ Deputy. 0.C.
g o e,*
2, or 0.C.
9.
Radiochemistry
- 0. C. Di v.
Tech Functions Div.Dir./ Deputy. 0.C.
C s
o or 0.C.
- 10. Fire Protection Operating
- 0. C. Di v.
- 0. C. Di v.
Div.Dir./ Deputy. 0.C.
ce 11 Experfments 0.C. Div. or Tech Tech functions or Div.Dir./ Deputy. 0.C.
b,o' Functions 0.C. Div.
n l
12.
Effluent Monitoring 0.C. Di v.
0.C. Di v.
Div.Dir./ Deputy 0.C.
c+
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m5 3m C.
MAINTENANCE Q,
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1.
Calibration MCFf or 0.C. Di v.
0.C. Div.
Div.Dir./ Deputy, MCF or y5 I
Oyster Creek s2 oc l
2.
Control of Measuring MCFI or 0.C. Div.
0.C. Div.
Div.Dir./ Deputy, MCF or s2 j
4 Test Equipment Oyster Creek os o c) l 3.
Preventive Maintenance MCFI or 0.C. Div.
0.C. Di v.
Div.Dir./ Deputy, MCF or
'u O, c.T Oyster Creek o o-o%
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Corrective Maintenance MCFI 0.C. Di v.
Div.Dir./ Deputy, MCF cbq
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SURVEILLANCE I
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Surveillance O.C. Div.
0.C. Di v.
Div.Dir./ Deputy 0.C.
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RADIOLOGICAL CONTROLS PROCEDURES N
- o. O 1.
Radiological Controls Rad Con Rad Engr./
Rad Con Director l
E 5S Rad Mynt.
2.
Environmental Monitoring e
I a.
Padiological Radiological Biological Mgr. - Env. Con.
S b.
Biological Biological Radiological Mgr. - Env. Con.
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PLANS /IMPtD4ENT!NG PROCEDURES b
1.
Emergency Plan Emergency
- Emergency O/P Approves g
Preparedness Preparedness Division Dirs. Concur o
- = Input from Tech Functions 2
--* Z
- = MCF Division prepares procedures and performs reviews in accordance with their Work Management System Sy which ensures that maintenance activities are performed correctly and in accordance with spect fled o cr Engineering, Rad. Con., and Plant operation requirements.
0.C. Division will review and concur with w$
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A OYSTER CREEK REVIEW AND APPROVAL MATRIX 5
PREPARATION /
INDEPEft)ENT TECHNICAL SAFETY IMPLD4ENTING SUBJECT RLVIEW REVIEW APPROVAL
<D O
F.
PLANS / IMPLEMENTING PROCEDURES (Con't.)
<o mm um I
a.
Emergency Plan Implementing Pro-Emergency Emergency Emer Prep Mgr.
Ea cedures (EPIP) (Except Rad Con Preparedness Preparedness Approves - Div.Dir./
o5 Procedures)
Deputy. 0.C. Concurs g*
9 g'o b.
Emergency Plan Implementing Pro-Emergency Emergency Emer Prep Mgr.
cedures (EPIP) (Rad Con related)
Preparedness Preparedness Approves,- Mgr. Rad y
Con Concurs yy ---
<n l
2.
Security Plan Security Security Div.Df r. Admin.
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Mgr. Securfty and Q7 gQ U
Div.Dir./ Deputy. 0.C.
u
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Security Plan laplementing Pro-Security Securi ty Mgr. Security m
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Deputy. 0.C. Concurs 3
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Fire Protection Program Plan 0.C. Di v.
Tech Functions 0/P Approves and Q
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Di v.Di r./ Deputy. 0.C.
a n
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Operational QA Plan (00AP)
QA Quality & Rad Con 0/P Approves, Div.Dirs.
3%
O and Dir. QA Concur e
(Corporate Level-QA Dept. Responsible)
Div. Dirs. Concur y
a
(Department Level)
QA Section Mgrs. Concur
(Section Level) signee) Approves, Af fected QA Section/ Subsection Managers Concur m
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- d. OQAP Implementing Procedures Tech Functions Q4RC Tech Funct'ns,0$RC Responsible Division C
(Other Departments)
Adeln., MCF, Plan.5 Admin., MCF. Plan.8 Approves, All Affected W-huclear Safety Nuclear Safety Divisions Concur g
I 5.
Radiation Protection Plan Rad con Rad Engineering 0/P Approves Div.Dir.
m QERC and All Dther l
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. e
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OYSTER EREEK REVIEW AND APPROVAL MATRIX (D
PREPARATION /
INDEPEM)ENT TECHNICAL SAFETY IMPLD9ENTING SUBJECT REVIEW REVIEW APPROVAL Z&
F.
PLANS / IMPLEMENTING PROCEDURES (Con't)
- o *c cl g l
6.
Process Control Program (PCP) 0.C.
OC or Tech Di v.Di r. /De pu ty,0. C.
O l
Functions
- a. PCP Implementing Procedures 0.C.
0.C. or Tech Di v.Di r. / Deputy,0. C.
l Functions
,C l
s tu cl.
7.
Offsite Dose Calculation Manual (0001)
Rad Con or Env. Control or Div.Dir.-Q & RC Env. Controls Rad Engr.
p, 3
- a. 00CM Implementing Rad Con Procedures Rad Con Rad Engr.or Manager - Rad Con V s Env. Controls
]z ___ _ _
- b. (DO( Implementing Env. Cont. Procedures Env. Controls Rad Engr.or Env.
Manager - Env. Controls oc Controls o, O_
8.
QA Program for Effluent Monitoring
- 0. C. Di v.
0.C. Di v.
Di v.Dir./ Deputy. 0.C.
l o*
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QA Program for Environ.acntal Monitoring Env. Con.
Rad Con or Div.Dir. Q 3 RC o
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QA Director Concurs m
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Nuclear and Radiation Safety Plan NSAD NSAD C/P Approves I
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II. CHANGES TO TE FACILITY ro ca. o.g c
5 A.
Design Changes & Modification C
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to Unit Systems & Equipment (1) 1.
PEDR review package documents Tech functions **
Tech functions Mgr. Engr. Prof.
3
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Z such as: 500 I, Preliminary SDD II. Flow Diagr.ms, Elementary e
c Diagrams, General Arrangement Dwgs A',
& the Safety Determination / Evaluation 2.
Field Change Request that changes Any Organization /
Tech Functions Mgr. Engr. Proj.
associated Safety Deterutnation/ Evaluation Tech Functions #
g mn Preparation / Technical Review by Tech Functions or as otherwise specified in Tech Functions procedures.
If the nature of the Concur ence as defined in Section 3.1 by 0.C. Div. with resolution of cosaments per EP-008.
modification is such that there is no PEDR package. 0.C. Div. will review and concur with the Safety Determination / Evaluation and its associated documents. Changes to the Safety Deterutnation/ Evaluation and other
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(D CC PEDR review package documents will be reviewed by the PEDR Chairman and cognizant personnel in other appropriate 1
Oh Divisions as designated by him.
vi e (D Changes to the Safety Determination / Evaluation will be reviewed by the PEDR Chairman and cognizant personnel in "g
k5 6
o other appropriate divisions as designated by him.
a 3
(1) MCF Division prepares procedures and performs reviews in accordance with their Work Management System which g
f Notes:
ensures that the installations, modifications, and maintenance activities are performed correctly and in l
o ro accordance with spect fled Engineering, Rad. Con. and Plant operation requirements.
e
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OYSTER OtEEK REVIEW AND APPROVAL MATRIX c
PREPARATION /
INDEPEM)ENT to TECHNICAL SAFETY IMPLEMENTING SUBJECT REVIEW REVIEW APPROVAL II. CHANGES TO THE FACILITY (Con't) 1.
Standard Maintenance /
MCF+
0.C. Di v.
Div.Dir./ Deputy. MCF Ed (
Installation Procedures
<g 4 Startup & Test Procedure and Tech Functions 0
- 0. C. Di v.
Mgr. SAT Approves; I
0
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Sa fety Deterui nation /Evalua tion Div.Dir./ Deputy. O.C o, "
i Concurs g*
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Field Change Notice resulting Startup&Testg Tech Functions Mgr. Engr. Proj.
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from testing that changes Tech Functions E'
associated Safety Determinatton/
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8.
Temporary Facility Variations
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Applicable Procedures and Documentation Any Division %
Any Division Any Divisf on 1
I
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Tests & Experiments 82 OE 1.
Test or Experiment Procedure O.C. Div. or Tech 0.C. Di v. or Di v.Di r./ Deputy. 0.C.
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Functions Tech Functions 5
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Licensee Event Report Div. Responsible Plan.1 bc. Safety
- Di v.Di r./ Deputy. 0.C.
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8.
Tech Specs / License Change Request G.C. Di v. or Plan.8 hc. Safety Div.Dir./ Deputy. 0.C.
g Plan.& Nuc. Safety or 0.C. Di v.
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00 Input from 0.C. Div. via Membership on the Test Approval Group. Supplemental test procedures do not requf re
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Changes to the Safety Determination / Evaluation will be reviewed by the PEDR Chaf raan and cognizant personnel in other V
appropriate divisions as designated by him.
- n 1
In accord with approved Division procedures.
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Licensing wfil assign an ISR to the appropriate department.
0.C. Division will review and concur with Standard Maintenance / Installation Procedures as defined in MCF Division
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Procedures A000-WMS-1220.14 and A000-ADM-1220.7.
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REVIEWS AM) EVALUATIONSI1) d'
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A.
Violations, deviations and Division Responsible ISR os reportable events which
. equire reporting to the "2
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o"e B.
Investigation of all Violations of Division Respon-RTR
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Evaluate Operating Experience of the Tech Functions As assigned by Tech Functions l
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Other Reviews Deemed Necessary by an Independent Safety-As assigned by Independent l
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Safety Reviewer 3,,
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Review Written Susanaries of Audit Quality & Rad Con As assigned by Quality & Rad Con (ISR) l
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Review of Every Unplanned Release of 0.C.
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I o.
Radioactivity to the Environment o'
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or (1) No specific product.
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(2) Review Coordinator - is responsible to initiate or identify issues of potential safety significance and forward appropriate data to the assigned review organization and ensure that the resulting review is documented, g
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GPU Nuclear Corpor ate Number Policy and Procedure Manual 1000-ADH-1291.01 Title Procedure for Nuclear Safety and Environmental Impact Revision No.
Review and Approval of Documents 1
Exh! bit 3 Determination of the Extent of Applicability of 1000-ADM 1291.01 ExwWT 7 (OUEST109 81)
EXHeT 7 f0LKST104 fD iM7 2 2)
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Review and Approval of Documents 1
EXHIBIT 4 Summary of Safety Review Process Alternatives inst TREA ME%
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- 1291 Not APPtDaLE e TRADITchAL MA%AGEWENT CONTROLS APPLY (NOTE 4 e Y2916 APPLO8Lt
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,a (UClear' ll GPU Nuclear Corporate l Number Policy and Procedure Manual l 1000-ADM-1291.01' I
Title Procedure for Nuclear Safety and Environmental Impact l Revision No.
Review and Approval of Documents l
3r I
EXHIBIT 5 Flow Chart for Matrix Sections I and 11 Documents 9"
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Review and Approval of Documents 1
EXHIBIT 6 Flow Chart for Matrix Section ill Documents Ec'S(77 I
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MUClear ll GPU Nuclear Corporate 1 Number Policy and Procedure Manual l 1000-ADM-1291.01 1
Title Procedure for Nuclear Safety and Environmental Impact i Revision No.
Review and Approval of Documents 1
3 1
EXHIBIT 7 Nuclear
(
SAFETY / ENVIRONMENTAL DETERMINATION AND 5o.59 REVIEW l
D.-w w occ No Rev No occumn ice Thes Determinaten form (or equivalent)is required for all documents in Sections I and il of the Matrices in l
Corporate Procedure 1000-ADM 129101:
1.
Is ins document type hsted on the Matrix?
UYes UNo if the answer to question 1 es yes, proceed to answer question 2 If the answer to queston 1 is no, then Pro-cedure 1004ADM-129101 is not apphcable. No documentaten is required. Refer to Section 4.15 for further informale and guidance.
- 2. Is tNs a substantive revision to the document? For examples of non substantive revisions, refer to Secten 23 A new document is considered to be equivalent to a substantrve revison.
Oyes CNo l
If the answer to questm 2 is yes then Procedure 1000 ADM-1291014 applicable Proceed to answer ques-tons 3 through 7 to determine the extent of procedure applicabihty and to assess the need for a wntten safe.
l ty evaluaton.11 the answer to question 2 is no, then Procedure 1004ADM-129101 *s not applicable and documentaten of this decison is not required.
Does this document or change have the potential to adversety affect nuclear safety or safe plant operatons?
- 3 Refer to Section 4.2.
Oyes ONo Does the document or change require revision of the systemkomponent descripton in the FMA or otherwise
- 4.
require levison of the Technical Spooficatons or any oi%er Licensir$g Basis Document?
Oyes ONo Does the document or change require revision of any procedural or operatog descripton in the FSAR. or
' 5.
otherwise require revison of the Technical Specifications or any other beensing Basis Document?
UYes CNo l
l
- 6 Are tests or expenments conducted which are not desenbed in the FMR. the Technical Specificatons, or i
any other Licensing Bas.3 Document?
Oyes CNo 7 Does tNs document involve any potential env-onmental impact? Refer to Section 3 4 Oyes CNo (11 yes, or if in doubt. lorward the document to Oual.ty and Radolog* cal Controis Divison or lo Environmental Lcensing for detailed evaluat~ n).
o
- lf any of the answers to questions 3. 4,5. OR 6 are yes, proceed to EXHIBli 8 and prepare a wntten saiety evaluaton. If the answers to 3,4,5. AND 6 are no, tNs preciudes the occurrence of an Unreviewed Sa'ety Queston or Technical Specificatons change. Provide wntten statements which support the determinaten that no unreve*ed Sa'ety Ovestion or Technical Specificaton change is invoNed. These wntien statements shall prov4e JustJ.caton for the "no" answers to queston 14. 5 and 6. Use the space provided for each quesion and attach additional sheets, if necessary
$_lgnatures Dates ewwer section Wa^490' Aespons1tse Tecnrweas Revenee cWe Aevveens)
N8??45 (06 s 1 E7-1
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GPU Nuclear Corporate l Number Policy and procedure Manual l 1000-ADM-1291.01 I
Title Procedure for Nuclear Safety and Environmental Impact Revision No.
Review and Approval of Documents l
3 l
EXHIBIT 8
' Nuclear SAFETY EVALUATloN L w. van Doc M Ae. ho Doc mes T4e The purpose of this Sa'ety Evalusten is to provide the bas <s for determming whether this document or change evolves an Unreviewed Safety Queston, a change to tre Technecal Spec 4ations or an unpect on nuclear sa'ety l
The followeg Questens must be answered, and reason (s) for each answer must be orthnded. A simple sta!ement of conclusen m itself is not suffcont. The scope and cepth of each reason should be commensurate with the safety sign 4ance and complenty of the proposed change.
- 1. ' is the ma gin of safety as defined in Lcensing Basis Documents tiher than the Tchncal Sp heatens reduced?
Oyes CNo 2.
Wdl smplementabon of the document adverseiy affect nuclear safety?
Cyes CNo The followeg questens compnse the $0.59 conseerstens and evaluaton to determee d an Unrevwwod i
. Safety Questen exists or if any change to the Techncal Specrheatens is required:
l 1 is the probabdity of occurrence or the consequences of an ace:$ent or malfuncton of equipment important to safety provcusty ovaiuated m the Safety Antsysis Report mcreased?
Cyes CNo is the poss;bshty for an acceent or maNncton of a different type than any evaluated prevously in the Sa ety 4
e Anaysis Report created?
Cyes CNo i is the mayn of safety as dehned an the basis for any Techn+ cal Specihcaten reduced?
Cyes CNo l
& Is a Techncal Speerheatens change, or a change to any other Lcensing Bas,s Document required?
Cyes CNo Reasons hr answers above (This constdutos a wntten safeh evaluaten. Use adodenal sheets if necessaryr if unsure of ans*er or d a "no" answer es not futty justifiable. then the answer must be checked "yes". If any answer above is "yes". an ampact on nuclear safety or an Unrev4wed Saiety Queston ersts. or a Technical Soecrbcatens change is reovired. Revse or redesign. or forward to Licenseg with any additenal doeurmenta.
bon to support a request for NRC approval pnor to impiemonteg approval (o g., Techncal Specification or
)
other L)censeg Basis Document change requests).
Sognatures Detes Peeggy Seebon MN Aes. 904 ?ocame 4 eve =or wee-ee; Saw 6 ;_;
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GPU Nuclear Corporate Number Policy and Procedure Manual 1000-ADH-1291.01 Title Procedure for Nuclear Safety and Environmental Impact Revision No.
Review and Approval of Documents 1
EXHIBIT 9 (UClear INmA CUmMCATION FORM ReepoNilde 1pehnical E-.f-':J.C4 Setety Revtewer NAne t.am Fve wine tw Pea comumdeNT/ LOCAn0N cart Pombs CCeepL,2Tto Quennsation ":;J--- 14.:
Responette Inchneel Rowwwer (RTR) indMouais shed meet or ecced the quairncanone of Al48 tans 411979 (N1411973) Soccon 4.4 ter Reactor Engneonne, inseumenamon and Contred. Chemetry and Radiochemsey Raeshon Proseccan and Quairry Asburence w or have sown @ ym of approgree emportow m thov specialty. As othere ened how a Bachelor's Degree e Engneenne or the Phyecal Saences and three years nucteer power en-ponence or eine shes how seen m years at approonene exponence e thov speoeny. Creet o.ard on.
ponence me be grven for advanced degrees on a one-forene been up t e masamum of huo (2) years, independent SetWy Renewer (ISR)
IndMouais shed coor have a Bachetor's Degree m Engreering or the Phyecal Soonces and Mve (5) years of prosessensi leves esponence in the area beme recewed or how nee (t) years of apprognate expenence e ther speaaNy Creet tenerd steenence mil be gngn for aftenced doyees on a onodor one baans up to a meaumum of two (2) years.
A. Summary of QuatAcenone.
- 1. Beceedor's Depeo CWe CW Mapor Gradusse Depos CWe CNo Mapor
- 2. Inchnscal E.zpertence A technscal esponence summary contameg the tonowing iniormecon must be enached to tNe form:
Demonsoon of E.xperience Type (nucceer or ren nucceer)
'M (WWR, PWR, or both)
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