ML19312B940

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Proposed Tech Spec 6.1.2 Re Establishment of Controls in Lieu of Onsite Review Committee
ML19312B940
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 02/28/1975
From:
DUKE POWER CO.
To:
Shared Package
ML19312B936 List:
References
NUDOCS 7911270728
Download: ML19312B940 (9)


Text

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o 6.0 ADMINISTRATIVE CONTROLS 6.1 ORGANIZATION, REVIEW, AND AUDIT 6.1.1 Organization 6.1.1.1 The station Manager shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence.

6.1.1.2 In all matters pertaining to actual operation and maintenance and to these Technical Specifications, the station Manager shall report to and be directly responsible to the Vice President, Steam Production, through the Manager, Nuclear Production. The organization is shown in Figure 6.1-2.

6.1.1.3 The station organization for Operations, Technical Services, and Maintenance shall be functionally as shown in Figure 6.1-1.

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Minimum operating chift requirements are specified in Table 6.1-1.

4 6.1.1.4 Incorporated in the staff of the station shall be supervisory and professional personnel meeting the minimum requirements encompassing the training and experience described in Section 4 of the ANSI 18.1-1971, " Selection and Training of Nuclear Power Plant Personnel."

i 6.1.1.5 Retraining and replacement of station personnel shall be in accordance with Section 5.5 of the ANSI 18.1-1971, " Selection l

and Training of Nuclear Power Plant Personnel."

6.1.2 Technical Review and Control 6.1.2.1 Activities a.

Procedures required by Technical Specification 6.4 and other procedures which affect station nuclear safety, and major changes thereto, shall be prepared by a qualified individual /orzanization.

The preparation of each such procedure, or procedure ch_ age, shall be checked by an individual /

group other than the individual / group which prepared the procedure, or procedure change, but who may be from the same organization as the individual / group which prepared the procedure, or procedure change.

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preparation and check of a procedure, and major changes thereto, shall include the determination as to whether or not each such procedure, or procedure change, involves an unreviewed safety question.

Such procedures, and procedure changes, shall be approved prior to use by the station Manager, the Operating Superintendent, the Technical Services Superintendent or the Maintenance Superintendent.

b.

Proposed tests and experiments which affect station nuclear safety and are not addressed in the FSAR or Technical Specifications shall be reviewed by the station Manager, the Operating Superintendent, the I

Technical Services Superintendent or the Maintenance' Superintendent.

49112W 6.1-1 Entire Page Revised

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c.

Proposed changes to the Technical Specifications shall be prepared by a qualified individual / organization.

The preparation of each proposed Technical Specifications change shall be checked by an individual / group other than the individual / group which prepared the proposed change, but who may be from the same organization as the individual / group which prepared the proposed change.

Proposed changes to the Technical Specifi-cations shall be approved by the station Manager.

d.

Proposed modifications to station nuclear safety-related structures, systems and components shall be designed by a qualified individual /

organization.

The design of each such modification shall be checked by an individual / group other than the individual / group which designed the modification but who may be from the same organization as the individual /

group which designed the modification.

This design and check of a proposed modification shall include the determination as to whether or not the modification involves an unreviewed safety question. Proposed modifications to station nuclear safety-related structures, systems and components shall be approved prior to implementation by the station Manager, the Operating Superintendent, the Technical Services Superin-tendent or the Maintenance Superintendent.

e.

Incidents reportable pursuant to Technical Specification 6.6.2.1 and violations of Technical Specifications shall be investigated and a report prepared which evaluates the occurrence and ihich provides recommendations to prevent recurrence.

Such reporcs shall be approved by the station Manager and transmitted to the Vice President, Steam Production, or his designee; and to the supervisor of the Nuclear Safety Review Unit.

f.

The station Manager shall assure the performance of special reviews and investigations, and the preparation and submittal of reports thereon, as requested by the Vice President, Steam Production.

g.

The station security program, and implementing procedures therefore, shall be reviewed at least annually.

Changes determined to be necessary as a result of such review shall be approved by the station Manager and transmitted to the Vice President, Steam Production, or his designee; and to the supervisor of the Nuclear Safety Review Unit.

h.

The station emergency plan, and implementing procedures therefore, shall be reviewed at least annually.

Changes determined to be necessary as a result of such review shall be approved by the station Manager and transmitted to the Vice President, Steam Production, or his designee; and to the supervisor of the Nuclear Safety Review Unit.

6.1.2.2 Records Records of the above activities shall be maintained.

6.1.3 Independent Review and Audit A review and audit program shall be established by the Nuclear Safety Review Unit (NSRU) of the Duke Power Company Steam Production Department.

6.1-2 Entire Page Revised

l 6.1.3.1 Function The NSRU shall function to provide independent review and audit of designated activities in the areas of:

a.

Nuclear power plant operations b.

Nuclear engineering c.

Chemistry and radiochemistry d.

Metallurgy e.

Instrumentation and control f.

Radiological safety g.

Mechanical and electrical engineering h.

Quality assurance practices 6.1.3.2 Organization The NSRU shall have primary responsibility for review and audit of a.

operational phase activities.

The supervisor of the NSRU shall schedule periodic formal meetings of the staff, or appropriate subparts thereof.

The period between these meetings shall not exceed 30 days.

b.

Consultants shall be utilized as determined by the supervisor of the NSRU to provide expert advice to the NSRU.

6.1.3.4 Subjects Requiring Review The following subjects shall be reported to and reviewed by the NSRU:

a.

The safety evaluations for (1) changes to procedures, equipment or systems, and (2) tests or experiments completed under the provisions of 10 CFR 50.59(b) to verify that such actions did not constitute an unreviewed safety question.

b.

Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in 10 CFR 50.59.

c.

Proposed tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59.

d.

Proposed changes in Technical Specifications or the Facility Operating Licenses.

e.

Violations of applicable statutes, codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.

f.

Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety.

g.

Incidents that are the subjects of non-routine reports submitted to the Commission.

nt re age evised 6.1-3

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Quality Assurance Department audits relating to station operations and actions taken in response to these audits.

6.1.3.5 Audits Audits of station activities shall be performed under the cognizance of the NSRU.

These audits shall encompass:

a.

The conformance of station operation to provisions contained within the Technical Specifications and applicable facility operating license conditions at least once per year.

b.

The performance, training and qualifications of the station staff at least once per year.

c.

The results of actions taken to correct deficiencies occurring in equipment, structures, systems or methods of operation that affect nuclear safety at least once per six months.

d.

The performance of activities required by the quality assurance program to meet the criteria of Appendix B to 10 CFR 50 at least once per two years.

e.

The station emergency plan and implementing procedures at least once per two years.

f.

The station security plan and implementing procedures at least once per two years.

g.

Any other area of station operation considered appropriate by the NSRU or the Vice President, Steam Production.

6.1.3.6 Responsibilities and Authorities a.

The NSRU shall report to and advise the Vice President, Steam Production, on those areas of responsit_lity specified in Specifications 6.1.3.4 and 6.1.3.5.

b.

Minutes shall be prepared and forwarded to the Vice President, Steam Production, and to the Senior Vice President, Production and Transmission, following each formal meeting of the NSRU.

c.

Recotds of activities performed in accordance with Specifications 6.1.3.4 and 6.1.3.5 shall be maintained.

d.

Audit reports encompassed by Section 6.1.3.5 shall be forwarded to the Vice President, Steam Production, to the Senior Vice President, Production and Transmission, and to the management positions responsible for the areas audited.

Entire Page Revised 6.1-4

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Performance Operating Engineer Maintenance Engineer Engineer SRO Shift Instrument and ilealth Physics Supervisors Control Supervisor SRO Engineer

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STATION ORGANIZATION CHART

.s FIGURE 6.1-1 l14/9/1

1 Senior Vice President Production and Transmission Vice President Nuclear Safety Steam Production Review Unit Manager Nuclear Production Manager Oconee Nuclear Station OCONEE NUCLEAR STATION IIANAGEMENT ORGAfHZATION Figure 6.1-2 6.1-7 Entire Page Revised

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6.2 ACTION TO BE TAKEN IN TIIE EVENT OF AN INCIDENT REPORTABLE TO THE COMMISSION 6.2.1 Any incident reportable to the Commission pursuant to Specifi-cation 6.6.2 shall be investigated promptly by the station Manager.

6.2.2 The Vice President, Steam Production, shall be notified of any such reportable incident. A written report shall be prepared which describea -he circumstances leading up to and resulting from the inciaenu and shall recommend appropriate action to prevent or minimize the probability of a recurrence. The report shall be submitted to the Vice President, Steam Pro-duction, and to the supervisor of the Nuclear Safety Review Unit.

6.2.3 The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.6.2.

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6.2-1 Entire Page Revised

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.s 6.3 ACTION TO BE TAKEN IN THE EVENT A SAFETY LLMIT IS EXCEEDED 6.3.1 If a safety limit is exceeded, the reactor shall be shut down imediately and maintained in a safe shutdown condition until the Comission authorizes resumption of operation.

6.3.2 The violation of a safety limit shall be reported to the Com-mission, the Vice President, Steam Production, and to the supervisor of the Nuclear Safety Review Unit immediately.

6.3.3 A report shall be prepared which describes (1) applicable circumstances preceding the violation, (2) effects of the violation upon structures, systems or components, and (3) corrective action taken to prevent recurrence.

The report shall be reviewed by the Operating Superintendent and the station Manager.

The report shall be submitted to the Vice President, Steam Production, and the supervisor of the Nuclear Safety Review Unit.

6.3.4 A report of the violation, with appropriate analyses and corrective action to prevent recurrence shall be submitted to the Comission within 10 days of the violation.

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6.3-1 Entire Page Reviced l

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