ML19312C008
| ML19312C008 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 06/19/1975 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML19312C005 | List: |
| References | |
| NUDOCS 7911270782 | |
| Download: ML19312C008 (10) | |
Text
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6.0 ADMINISTRATIVE CONTOLS 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.
i 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.
Minimum operating shift requirements are specified in Table 6.1-1.
6.1.1.4 Incorporated in the staff of the station shall be supervisory and professional personnel meeting the minimum requirements encompas-sing the training and experience described in Section 4 of the ANSI N18.1-1971, " Selection and Training of Nuclear Power Plant Personnel."
6.1.1.5 Retraining and replacement of station personnel shall be in accordance with Section 5.5 of the /LNSI N18.1-1971, " Selection sad Training of Nuclear Power Plant Personnel."
6.1.2 Technical Review and Control 6.1.2.1 Activities Procedures required by Technical Specification 6,1 and other procedure s a.
which af fect station nuclear safety, and change $ (other than editoria:
or typographical changes) thereto, shall be prepared by a qualified indisidual/
organization. Each such procedure, or procedure change, shall be rev.ewed by an individual / group other than the individual / group which prepared the procedure, or procedure change, but who may be from the same organizaaion as the individual / group which prepared the procedure, or procedure change.
Such procedures and procedure changes may be approved for temporary use by two members of the station staff, at least one of whom holds a Senior Reactor Operator's License on the unit (s) affected.
Procedures and procedure changes shall l be approved prior to use or within seven days of receiving temporary approv-al for use by the station Manager; or by the Operating Superintendent, the 1
Technical Services Superintendent or the Maintenance Superintendent, as previously designated by the station Manager.
b.
Proposed changes to the Technical Specifications shall be prepared by'a qualified individual / organization.
The preparation of each proposed Tech-nical Specifications change shall be reviewed by an individual / group other than the individual / group which prepared the proposed change, but who may 6.1-1 you s'to } U
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be from the same organization as the individual / group which prepared the proposed change. Proposed changes to the Technical Specifications shall be approved by the station Manager.
Proposed modifications to station nuclear safety-related structures, sys-c.
tems and components shall be designed by a qualified individual / organization.
Each such modification shall be reviewed 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.
Proposed modifications to station nuclear safety-related structures, systems and components shall be approved prior to implementation by the station Manager; or by the Operating Superintendent, the Technical Services Super-intendent, or the Maintenance Superintendent, as previously designated by the station Manager.
d.
Individuals responsible for reviews performed in accordance with 6.1.2.1.a, 6.1.2.1.b, and 6.1.2.1.c shall have a minimum of five years of technical-experience, of which a minimum of one year shall be nuclear experience. A i
maximum of four years of this five years of experience may be fulfilled by academic or related technical training, Proposed tests and experiments which affect station nuclear safety and are e.
not addressed in the FSAR or Technical Specifications shall be reviewed by the station Manager; or by the Operating Superintendent, the Technical Servi-ces Superintendent or the Maintenance Superintendent, as previously desig-J nated by the station Manager.
f.
Incidents reportable pursuant to Technical Specification 6.6.2.1 and vio-lations of Technical Specifications shall be investigated and a report pre-pared which evaluates the occurrence and which provides recommendations to prevent recurrence.
Such reports 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.
g.
The station Manager shall assure the performance of special reviews and investigations, and the preparation and subuittal of reports thereon, as requested by tne Vice Presiuent, Steam Production.
h.
The station security program, and implementing procedures, 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 trans-mitted to the Vice President, Steam Production, or his designee n-i to the supervisor of the Nuclear Safety Reviev Unit.
i.
The station emergency plan, and implementing procedures, 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 trans-mitted to the Vice President. Steam Production, or his designee; and to the supervisor of the Nuclear Safety Review Unit.
6.1-2
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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.
i 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.
Administrative control and quality assurance practices 6.1.3.2 Organization The NSRU shall have primary responsibility for review and audit of opera-a.
tional phase activities. The supervisor of the NSRU shall schedule periodic formal meetings of the staff, or appropriate subparts thereof, for the pur-pose of assuring interaction in reviews of specific operational phase acti-vities.
The period between these meetings shall not exceed 60 days.
b.
Members of the NSRU shall have a minimum of seven years of technical exper-ience, of which a minimum of three years shall be in one or more of the areas given in 6.1.3.1.
A mnximum of four years of this seven years of experience may be fulfilled by academic or related technical training.
Consultants shall be utilized as determined by the supervisor of the NSRU c.
to provide expert advice to the NSRU.
6.1. 3. 3 Subjects Requiring Review The following subjects shall be reported to and reviewed by the NSRU:
The safety evaluations for (1) changes to procedures, equipment or systems, a.
and (2) tests or experiments completed under the provisions of 10 CFR 50.59 (a)(1) to verify that such actions did not constitute an unreviewed safety question.
b.
Proposed changes to procedures, equipment or systems which involve an un-reviewed safety question as defined in 10 CFR 50.59.
6.1-3 4
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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.
l e.
Violations of applicable statutes, codes, regulations, orders, Technical
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Specifications, license requirements, or of internal procedures or instruc-l tions having nuclear safety significance.
i f.
Significant operating abnormalities or deviations from normal and expected performance of station equipment that affect nuclear safety.
l g.
Incidents that are the subjects of non-routine reports submitted to the Commission.
h.
Quality Assurance Department audits relating to station operations and actions taken in response to these audits.
i 6.1.3.4 Audits Audits of station activities shall be performed under the cognizance of the j
NSRU. These audits shall encompass:
a.
The conformance of station operation to provisions contained within the Technical Specifications and applicable facility operating license condi-tions at least once per year.
b.
The performance, training and qualifications of the station staff at least j
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.
I 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.
The station emergency plan and implementing procedures at least once per e.
two years.
f.
The station security plan and implementing procedures at least once per two years.
g.
Any otner area of station operation considered appropriate by the JSRU or tne Vice President, Steam Production.
6.1. 3. 5 Responsibilities and Authorities a.
The NSRU shall report to and advise the Vice President, Steam Production, on those areas of responsibility specified in Specifications 6.1.3.3 and 6.1.3.4 l
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f 6.1-4
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b.
Minutes shall be prepared and forwarded to the Vice President, Steam Produc-tion, and to the Senior Vice President, Production and Transmission, within 14 days following each formal meeting of the NSRU.
I c.
Records of activities performed in accordance with Specifications 6.1.3. 3 and 6.1.3. 4 shall be maintained.
d.
Audit reports encompassed by Section 6.1.3. 4 shall be forwarded to the Vice j
President, Steam Production, and to the Senior Vice President, Production and Transmission, and to the management positions responsible for the areas audited within 30 days of completion of each audit.
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1 6.1-5
Table 6.1-1 Minimur Operating Shift Requirements With Fuel in t!.e Three Reactor Vessels Unit i or 2 Above Units 1 and 2 Above Uni t a.
I or 2 Above Units 1 and 2 Cold Units 1. 2 Units 1.2 Minimum AtC Cold Shutdown; l'ntt Cold Shutdown; Unit Cold Shutdown; Unit Shutdown; Unit 3 and 3 Above and 3 Cold L6 tense k cqu i s emen t i Cold $hutJ.~n i Cold Shutd vn 3 Above Cold Shutdown Above Cold Shutdan Cold Shutdown Shutdown Senius Heac tos oper.s tor 2
2 2
2 3
2 Reactor Operatur 4
4 4
4 4
3 s.)
11nliiansed operator 2
2 2
2 4
AJJithonal kcquirecients:
m 1.
une liarn3rd.-pesator per unit sh.e l l t,e in the Control Hoom at.a l l times when there is l'ue!
in the s e.ac t or vessel g
am 2.
T w.. licensed operators sha.1 he in alie Cont rol Ro.un during startup and scheduled shutdown of a a c.a. t or,
s.
At least one lisensed operator sh.ill be in the reactor building when fuel handling operations in t h*e reattor building are in progress.
4.
An operator holding a Senior Heactor operator license and assigned no other operational duties sh. ell be in darest iharge os retueling oper.itions 5.
At least one person p : shift shall have suitleirut training to perform routine health physics acquirements.
ti.
ll the eomputer for. reactot is i nope r a b l e-l'or Im s t ea than e igle t hours, an operator in addit!On to s how s i qu i re.4.above shsil suppl.
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Manager Oconce Nuclear Station
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i Operating Maintenance Technical Services Superintendent Superintendent
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Superintendent SRO as Performance Maintenance L
Operating Engineer 4
Engineer Engineer SRO Shift Instrument and
!!ealth Physics Supervisors Control Supervisor SRO Engineer Chemist Shift Personnel E'
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uni OCONEE NUCLEAR STATION STATION ORGANIZATION CHART j FicuRE 6.1-1 l14/9/1
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s, Senior Vice President Production and Transmission Vice President Nuclear Safety Steam Production
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Review Unit Manager Nuclear Production i
Manager Oconee Nuclear Station
'0 OCOItEE NUCLEAR STATION 4
fiANAGEMENT ORGANIZATION Figure 6.1-2 6.1-8 Entire Page Revised
6.2 ACTION TO BE TAKEN IN THE EVENT OF AN INCIDENT REPORTABLE TO THE i
COMNISSION 4
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 describes the circumstances leading up to and resulting from the incident 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 Entire Page Revised
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- 6. 3, ACTION TO BE TAKEN IN THE EVENT A SAFETY LIMIT IS EXCEEDED 6.3.1 If a safety limit is exceeded, the reactor shall be shut down immediately and maintained in a safe shutdown condition until the Commission authorizes resumption of operation.
a 6.3.2 The violation of a safety limit shall be reported to the Com-i 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 Commission within 10 days of the violation.
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4 6.3-1 Entire Page Revised i
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