ML19322B367
| ML19322B367 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 02/13/1976 |
| From: | Purple R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19322B358 | List: |
| References | |
| NUDOCS 7912020213 | |
| Download: ML19322B367 (13) | |
Text
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UNITED STATES NUCLEAR REGULATORY CCMMISrlON C. 20555 W ASHINGToN, D.
DUKE POWER COMPANY _
0 DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT 3_
AMENDMENT TO FACILITY OPERATING LICENSE _
Amendment No.I 5 License No. DPR-55 has founi that:
The Nuclear Regulatory Commission (the Commission) f 1.
The application for amendment by Duke Power Company 19, 28, 1975, as supplemented June A.
d licensee) dated February and December 5, 1975, complies with the standards an ded requirements of the Atomic Energy Act of 1 forth in 10 CFR Chapter I; i tion, The facility will operate in conformity with the appl ca l tions of the provisions of the Act, and the rules and regu a B.
the Commission; thorized There is reasonable assurance (i) that the activitie by this amendment can be conducted w C.
ii egulations; i
will be conducted in compliance with the Commiss on s r defense and security or to the health an i
The D.
and d not be An environmental statement or negative d
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h i al Accordingly, the license is amended,by a change to the Te i
Specifications as indicated in the attachment to this l ce 2.
DPR-55 is amendment and Paragraph 3.B of Facility License No.
hereoy amended to read as follows:
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Technical Specifications The Technical Specifications contained in Appendices A and B, as revised, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective March 15 1976.
FOR 'lllE NUCLEAR REGULATORY COMMISSION l
prisinal signed bx R. A. Purple i.
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Robert A. Purple, Chief Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
I Changes to the Technical Specifications Date of Issuante: FEB 131976 i
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4 ATTACIBENT 'IU LICENSE AFENDFENTS AMENDMENT NO.I 8TO FACILITY LICENSE NO. DPR-38 AMENDFENT'NO.1 STO FACILITY LICENSE NO. DPR-47 AFENDMENT h'O.
FACILITY LICENSE NO. DPR-55 DOCKET NOS. 50-269, 50-270 AND 50-287 Revise Appendix A as follows:
Remove Pages Insert Pages
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6.1-1 6.1-1 6.1-2 6.1-2 6.1-3 6.1-3 6.1-4 6.1-4 0.1-5 6.1-5 6.1-6 6.1-6 6.1-7 6.1-7 6.1-8 6.1-8 6.2-1 6.2-1 6.3-1 6.3-1 k
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6.0 ADMINISTRATIVE CONTOLS_
i 6.1 ORGANIZATION, REVIEW, AND AUDIT 6.1.1 Organization The station Manager shall be responsible for overall facility 6.1.1.1 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.
Minimum operating shift requirements are specified in Table 6.1-1.
6.1.1.4 Incorporated in the staff of the station shall be personnel j
meeting the minimum requirements encompassing 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 replacemen,L of station personnel shall be in accordance with Section 5.5 of the MSSI N18.1-1971, " Selection and Training of Nuclear Power Plant Personnel."
6.1.2 Technical Review and Control 6.1.2.1 Activities Procedures required by Technical Specification 6.4 and other procedures
- a. - which af fect station nuclear saf ety, and changes (other than editorial or typographical changes) thereto, shall be prepared by a qualified individual /
organization.
Each such procedure, or procedure change, shall be reviewed 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.
Such procedures and procedure changes may be approved for temporary use by two members of the station staf f, at least one of whom holds a Senior Reactor Operator's License on the unit (s) affected.
Procedures and pcocedure changes shalf 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 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
<1 6.1-1 FEB 131976,
t 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 indivilcal/ group which designed the modification but who may be from the same organizat on as the individual / group which designed the modification.
i Proposed modifi ations to station nuclear safety-related structures, systems and components shall be approved prior to implementation by the staticn Manager; or by the Operating Superintendent, the Technical Services Supar-intendent, or the Maintenance Superintendent, as previously designated by the station Manager.
- d. Individuals responsibic for reviews performed in accordance with 6.1.2.1.a.
6.1.2.1.b, and 6.1.2.1.c shall be members of the station supervisory staff, previously designated by the station Manager to perform such reviews.
Each such review shalJ include a determination of whether or not additional, cross-disciplinary, review is necessary.
If deemed necessary, such review shall be performed by the nppropriate designated station review personnel.
Proposed tests and experiments which affect station nuclear safety and are c.
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-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 Director of the Nuclear Safety Review Board.
- g. ' 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 Presioent, 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; and to the Director of the Nuclear Safety Review Board.
i.
The station emergency plan, and implementing procedures, shall be reviewed at least annually.
Changes determined to be necessary as a result of such revicw shall be approved by the station Manager and trans-mitted to the Vice President. Steam Production, or his designee; and to the Director of the Nuclear Safety Review Board.
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6.1-2 FEB 1 31976
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t 6.1.2.2 Records Records of the above activities shall be maintained.
6.1.3 Nuclear Safety Review Board 6.1.3.1 Function The NSRB shall function to provide independent review and audit of designated activitics in the areas of:
a.
Nuclear powcr plant operations b.
Nuclear Engineering c.
Chemistry and radiochemistry d.
Metallurgy c.
Instrumentation and control f.
Radiological safety Mechanical and electrical engineering g.
h.
Administrative control and quality assurance practices 6.1.3.2 organization The Director, members and alternate members of the NSRB shall bc a.
formally appointed by the Vice President, Stcan Production; shall have an academic degree in an engineering or physical scoince ficid; and in addition, shall have a minimum of five years technical experience,-
of which a minimum of three years shall be in one or more areas given in 6.1.3.1.
b.
The NSRB shall be composed of at 1 cast five members, including the Director, Members of the NSRB may be from the Steam Production Department, from other departments within the Company or from external to the Company.
A maximum of one member of the NSRB may be from the
'Oconce Nuclear Station staff.
Consultants may be utilized by the NSRB to provide expert advice to the c.
NSRB, as determined necessary by the Director of the NSRB.
d.
Staff assistance may be provided to the NSRB in order to promote the proper, timely and expeditious performance of its functions.
The NSRB shall meet at least once per six months.
The period between c.
such meetings shall not exceed eight months.
f.
A quorum of the NSRB shall consist of the Director, or his designated alternate, and at least two other USRB members or alternate members.
No morc than a minority of the quorum shall have line responsibility
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for operation of Oconce Nuclear Station.
1 6.1.3.3 Subjects Requiring Review The following subjects shall be reported to and revicwed by the NSRB:
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6.1-3' FEB 13 876
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and (2) tests or experiments completed under the prov a.
50.59(a)(1) to verify that such actions did not constitute an unreviewed safety question.
b.
Proposed changes to procedures, equipmer.
reviewed safety question as defined 'a 10 CFR 50.59.or systems which involve an un-Proposed tests or experiments which involve an unreviewed safety quest' ion c.
as defined in 10 CFR 50.59.
d.
Proposed changes in Technical Specifications or the Facility Operating Licenses.
Violations of applicable statutes, codes, regulations, orders,' Technical e.
Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.
f.
Significant operating abnprmalities or deviations from normal and expected performance of station cqeipment that affec. nuclear safety.
g.
Incidents that are the subject 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.
- l 6.1.3.4 Audits Audits of station activities shall be performed under the cognizance of the NSRB.
These audits shall encompass:
The conformance of station operation to provisions contained within the a.
Technical Specificatio'ns 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.
The results of actions taken to correct deficiencies occurring in equip-c.
ment, 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 The station emergene_y. plan and implementing procedures at least once e.
two years.
f.
The station secur15y p'lan'and implementing procedures at least once per two years.
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6.1-4 FEB 131976 p-Ls
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g.
Any other area of station operation considered appropriate by the NSRB or the Vice President, Steam Production.
6.1.3.5 Responsibilities and Authorities a.
The NSRB 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.
b.
Minutes shall be prepared and forwarded to the Vice President, Steam Pro-duction, and to the Senior Vice President, Production and Transmission, within 14 days following each formal meeting of the NSRB.
Records of activities performed in accordance with Specifications 6.1.3.3 c.
and 6.1.3.4 shall be maintained.
d.
Audit reports encompassed by Section 6.1.3.4 shall be forwarded to the Vice President, Steam Production, and to the Senior Vice President, Production and Transmission, and to the management positions recponsible for the areas audited within 30 days of completion of each audit.
6.1-5 FEB 131976
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Table 6.1-1 l.
Minimum Operating Shift Requiremento With Fuel in the Three Reactor Vessels
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Unit 1 or 2 Above Units 1 and 2 Above Units 1 or 2 Above Units 1 and 2 Cold Units 1. 2 Units 1. 2 Minimum AEC Cold Shutdown; Unit Cold Shutdown; Unit Cold Shutdown; Unit Shutdown; Unit 3 and 3 Above and 3 Cold License Requirement 3 Cold Shutdown 3 Cold Shutdown 3 Above Cold Shutdown Above Cold Shutdown Cold Shutdown Shutdown 4
Senior Resctor Operator 2
2 2
2 3
2 i
4 4
4 4
4 3
ReictorOperat.ch Unlicensed opnator 2
2 2
2 4
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Additional Requirements:
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,e 1.
une licensed operator per unit shall be in the Control Room at all times when tsere is fuel in the reactor vessel p
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- 2..Two licensed operators shall be in the Control Room during startup and scheduled shutdown of a Q
reactor.
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At least one licensed operator shall he in the reactor building when fuel handling operations in th*e reartor building are in progress.
4.
An operator holding a Senior Reactor Operator license and assigned no other operational duties shall be in direct charge of refueling operations.
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5.
At least one person per shift shall have sufficient training to perform routine health physics requirements.
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6.
If the computer for a reactor is inoperable for more than eight hours, an operator in addition
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required ahi,v sh.iin suppie cnt the shift crew.
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Manager Oconee Nuclear Station l
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Maintenance Technical Services Operating Superintendent Superintendent Superintendent
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Engineer Engineer Enginee,r
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4 SRO Instrument and Shift l
Health Physics Control Supervisors Supervisor SRO Engineer
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i Shift Chemist E'
Personnel 3
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OCONEE NUCLEAR STATION STATION ORGANIZATION CMART a
1 FIGURE 6.1-1 l14/9/1 i-
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Senior Vice President Production and Transmission Vice President Steam Production Nuclear Safety Review Board Manager
.s Nuclear Production Manager Oconee Nuclear Station ocurcath OCONEE NUCLEAR llANAGEMENT ORGANIZAT Figure 6.1-2 I
6.1-8 Entire Page Revised FEB 131976
I 6.2 ACTION TO BE TAKEN IN THE EVENT OF A' REPORTABLE OCCURRENCE 6.2.1 Any reportable occurrence shall be investigated promptly by the station Manager.
6.2.2 The Vice President, Steam Production, shall be notified of any reportable occurrence.
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 Production, and to the Director of the Nuclear Safety Review Board.
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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.2 6.2-1 Entire Page Revised FEB 131976 '
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6.3 ACTION TO BE TAKEN IN THE EVENT A SAFETY LIMIT 6.3.1 immediately and maintained in a safe shutdo the Commission 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 Director of the Nuclear Safety Review Board 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.
shall be reviewed by the Operating Superintendent and the The report station Manager.
President, Steam Production, and theThe report shall be submitted Director of the Nuclear Safety Review Board.
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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h 6.3-1 Entire Page Revised L
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