ML19331E140
| ML19331E140 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 09/23/1974 |
| From: | Goller K US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19331E139 | List: |
| References | |
| NUDOCS 8009050554 | |
| Download: ML19331E140 (15) | |
Text
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UNITED STATES
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ATOMIC ENERGY COMMISSION i.i'** y 7
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DUKE POWER COMPAclY DOCKET NO. 50-269 OC0f1EE flVCLEAR STATI0ft, UtilT 1 AME!1Df'ENT TO FACILITY OPERATIt!G LICE *!SE Amendment fio. 4 License fio. OPR-33 1
The Admic Energy Commission (the Commission) having found that:
A.
The application for amenwent by Duke Power Comoany (the licensee) dated August 19, 1974, complies with the standards and requirc: ents of the Atomic Energy Act of 1954, as anended, and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will ocarate in confornity with the aonlication.
the provisions of the Act, and the rules and regulations or :ne Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the neaitn and safety of the public, and (ii) that such activities will be conducted in ccmpliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
Prior public notice of this amend::'ent is not recuired since the amendraent does not involve a significant hazards consideration.
2.
Accordingly, the license is amended by a change to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 3.B. of Facility License No. OPR-38 is i
hereby amended to read as follows:
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. "B.
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, as revised by issued changes thereto through Change No. 14 "
3.
This licente amendment is effective as of the date of its issuance.,
FOR THE ATOMIC EtlERGY C0ft1ISS10fl
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Karl R. Coller, Assistant Director for Operating Reactors Directorate of Licensing
Attachment:
Change *;o. 14 to Tecn11 cal Seccifications Date of Issuance: SeP tember 23, 1974-
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ATOMIC ENERGY COMMISSION
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'* l waswiworow. o.c. ps4s DUKE POWER C0!'PANY DOCKET NO 50-270 OCONEE tiUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY CPERATING LICENSE Amendment 'lo. 4 License tio. OPR-47 1.
The Atomic Energy Commission (the Ccr. mission) h3ving found that:
A.
The application for amendment by Duke Power Company (the licensee) dated August 19, 1974, complies with the standards and requirerents of the Atomic Energy Act of 1954, as amended, and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility sill cecrate in conformity with the application, the provisions of the Act, and the rules and regulations of the Connission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can iae conducted without endangering the healtn and safety of the public, and (ii) that such activitics will be conducted in compliance with the Cormission's regulations; 4
D.
The issuance of this anendment will not be inimical to the comron defense and security or to the health and safety of the public; and-E.
Prior public notice of this arandment is nat recuired sir.ce the amendment does not involve a significant hazards consideration.
2.
Accordingly, the license is amended by a change to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 3.B. of Facility License No. DPR-47 is hereby amended to read as follows:
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"B.
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, as revised by issued changes thereto through Change tio. 9."
3.
This license amendment ~is effective as of the date of its issuance.
FOR Tile AT0111C Ef4ERGY C0!411SSI0tl
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Karl R. Goller, Assistant Director 3'
for Operating Reactors Directorate of Licensing
Attachment:
Change flo. 9 to Technical Specifications Date of Issuance: September 23, 1974 5
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ATOMIC ENERGY COMMISSION g;
-7 wasuiwarou. o.c. zos4s DUKE POWER COMPANY 00CKET NO. 50-287 OC0 flee NUCLEAR STATIO!1, Uti!T 3 AMENDt1EtlT TO FACILITY OPERATitiG LICENSE Amendment t!o. 1 License flo. OPR-55 1.
The Atomic Energy Ccamission (the Commission) having found that:
A.
The application for amendment by Duke Power Company (the licensee) dated August 19, 1974, complies with the standards and requirec.cnts of the Atomic Energy Act of 1954, as amended, and the Cormission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commissicn; C.
There is reasonable assurance (i) that the activities authori:cd by this amendment can be conducted without endancerino the health and safety of the public, and (ii) that such activities will be conducted in compliance witn the Commission's regulations; D.
The issuance of this amendment will not be ininical to the ccmnon defense and security or to the health and safety of the,'ablic; and E.
Prior public notice of this amendment is not required since the amendment does not involve a significant hazards consideration.
2.
Accordingly, the license is amended by a change to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 3.B. of Facility License No. Of R-55 is hereby amended to read as follows:
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,. "B.
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, as revised by issued changes thereto through Change flo.1."
3.
This license amendment is effective as of the date of its issuance.
FOR THE ATOMIC ENERGY COUNISSION
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Karl R. Goller, Assistant Director for Operating Reactors Directorate of Licensing Attachmen.*.:
Change flo. I to Technical Specifications Date of Issuance: eeptember 23, 1974
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3 ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 4 TO FACILITY LICENSE NO. DPR-38, CHANGE NO. 14 TO TECHNICAL SPECIFICATIONS; AMENDMENT NO. 4 TO FACILITY LICENSE NO. DPR-47, CHANGE NO. 9 TO TECHNICAL S?ECIFICATIONS; AMENDMENT NO. 1 TO FACILITY LICENSE NO. DPR-55, CHANGE NO. 1 TO TECHNICAL SPECIFICATIONS DUKE POWER COMPANY OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 DOCKET NOS. 50-269, 50-270, AND 50-287 Revise Appendix A as follows:
Remove pages 6.1-1, 6.1-1, 6.1-3, 6.144, 6.1-7, 6.1-8, 6.2-1, and 6.3-1 and insert the attached pages.
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O SEP 2 3 }974 6.0 ADMINISTRATIVE C0h"rROLS 6.1 ORGANIZATION, REVIEW, AND AUDIT 6.1.1 Organization 6.1.1.1 The station Manager is directly responsible for the safe operation of the facility.
6.1.1.2 In all matters pertaining to actual operation and maintenance and to these Technical Specifications, the station Kanager shall report to and be directly responsible to the Assistant Vice President, Steam 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 encompassing the training and experience described in Section 4 of the ANSI 18.1, " 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 ANSI 18.1, " Selection and Training of Nuclear Power Plant Personnel."
6.1.2 Review and Audit In matters of nuclear safety and radiation exposure, review and audit of station operation, maintenance, and technical matters shall be provided by two committees as follows:
(Reference Figure 6.1-2) 6.1.2.1 Station Review Connittee a.
Membership The station Manager shall appoint an on-site review committee consisting l14/9/1 of at least five members of the station supervisory staff.
Representation shall be provided from Operations and from Technical Services. Membership shall include expertise appropriate to the items being considered by the committee.
The chairman of the on-site review committee shall be appointed by the station Manager.
l14/9/1 b.
Meeting Frequency This committee shall meet at least once each month and as required on call by the chairman.
6.1-1 g
SEP 2 31974 c.
Quorum The chairman plus two members shall constitute a quorum.
d.
Responsibilities
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' The committee shall have the following responsibilities:
1.
Review all new procedures or changes to existing procedures determined by the station Manager or his designate to affect operational safety.
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2.
Review station operation and safety considerations.
3.
Review abnormal occurrences, unusual events, and violations of Technical Specifications and make recommendations to prevent recarrence.
4.
Review all proposed tests that affect nuclear safety or radiation safety.
5.
Review proposed changes to Technical Specifications and safety-i related changes or modifications to the station design.
e.
Authority The Station Review Committee shall make recommendations to the station i
Manager regarding Specification 6.1.2.1-d.
l14/9/1 f.
Records Minutes of all meetings of the committee shall be kept at the station, and copies shall be sent to the station Manager, Assistant Vice President l14f9/1 Steam Production, and the chairman of the Nuclear Safety Review Committee.
6.1.2.2 Nuclear Safety Review Committee a.
The Executive Vice President and General Manager shall appoint a Nuclear Safety Review Committee having responsibility to verify that operation of the station is consistent with company policy and rules, approved operating procedures, and license provisions; to review important pro-posed station changes, and tests; to verify that abnormal occurrences and. unusual events are promptly fnvestigated and corrected in _ manner which reduces the probability of recurrence of such events; and to detect trends which may not be apparent to a day-to-day observer.
b.- The activities of the Nuclear Safety Review Committee shall be guided by a written charter that contains the following:
Subjects within the purview of the committee Responsibility and authority Mechanisms - for convening meetings Provisions for use of specialists or subgroups 6.1-2
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SEP 2 3 574 Authority for access to station records Reporting requirements
' Identification of management position to which the group reports Provisions for assuring that the committee is kept informed of matters within its purview c.
The committee shall be composed of:
Chairman At least two members from the Steam Production Department.
(May include station Manager but not other Oconee ' Nuclear Station personnel.)
14/9/1 At least two members from the Zngineering Department Others deemed advisable.
(May include consultant from outside the company.)
The committee shall elect a vice chairman.
Qualified alternates shall be appointed or other provisions shall be made for covering the absence of full-time members of the group. The use of alternates shall be. restricted to legitimate and unavoidable absences of j
principals.
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d.
Qualifications:
i At least one-half of the members of the committee (and/or alternates i
attending a specific meeting) shall have extensive nuclear experience 4
and all members and alternates shall be engineering or. science graduates.
No more than a minority of the members or alternates shall have a direct line responsibility for station operation. All members shall have a l
minimum of three years professional level experience in nuclear services, nuclear station operation, or nuclear engineering and the necessary overall nuclear background to detect when to call consultants and contractors for dealing with complex problems beyond the scope of their own organization.
e.
Members of the committee shall collectively have the capability required to review the areas of:
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Nuclear Power Station Operations 2.
Nuclear Engineering -
3.
Chemistry and Radiochemistry 4.
Metallurgy S.
Instrumentation and Control 6.' Radiological 1 Safety 7.
Mechanical and Electrical Engineering 8.
Other appropriate fields associated with the unique characteristics of the Oconee Nuclear Station When the nature of a particular situation dictates, special consultants shall be uti.lized'to provide expert advice to the committee.
6.1-3
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'SEP 2 31974 f.
Meeting Frequency:
The committee shall meet.at least three times per year at intervals not to exceed five months and as required o". call by the-chairman. During the period of initial operation, this t.ommittee shall meet at least once per calendar quarter.
g.
Quorum:
The chairman or vice-chairman plus three members, or appointed alternates, shall constitute a quorum. No more than a minority of the quorum shall have direct line responsibility for station operation.
h.
Meeting Minutes:
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Minutes of all scheduled meetings of the committee shall be prepared and shall identify all documentary materials reviewed.
These minutes shall be formally approved, retained, and also promptly distributed to the Executive Vice President and General Manager; Senior Vice President, 4
Engineering and Construction; Senior Vice President, Production and Trans-mission; Vice President, Design Engineering; Assistant Vice President, Stean Production; and station Manager. A copy of these minutes shall be 10/9/,
kept ou file at the station.
1.
As a safety review to the normal operating organization, the committee shall review the following:
1.
Proposed tests and experiments, and results thereof, when these con-stitute an unreviewed safety question defined in 10CFR50.59.
2.
Proposed ch'anges in equipment or systems which constitute an unreviewed safety question defined in 10CFR50.59, or which are referred by the operating organization.
3.
All requests to the AEC/ DOL for changes in Technical Specifications or' license that involve unreviewed safety questions as defined in 10CFR50.59.
t 4.
Violations of statutes, regulations, orders, Technical Specifications, license requirements, or internal procedures, or instructions having safety significance as determined by the NSRC.
5.
Abnormal occurrences or unusual events as defined in 1.0 of these specifications.
6.
Special reviews.or investigations as required by the Assistant Vice President, Steam Production, or the station Manager.
l14/9/1 6.1-4 w
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Mana.ger Oconee Nuclear Station I
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Ms1ntenance Operating Technical Services Superintendent Superintendent
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Superintendent SRO
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Maintenance 4
Performance Operating Engineer
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Engineer Engineer SRO Instrument and Shift liealth Physics Control Supervisor Supervisors Engineer GRO Shift Chemist Personnel
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SRO - Senior Reactor Operator License frowf OCONEE NUCLEAR STATION g
STATION ORGANIZATION CilART 2
i, ce FIGURE 6.1-1 14/9/1 e2 i
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SEP 2 31974 Executive Vice President and General Manager
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t Senior Vice President Nuclear Safety Production and Transmission Review Committee Assistant Vice President Steam Production Manager
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Oconee Nuclear Station
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f Station Review Committo OCONEE NUCLEAR STATION MANAGEMENT ORGANIZATION CHART,
FIGURE 6.1-2 l'/9/1 c < o... A t_a
SEP 2 31974 6.2 ACTION TO BE TAKEN IN THE EVENT OF AN ABNORMAL OCCURRENCE OR UNUSUAL EVENT 6.2.1_
Any abnormal occurrence or unusual event shall be investigated promptly by the station Manager.
6.2.2 The station Manager shall promptly notify the Assistant Vice President, Steam Production, of any abnormal occurrence or unusual event. The Station Review Committee shall review a 14/9/.
written report which shall describe the circumstances leading up to and resulting from the occurrence and shall recomend appropriate action to prevent or minimize the probability of a recurrence.
6.2.3 The Station Review Comittee report shall be submitted to the Nuclear Safety Review Comittee for review of any recomendations.
Copies shall also be sent to the station Manager and the Assistant Vice President, Steam Production.
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6.2-1
o SEP 2 31974
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6.3 ACTION TO BE TAKEN IN THE EVENT A SAFETY LIMIT IS EXCEEDED Specification Lf a safety limit is exceeded:
6.3.1 The reactor shall be shut down immediately and maintained in a safe shutdown condition until otherwise authorized by the AEC.
6.3.2 Th'e station Manager shall make an immediate report to the l14/9/1 Assistant Vice President, Steam Production; the Senior Vice President, Production and Transmission; and the Chairman of the Nuclear Safety Review Consnittee.
6.3.3 The circumstances shall be promptly reported to the AEC by the Senior Vice President, Production and Transmission as indicated in Section 6.6.2.1, Station Reporting Requirements.
6.3.4 The station Manager shall direct the Station Review Committee to l14/9/1 perform an analysis of the circumstances leading up to and resulting from the situation together with recommendations to prevent a recurrence. The repcrt covering this analysis shall be sent to the Nuclear Safety Review Committee for review and approval. Copies of this report shall also be submitted to the station Manager; Assistant Vice President, Steam Production; 14/9/1 the Senior Vice President, Production and Transmission; the Chairman of the Nuclear Safety Review Committee; the Senior Vice Presiden*, Engineering and Construction; Vice President, Design Engineering; and the Executive Vice President and General Manager. Appropriate analyses or reports shall be submitted to the AEC by the Senior Vice President, Production and Transmission as indicated in Section 6.6.2.1, Station Reporting Requirements.
6.3-1
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