Proposed Tech Specs 6.1,6.2 & 6.3 Re Operating Characteristics of Independent Review & Audit Body, Restraints on Director of Audit Body & Min Qualification Requirements of Audit Body Members| ML19312B875 |
| Person / Time |
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| Site: |
Oconee  |
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| Issue date: |
12/05/1975 |
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| From: |
DUKE POWER CO. |
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| To: |
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| Shared Package |
|---|
| ML19312B871 |
List: |
|---|
| References |
|---|
| NUDOCS 7911250071 |
| Download: ML19312B875 (10) |
|
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|---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20155C6391998-10-26026 October 1998
Proposed Tech Specs Tables 4.1-1 & 4.1-2,revised Surveillance Frequency of Refueling Outage to 18 Months
ML20154C1021998-09-30030 September 1998
Proposed Tech Specs Changing UFSAR by Increasing Max Rod Internal Pressure in Spent Fuel Pool from 1,200 to 1,300 Psig
ML20236V9611998-07-27027 July 1998
Corrected TS Bases Pages 3.5-30b of 961211 & 3.16-2 of 970205,correcting Amend Numbers
ML20236T5171998-07-20020 July 1998
Proposed Tech Specs Re one-time Extension to Functional Test Frequencies for Hydraulic & Mechanical Snubbers
ML20236R1901998-07-16016 July 1998
Proposed Tech Specs Extending TS Surveillances TS 4.20.2(a), Table 4.20-1,items 1,2 & 4,TS 4.1-1,Table 4.1-1,items 8,9,10 & 11 & TS 4.5.1.2.1,item b(1)
ML16141A8111994-04-20020 April 1994
Proposed Tech Spec Table 4.1-2, Min Equipment Test Frequency.
ML20044C9581993-05-0404 May 1993
Proposed TS 4.7.1, Control Rod Trip Time Test.
ML18032A3441987-05-29029 May 1987
Proposed Tech Specs,Clarifying Trip Level Setting in Table 3.2.A for Standby Gas Treatment Sys Relative Humidity Heater
ML16134A6761982-08-11011 August 1982
Proposed Tech Spec Revisions Re Reload Design Calculations for Cycle 7
ML16134A6731982-05-0303 May 1982
Proposed Tech Spec Changes Re Core Protection Safety Limits, Protective Sys Max Allowable Setpoints & Rod Position Limits
ML15223A7671982-01-12012 January 1982
Proposed Revisions to Tech Spec Section 3.1.2 Re Heatup Cooldown & Inservice Test Limitations for RCS
ML16148A4421981-11-13013 November 1981
Proposed Tech Spec Revision Re Core Protection Safety Limits Protective Sys Max Allowable Setpoints & Rod Position Limits
ML16148A4351981-10-28028 October 1981
Proposed Revision to Tech Spec Figure 3.5.2-4B2,allowing Cycle 5 to Run at 100% Full Power W/Axial Power Shaping Rods Fully Inserted
ML16148A4281981-08-19019 August 1981
Proposed Revision to Tech Spec Figures 3.5-16a,3.5.19a, 3.5-22 & 3.5-25a Re Extension of Operating Limits
ML15223A7321981-05-29029 May 1981
Proposed Tech Specs 2.1-2,2.1-3,2.1-7,2.3-5,3.2-1,3.2-2, 3.3-1,3.3-2,3.3-3,3.3-4,3.3-5,3.3-6,3.5-9,3.5-10,3.5-15, 3.5-15a & b,3.5-18,3.5-18a,b,c,d & e,3.5-21,3.5-21a & B, 3.5-24,3.5-24a & b,3.8-2 & 3.8-3 Re Core Protection
ML16134A6651980-08-25025 August 1980
Proposed Tech Specs Revision for Cycle 6
ML16148A3351980-07-16016 July 1980
Proposed Revision to Tech Spec 3.3.1.c Allowing Continued Operation of Unit 2 of Full Rated Power While Maint Continues on HPI Pump Until 800718
ML19318B9731980-06-24024 June 1980
Proposed Tech Spec Interpreting Term Operable as Applied to Various Tech Spec Requirements
ML16148A2691979-11-16016 November 1979
Proposed Changes to Tech Spec Pages 2.1,2.3,3.2 & 3.5. Changes Affect Core Protection Limits,Reactor Protective Sys Max Allowable Setpoints & Vol Requirements for Borated Water Storage Tank
ML19317D2701978-09-25025 September 1978
Proposed Tech Spec 3.5.2 Re Control Rod Group & Power Distribution Limits & Table 4.1-2 Re Min Equipment Test Frequency
ML19317D2621978-09-18018 September 1978
Proposed Revisions to Tech Specs 2.1,2.3,3.2 & 3.5 Re Core Protection Safety Limits & Protective Sys Max Allowable Setpoints
ML19317D2731978-09-0606 September 1978
Revised Tech Spec Page,Figure 2.3-2A,re Protective Sys Max Allowable Setpoints
ML19317D2491978-08-22022 August 1978
Proposed Revision to Tech Specs 4.18 Re Hydraulic Shock Suppressors (Snubbers)
ML19322B9961978-08-21021 August 1978
Proposed Revision to Tech Spec 2.3 Re Cycle 5
ML19312B7931978-07-17017 July 1978
Proposed Tech Spec 3.1.6.4,changing Steam Generator Leak Rate Limit
ML19308D6271978-06-28028 June 1978
Tech Spec Change Request Re Paragraph 2.B(6),stipulating That Byproduct & SNM Associated W/Four Fuel Assemblies Acquired by Fl Power Corp from Duke Power Co Previously Irradiated in Oconee 1 May Be Possessed
ML19317D2301978-06-26026 June 1978
Proposed Tech Specs 2.1,2.3,3.2,3.5 & 4.1 Required to Support Operation of Unit 1 at Full Rated Power During Cycle 5,including Core Protection Safety Limits & Protective Sys Mac Allowable Setpoint
ML19316A6501978-06-22022 June 1978
Proposed Replacement Page for Tech Spec 4.1-2 Re Min Equipment Test Frequency
ML19316A5381978-06-14014 June 1978
Proposed Changes to Tech Specs Re thermal-hydraulics Analysis.Revision to BAW-1486, Unit 3,Cycle 4 Reload Rept.
ML19312B8161978-06-12012 June 1978
Proposed Tech Specs 3.8,4.4 & 4.6 Re Fuel Loading & Refueling,Structural Integrity & Emergency Power Periodic Testing
ML19317D2341978-06-0909 June 1978
Proposed Tech Spec 3.9 Deleting Requirements Not Applicable to Liquid Effluent Monitoring Sys Due to Installation of Offline Monitor
ML19317D2221978-06-0808 June 1978
Proposed Tech Spec 3.1 Allowing Max 1 Gallon Per Minute Leakage Through Steam Generator Tubes Prior to Initiation of Unit Shutdown
ML19317D2121978-06-0202 June 1978
Proposed Tech Spec 4.2 Allowing re-insp of Reactor Coolant Outlet Nozzles at Future Refueling Outage
ML19316A5271978-05-30030 May 1978
Proposed Revisions to Tech Specs 2.3,3.2 & 3.5.2.4 to Support Cycle 4 Operation at Full Power
ML19312B7971978-04-27027 April 1978
Proposed Tech Spec 6.4,incorporating Operating Procedure Requirements Re B&W Small Break ECCS Analysis
ML19312B8091978-04-20020 April 1978
Proposed Tech Spec 3.3 Incorporating New Tech Spec 3.3.8 Requiring Operability of Three HPI Pumps for Each Unit During Power Operation Above 60% Full Power
ML19317D2001978-03-20020 March 1978
Proposed Tech Spec 3.5 Including 6.03% Quadrant Power Tilt Limit & Provision for Notifying NRC If Tilt Exceeds 3.5%
ML19317D2131978-02-21021 February 1978
Proposed Tech Spec 3.1. Incorporating Revision to Pressurization,Heatup & Cooldown Limitations.B&W 780125 Ltr to Util Re Corrections to Errors Discovered in B&W Rept BAW-1436 Encl
ML19317D2211978-02-16016 February 1978
Proposed Tech Spec 2.3 Deleting Loss of One Pump Trip Setpoint,Outdated Info & Setpoints Associated W/Single Loop Operation
ML19340A2641978-02-0808 February 1978
Tech Specs 3.3.2 Through 3.3.5 for ECCS
ML19316A4801978-02-0101 February 1978
Proposed Changes to Tech Spec 3.7 Re Limiting Conditions for Operation & Surveillance Requirements for 125 Volt Distribution Sys
ML19317D2271978-01-23023 January 1978
Proposed Tech Spec 3.5 Incorporating Control Rod Position & Axial Imbalance Limits to Period After 100 Plus or Minus 10 Effective Full Power Days
ML19312B7891978-01-0303 January 1978
Proposed Tech Spec 2.3-9 & 10 Re Computer Software Used to Process Incore Detector Signal.Includes Modified power-imbalance Trip Setpoints to Account for Bias in Positive Imbalance Measured by Incore Detector Sys
ML19316A5081977-12-0202 December 1977
Amend to Tech Specs 3.9 Re Radwaste Discharge
ML19312B8001977-12-0202 December 1977
Proposed Tech Spec 6.6.2.1 Providing Requirement for Prompt Written Notification of Certain ROs by Telephone,Mailgram or Facsimile Transmission
ML19312B7771977-11-0909 November 1977
Proposed Tech Spec 3.5.2 Permitting Operation of Unit 1 During Cycle 4 in Unrodded Mode
ML19312B8061977-10-31031 October 1977
Proposed Tech Specs 6.6-1,-2,-3 & -4 Deleting Redundant Info Currently Being Reported in Annual Operating Rept
ML19312B8101977-10-26026 October 1977
Proposed Tech Specs 3.5-9 & 3.5-24a,deleting Existing Reactor Core Quadrant Power Tilt & Control Rod Position Limits & Instituting More Conservative Limits
ML19312B8151977-10-0707 October 1977
Proposed Changes to Tech Specs 3.7 & 4.6 Re Auxiliary Electrical Systems & Emergency Power Periodic Testing
ML19329A4011977-10-0606 October 1977
Revised Tech Specs,Table 4.1-3 Re Min Sampling Frequency
1998-09-30
[Table view]
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211A9881999-08-18018 August 1999
Rev 5 to DPC Nuclear Security Training & Qualification Plan
ML20204B4141999-03-27027 March 1999
Revised Oconee Nuclear Station Selected Licensee Commitments, List of Effective Pages
ML20155C6391998-10-26026 October 1998
Proposed Tech Specs Tables 4.1-1 & 4.1-2,revised Surveillance Frequency of Refueling Outage to 18 Months
ML20154L7191998-10-0505 October 1998
Rev 8 to DPC Nuclear Security & Contingency Plan, for Oconee,Mcguire & Catawba Nuclear Stations
ML20154C1021998-09-30030 September 1998
Proposed Tech Specs Changing UFSAR by Increasing Max Rod Internal Pressure in Spent Fuel Pool from 1,200 to 1,300 Psig
ML20236V9611998-07-27027 July 1998
Corrected TS Bases Pages 3.5-30b of 961211 & 3.16-2 of 970205,correcting Amend Numbers
ML20236T5171998-07-20020 July 1998
Proposed Tech Specs Re one-time Extension to Functional Test Frequencies for Hydraulic & Mechanical Snubbers
ML20236R1901998-07-16016 July 1998
Proposed Tech Specs Extending TS Surveillances TS 4.20.2(a), Table 4.20-1,items 1,2 & 4,TS 4.1-1,Table 4.1-1,items 8,9,10 & 11 & TS 4.5.1.2.1,item b(1)
ML20217F2841998-04-20020 April 1998
Rev 7 to DPC Nuclear Security & Contingency Plan, for Oconee,Mcguire & Catawba Nuclear Stations
ML20141F1521997-06-25025 June 1997
Rev 4 to Nuclear Security Training & Qualification Plan
ML20134K5401996-10-31031 October 1996
Rev 6 to Chemistry Manual 5.1, Emergency Response Guidelines
ML20117J0181996-08-15015 August 1996
Revised Chapter 16 of Oconee Selected Licensee Commitments Manual
ML20095H1291995-12-0505 December 1995
Rev to ONS Selected Licensee Commitments (SLC) Manual, Revising SLC 16.6.1, Containment Leakage Tests to Reflect Current Plant Configuration & Update Testing Info
ML20091P2461995-08-21021 August 1995
Rev to ONS Selected Licensee Commitments Manual
ML16141A8111994-04-20020 April 1994
Proposed Tech Spec Table 4.1-2, Min Equipment Test Frequency.
ML15224A3521993-10-26026 October 1993
Safety Assurance Directive 6.1, Oconee Nuclear Site Safety Assurance Emergency Response Organization.
ML20044C9581993-05-0404 May 1993
Proposed TS 4.7.1, Control Rod Trip Time Test.
ML20045F0721993-04-0707 April 1993
Rev 9 to Corporate Process Control Program Manual.
ML20097D9451992-05-28028 May 1992
Rev 11 to Training & Qualification Plan
ML20096C2561992-04-30030 April 1992
Public Version of Revised Crisis Mgt Implementing Procedures (Cmip),Including Rev 46 to CMIP-1,Rev 39 to CMIP-4,Rev 45 to CMIP-5,Rev 49 to CMIP-6,Rev 48 to CMIP-7,Rev 42 to CMIP-9 & Rev 3 to CMIP-15
ML20096D5451992-04-0707 April 1992
Public Version of Revised Crisis Mgt Implementing Procedures (Cmip),Including Rev 45 to CMIP-1,Rev 27 to CMIP-13 & Notification of Deletion of CMIP-8.Procedure CMIP-8 Reserved for Future Use
ML20092M5891992-02-0606 February 1992
Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 43 to CMIP-1,Rev 43 to CMIP-5,Rev 33 to CMIP-8,Rev 25 to CMIP-13,Rev 6 to CMIP-18,Rev 4 to CMIP-22 & Rev 38 to CMIP-4
ML20094H2391992-01-0101 January 1992
Rev 33 to McGuire Nuclear Station Odcm
ML20094H2511992-01-0101 January 1992
Rev 34 to Catawba Nuclear Station Odcm
ML20087F3931991-12-11011 December 1991
Public Version of Rev 13 to Crisis Mgt Implementing Procedure CMIP-11, Emergency Classification - Mcguire. W/ 920121 Release Memo
ML20086K8831991-11-18018 November 1991
Public Version of Revised Crisis Mgt Implementing Procedures (Cmips),Including Rev 42 to CMIP-1,Rev 29 to CMIP-2,Rev 42 to CMIP-5,Rev 12 to CMIP-11 & Rev 37 to CMIP-21
ML20086G7711991-10-16016 October 1991
Public Version of Revs to Crisis Mgt Implementing Procedures (Cmip),Including Rev 41 to CMIP-1,rev 37 to CMIP-4,rev 41 to CMIP-5,rev 46 to CMIP-6 & CMIP-7,rev 32 to CMIP-8,rev 40 to CMIP-9,delete CMIP-12 & Rev 24 to CMIP-13
ML20082C7441991-06-11011 June 1991
Public Version of Rev 13 to Crisis Mgt Implementing Procedure CMIP-12, Classification of Emergency for Oconee Nuclear Station
ML20076A7241991-06-10010 June 1991
Public Version of Crisis Mgt Implementing Procedures, Including Rev 39 to CMIP-1,rev 28a to CMIP-2,rev 44 to CMIP-7,rev 39 to CMIP-9 & Rev 10 to CMIP-11
ML20081J9841991-06-10010 June 1991
Rev 3 to EDA-1, Procedure for Estimating Food Chain Doses Under Post-Accident Conditions
ML20081K0101991-06-0606 June 1991
Rev 8 to EDA-3, Offsite Dose Projections for McGuire Nuclear Station
ML20072S0521991-03-15015 March 1991
Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 9 to CMIP-11, Classification of Emergency for McGuire Nuclear Station & Rev 11 to CMIP-12, Classification of Emergency for Oconee Nuclear Station
ML20066G3621991-02-0101 February 1991
Public Version of Crisis Mgt Implementing Procedures, Including Rev 28 to CMIP-2,Rev 34 to CMIP-4,Rev 38 to CMIP-5,Rev 43 to CMIP-6,Rev 42 to CMIP-7,Rev 29 to CMIP-8, Rev 37 to CMIP-9 & Rev 34 to CMIP-21
ML20082P7611991-01-0101 January 1991
Rev 30 to Odcm,Catawba Nuclear Station
ML20072S9621991-01-0101 January 1991
Public Version of Rev 12 to Crisis Mgt Implementing Procedure CMIP-12, Classification of Emergency for Oconee Nuclear Station
ML20082P7711991-01-0101 January 1991
Rev 31 to Odcm,Mcguire Nuclear Station
ML20072P9621990-11-0808 November 1990
Rev 9 to Crisis Mgt Implementing Procedure CMIP-12, Classification of Emergency for Oconee Nuclear Station
ML20028H2211990-10-31031 October 1990
Public Versions of Revised Crisis Mgt Implementing Procedures,Including Rev 37 to CMIP-1,Rev 27a to CMIP-2,Rev 33 to CMIP-4,Rev 37 to CMIP-5 & Rev 42 to CMIP-6
ML20059F4301990-08-22022 August 1990
Public Version of Rev 27 to Crisis Mgt Implementing Procedure CMIP-2, News Group Plan
ML20063Q2721990-08-14014 August 1990
Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 36 to CMIP-1,Rev 32 to CMIP-4,Rev 36 to CMIP-5,Rev 41 to CMIP-6,Rev 40 to CMIP-7,Rev 27 to CMIP-8,Rev 35 to CMIP-9 & Rev 7 to CMIP-11
ML20043F4841990-05-23023 May 1990
Public Version of Crisis Mgt Implementing Procedures, Consisting of Rev 20 to CMIP-13 & Deletion of CMIP-15 & CMIP-17
ML20043B2651990-05-0909 May 1990
Revised Crisis Mgt Implementing Procedures,Including Rev 35 to CMIP-1,Rev 26 to CMIP-2,Rev 31 to CMIP-4,Rev 35 to CMIP-5,Rev 40 to CMIP-6,Rev 39 to CMIP-7,Rev 26 to CMIP-8, Rev 33 to CMIP-9,Rev 2 to CMIP-14 & Rev 10 to CMIP-16
ML20043F4621990-04-20020 April 1990
Rev 5 to Oconee-specific Process Control manual.W/900606 Ltr
ML20006C0571990-01-18018 January 1990
Public Version of Rev 33 to Crisis Mgt Implementing Procedure CMIP-1, Recovery Manager & Immediate Staff & Rev 24 to CMIP-2, News Group Plan.
ML16152A8951990-01-0202 January 1990
Rev 33 to Public Version of Crisis Mgt Plan for Nuclear Stations.
ML15264A1571990-01-0202 January 1990
Revised Crisis Mgt Implementing Procedures,Including Rev 32 to CMIP-1,Rev 29 to CMIP-4,Rev 33 to CMIP-5,Rev 38 to CMIP-6,Rev 37 to CMIP-7,Rev 32 to CMIP-9,Rev 1 to CMIP-14 & Rev 30 to CMIP-21
ML20012A3801990-01-0101 January 1990
Rev 28 to, Offsite Dose Calculation Manual,Oconee,Mcguire & Catawba Nuclear Stations.
ML20012A3791990-01-0101 January 1990
Rev 27 to, Offsite Dose Calculation Manual,Oconee Nuclear Station.
ML20011D2441989-12-0101 December 1989
Crisis Mgt Implementing Procedures.
ML20012A3731989-11-15015 November 1989
Rev 4 to, Process Control Program Oconee Nuclear Station.
1999-08-18
[Table view] |
Text
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P 6.0 ' ADMINISTRATIVE CONTOLS 6.1 ORGANIZATION, REVIEU, 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.
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 replacer;nt of station personnel shall be in accordance with Section 5.5 of the /WSI N18.1-1971, " Selection 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 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 staff, at least one of whom holds a Senior Reactor Operator's License on the unit (s) affected. Procedures and procedure changes shall 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 i 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
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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.
- c. Proposed modifications to station nuclear safety-related structures, sys-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 mini =um of five years of technical experience, of which a minimum of one year shall be nuclear experience. A maximum of four years of this five yeacs of experience may be fulfilled by academic or related technical training.
- e. 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; 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 ReviewBoard.
- g. The station Manager shall assure the performance of special reviews and investigations, and the preparation and subui:tal of reports thereon, as requested by the Vice Presicent, Steau 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; ard to the Director of the Nuclear Safety Review Board. ~
- 1. 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 app.3ved by the station Manager and trans-mitted to the Vice President, Steau Production, or his designee; and to the Director of the Nuclear Safety Review Board.
6.1-2
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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 activities in the areas of:
- a. Nuclear power plant cperations
- 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
- a. The Director, membtrs and alternata members of the NSRB shall be formally appointed by the Vice President, Steam Production, and shall have a minimum of nine years of technical experience, of which a minimum of three years shall be in one or more of the areas given in 6.1.3.1. A maximum of four years of this nine years of experience may be academic training.
- b. The NSRB shall be composed of at least 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 Oconee Nuclear Station staff.
- c. Consultants may be utilized by the NSRB to provide expert advice to the 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, timelv and expeditious performance of its functions.
- e. The NSRB shall meet at least once per six months. The period between 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 NSRB members or alternate members. '
No more than a minority of the quorum shall have line responsibility for operation of Oconee Nuclear Station.
6.1.3.3 Subjects Requiring Review The following subjects shall be reported to and reviewed by the NSRB:
6.1-3 l
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- 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(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.
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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.
- 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 nor=al and expected performance of station equipment that affect 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.
6.1.3.4 Audits Audits of station activities shall be performed under the cognizance of the NSRB. 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 equip-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.
- 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
.
6.1-4
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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. N1nutes shall be prepared and forwarded to the Vice President, Steam Pro-duction, and to the Senior Vi:e President, Production and Tra2smission, within 14 days following each formal meeting of the NSRB.
- 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 President, Steam Production, and to the Senior Vice President, Production and Transmission, and to the managenent positions responsible for the areas audited within 30 days of completion of each audit.
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6.1-5 J
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Table 6.1-1 Hinimum Operat ing Shif t Requirements With Fuel in the Three Reactor Vessels Unit I or 2 Ahove Units I and 2 Above Units 1 or 2 Above Units 1 and 2 Cold Units 1, 2 Units 1,2 Hinimum Alt: Cold Shutdown; Unit Culd Shutdown; Unit Cold Shutdown; Unit Shutdown; Unit 3 and 3 Above and 3 Cold I.ecente Requirement I Cold Shutdown 3 Cold Shutdown 3 Above Cold Shutdown Above Cold Shutdown Cold Shutdown Shutdown Senior Heactor operator 2 2 2 2 3 2 Re. actor Operator 4 4 4 4 4 3 Unlicensed operator 2 2 2 2 4 Additiona! Hequirements:
G 1. One t h ensed operator per unit sh.all he in the Conttul Noom at all times when there is fuel
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s in the reastor vessel I
- 2. Two licensed operators shall he in the Control Room during startup and scheduled shutdown of a scactor.
- 1. At le ast one licensed oper.ator shall he in the s e.ac tor building when t uel handling operat ions in th*e reasfor building .sre in progress.
- 4. An oper atos holding a Senior Reactor Operator liten e and assigned no other operational duties shall be in direct tharre of refueling operations.
g
') . At least one person per shift sh.all have sufficient training to perform routine health physics requirements, t> . It the aomputer for a reactor is inoperable for more th.an eight hours, an operator in addition to those acquired above shall supplement t he sh i f t crew.
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Manager Oconee Nuclear Station a
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Operating _
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Superintendent Superintendent Superintendent SRO
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Engineer Engineer ".sgineer 2.
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SRO Engineer .,
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OCONEE NUCLEAR STATION STATION ORGANIZATION CHART S
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FIGURE 6.1-1 l14/9/1
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Senior Vice President Production and Transmission Vice President Nuclear Safety Steam Production - - - - -
, Review Unit Manager Nuclear Production Manager Oconee Nuclear Station
{84, jOCONEE NUCLEAR STATI liANAGEMENT ORGAf11ZATION Figure 6.1-2 6.1-8 Entire Page Revised
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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 pr(bability 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 s pursuant to the requirements of Specification 6.6.2.
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6.2-1 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.
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 Lamediately.
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 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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I 6.3-1 Entire Page Revised
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