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Category:OPERATING LICENSES & AMENDMENTS
MONTHYEARML20127D3861993-01-13013 January 1993 Amend 67 to License DPR-45,revising TS by Deleting Requirement That Radioactive Effluent Release Rept Be Submitted Semiannually & Adding Requirement That Rept Be Submitted Annually ML20245J7171989-04-26026 April 1989 Amend 65 to License DPR-45,revising Tech Specs Re Storage of Fuel for Fire Pump Diesel Engines to Accommodate Installation & Use of New Diesel Fuel Tanks ML20155F9081988-05-31031 May 1988 Amend 62 to License DPR-45,revising Tech Specs Per Util 870930 Request as Revised on 880222 ML20151G0571988-04-11011 April 1988 Amend 60 to Provisional License DPR-45,revising Tech Specs in Response to 871112 & 880129 Application ML20148C3791988-03-15015 March 1988 Amend 59 to License DPR-45,revising Tech Specs to Reflect Exemption from 10CFR50.54(o) & 10CFR50,App J Requirements to Perform Type a Containment Bldg Integrated Leak Rate Tests Per 10CFR50.12(a)(ii) ML20149G0601988-01-0404 January 1988 Amend 58 to License DPR-45,revising Tech Specs to Show possession-only Status,To Reduce Fire Brigade from Five to Three Members & to Reassign Training Responsibilities for Fire Brigade ML20235B5551987-09-15015 September 1987 Amend 57 to License DPR-45,revising Tech Specs to Delete Requirements for Inservice Insp & Nuclear Instrumentation ML20206G6141987-04-0808 April 1987 Amend 55 to License DPR-45,changing Tech Specs to Add New Reporting Requirements of 10CFR50.73 & Details to Requirements of Repts Required for Diesel Generator Failures ML20214N3811986-09-10010 September 1986 Amend 54 to License DPR-45,updating Util Organization Chart for Tech Spec Figure 6.2.2-1 ML20209E9121986-09-0505 September 1986 Amend 53 to License DPR-45,revising Tech Specs to Add Operational Requirements on Containment Bldg Ventilation Inlet & Exhaust Dampers & Correcting Typo in Amend 50 ML20209D9611986-09-0202 September 1986 Amend 52 to License DPR-45,transfering Design Tech Spec Section 2.6, Electrical Power Supply to Bases of Operability Tech Spec Section 4.2.3, Electrical Power Sys ML20204J2451986-07-30030 July 1986 Amend 51 to License DPR-45,consolidating & Clarifying Operability & Surveillance Requirements for ECCS ML20203H3031986-07-15015 July 1986 Amend 50 to License DPR-45,revising Tech Spec Re Reactor Coolant Chemistry to Ensure That Facility Personnel Uniformly Interpret Necessary Actions to Be Taken ML20207G2601986-07-15015 July 1986 Amend 49 to License DPR-45,revising Tech Specs Re Change of Functional Testing Frequency for Installed Area Radiation Monitors to Quarterly & Calibr Frequency to Once Per 18 Months ML20141F4211986-04-14014 April 1986 Amend 48 to License DPR-45,modifying Tech Spec Sections 4.2.3 & 2.6 to Describe Replacement & Mod of Noninterruptible Bus 1C ML20154S4701986-03-27027 March 1986 Amend 47 to License DPR-45,modifying Tech Spec to Allow Use of Control Rods of ASEA-ATOM Plate Design or Current Allis Chalmers Tube Sheath Design ML20140F3531986-03-25025 March 1986 Amend 46 to License DPR-45,increasing Max Average Exposure of Any Fuel Assembly Not on Periphery of Core to 18,000 Mwd/Mtu ML20141F6951986-01-0606 January 1986 Amend 45 to License DPR-45,authorizing Addition of New Paragraph 4.1.6 to Tech Specs,Requiring Reactor Shutdown When Plant in Conditions 1,2 or 3 & Mississippi River Level Expected to Exceed 640 Ft ML20133F6461985-10-0808 October 1985 Amend 44 to License DPR-45,adding Paragraph 4.2.23 to Tech Specs Requiring Demineralized Virgin Water Tank to Be Operable W/Min Water Level of 1 Ft & Surveillance Requirement to Verify Min Water Level Every Wk ML20126E5021985-06-0707 June 1985 Amend 43 to License DPR-45,incorporating New Requirements for Operability & Surveillance Testing of RCS Safety Valves ML20125D1681985-06-0505 June 1985 Amend 42 to License DPR-45,removing Specific Quantity Limitations for Radioactive Byproduct,Source,Or SNM Used for Sample Analysis or Instrument Calibr ML20128K9511985-05-28028 May 1985 Amend 41 to License DPR-45,changing Tech Specs Re Exclusion Area,Coolant Water Purity Limits & Containment Airlock Door Seals ML20205A0011985-04-11011 April 1985 Errata to Amend 36 to License DPR-45,adding Tech Spec Page 5-2 Re Section 5.1.6 on Channel Check,Test & Calibr & Containment Testing ML20062D9591982-07-30030 July 1982 Amend 29 to License DPR-45,changing Tech Specs Re Containment Integrity & High Radiation Areas ML20062B9911978-10-11011 October 1978 Amend 14 to License DPR-45,revising Tech Specs Re Deletion of Requirement for Operable Fire Detectors in Reactor Containment Bldg During Performance of Containment Integrated Leak Rate Test 1993-01-13
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20059L6211993-11-0505 November 1993 Application for Amend to License DPR-45 Revising TS Per Requirements of Revised 10CFR20 Regulations for Radiation Protection ML20127D3861993-01-13013 January 1993 Amend 67 to License DPR-45,revising TS by Deleting Requirement That Radioactive Effluent Release Rept Be Submitted Semiannually & Adding Requirement That Rept Be Submitted Annually ML20245J7171989-04-26026 April 1989 Amend 65 to License DPR-45,revising Tech Specs Re Storage of Fuel for Fire Pump Diesel Engines to Accommodate Installation & Use of New Diesel Fuel Tanks ML20247F9891989-03-28028 March 1989 Application for Amend to License DPR-45,revising Tech Spec Pages 2-2,2-3 & 2-4 to Add Definition of Controlled Area & Estimated Whole Body Dose for Duration for Safestor ML20235G8621989-02-15015 February 1989 Supplemental Application for Amend to License DPR-45, Revising 880222 Application by Changing Tech Spec 5.4.2.2.a to Propose Min Inventory of 150 Gallons Per Fuel Storage Tank ML20155F9081988-05-31031 May 1988 Amend 62 to License DPR-45,revising Tech Specs Per Util 870930 Request as Revised on 880222 ML20151G0571988-04-11011 April 1988 Amend 60 to Provisional License DPR-45,revising Tech Specs in Response to 871112 & 880129 Application ML20148C3791988-03-15015 March 1988 Amend 59 to License DPR-45,revising Tech Specs to Reflect Exemption from 10CFR50.54(o) & 10CFR50,App J Requirements to Perform Type a Containment Bldg Integrated Leak Rate Tests Per 10CFR50.12(a)(ii) ML20147B3271988-02-22022 February 1988 Application for Amend to Provisional License DPR-45,revising LACBWR Tech Specs.Proposed Safstor Tech Specs Encl for Review.Fee Paid ML20149H0771988-02-10010 February 1988 Application for Amend to License DPR-45,deleting Request to Convert License Into full-term Ol,Authorizing Safe Storage Condition as Described in Decommissioning Plan & Continuing to Maintain Possession Only Status During Safestor Period ML20149D7101988-01-29029 January 1988 Application for Amend to License DPR-45,changing Tech Spec Section 6.2.2.d Such That Individual Qualified in Radiation Protection Procedures Will Be Either Qualified Health Physics Technician or Shift Supervisor ML20149G0601988-01-0404 January 1988 Amend 58 to License DPR-45,revising Tech Specs to Show possession-only Status,To Reduce Fire Brigade from Five to Three Members & to Reassign Training Responsibilities for Fire Brigade ML20236Q6301987-11-12012 November 1987 Application for Amend to License DPR-45,revising Administrative Section of Tech Specs Due to Permanent Shutdown of Plant on 870430.Fee Paid ML20235V6691987-09-30030 September 1987 Application for Amend to License DPR-45,revising Tech Specs by Eliminating Sections That Do Not Apply Due to Shutdown of Plant on 870430 ML20235B5551987-09-15015 September 1987 Amend 57 to License DPR-45,revising Tech Specs to Delete Requirements for Inservice Insp & Nuclear Instrumentation ML20237F7621987-08-21021 August 1987 Application for Amend to License DPR-45 & Request for Exemption from 10CFR50,App J Requirement to Perform Type a Containment Bldg Integrated Leak Rate Tests.Amend to Delete Requirements Re Type a Leak Rate Tests.Fee Paid ML20237L1481987-08-21021 August 1987 Revised Page 2 & Attachment 1, Dose Calculations, to Util 870821 Application for Amend to License DPR-45,requesting Exemption from Type a Containment Bldg Integrated Leak Rate Tests ML20237J2901987-08-18018 August 1987 Application for Amend to License DPR-45,revising Tech Spec Sections 6.2.2.f,6.4.1,6.4.2,6.5.1.2 & Figure 6.2.2-1 to Reflect Permanent Shutdown.Fee Paid ML20206G6141987-04-0808 April 1987 Amend 55 to License DPR-45,changing Tech Specs to Add New Reporting Requirements of 10CFR50.73 & Details to Requirements of Repts Required for Diesel Generator Failures ML20205P8201987-03-24024 March 1987 Supplemental Application for Amend to License DPR-45, Creating Assistant General Manager for Operations Position & Changing Title of Director of External Affairs to Director of External Relations ML20207J8031986-12-19019 December 1986 Application for Amend to License DPR-45,changing Tech Specs to Reflect Replacement of Aging Nuclear Instruments & Provide Shutdown Functions for Reactor.Proposed Tech Specs & Proprietary GE Info Encl.Ge Info Withheld (Ref 10CFR2.790) ML20212B3501986-12-17017 December 1986 Application for Amend to License DPR-45,altering Requirement for Partial Scram on Low Oil Level or Low Gas Pressure in CRD Mechanism Accumulator & Instituting Limiting Condition for Operation as Tech Spec 4.2.7.1 ML20214N3811986-09-10010 September 1986 Amend 54 to License DPR-45,updating Util Organization Chart for Tech Spec Figure 6.2.2-1 ML20209E9121986-09-0505 September 1986 Amend 53 to License DPR-45,revising Tech Specs to Add Operational Requirements on Containment Bldg Ventilation Inlet & Exhaust Dampers & Correcting Typo in Amend 50 ML20209D9611986-09-0202 September 1986 Amend 52 to License DPR-45,transfering Design Tech Spec Section 2.6, Electrical Power Supply to Bases of Operability Tech Spec Section 4.2.3, Electrical Power Sys ML20204J2451986-07-30030 July 1986 Amend 51 to License DPR-45,consolidating & Clarifying Operability & Surveillance Requirements for ECCS ML20203H3031986-07-15015 July 1986 Amend 50 to License DPR-45,revising Tech Spec Re Reactor Coolant Chemistry to Ensure That Facility Personnel Uniformly Interpret Necessary Actions to Be Taken ML20207G2601986-07-15015 July 1986 Amend 49 to License DPR-45,revising Tech Specs Re Change of Functional Testing Frequency for Installed Area Radiation Monitors to Quarterly & Calibr Frequency to Once Per 18 Months ML20141F4211986-04-14014 April 1986 Amend 48 to License DPR-45,modifying Tech Spec Sections 4.2.3 & 2.6 to Describe Replacement & Mod of Noninterruptible Bus 1C ML20205M5721986-04-0707 April 1986 Application for Amend to License DPR-45,revising Tech Specs to Reflect Reorganization of Offsite Mgt Staff.Fee Paid ML20203B2771986-04-0707 April 1986 Application for Amend to License DPR-45,changing Tech Specs Re Reporting of Primary Coolant Iodine Spikes & Elimination of 800 H Per 12-month Period Cap for Exceeding Activity Limits,Per Generic Ltr 85-19.Fee Paid ML20202A9061986-04-0101 April 1986 Application for Amend to License DPR-45,changing Surveillance Requirements for HPCS Pumps.Functional Test Will Verify That Each Pump Operates at Flow Rate Greater than or Equal to 50 Gpm Design Flow Rate ML20154S4701986-03-27027 March 1986 Amend 47 to License DPR-45,modifying Tech Spec to Allow Use of Control Rods of ASEA-ATOM Plate Design or Current Allis Chalmers Tube Sheath Design ML20140F3531986-03-25025 March 1986 Amend 46 to License DPR-45,increasing Max Average Exposure of Any Fuel Assembly Not on Periphery of Core to 18,000 Mwd/Mtu ML20153G0581986-02-21021 February 1986 Application for Amend to License DPR-45,revising Tech Specs to Clarify & Correct Description of Electrical Power Sys. Fee Paid ML20210B8611986-02-0404 February 1986 Application for Amend to License DPR-45,modifying Tech Spec Sections 4.2.3 & 2.6,to Describe Replacement & Mod to Noninterruptible Bus 1C.Fee Paid ML20141F6951986-01-0606 January 1986 Amend 45 to License DPR-45,authorizing Addition of New Paragraph 4.1.6 to Tech Specs,Requiring Reactor Shutdown When Plant in Conditions 1,2 or 3 & Mississippi River Level Expected to Exceed 640 Ft ML20138J8471985-12-12012 December 1985 Application for Amend to License DPR-45,changing Tech Specs 4.2.4.2.5 & 5.2.17.5,to Increase Max Average Fuel Assembly Exposure Limit from 16,800 to 18,000 Mwd/Mtu in Operational Condition 1.Fee Paid ML20138J7651985-12-12012 December 1985 Application for Amend to License DPR-45,changing Tech Specs to Incorporate Use of Design AA Replacement Control Rods & Deleting Tech Spec 4.2.4.10.Fee Paid ML20133F6461985-10-0808 October 1985 Amend 44 to License DPR-45,adding Paragraph 4.2.23 to Tech Specs Requiring Demineralized Virgin Water Tank to Be Operable W/Min Water Level of 1 Ft & Surveillance Requirement to Verify Min Water Level Every Wk ML20132C6111985-09-17017 September 1985 Application for Amend to License DPR-45,revising 840711 Proposed Addl Tech Specs on Containment Ventilation Dampers to Clarify Actions Required When Both Dampers in Penetration Inoperable ML20133C2281985-09-16016 September 1985 Application for Amend to License DPR-45,revising Tech Specs to Delete Section 2.4.7 & Simplifying & Making More Stringent Conditions for Low Pressure Core Spray ML20126L0521985-07-26026 July 1985 Application for Amend to License DPR-45,granting Exemption from Full Amount of Available Onsite Primary Property Damage Insurance & Continuing 830912 Exemption from Excess Property Insurance Requirements,Per 850207 & 0712 Ltrs ML20129A8671985-06-25025 June 1985 Application for Amend to License DPR-45,revising Site Flooding Tech Specs to Require Plant to Be in Cold Shutdown Before Flooding Above Grade Floor of Plant Starts ML20126E5021985-06-0707 June 1985 Amend 43 to License DPR-45,incorporating New Requirements for Operability & Surveillance Testing of RCS Safety Valves ML20125D1681985-06-0505 June 1985 Amend 42 to License DPR-45,removing Specific Quantity Limitations for Radioactive Byproduct,Source,Or SNM Used for Sample Analysis or Instrument Calibr ML20128K9511985-05-28028 May 1985 Amend 41 to License DPR-45,changing Tech Specs Re Exclusion Area,Coolant Water Purity Limits & Containment Airlock Door Seals ML20205A0011985-04-11011 April 1985 Errata to Amend 36 to License DPR-45,adding Tech Spec Page 5-2 Re Section 5.1.6 on Channel Check,Test & Calibr & Containment Testing ML20062D9591982-07-30030 July 1982 Amend 29 to License DPR-45,changing Tech Specs Re Containment Integrity & High Radiation Areas ML20054F2141982-06-0909 June 1982 Application to Amend License DPR-45 Adding Section 5.2.1.6, Containment Ventilation Isolation Valve Leakage Tests, to Tech Specs.Addl Tests Will Detect Excessive Degradation of Containment Ventilation Sys Dampers 1993-11-05
[Table view] |
Text
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' [uo mievS o UNITED STATES
!" n NUCLEAR REGULATORY COMMISSION
- W ASHINGTON, D. C. 20555
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DAIRYLAND POWER COOPERATIVE DOCKET NO. 50-409 LA CROSSE DOILING WATER REACTOR (LACBWR)
AMENDMENT TO PROVISIONAL LICENSE Amendment No. 58 License No. DPR-45
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The applications for amendment filed by Dairyland Power Cooperative (the licensee) dated April 7, 1986, March 24, 1987, and August 18, ,
. 1987 comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I; B. The facility will be maintained in confornity with the applications, the provisions of the Act, and the rules and regulations of the Comission; C. There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public; ard (ii) that such activities will be conducted in compliance with the Comission's regulativns set forth in 10 CFR Chapter I; 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. The issuance of this amerdment is in accurdance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have i been satisfied. l I
I Occd$ljg$ PD '
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- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license amendment, and Paragraph 2.C.(2) of Provisional License No. DPR-45 is hereby amendcd to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 58, are hereby incorporated in the license. The licensee shall maintain the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of issuarce.
FOR THE NUCLEAR REGULATORY COMMISSION ssAp;&%
lester 5'. Rubenstein Director *
. Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, Y and Special Projects Office of Nuclear Reactor Regulation
Enclosure:
Changes to the Technical Specifications Date of Issuance: January 4, 1988 I
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1 ENCLOSURE TO LICENSE AMENDMENT NO. 58 PROVISIONAL LICENSE NO. DPR-45 DOCKET NO. 50-409 Replace the following pages and figures of the Appendix A Technical Specifications as indicated below. The revised pages and figures are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Pages INSERT Pages 6-1 6 6-5 6-5 6-7 6-7 6-8 6-8 6-11 6-11 Remove Figures Insert Figures I
6.2.1-1 6.2.1-1 6.2.2-1 6.2.2-1 P
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. . . . l l
)
. f. A Fire Brigade of at least 3 members shall be maintained on site at all times.*
- g. At all times when the reactor is critical, or when its controls are being manipulated with fuel in the reactor, the control Room shall be attended by a minimum of two persons, one of whom shall have a valid Operators License and shall have full responsibility for operation of the facility.
- h. The working hours of the Reactor Control Operator. Turbine Generator Control Board Operator, the Duty Shift Supervisor, hkchanical Maintenance and Instrument & Electrical Technicians and Auxiliary Operator, when performing duties which may affect nuclear safety, and Health Physics Technicians, when performing radiation protection duties which may affect the safety of the public, shall be limited.
In the event overtime must be used, the following restrictions shall be followed:
- 1. The specified personnel shall not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time.
- 2. The specified personnel shall not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any *
, 4 -hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day period.
- 3. A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> shall be allowed following overtime before the next scheduled shift for the specified personnel, if the above limits are exceeded.
In the event overtime must be used in excess of the above restrictions, the Plant Superintendent or his designate, must
, authorize the deviation and the cause must be documented.
6.2.3 Shift Technical Advisor The Shift Technical Advisor shall serve in an advisory capacity to the Shift Supervisor on matters pertaining to the engineering aspects assuring safe operation of the unit.
- Fire Brigade composition may be less than the minimum requirements for a period of time not to exceed two hours in order to accommodate unexpected absence of Fire Brigade members provided immediate action is taken to restore the Fire Brigade to within the minimum requirements.
This provision does not permit any Fire Brigade position to be unnsnned upon shift change due to an oncoming brigade member being late or absent.
6-1 l PC4-20 i Amendment No. 58
DAIRYIAND POWER COOPERATIVE OFFSITE MANAGMENT l BOARD OF. DIRECTORS l l GENERAL MANAGER _l 1
-m 4
l SECRETARY & l l ADMINISTRATIVE l '
~
l ASSISTAVr l I i l I I ASSISTANI l l ASSISTANT l l ASSISTA!C l l DIRECTOR l l ASSISTAhT l l l GENERAL MANAGER l l G MERAL MANAGER l l GENERAL MANAGER l l EXTERNAL l l GENERAL MANAGER l l l FOR ENGINEERING l l FOR l l & CONTROLLER l RELATIONS l l FOR OPERATIONS l l AND l l ADMINISTRATIVE l 9 l TECHNICAL SERVICES _l 7
s 2
o FIGURE 6.2.1-1
-0FFSITE ORGANIZATION E
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- , , - - - v -- - -
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I
. l GENERAL MANAGER: : SAFETY REVIEW COPNITTEE:
- : ASSISTANT GENERAL :
- : MANAGER FOR OPERATIONS:
- : TECHNICAL SUPPORT: : LACBWR : : OPERATIONS :
- : CONTRACTORS : : PLANT SUPERINTENDENT: : REVIEW COPNITTEE:
- I I I l
, : QUALITY ASSURANCE: : ADMINISTRATIVE: : HEALTH & SAFETY: :ONSITE-TECHNICAL:
! : SUPERVISOR : : ASSISTANT : : SUPERVISOR : : SUPPORT :
I : ENGINEERS * :
- AND :
- HEALTH PHYSICS: : TECHNICAL :
- QA/QC : : TECHNICIANS : : SUPPORT :
, : TECHNICIANS: : SECRETARIES :
h 2' SECURITY & SAFETY:
- SUPERVISOR :
): :
- MECHANICAL :
'I l MAINTENANCE: : OPERATIONS SUPERVISOR:
- ! : SUPERVISOR :
i MECHANICAL :
y : MAINTENANCE: l .
!g : SHIFT : :INSTRIMENT &:
- !g
- SUPERVISORS;** : ELECTRICAL : Note
- ya
- TECHNICIANS: Engineer is designated as responsible for Fire I! 2 : PLANT OPERA 10RS: Protection Program and
.l. . Emergency Planning
'i un " ** A Shift Supervisor is DAIRYLAND POWER COOPERATIVE responsible for training LACBWR FACILITY ORGANIZATION FIGURE 6.2.2-1
ADMINISTRATIVE CONTR0!.S 6.3 UNIT STArr QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualificaticns of ANSI N18.1-1971 for comparable positions and the supplemental requirements apecified in Sections A and C of Enclosure of the March 28, 1980 NRC letter to all licensees, except for the Health Physics Supervisor who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.
6.4 TRAINING G.4.1 A retraining and replacement training program for the unit staff shall be maintained which shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and 10 CFR Part 55.
6.4.2 A training program for the Fire Brigades shall be maintained under the direction of the Technical Support Engineer and shall meet the requirements l of Section 27 of the NFPA Code-1975, except for the frequency of Fire Brigade training sessions, which shall be held at least once per 92 days. .
6.5 REVIEW AND AUDIT 6.5.1 Operations Review Committee (ORC)
Function 6.5.1.1 The Operations Review Committee shall function to advise the Plant Superintendent on all matters related to nuclear safety.
- Composition 6.5.1.2 The Operations Review Committee shall be composed of the:
Chairman: Plant Superintendent Members: Operations Supervisor Mechanical Maintenance Supervisor l Security and Safety Supervisor i Health and Safety Supervisor Staff Engineers Shift Supervisors (only 1 per quorum)
Management (non-union) SR0s Alternates:
6.5.1.3 All alternate members shall be appointed in writing by the ORC Chairman to serve on a temporary basis; however, no more than two alternstes shall participate as voting members in ORC activities at any one time.
6-5 Amendment No.58 l
ADMINISTRATIVE CORTROLS AUTIIORITY 6.5.1.7 The Opera'. ions Review Committee shallt
- a. Recommend in writing to the Plant Superintendent approval or dis-approval of items considered under 6.5.1.6a through d above.
- b. Render determinations in writing with regard to whether or riot each item considered under 6.5.1.6a through e above constitutes an unreviewed safety question.
- c. Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the General Manager g and the SRC of disagreement between the ORC and the Plant Superintendent; however, the Plant Superintendent shall have to 6.1.1 responsibility of resolution of such disagreements pursuant above.
RECORDS 6.5.1.8 The Operations Review Committee shall maintain written minutes of *
- each ORC meeting that, at a minimum, document the results of all ORC activities performed under the responsibility and authority provisions of r these Technical Specifications. Copies shall be provided to the General ;
I
. Manager and the SRC.
6.5.2 SAFETY REVIEW COHHITTEE (SRC)
FUNCTION 6.5.2.1 The SAFETY REVIEW COMMITTEE 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, i
- g. Hechanical and electrical engineering, and II . Quality assurance practices.
I LACBWR 6-7 Amendment N4 58
e ADMINISTRATIVE CONTROLS ,
COMPOSITION 6.5.2.2 The SRC shall be composed of the:
Chairman: Consultant ,
Members: Consultant Plant Superintendent Director External Relations General Manager i ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the SRC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in SRC activities at any one time.
CONSULTANTS 6.5.2.4 Consultants shall be utilized an determined by the SRC Chairman to
. provida expert advice to the SRC.
HEETING FREQUPNCY 6.5.2.5 The SRC shall meet at least once per six months.
QUORUM .
6.5.2.6 The minimum quorum of the SRC necessary for the performance of the SRC review and audit functions of these Technical Specifications shall consist of the Chairman, or his designated alternate, and at least 3 SRC members, including alternates. No more than a minority of the quorum shall have line responsibility for operation of the unit.
REVIEW 6.5.2.1 The Safety Review Committee shall reviews
- a. The safety evaluations for 1) changes to procedures, equipment or systems and 2) tests or experiments completed under the provisions of Section 50.59, 10 CFR, 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 Section 30.59, 10 CFR.
6-8 Amendment No. 58 LACBWR
~ - .- . -
ADHitalSTRATTVE COf1 TROT S
' I 6.6 REPORTABLE EVENT ACTION 6.6.1 The foll' wing o actions shall be taken for REPORTABLE EVENTS:
- a. The Commission shall be notified and a report submitted '
pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and
- b. Each REPORTABLE EVENT shall be reviewed by the ORC and ,
General Manager. ;
submitted to the SRC and the 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall bs taken in the event a Safety l Limit is violated f
- s. The unit shall be placed in at least HOT SHUTDOWN within j tWO hours.
- b. The NRC Operations Center shall be notified as soon as ,
possibli and in all cases within one hour. The and the SRC shall be.notifie'd l
General Manager. l within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
A, Saf ety Limit Violation Report shall be prepared. The !
- c. j report shall be reviewed by the ORC This report shall j describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon unit i
components, systems or structures, and (3) correctlye ~
l
- ' action taken to prevent recurrence.
I
- d. The Safety Limit Violation Report shall be submitted to and14thedays of ,the
.. General the Commissioni the SRC within violation. ;
Manager.
6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and l maintained covering the activities ref erenced belows The applicable procedures recommended in Appendix "A" of a.
Regulatory Guide 1.33, Revision 2, February 1978.
- b. Refueling operations.
- c. Surveillanceandtestactivitiesofsafeyyrelated og,uipment.
6-11 Amendment No. 58 l