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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML18066A6641999-09-30030 September 1999 Proposed Tech Specs Re Surveillance Implementation ML18066A6501999-09-17017 September 1999 Final Clean Copies of ITS & Bases Pages Incorporating Proposed Changes,Editorial Changes & Bases Clarifications as Result of Ongoing Reviews to ITS LCOs 3.5.2,3.6.3,3.6.6, 3.7.5 & 3.7.7 & 3.7.8 ML18066A5911999-07-30030 July 1999 Proposed Tech Specs Sections 3.3,3.5 & 3.6,converting to Its,Per NUREG-1432 ML18066A5691999-07-19019 July 1999 Proposed Tech Specs Section 3.7, Plant Systems, Converting to ITS ML18066A5011999-06-11011 June 1999 Proposed Tech Specs Pages Re 980126 Submittal & Replacement Pages for Sections 3.3,3.4 & 3.9 ML18068A5851999-05-0303 May 1999 Proposed Tech Specs Section 3.5,converting to ITS ML18066A4551999-04-0707 April 1999 Proposed ITS Pages 3.1.4-2 & 3.1.4-8,revising Completion Time for Action D.1 ML18066A4431999-03-30030 March 1999 Proposed Tech Specs Section 3.7,converting to ITS ML18066A4251999-03-22022 March 1999 Revised TS Pages for ITS Section 3.4 ML20207B2501999-03-0101 March 1999 Proposed Tech Specs Sections 2.0,3.1 & 3.2,converting to ITS ML18066A3281998-11-0909 November 1998 Proposed Tech Specs,Deleting CVCS Operability Requirements Currenty in LCOs 3.2 3.17.6 & Associated Testing Requirements Currently in SRs 4.2 & 4.17 ML20195E4451998-11-0909 November 1998 Proposed Tech Specs,Converting to Its,Consistent with NUREG-1432,Rev 1,in Response to 980824 RAI ML20154N2901998-10-12012 October 1998 Proposed Tech Specs Sections 1.0,3.0,4.0 & 5.0,converting to Improved Tech Specs ML20151Z8111998-09-14014 September 1998 Proposed Tech Specs Converting to Improved Tss, Consistent with NUREG-1432,Rev 1 ML18066A3021998-09-14014 September 1998 Proposed Tech Specs Markups of Previously Submitted Pages & Revised ITS Submittal Pages ML18066A2011998-06-17017 June 1998 Proposed Tech Specs,Reflecting Reduced Min Reactor Vessel Flow Rate Assumption in Accident Analyses ML18065B1801998-03-13013 March 1998 Proposed Tech Specs Allowing Installation of Plant Mod W/O Requiring Plant Shutdown ML18067A8161998-01-26026 January 1998 Proposed Tech Specs Converting to Improved Ts,Consistent W/ NUREG-1432,Rev 1.Includes Vols 1-20 ML18066A4901998-01-20020 January 1998 Proposed Tech Specs Re Partial Response to 990126 Request RAI for ITS Section 3.6, Containment. ML18067A7071997-10-0101 October 1997 Proposed Tech Specs,Stating That TS Flywheel Insp Period Be Lengthened to Ten Years & Deleting Note of Insp at End of Cycle 12 ML18067A6731997-09-0303 September 1997 Proposed Tech Specs,Updating TS to Reflect Capabilities of Installed CR Ventilation Equipment & to Emulate Std TS, CE Plants - NUREG 1432 Requirements for That Sys ML18067A6771997-09-0303 September 1997 Proposed Tech Specs,Deleting Snubber Operability Requiements in LCO 3.20 & Snubber Testing Requirements Currently in SR 4.16 ML18067A6001997-06-27027 June 1997 Proposed Tech Specs Revising Electrical Power Systems ML18067A4701997-03-28028 March 1997 Proposed Tech Specs Pp Supporting Completion of Administrative Control Changes Proposed in 951211 Safety Evaluation for Amend 174 ML20137H5901997-03-27027 March 1997 Proposed Tech Specs Change Request Re Change in Co Name ML18067A4531997-03-26026 March 1997 Proposed Tech Specs,Allowing Entry Into Air Lock to Perform Repairs on Inoperable Air Lock Door & Thereby Avoid Potential for Unnecessary Plant Shutdown ML18065B0331996-10-25025 October 1996 Proposed Tech Specs Change Request,Revising Administrative Controls Sections of Plant TS ML18065B0171996-10-18018 October 1996 Proposed Tech Specs,Providing Info Necessary for Completion of Review & Approval Process Re Writting Commitment Be Made That Description of Palisades Operating Requirements Manual Will Be Added to FSAR ML18065A9551996-10-0202 October 1996 Proposed Tech Specs 4.6.1 Re Safety Injection sys,4.6.2 Re Containment Spray sys,4.6.3 Re Pumps & 4.6.4 Re Valves ML18065A9111996-09-0404 September 1996 Proposed Tech Specs 3.7, Electrical Power Systems. ML20117K9581996-09-0303 September 1996 Proposed Tech Specs,Revising Administrative Control & Resolution of NRC Comments ML18065A8631996-08-14014 August 1996 Proposed TS Table 4.3.2 Re Miscellaneous Surveillance Items ML18065A5861996-03-29029 March 1996 Proposed Tech Specs,Upgrading Plant TS & Bases to Emulate STS for Combustion Engineering Plants,NUREG-1432,Rev 1 ML18065A4911996-02-0606 February 1996 Proposed Tech Specs Re Removal of cross-train Testing Requirements from LCO Action Statements ML18065A4411996-01-18018 January 1996 Proposed Tech Specs Allowing Use of 10CFR50 App J Option B Containment Testing & Use of Warning Light to Identify Certain High Radiation Areas ML18065A4361996-01-18018 January 1996 Proposed Tech Specs Re Primary Coolant Pump Flywheel Insps ML18065A4111996-01-10010 January 1996 Proposed Tech Specs,Requesting Exemption from 10CFR50 App J & TS Change Request Concerning Local Leak Test Requirements for Emergency Escape Airlock in Plant Containment Bldg ML18065A3841996-01-0505 January 1996 Proposed Tech Specs,Revising SDC Requirements & Bases for TS Section 3.1.9.3 Prior to 1996 Refueling Outage ML18065A3771995-12-27027 December 1995 Proposed Tech Specs,Rewriting Electrical Power Sys Sections of TS & Bases to Closely Emulate STS ML18065A3481995-12-11011 December 1995 Proposed Tech Specs,Revising Administrative Controls Section to Emulate CE STS by Removing Review & Audit Requirements of Section 6.5 & Record Retention Requirements of Section 6.10 of TS Relocating in CPC Quality Program Description ML18065A3341995-12-0606 December 1995 Proposed Tech Specs,Relocating Crane Operation & Movement of Heavy Loads Requirements & Bases from TS to Other Plant Documents Prior to 1996 Refueling Outage ML18065A1761995-10-17017 October 1995 Proposed Tech Specs,Changing Pressurizer Cooldown Limit from 100 to 200 F/H,Adding Word Shall to TS 3.1.2c,adding Average Hourly to Column Headings in TS 3.1.2c & Removing Action 3.3.3C from Page 3-31 to 3-30 ML18065A1241995-09-21021 September 1995 Proposed Tech Specs Re Diesel Generator Testing ML18064A8411995-07-0505 July 1995 Proposed Tech Specs,Deleting Section 6.4, Training, & Revising Sections 6.5.1.2 on Plant Review Committee Composition & 6.5.3.1 & 6.5.3.2,clarifying & Modifying Function & Composition of Plant Safety & Licensing Staff ML18064A7611995-05-0101 May 1995 Proposed Tech Specs Re Requirements for Periodic DG Peak Load Tests ML18064A7331995-04-27027 April 1995 Revised Proposed Ts,Consisting of Changes to Basis in First Paragraph of Page 3-2 & Rev to List of Approved Methodology Repts ML18064A7361995-04-27027 April 1995 Proposed Tech Specs,Supporting Action Statements for Inoperable Safety Valves in Proposed Specs 3.1.7 of TS Change Request of 950103 ML18064A6631995-03-30030 March 1995 Proposed Tech Specs for One Time Surveillance Deferment ML18064A6691995-03-24024 March 1995 Proposed TS Re pressure-temp Limits ML18064A6221995-02-20020 February 1995 Proposed TS Figure 3-4, LTOP Setpoint Limit. 1999-09-30
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML18066A6641999-09-30030 September 1999 Proposed Tech Specs Re Surveillance Implementation ML18066A6501999-09-17017 September 1999 Final Clean Copies of ITS & Bases Pages Incorporating Proposed Changes,Editorial Changes & Bases Clarifications as Result of Ongoing Reviews to ITS LCOs 3.5.2,3.6.3,3.6.6, 3.7.5 & 3.7.7 & 3.7.8 ML18066A5911999-07-30030 July 1999 Proposed Tech Specs Sections 3.3,3.5 & 3.6,converting to Its,Per NUREG-1432 ML18066A5691999-07-19019 July 1999 Proposed Tech Specs Section 3.7, Plant Systems, Converting to ITS ML18066A5011999-06-11011 June 1999 Proposed Tech Specs Pages Re 980126 Submittal & Replacement Pages for Sections 3.3,3.4 & 3.9 ML18068A5851999-05-0303 May 1999 Proposed Tech Specs Section 3.5,converting to ITS ML18066A4551999-04-0707 April 1999 Proposed ITS Pages 3.1.4-2 & 3.1.4-8,revising Completion Time for Action D.1 ML18066A4431999-03-30030 March 1999 Proposed Tech Specs Section 3.7,converting to ITS ML18066A4251999-03-22022 March 1999 Revised TS Pages for ITS Section 3.4 ML20207B2501999-03-0101 March 1999 Proposed Tech Specs Sections 2.0,3.1 & 3.2,converting to ITS ML18066A3281998-11-0909 November 1998 Proposed Tech Specs,Deleting CVCS Operability Requirements Currenty in LCOs 3.2 3.17.6 & Associated Testing Requirements Currently in SRs 4.2 & 4.17 ML20195E4451998-11-0909 November 1998 Proposed Tech Specs,Converting to Its,Consistent with NUREG-1432,Rev 1,in Response to 980824 RAI ML20154N2901998-10-12012 October 1998 Proposed Tech Specs Sections 1.0,3.0,4.0 & 5.0,converting to Improved Tech Specs ML18066A3021998-09-14014 September 1998 Proposed Tech Specs Markups of Previously Submitted Pages & Revised ITS Submittal Pages ML20151Z8111998-09-14014 September 1998 Proposed Tech Specs Converting to Improved Tss, Consistent with NUREG-1432,Rev 1 ML18066A2011998-06-17017 June 1998 Proposed Tech Specs,Reflecting Reduced Min Reactor Vessel Flow Rate Assumption in Accident Analyses ML18066A1841998-06-10010 June 1998 Simulator Four-Year Test Rept & Schedule for Performance Testing for Next Four-Year Period. ML18068A3451998-04-29029 April 1998 Rev 9 to EI-9, Offsite Radiological Monitoring. ML18068A3441998-04-28028 April 1998 Rev 3 to EI-6.6, Gamma E Determination. ML18065B2271998-04-21021 April 1998 Reactor Vessel Neutron Fluence Methodology. ML20217C3101998-03-24024 March 1998 Palisades,Review of Actual Fluence Determination ML18065B1801998-03-13013 March 1998 Proposed Tech Specs Allowing Installation of Plant Mod W/O Requiring Plant Shutdown ML18065B2021998-03-10010 March 1998 Rev 7 to Relocated TS Per GL 89-09. ML18067A8161998-01-26026 January 1998 Proposed Tech Specs Converting to Improved Ts,Consistent W/ NUREG-1432,Rev 1.Includes Vols 1-20 ML18066A4901998-01-20020 January 1998 Proposed Tech Specs Re Partial Response to 990126 Request RAI for ITS Section 3.6, Containment. ML20197G3851997-12-17017 December 1997 Rev 17 to Palisades Nuclear Plant Suitability,Training & Qualification Plan ML18065B2321997-10-24024 October 1997 Rev 5 to Procedure HP 10.10, Palisades Radiological Environ Program Sample Collection & Shipment. ML18067A7071997-10-0101 October 1997 Proposed Tech Specs,Stating That TS Flywheel Insp Period Be Lengthened to Ten Years & Deleting Note of Insp at End of Cycle 12 ML18067A6731997-09-0303 September 1997 Proposed Tech Specs,Updating TS to Reflect Capabilities of Installed CR Ventilation Equipment & to Emulate Std TS, CE Plants - NUREG 1432 Requirements for That Sys ML18067A6771997-09-0303 September 1997 Proposed Tech Specs,Deleting Snubber Operability Requiements in LCO 3.20 & Snubber Testing Requirements Currently in SR 4.16 ML18067A6001997-06-27027 June 1997 Proposed Tech Specs Revising Electrical Power Systems ML18067A4701997-03-28028 March 1997 Proposed Tech Specs Pp Supporting Completion of Administrative Control Changes Proposed in 951211 Safety Evaluation for Amend 174 ML20137H5901997-03-27027 March 1997 Proposed Tech Specs Change Request Re Change in Co Name ML18067A4531997-03-26026 March 1997 Proposed Tech Specs,Allowing Entry Into Air Lock to Perform Repairs on Inoperable Air Lock Door & Thereby Avoid Potential for Unnecessary Plant Shutdown ML18067A5151997-02-11011 February 1997 Rev 5 to Health Physics Procedure HP 10.10, Palisades Radiological Environ Program Sample Collection & Shipment. ML18065B2011996-12-24024 December 1996 Rev 11 to Offsite Dose Calculation Manual. ML18065B0861996-11-27027 November 1996 Corrected Pages 14 & 15 to Rev 18 to EM-09-02, Inservice Testing Program Relief Request Valve Relief Request 20. ML20134P4071996-11-19019 November 1996 Suitability,Training & Qualification Plan, Rev 16 ML20137G3871996-10-29029 October 1996 Rev 6 to Relocated TS Per NRC GL 89-09 ML18065B0331996-10-25025 October 1996 Proposed Tech Specs Change Request,Revising Administrative Controls Sections of Plant TS ML18065B0171996-10-18018 October 1996 Proposed Tech Specs,Providing Info Necessary for Completion of Review & Approval Process Re Writting Commitment Be Made That Description of Palisades Operating Requirements Manual Will Be Added to FSAR ML18065A9551996-10-0202 October 1996 Proposed Tech Specs 4.6.1 Re Safety Injection sys,4.6.2 Re Containment Spray sys,4.6.3 Re Pumps & 4.6.4 Re Valves ML18065A9111996-09-0404 September 1996 Proposed Tech Specs 3.7, Electrical Power Systems. ML20117K9581996-09-0303 September 1996 Proposed Tech Specs,Revising Administrative Control & Resolution of NRC Comments ML18065A8631996-08-14014 August 1996 Proposed TS Table 4.3.2 Re Miscellaneous Surveillance Items ML18065A7661996-06-10010 June 1996 Expired Temporary Change O-96-044 to Rev 17 to SOP-17A, Clean Radwaste Sys. ML18065A7651996-06-10010 June 1996 Cancelled Tcn O-96-045 to Rev 17 to SOP-17B, Dirty Radwaste Sys. ML18065A5861996-03-29029 March 1996 Proposed Tech Specs,Upgrading Plant TS & Bases to Emulate STS for Combustion Engineering Plants,NUREG-1432,Rev 1 ML18065A8021996-02-21021 February 1996 Rev 2 to EM-09-13, ISI Pressure Testing Program. ML20137G3631996-02-16016 February 1996 Rev 10 to Offsite Dose Calculation Manual 1999-09-30
[Table view] |
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ATTACHMENT Consumers Power Company Palisades Plant Docket 50-255 PROPOSED TECHNICAL SPECIFICATION PAGE CHANGES September 21, 1988
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TSP0488-0107-NL02-NL04
PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS - APPENDIX A SECTION DESCRIPTION PAGE NO 4.0 SURVEILLANCE REQUIREMENTS (Continued) 4.24.6 Gaseous Waste System 4-91 4.24.7 Solid Radioactive Waste 4-91 4.24.8 Total Dose 4-91 Table 4.24-1 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements 4-92 Table 4.24-2 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements 4-93 Table 4.24-3 Radioactive Liquid Waste Sampling and Analysis Program 4-95 Table 4.24-5 Radioactive Gaseous Waste Sampling and Analysis Program 4-97 5.0 DESIGN FEATURES 5-1 5.1 SITE 5-1 5.2 CONTAINMENT DESIGN FEATURES 5-1 5.2.1 Containment Structures 5-1 5.2.2 Penetrations 5-2 5.2.3 Containment Structure Cooling Systems 5-2 5.3 NUCLEAR STEAM SUPPLY SYSTEM (NSSS) 5-2 5.3.1 Primary Coolant System 5-2 5.3.2 Reactor Core and Control 5-3 5.3.3 Emergency Core Cooling System 5-3 5.4 FUEL STORAGE 5-4 5.4.1 New Fuel Storage 5-4 5.4.2 Spent Fuel Storage 5-4a Figure 5-1 Site Environment TLD Stations 5-5 6.0 ADMINISTRATIVE CONTROLS 6-1 6.1 RESPONSIBILITY 6-1 6.2 ORGANIZATION 6-1 6.2.1 Offsite and Onsite Organization 6-1 I 6.2.2 Plant Staff 6-la I 6.2.3 Plant Safety Engineering (PSE) 6-2 I 6.3 PLANT STAFF QUALIFICATIONS 6-3 I Table 6.2-1 Minimum Shift Crew Composition 6-4 6.4 TRAINING 6-5 vi Amendment No S$, 10$, 10$,
TSP0488-0107-NL02-NL04
ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Plant General Manager shall be responsible for overall plant operation and shall delegate in writing the succession for this responsibility during his absence.
6.1.2 The Shift Supervisor or in his absence from the control room,* the second licensed senior operator on duty shall be responsible for the shift command function. A directive to this effect shall be issued annually by the Vice President - Nuclear Operations.
6.2 ORGANIZATION 6.2.1 OFFSITE AND ONSITE ORGANIZATIONS I Onsite and off site organizations shall be established for plant I operation and corporate management, respectively. The onsite and I offsite organizations shall include the positions for activities I affecting the safety of the Palisades Plant. I
- a. Lines of authority, responsibility and communication shall be I established and defined for the highest management levels I through intermediate levels to and including all operating I organization positions. ~hese relationships shall be I documented, and updated, as appropriate, in the form of I organization charts, functional descriptions of departmental I responsibilities and relationships, and job descriptions for I key positions, or in equivalent forms of documentation. These I requirements shall be documented in the FSAR. I
- b. The Plant General Manager shall be responsible for overall I plant safe operation and shall have control over those onsite I activities necessary for safe operation and maintenance of the I plant. I
- c. The Vice President - Nuclear Operations shall have corporate I responsibility for overall plant nuclear safety and shall take I any measures needed to ensure acceptable performance of the I staff in operating, maintaining and providing technical I support to the plant to ensure nuclear safety. I
- d. The individuals who train the operating staff and those who I carry out health physics and quality assurance functions may I report to the appropriate onsite manager; however, they shall I have sufficient organizational freedom to ensure their I independence from operating pressures. I 6-1 Amendment No ii, i7, ~0, 7$, !0S TSP0488-0107-NL02-NL04
ADMINISTRATIVE CONTROLS 6.2.2 PLANT STAFF
- a. Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.
- b. At least one licensed Senior Reactor Operator shall be in the I control room at all times during conditions other than cold shutdown or refueling. In addition to this Senior Reactor I Operator, at least one licensed Reactor Operator or Senior I Reactor Operator shall be present at the controls at all I times when fuel is in the reactor.
- c. A Radiation Safety Technician shall be on site when fuel is in the reactor.*
- d. All core alterations, after the initial fuel loading, shall either be performed under the direct supervision of a
- licensed Senior Reactor Operator or Senior Operator holding I a license limited to fuel handling. During this time, no other responsibilities shall be assigned to this individual.
- e. A Fire Brigade of at least 5 members shall be maintained on site at all times.* The Fire Brigade shall not include 3 members of the minimum shift crew necessary for safe shutdown or any personnel required for other essential functions during a fire emergency.
- f. Administrative procedures shall limit the working hours of Plant staff who perform safety-related functions.
In the event that overtime is used, the following guidelines shall be followed:
A. An individual 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).
B. An individual 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, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
- in any 48-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 seven-day period (all excluding shift turnover time).
C. A break of at least eight hours shall be allowed between work periods (including shift turnover time).
- The Radiation Safety Technician and the 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 provided immediate action is taken to restore the minimum requirements.
6-la Amendment No ii, i7, ~0, 7$, ¥08 TSP0488-0107-NL02-NL04
ADMINISTRATIVE CONTROLS e
6.2.2.f PLANT STAFF (Continued)
D. Except during extended shutdown periods the use of overtime should be considered on an individual basis and not for the entire staff on a shift.
Deviations from the overtime guidelines shall be authorized by the Plant General Manager or his Alternate. The basis for granting the deviation shall be documented. Routine deviations are not to be authorized.
Indiv'iduai overtime will be reviewed monthly by the Plant General Manager or his designee to assure that excessive hours have not been assigned.
6.2.3 PLANT SAFETY ENGINEERING (PSE) 6.2.3.1 FUNCTION PSE shall function to examine plant operating characteristics, NRC issuances, industry advisories, Licensee Event Reports and other sources ~which may indicate areas for improving plant safety. The organization shall report to the Director of Nuclear Safety. With the concurrence of the Director, PSE may function as staff to the onsite and offsite review organizations and provide technical support for problem resolution.
6.2.3.2 COMPOSITION PSE shall consist of a minimum of five (5) technical personnel located at the Palisades Plant.
6.2.3.3 QUALIFICATIONS At least three of the full-time members at the Palisades Plant shall have a bachelor's degree in engineering or a related science. At least one of the three shall have a minimum of five years' professional experience which includes a minimum of two years' experience in nuclear pow~r plant operation and/or design. Those individuals comprising the minimum complement of five and not having bachelor's degrees in engineering or a related science shall have at least two years' experience in the field for which they will provide expertise to PSE.
6-2 Amendment 7$, 108 (INCLUDED FOR CONTINUITY)
TSP0488-0107-NL02-NL04
e ADMINISTRATIVE CONTROLS 6.2.3.4 REPORTS Reports of PSE activities shall be submitted regularly to the NSB.
6.3 PLANT STAFF QUALIFICATIONS 6.3.1 Each member of the plant staff shall meet or exceed the minimum qualifications of ANSI Nl8.1-1971 for comparable positions.
6.3.2 A Radiation Safety Manager shall be designated by the Plant General I Manager and shall meet or exceed the qualifications of a Radiation I Protection Manager as defined in Regulatory Guide 1.8, September I 1975.* The Radiation Safety Manager shall have direct access to I the Plant General Manager in the matters of radiation safety. I 6.3.3 The Shift Technical Advisor shall have a bachelor's degree or equivalent and the Shift Engineer shall have a bachelor's degree in a scientific or engineering discipline. Specific training I shall include plant design, operations, and response and analysis I of the plant for transients and accidents. The Shift Engineer shall hold a Senior Reactor Operator License. -/
6.3.4. The individual responsible for directing the activities of I licensed operators shall hold a Senior Reactor Operator license. I
- For the purpose of this section, "Equivalent," as utilized in Regulatory Guide 1.8 for the bachelor's degree requirement, may be met with four years of any one or combination of the following: (a) Formal schooling in science or engineering, or. (b) operational or technical experience/
training in nuclear power.
6-3 Amendment Noll, l7, ~7, ~S, 7$, !0S TSP0488-0107-NL02-NL04
ADMINISTRATIVE CONTROLS 6.4 TRAINING 6.4.1 A retraining and replacement training program for the plant staff shall be maintained and shall meet or exceed the requirements I and recommendations of Section 5.5 of ANSI NlS.1-1971 and I 10 CFR Part 55. I 6.4.2 A fire brigade training program shall be maintained and shall, I as practicable, meet or exceed the requirements of Section 27 of the NFPA Code-1975. Fire brigade, training drills shall be held at least quarterly.
6.5 REVIEW AND AUDIT 6.5.1 PLANT REVIEW COMMITTEE (PRC) 6.5.1.1 FUNCTION The Plant Review Committee (PRC) shall function to advise the Plant
- General Manager on all matters related to nuclear safety.
6.5.1.2 COMPOSITION The PRC shall be composed of:
Chairman: Technical Engineer or Designated Alternate Member: Operations Manager*
Member: . Engineering and Maintenance Manager*
Member: Radiological Services Manager*
Member: Technical Director*
- Member: Reactor Engineering Superintendent Member: Operations Superintendent Member: Instrumentation and Control Superintendent Member: Shift Supervisor or Shift Engineer (1)
- may serve as Designated Alternate for the Chairman 6.5.1.3 ALTERNATES Alternate members of the PRC shall be appointed in writing by the PRC Chairman to serve on a temporary basis. No more than two alternates shall participate as voting members at any one time in PRC activities. Members identified with a asterisk (*) above may function as the Designated Alternate for the Chairman, and in so doing,- are not considered alternate members for voting purposes.
6-5 Amendment No. t~, ~~. 7$, !0S, TSP0488-0107-NL02-NL04