|
---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML18039A8811999-09-28028 September 1999 Proposed Tech Specs Re Increased MSIV Leakage Rate Limits & Exemption from 10CFR50,App J ML18039A8241999-07-28028 July 1999 Proposed Tech Specs Providing TS for Operation of Oscillation PRM Upscale Trip Function in Aprm,Which Is Part of Power Range Neutron Monitoring Sys ML18039A8001999-06-0303 June 1999 Proposed Tech Specs,Reducing Allowable Value Used for Reactor Vessel Water Level - Low,Level 3 for Several Instrument Functions ML18039A6991999-02-22022 February 1999 Proposed Tech Specs & Bases Pages Incorporating NRC Approved TS Change 354,requiring Oscillation PRM to Be Integrated Into Approved Power uprate,24-month Operating Cycle & Single Recirculation Loop Operation ML18039A6601998-12-15015 December 1998 Proposed Tech Specs,Revising pressure-temp Curves to Extend Validity of Curves to 32 EFPY ML18039A5041998-09-0808 September 1998 Proposed Tech Specs Providing TS for Operation of Oscillation Power Range Monitor Upscale Trip Function in Aprm,Which Is Part of Power Range Neutron Monitoring Sys ML18039A5001998-09-0404 September 1998 Proposed Tech Specs Re Use of Containment Overpressure for ECCS Pump Net Positive Suction Head Analyses ML18039A4791998-08-14014 August 1998 Proposed Tech Specs Pages Re Amends to Licenses DPR-33, DPR-52 & DPR-68 to Change Ts.Proposed Changes Decrease Frequency of once-per-cycle Instrument Calibrations by Substituting 24 Months for 18 Months ML18039A4611998-07-31031 July 1998 Proposed Tech Specs B 3.6-2,B 3.6-7 & B 3 3.7-2 for Power Uprate Operation Omitted Pages ML18039A4481998-07-17017 July 1998 Proposed Tech Specs,Adding LCO 3.4.10 & Accompanying TS Bases Provisions from Improved TS-362 Conversion Package as Adapted for Power Uprate Conditions ML18039A4091998-06-26026 June 1998 Proposed Tech Specs Section 3.4,allowing Units 2 & 3 to Operate at Uprated Power Level of 3458 Mwt ML18039A4021998-06-19019 June 1998 Proposed Tech Specs (TS) Converting from Existing Custom TS to Improved TS ML18039A3921998-06-12012 June 1998 Proposed Tech Specs Change 390,decreasing Frequency of once-per-cycle SRs by Substituting 24 Months for 18 Months in Affected TS SRs ML20249A5661998-06-10010 June 1998 Proposed Tech Specs Section 5.0,revising Administrative Controls ML20248C5151998-05-27027 May 1998 Proposed Tech Specs Section 3.8.1,revising AC Sources- Operating ML18039A3181998-04-16016 April 1998 Proposed Rev 2 to Tech Specs Section 3.6, Containment Systems, Converting from Current TS to Improved TS ML18039A2711998-03-16016 March 1998 Proposed Tech Specs Re Power Uprate Operation ML18039A2671998-03-13013 March 1998 Proposed Tech Specs,Converting to Improved Std Ts,Per NUREG- 1433,rev 1, Std TS for GE BWRs (BWR/4). ML18039A2641998-03-12012 March 1998 Proposed Tech Specs ITS Section 3.8 Re Electrical Power Sys. ML18039A2611998-03-0303 March 1998 Proposed Tech Spec Changes TS 393 Re Reactor Vessel Pressure Temperature Curves ML20199E8051998-01-23023 January 1998 Proposed Tech Specs Section 5.0 Re Administrative Controls ML18039A2221997-12-30030 December 1997 Proposed Tech Specs Re RHR SW Pumps Required for multi-unit Operation & Cold Shutdown ML18039A2151997-12-23023 December 1997 Proposed Tech Specs Section 3.7 Re Plant Sys ML18039A2181997-12-22022 December 1997 Proposed Tech Specs Section 3.8 Re Electrical Power Sys ML18039A2101997-12-0404 December 1997 Proposed Tech Specs Pages Re TS Change 362,suppl 7 Re ITS Section 3.1, Reactivity Control Sys. ML18039A2071997-12-0404 December 1997 Proposed Tech Specs Pages Re Suppl 9 to TS Change 362, Including Rev Pages to Improved TS Section 3.5 ML18039A2011997-12-0303 December 1997 Proposed Tech Specs Section 3.9 Re Refueling Operations & Section 3.10, Special Operations. ML18039A1981997-12-0303 December 1997 Improved Tech Specs Pages Re Section 5, Administrative Controls. ML20199D5471997-11-14014 November 1997 Proposed Tech Specs Section 3.0, Limiting Condition for Operation (LCO) Operability & Section 4.0, Design Changes ML20199E1361997-11-14014 November 1997 Proposed Tech Specs Section 3.4 Re Reactor Coolant Sys ML20198Q4521997-11-0505 November 1997 Proposed Tech Specs,Incorporating Improved TS (ITS) Bases Revs & Changes to Supporting Documentation Resulting from Responding to NRC Questions ML18038B9611997-10-0101 October 1997 Proposed Tech Specs,Allowing Bfn,Units 2 & 3,to Operate at Uprated Power Level of 3458 Mwt ML18038B9361997-08-15015 August 1997 Proposed Tech Specs,Extending Existing 7-day EDG Allowed Outage Time to Fourteen Days ML18038B9061997-06-19019 June 1997 Proposed Tech Specs Supporting one-time 14-day Limiting Condition for Operation for Each EDG to Accommodate Pending Vendor Recommended Maint Activities ML20138J3781997-05-0101 May 1997 Proposed Tech Specs,Revising TS-362 Amend for Section 3.8, Electrical Power Sys Which Addresses NRC Review Comments ML18038B8651997-04-24024 April 1997 Proposed Tech Specs,Submitting Revised BFN TS Bases Section 3.5.N, References, Reflecting Updated LOCA Analyses for Units 2 & 3 ML20137U1691997-04-11011 April 1997 Proposed Tech Specs Re Pr Neutron Monitor Upgrade W/ Implementation of Average Pr Monitor & Rod Block Monitor TS (ARTS) Improvements & Max Extended Load Line Limit Analyses ML18038B8341997-03-12012 March 1997 Proposed Tech Specs Re Extended EDG Allowed Outage Time ML20136F7851997-03-0606 March 1997 Proposed TS Supporting Planned Replacement of Current Power Range Monitoring Portion of Existing Nms W/Ge Digital Nuclear Measurement Analysis & Control Power Range Neutron Monitor Retrofit Design ML20134G5401997-02-0505 February 1997 Proposed Tech Specs Revising Bases Section 3.7.A/4.7.A, Primary Containment, to Delete Wording Re Maintaining Drywell to Suppression Chamber Differential Pressure Constant for Duration of Drywell to Suppression Chamber ML20132B7401996-12-11011 December 1996 Proposed Tech Specs 2.2.A Re Safety/Relief Valve Setpoint Requirements for Reactor Coolant Sys Integrity ML20117P3341996-09-15015 September 1996 Proposed Tech Specs to Change Unit 3 TS LCO 3.6.F.1 in Order to Perform Repairs & Maint Necessary to Return RCS Recirculation Loop a to Operations ML18038B7541996-09-0606 September 1996 Proposed Conversion from Current TSs to Improved STS Consistent w/NUREG-1433,rev 1 ML20117G7121996-08-30030 August 1996 Proposed Tech Specs Re License Condition on Compliance W/Thermal Water Quality Stds ML20113B1951996-06-21021 June 1996 Proposed Tech Specs,Revising Change in SLMCPR & Bases Description of RHR Suppl Fuel Pool Cooling Mode ML20112G3891996-06-0606 June 1996 Proposed Tech Specs,Revising Section 6, Administrative Controls, to Be More Closely Aligned W/Requirements of Improved Std TSs ML20117H5231996-05-20020 May 1996 Proposed Tech Specs Implementing Guidance of GL 87-09 & NUREG-1433,Rev 1 ML20108D9021996-05-0303 May 1996 Proposed Tech Specs,Withdrawing Amend 219,temporary TS 343T, Rv Water Level Instrumentation & Amend 228,temporary TS 347T,250 Volt DC Control Power Supply Sys AOT for Unit 2 ML20107F9721996-04-14014 April 1996 Proposed Tech Specs,Revising Minimum Required Number of Operable Rv Water Level Trip Sys During Period That RCS Instrument Line Excess Flow Check Valve Surveillance Tests Being Performed ML20096C4401996-01-10010 January 1996 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B,Performance Based Testing 1999-09-28
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML18039A8811999-09-28028 September 1999 Proposed Tech Specs Re Increased MSIV Leakage Rate Limits & Exemption from 10CFR50,App J ML18039A8241999-07-28028 July 1999 Proposed Tech Specs Providing TS for Operation of Oscillation PRM Upscale Trip Function in Aprm,Which Is Part of Power Range Neutron Monitoring Sys ML18039A8001999-06-0303 June 1999 Proposed Tech Specs,Reducing Allowable Value Used for Reactor Vessel Water Level - Low,Level 3 for Several Instrument Functions ML18039A6991999-02-22022 February 1999 Proposed Tech Specs & Bases Pages Incorporating NRC Approved TS Change 354,requiring Oscillation PRM to Be Integrated Into Approved Power uprate,24-month Operating Cycle & Single Recirculation Loop Operation ML18039A6601998-12-15015 December 1998 Proposed Tech Specs,Revising pressure-temp Curves to Extend Validity of Curves to 32 EFPY ML20206F8131998-12-0303 December 1998 Rev 12 to ODCM, for BFN ML18039A5041998-09-0808 September 1998 Proposed Tech Specs Providing TS for Operation of Oscillation Power Range Monitor Upscale Trip Function in Aprm,Which Is Part of Power Range Neutron Monitoring Sys ML18039A5001998-09-0404 September 1998 Proposed Tech Specs Re Use of Containment Overpressure for ECCS Pump Net Positive Suction Head Analyses ML18039A4791998-08-14014 August 1998 Proposed Tech Specs Pages Re Amends to Licenses DPR-33, DPR-52 & DPR-68 to Change Ts.Proposed Changes Decrease Frequency of once-per-cycle Instrument Calibrations by Substituting 24 Months for 18 Months ML18039A4611998-07-31031 July 1998 Proposed Tech Specs B 3.6-2,B 3.6-7 & B 3 3.7-2 for Power Uprate Operation Omitted Pages ML18039A4481998-07-17017 July 1998 Proposed Tech Specs,Adding LCO 3.4.10 & Accompanying TS Bases Provisions from Improved TS-362 Conversion Package as Adapted for Power Uprate Conditions ML18039A4091998-06-26026 June 1998 Proposed Tech Specs Section 3.4,allowing Units 2 & 3 to Operate at Uprated Power Level of 3458 Mwt ML18039A4021998-06-19019 June 1998 Proposed Tech Specs (TS) Converting from Existing Custom TS to Improved TS ML18039A3921998-06-12012 June 1998 Proposed Tech Specs Change 390,decreasing Frequency of once-per-cycle SRs by Substituting 24 Months for 18 Months in Affected TS SRs ML20249A5661998-06-10010 June 1998 Proposed Tech Specs Section 5.0,revising Administrative Controls ML20248C5151998-05-27027 May 1998 Proposed Tech Specs Section 3.8.1,revising AC Sources- Operating ML18039A3181998-04-16016 April 1998 Proposed Rev 2 to Tech Specs Section 3.6, Containment Systems, Converting from Current TS to Improved TS ML18039A2711998-03-16016 March 1998 Proposed Tech Specs Re Power Uprate Operation ML18039A2671998-03-13013 March 1998 Proposed Tech Specs,Converting to Improved Std Ts,Per NUREG- 1433,rev 1, Std TS for GE BWRs (BWR/4). ML18039A2641998-03-12012 March 1998 Proposed Tech Specs ITS Section 3.8 Re Electrical Power Sys. ML18039A2611998-03-0303 March 1998 Proposed Tech Spec Changes TS 393 Re Reactor Vessel Pressure Temperature Curves ML20199E8051998-01-23023 January 1998 Proposed Tech Specs Section 5.0 Re Administrative Controls ML18039A2401998-01-15015 January 1998 Bfnp Unit 2 Cycle 10 Power Ascension Test Program Start-Up Rept, for Period 970929-1105 ML18039A2221997-12-30030 December 1997 Proposed Tech Specs Re RHR SW Pumps Required for multi-unit Operation & Cold Shutdown ML18039A2151997-12-23023 December 1997 Proposed Tech Specs Section 3.7 Re Plant Sys ML18039A2181997-12-22022 December 1997 Proposed Tech Specs Section 3.8 Re Electrical Power Sys ML20217P5051997-12-0808 December 1997 Rev 10 to ODCM, Containing Markups to Rev 9 & 10 ML18039A2101997-12-0404 December 1997 Proposed Tech Specs Pages Re TS Change 362,suppl 7 Re ITS Section 3.1, Reactivity Control Sys. ML18039A2071997-12-0404 December 1997 Proposed Tech Specs Pages Re Suppl 9 to TS Change 362, Including Rev Pages to Improved TS Section 3.5 ML18039A2011997-12-0303 December 1997 Proposed Tech Specs Section 3.9 Re Refueling Operations & Section 3.10, Special Operations. ML18039A1981997-12-0303 December 1997 Improved Tech Specs Pages Re Section 5, Administrative Controls. ML20199D5471997-11-14014 November 1997 Proposed Tech Specs Section 3.0, Limiting Condition for Operation (LCO) Operability & Section 4.0, Design Changes ML20199E1361997-11-14014 November 1997 Proposed Tech Specs Section 3.4 Re Reactor Coolant Sys ML20198Q4521997-11-0505 November 1997 Proposed Tech Specs,Incorporating Improved TS (ITS) Bases Revs & Changes to Supporting Documentation Resulting from Responding to NRC Questions ML18038B9611997-10-0101 October 1997 Proposed Tech Specs,Allowing Bfn,Units 2 & 3,to Operate at Uprated Power Level of 3458 Mwt ML18038B9361997-08-15015 August 1997 Proposed Tech Specs,Extending Existing 7-day EDG Allowed Outage Time to Fourteen Days ML20210V1171997-07-29029 July 1997 Qualification Plan & Rept MIL-STD-462D,CS114,Conducted Susceptibility,Bulk Cable Injection Numac Reactor Bldg Vents Radiation Monitor TVA Bfn,Units 1,2 & 3 ML18038B9061997-06-19019 June 1997 Proposed Tech Specs Supporting one-time 14-day Limiting Condition for Operation for Each EDG to Accommodate Pending Vendor Recommended Maint Activities ML20138J3781997-05-0101 May 1997 Proposed Tech Specs,Revising TS-362 Amend for Section 3.8, Electrical Power Sys Which Addresses NRC Review Comments ML18038B8651997-04-24024 April 1997 Proposed Tech Specs,Submitting Revised BFN TS Bases Section 3.5.N, References, Reflecting Updated LOCA Analyses for Units 2 & 3 ML20137U1691997-04-11011 April 1997 Proposed Tech Specs Re Pr Neutron Monitor Upgrade W/ Implementation of Average Pr Monitor & Rod Block Monitor TS (ARTS) Improvements & Max Extended Load Line Limit Analyses ML18038B8341997-03-12012 March 1997 Proposed Tech Specs Re Extended EDG Allowed Outage Time ML20136F7851997-03-0606 March 1997 Proposed TS Supporting Planned Replacement of Current Power Range Monitoring Portion of Existing Nms W/Ge Digital Nuclear Measurement Analysis & Control Power Range Neutron Monitor Retrofit Design ML20134G5401997-02-0505 February 1997 Proposed Tech Specs Revising Bases Section 3.7.A/4.7.A, Primary Containment, to Delete Wording Re Maintaining Drywell to Suppression Chamber Differential Pressure Constant for Duration of Drywell to Suppression Chamber ML18038B8281997-01-31031 January 1997 Rev 1 to GE-NE-B13-01805-22, Internal Core Spray Line Flaw Evaluation Handbook for Browns Ferry Units 2 & 3. ML18038B8111997-01-22022 January 1997 Rev 0 to Browns Ferry Nuclear Plant,Surveillance Instruction,Inservice Insp Program,Unit 3. ML20132B7401996-12-11011 December 1996 Proposed Tech Specs 2.2.A Re Safety/Relief Valve Setpoint Requirements for Reactor Coolant Sys Integrity ML20117P3341996-09-15015 September 1996 Proposed Tech Specs to Change Unit 3 TS LCO 3.6.F.1 in Order to Perform Repairs & Maint Necessary to Return RCS Recirculation Loop a to Operations ML18038B7541996-09-0606 September 1996 Proposed Conversion from Current TSs to Improved STS Consistent w/NUREG-1433,rev 1 ML20117G7121996-08-30030 August 1996 Proposed Tech Specs Re License Condition on Compliance W/Thermal Water Quality Stds 1999-09-28
[Table view] |
Text
ENCLOSURE 1 PROPOSED CHANGES BROWNS FERRY NUCLEAR PLANT (BFN)
TS 201i SUPPLEMENT 3 shi2i60270 85000259 PDR ADOCN 0 PDR P
4 I
I' g"
1 41
Table 6.2.A Hinimum Shift Crew Re uirementsb Position Units in 0 eration T e of License 0 2d 3 Senior Operatora 1 1 1 1 SRO Senior Operator 0 1 2 2 SRO Licensed Operators 3 3 3 3 RO or SRO 4S Additional Licensed Operatorsc 0 1 2 2 RO or SRO Assistant Unit Operators (AUO) 4 4 5 -
5 None Shift Technical Advisor (STA) 0 1 1 1 None Health Physics Technician 1 1 1 1 None Note for Table 6.2.A
- a. A senior operator will be assigned responsibility for overall plant operation at all times there is fuel in any unit,
- b. Except for the senior operator discussed in note "a", the shift crew composition may be one less than the minimum requirements of Table 6.2.A for a period of time not to exceed two hours in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2.A. This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.
c~ One of the Additional Licensed Operators must be assigned to each control room with an operating unit.
The number of required licensed personnel, when the operating units are controlled from a common control room, are two senior operators and four operators.
6-3
6.3 PLANT STAFF VALIFICATIONS Qualifications of the Browns Ferry Nuclear Plant management and operating staff shall meet the minimum acceptable levels as described in ANSI-N18.1, Selection and Training of Nuclear Power Plant Personnel, dated March 8, 1971. The qualifications of the Health Physics Supervisor will meet or exceed the minimum acceptable levels as described in Regulatory Guide 1.8, Revision 1, dated September 1975. The Shift Technical Advisor shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design and transient and accident response and analysis.
6.4 TRAINING I
A retraining and replacement training program for station personnel shall be in accordance with ANSI N18.1, Selection and Training of Nuclear Power Plant Personnel, dated March 8, 1971. The minimum frequency of the retraining program shall be every two years.
6.5 PLANT REVIEW AND AUDIT 6.5.1 Plant 0 erations Review Committee (PORC) 6.5.1.1 Function
- a. The PORC shall function to advise the Plant Manager in all matters related to nuclear safety.
- b. This advisory function shall be performed by, the PORC acting in a formal meeting or by members acting individually without a formal meeting.
6-4
6.5.1.4 For expedited meetings, when it is not practical to convene 'as a-group, the chairman or alternate chairman may conduct committee business by polling the members individually (by telephone or in person) or via "a serialized review.
VORVM
~y 6.5.1.5 The quorum necessary for the PORC to act in a formal meeting shall consist of the chairman or alternate chairman and at least five members or their alternates. Members shall be considered present if they are in telephone communication with the committee.
RESPONSIBILITIES 6.5.1.6 The PORC shall be responsible for the activities listed below.
The PORC may delegate the performance of reviews, but will maintain cognizance over and responsibility for them, e.g.,
subcommittees.
- a. Review of administrative procedures for the control of the technical and cross-disciplinary review of (1) all procedures required by specification 6.8.1.1, and changes thereto, (2) any other procedures and changes thereto .
determined by the Plant Manager to affect nuclear safety.
- b. Review of the administrative procedures required by specification 6.8.l.l.a. and changes thereto.
- c. Review of emergency operating procedures and changes thereto.
- d. Review implementing procedures of the Radiological Emergency Plan and the Industrial Security Program.
6-6
shall be secured by lock(s). The key(s) shall be'nder the .
administrative control of the shift engineer. In the case of a high radiation area established for a period of 30 days or less, direct surveillance to prevent unauthorized entry may be substituted for permanent access control.
Health Physics personnel, or personnel escorted by Health Physics lg personnel, in accordance with approved emergency procedures, shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.
6.9 REPORTING RE UIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following identified reports shall be submitted to the Director of the Regional Office of NRC, unless otherwise noted.
6.9.1.1 STARTUP REPORT
- a. A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic 6-20
on pocket dosimeter, TLD, or film badge measurements. Small exposures totaling less than 207. of the individual total ~
dose need not be accounted for. In the aggregate, at least
,r 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.
- b. Any-mainsteam relief valve that opens in response to reaching its setpoint or due to operator action to control N
reactor pressure shall be reported.
"-A single submittal may be made for a multiple unit station.
~=This tabulation supplements the requirements of 20.407 of 10 CFR Part 20.
6.9.1.3 MONTHLY OPERATING REPORT Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Office of Inspection and Enforcement, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional Office, to be submitted no later than the fifteenth of each month following the calendar month covered by the report. A narrative summary of operating experience shall be submitted in the above schedule.
6.9.1.4 REPORTABLE EVENTS Reportable events, including corrective actions and measures to prevent reoccurrence, shall be reported to the NRC in accordance with Section 50.73 to 10 CFR 50.
6-22
I, 6.9.1.'5 RADIOACTIVE EFFLUENT RELEASE REPORT%
A report on the 'radioactive discharges released from the site during the previous 6 months of operation shall be submitted to the Director of the Regional Office of Inspection and Enforcemenmt- within 60 days after January 1 and July 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents released and solid waste shipped from the plant as delineated'in Regulatory Guide 1.21, Revision 1, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants" with data summarized on a quarterly basis following the format of Appendix B thereof.
The report shall include a summary of the meteorological conditions concurrent with the release of gaseous effluents during each quarter as outlined in Regulatory Guide 1.21, Revision 1, with data summarized on a quarterly basis following the-format of Appendix B thereof. Calculated offsite dose to humans resulting from the release of effluents and their subsequent dispersion in in the atmosphere shall be reported as recommended in Regulatory Guide 1.21, Revision l.
~A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.
6.9.1.6 SOURCE TESTS Results of required leak tests performed on sources if the tests reveal the presence of 0.005 microcurie or more of removable contamination.
6-23
BOARD OF DIRECTORS GENERAL MANAGER MANAGER OF aO DEPUTY MANAGER N
I NUCLEAR SAFETY REVIEW BOARD NUCLEAR DIRECTOR DIRECTOR DIRECTOR DIRECTOR DIRECTOR DIRECTOR SITE DIRECTORS OP OF OF OP OP OP NUCLEAR NUCLEAR NUCLEAR NUCLEAR NUCLEAR SAFETY
~
AND NUCLEAR NUCLEAR ROJECT MANAGERS CO&NSTRUCTION QA EhGINEERING SERVICES TRAINING & LICENSING Figurc 6.2-1 Offsite Organization for Facility Management and Technical Support
~ ~ 'I
I DIRECTOR DIRECTOR DIRECTOR DIRECTOR DIVISION OF OF NUCLEAR SITE DIVISION OF DIVISION OF NUCLEAR QA ENGINEERING DIRECTOR NUCLEAR NUCLEAR SAFETY CONSTRUCTION AND LICENSING SITE SITE SITE QA PROJECT PLANT SERVICES ODIFlCATION ENGINEER MANAGER MANAGER SAFETY AND MANAGER MANAGER LICENSING MANAGER ASSISTAN PLANT MANAGER INDUSTRIAL SAFETY>>
UNIT RADIOLOGICAL TECHNICAL UP ER INTEND ENTS MAINTENANCE CONTROL SUPERINTENDENT SERVICES (3) SUPERINTENDENT OPERATIOI'IS UNIT SUPERVISORS AINTENANCE (3) UPERVISORS HEMISTRY ENGINEERING 3)
SHIFT SHIFT CREWS TECHNICAL (3). ADVISOR SHIFT ENGINEER (SRO) ~ RESPONSIBIIJlY FOR FIRE PROTECTION PROGRAM ASSISTANT SHIFT ENGINEER SRO SENIOR REACTOR OPERATOR UCENSE UNIT OPERATOR (RO) (SRO) RO REACTOR OPERATOR IJCENSE ASSISTANT UNIT OPERATOR AUXILIARYUNIT OPERATOR FIGURE 6.2-2 FACILITY ORGANIZATION
4.
r'
Enclosure 2 Description and Justification TVA BFNP 201 Supplement 3 Descri tion of Additional Chan es Table 6.2.A, Minimum Shift Crew Requirements, page 6-3, is revised to delete note "e" which described shift technical advisor qualifications. The same words were added to section 6.3, Plant Staff Qualifications, page 6-4, and therefore no change to the current technical specification requirements or-those of theproposed amendment is made.
Plant Operations Review Committee (PORC) responsibility item 6.5.1.6.d is revised to include review of implementing procedures of the Industrial Security Program. This change will return this item to its current TS wording.
Pages 6-20, 6-22, .and 6-23 of the proposed amendment simply "had notes moved from the bottom of the page to the end of the section to which the notes apply.
The Offsite Organization, Figure 6.2-1 of TS 201 Supplement 2, is revised to include the Director of Nuclear Construction and to delete site organizations now shown on figure 6.2-2.
N The Facility Organization, Figure 6.2-2, of TS 201 Supplement 2, is revised to include the Site Safety and Licensing Manager, Project Engineer, Assistant Plant Manager, Plant Operations Review Staff, Industrial Safety, Shift Technical Advisor, and notes for licensed positions and fire protection responsibility.
Revised Justification for Chan e TVA is a corporate agency of the Federal Government whose major policies, programs, and organizations are determined by a full-time, three member Board of Directors. Members of the, Board are appointed by the President and confirmed by the Senate for nine-year terms. The staff of Browns Ferry Nuclear Plant within the Office of Nuclear Power is responsible for operating and maintaining TVA's Browns Ferry Nuclear Plant. The changes contained in this amendment request deal specifically and solely with the administrative controls required by TS.
Changing the Administrative Controls section to standard format with the standard page numbering system, deleting unnecessary notes, deleting references to previously deleted requirements, adopting STS terminologyf adding new minimum shift crew requirements, and updating the description of the TVA organization are all within the guidance provided by NRC in STS and will result in increased clarity and usefulness and therefore, increased safety.
The changes to the description of PORC and the technical review process are consistent with the regulatory position of Regulatory Guide 1.33, revision 2, February 1978. The requested amendment requires that decisions affecting
Revised Justification for Chan e (Continued) safety be made at the proper level of responsibility with the necessary technical advice and review. The Plant Manager retains overall responsibility for the execution of the administrative controls necessary to assure plant safety. However, the detailed technical reviews can be accomplished by qualified individuals not encumbered with other managerial duties, but possessing the technical expertise to provide a thorough review. The current TS requirement for review of changes is actually satisfied by individuals of a similar responsibility level; however, considerable management time is consumed in the assigning of these personnel to review each item, collecting results from..those reviews, and finally attending a formal meeting to recommend a disposition. The method requested by this amendment eliminates much of the unnecessary effort and at the same time provides for a more consistent and timely review and approval process. It= will focus responsibility and accountability to the technical reviewers and provide a better review. Cross-disciplinary review will also be improved from current methods since reviewers will be able to concentrate on their particular areas of expertise.
The most important safety consideration is that this amendment permits PORC members to focus their attention on the safety significance of the issues essential to the safe operation of the plant thereby improving PORC's effectiveness. This aspect is increasingly important because of the growing number of procedures, procedural changes, and modifications that must be reviewed.
For the reasons stated above, TVA has concluded that these proposed TS changes will significantly enhance nuclear safety.
0449y
f
/
I