Revised Pages 6-2,6-7 Through 6-9 & 6-11 Through 6-13 to Tech Specs,App a Re Administrative Controls & Revised Page 5-1-1 of Tech Specs,App B Re Organizational ChangesML19256F595 |
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Davis Besse |
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Issue date: |
12/06/1979 |
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TOLEDO EDISON CO. |
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Shared Package |
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ML19256F554 |
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References |
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TAC-12617, NUDOCS 7912190532 |
Download: ML19256F595 (9) |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20216E6111999-09-0707 September 1999 Proposed Tech Specs 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation & Associated Bases ML20210H0731999-07-28028 July 1999 Proposed Tech Specs 3/4.7.5.1, Ultimate Heat Sink, Allowing Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F ML20210G4311999-07-27027 July 1999 Proposed Tech Specs,Changing TSs 6.4, Training, 6.5.2.8, Audits, 6.10, Record Retention, 6.14, Process Control Program & 6.15, Odcm ML20210G4801999-07-26026 July 1999 Proposed Tech Specs 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation & Associated Bases ML20210G9161999-07-26026 July 1999 Proposed Tech Specs 3/4.3.3.1, Radiation Monitoring Instrumentation, 3/4.3.3.2, Instrumentation - Incore Detectors & 3/4.3.3.9, Instrumentation - Waste Gas Sys Oxygen Monitor ML20210G5391999-07-26026 July 1999 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B for Type B & C Containment Leakage Rate Testing ML20195F9351999-06-10010 June 1999 Proposed Tech Specs,Revising TS 3/4.6.4.4, Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.6.5.1, Crevs ML20207E7941999-05-21021 May 1999 Proposed Tech Specs Allowing Use of Expanded Spent Fuel Storage Capability ML20205E5031999-03-19019 March 1999 Proposed Tech Specs Withdrawing Proposed New Action B, Previously Submitted in 981027 Application ML20204F1821999-03-0909 March 1999 Proposed Tech Specs,Adopting Changes in Frequency & Scope of Volumetric & Surface Exams Justified by W TR WCAP-14535A ML20155E3231998-10-28028 October 1998 Proposed Tech Specs Revising Various Sections of 6.0, Administrative Controls, Including Relocation of 6.11 Contents to Plant Ufsar,Per NUREG-1430,Rev 1 ML20155E4971998-10-28028 October 1998 Proposed Tech Specs 4.0.2 Re Applicability of 25% Surveillance Interval Extension Allowance ML20155D7791998-10-27027 October 1998 Proposed Tech Specs Relocating TS SR 4.6.5.1.d.4 Re Evs Negative Pressure Testing to TS 3/4.6.5.2,deleting TS Definition 1.24 & Making Related Changes Associated with Deletion of Subject Definition ML20155E0721998-10-27027 October 1998 Proposed Tech Specs Revising 3/4.3.1.1 Re RPS Instrumentation & 3/4.3.2.3 Re ARTS Instrumentation,To Provide Potential Reduction in Spurious Trip Rate for Potential Cost Savings in Excess of $50,000 ML20155D8521998-10-27027 October 1998 Proposed Tech Specs Revising SRs 4.8.2.3.2.d,4.8.2.3.2.e, 4.8.2.3.2.f & Table 4.8-1 Re Testing of 125 Volt DC Station Batteries & Applicable TS Bases ML20151W2991998-09-0808 September 1998 Proposed Tech Specs Revising Section 3/4.7.6, Plant Systems - CREVS & Associated Bases ML20151W3071998-09-0808 September 1998 Proposed Tech Specs Permitting Use of Framatome Cogema Fuels M5 Advanced Alloy for Fuel Rod Cladding & Fuel Assembly Spacer Grids ML20217P8351998-04-24024 April 1998 Proposed Tech Specs Clarifying Discussion of Margin Between RPS High Pressure Trip Setpoint & Lift Setting for Pressurizer Code Safety Valves ML20217P8811998-04-24024 April 1998 Proposed Tech Specs 3/4.3.1.1,3/4.3.2.1,3/4.3.2.2 & Associated Bases Relocating Tables of Response Time Limits to Plant USAR Technical Requirements Manual ML20217C4881998-03-20020 March 1998 Proposed Tech Specs SR 4.4.5.3.c.1,providing Greater Specificity as to Location of Addl Insps in Unaffected SG ML20217N4471998-02-27027 February 1998 Proposed Tech Specs Pages Provided to Modify Proposed New Action 3.7.6.1.b to Make More Consistent w/NUREG-1431 ML20203L1111998-02-26026 February 1998 Proposed Tech Specs Pages Re Amend to License NPF-3 Involving Incorporation of New Repair Roll Process for SG Tubes W/Defects in Upper Tube Sheet ML20197J2621997-12-23023 December 1997 Proposed Tech Specs Pages Re Changes to TS Definition 1.2, TS 3/4/9.5 & New TS 3.0.6 & Associated Bases.Ts Index Rev to Reflect Change to TS 3/4.9.5,included ML20197J5971997-12-23023 December 1997 Proposed Tech Specs Pages,Revising TS Surveillance Requirements for ISI Requirements of Internal Auxiliary Feedwater Header,Header to Shroud Attachment Welds & External Header Thermal Sleeves ML20217R2821997-08-26026 August 1997 Proposed Tech Specs,Clarifying LCO 3.6.1.3.a & Revising Surveillance Requirement 4.6.1.3.c ML20217R2871997-08-26026 August 1997 Proposed Tech Specs,Modifying TS 3.2.5 Action Statement to Require Power Reduction to Less than 5% of Rated Thermal Power within Four Hrs If RCS Flow Rate Is Less than Specified Limit for Greater than Two Hrs ML20217G5981997-07-29029 July 1997 Proposed Tech Specs 3/4.4.3 Re Safety Valves & Pilot Operated Relief valve-operating ML20141F1101997-06-24024 June 1997 Proposed Tech Specs,Deleting Requirements for Safety Features Actuation Sys Containment High Radiation Monitors ML20138C3261997-04-18018 April 1997 Proposed Tech Specs 3/4.7.6 Revising Limiting Condition for Operation to Include New Required Actions in Event That One or Both Channels of Radiation Monitoring Instrumentation Becomes Inoperable ML20138A6891997-04-18018 April 1997 Proposed Tech Specs 3/4.5.3.2.1 & 3/4.5.2 Modifying Presently Specified 18-month Surveillance Frequencies to New Specified Frequencies of Once Each 24-months ML20138M1281997-02-14014 February 1997 Proposed Tech Specs 3.5.2 Re Emergency Core Cooling Systems & 4.5.2.f Re Surveillance Requirements ML20134L0561997-02-13013 February 1997 Proposed Tech Specs Re Changes Made Concerning Decay Heat Removal Sys Valve ML20134D7621997-01-30030 January 1997 Proposed Tech Specs Revising SR Intervals from 18 to 24 Months Based on Results of DBNPS Instrument Drift Study & TS 2.2, Limiting Safety Sys Settings, Based on Results of Revised Framatome RPS Instrument String Error ML20134F1811997-01-30030 January 1997 Proposed Tech Specs Re Possession & Use of SNM as Reactor Fuel ML20134B0591997-01-20020 January 1997 Proposed Tech Specs 3/4.5.3 Re ECCS Subsystems ML20132B7031996-12-11011 December 1996 Proposed Tech Specs Revising TS Definitions,Instrumentation TS & ECCS TS for Conversion to 24 Month Fuel Cycle for License NPF-3 ML20134F1891996-10-28028 October 1996 Proposed Tech Specs 3/4.8 Re Electrical Power Systems ML20117P5311996-09-17017 September 1996 Proposed Tech Specs,Supporting Conversion of DBNPS from 18 Month to 24 Month Fuel Cycle ML20117N8531996-09-12012 September 1996 Proposed Tech Specs Re Reactivity Control Systems & Emergency Core Cooling Systems ML20117M2201996-09-0404 September 1996 Proposed Tech Specs 6.2.3,removing Specific Overtime Limits & Working Hours ML20116K2631996-08-0707 August 1996 Proposed Tech Specs Re Definitions,Applicability Bases, Containment Spray Sys & Containment Isolation Valve for Conversion to 24 Month Fuel Cycle ML20117K1911996-05-28028 May 1996 Proposed Tech Specs 3/4.3.1.1 - RPS Instrumentation & TS 3/4.3.2.3 - Anticipatory RTS Instrumentation Increasing Trip Device Test Interval ML20101M1921996-03-29029 March 1996 Proposed Tech Specs 3/4.6.4.4 - HPS,3/4.6.5.1 - Shield Building Evs & 3.4.7.6.1 - CREVS Re Changing Surveillance Requirements for Charcoal Filter Lab Testing to Revise Methodology Used to Determine Operability in ESF AHUs ML20101C6961996-03-0606 March 1996 Proposed Tech Specs,Allowing Deferment of SR 4.5.2.b for ECCS Flowpath Containing HPI Pump 1-2 Until 10th Refueling Outage,Scheduled to Begin 960408 ML20100E0101996-02-0505 February 1996 Proposed TS 3/4.3.2.1,Table 3.3-3,safety Features Actuation Sys Instrumentation,Reflecting Design & Actuation Logic of Plant Sequencers & Essential Bus Undervoltage Relays ML20095F5891995-12-12012 December 1995 Proposed Tech Specs Re Containment Sys ML20094D0611995-10-31031 October 1995 Proposed TS Page 6-18,deleting TS 6.9.2.d, Seismic Event Analysis ML20098C5181995-10-0202 October 1995 Proposed Tech Specs,Revising TS Section 5.0,design Features & Adopting Improved STS for B&W Plants Format & Content ML20098C4111995-09-29029 September 1995 Proposed TS 3/4.1.2.8 Re Reactivity Control Sys - Borated Water Sources - Shutdown TS 3/4.1.2.8 Re Reactivity Control Sys - Operating & TS 3/4.5.1 Re ECCS - Core Flooding Tanks ML20098C1121995-09-29029 September 1995 Proposed TS 3.4.3 & Associated Bases,Modifying Lift Setting of Pressurizer Code Safety Valves to Greater than or Equal to 2,575 Psig,Corresponding to Lift Setting Tolerance of +3% of Nominal Lift Pressure 1999-09-07
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20216E6111999-09-0707 September 1999 Proposed Tech Specs 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation & Associated Bases ML20210H0731999-07-28028 July 1999 Proposed Tech Specs 3/4.7.5.1, Ultimate Heat Sink, Allowing Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F ML20210G4311999-07-27027 July 1999 Proposed Tech Specs,Changing TSs 6.4, Training, 6.5.2.8, Audits, 6.10, Record Retention, 6.14, Process Control Program & 6.15, Odcm ML20210G4801999-07-26026 July 1999 Proposed Tech Specs 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation & Associated Bases ML20210G9161999-07-26026 July 1999 Proposed Tech Specs 3/4.3.3.1, Radiation Monitoring Instrumentation, 3/4.3.3.2, Instrumentation - Incore Detectors & 3/4.3.3.9, Instrumentation - Waste Gas Sys Oxygen Monitor ML20210G5391999-07-26026 July 1999 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B for Type B & C Containment Leakage Rate Testing ML20195F9351999-06-10010 June 1999 Proposed Tech Specs,Revising TS 3/4.6.4.4, Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.6.5.1, Crevs ML20207E7941999-05-21021 May 1999 Proposed Tech Specs Allowing Use of Expanded Spent Fuel Storage Capability ML20205E5031999-03-19019 March 1999 Proposed Tech Specs Withdrawing Proposed New Action B, Previously Submitted in 981027 Application ML20204F1821999-03-0909 March 1999 Proposed Tech Specs,Adopting Changes in Frequency & Scope of Volumetric & Surface Exams Justified by W TR WCAP-14535A ML20155E4971998-10-28028 October 1998 Proposed Tech Specs 4.0.2 Re Applicability of 25% Surveillance Interval Extension Allowance ML20197G5521998-10-28028 October 1998 Rev 8 to Dbnps,Unit 1 Technical Requirements Manual ML20155E3231998-10-28028 October 1998 Proposed Tech Specs Revising Various Sections of 6.0, Administrative Controls, Including Relocation of 6.11 Contents to Plant Ufsar,Per NUREG-1430,Rev 1 ML20155D7791998-10-27027 October 1998 Proposed Tech Specs Relocating TS SR 4.6.5.1.d.4 Re Evs Negative Pressure Testing to TS 3/4.6.5.2,deleting TS Definition 1.24 & Making Related Changes Associated with Deletion of Subject Definition ML20155D8521998-10-27027 October 1998 Proposed Tech Specs Revising SRs 4.8.2.3.2.d,4.8.2.3.2.e, 4.8.2.3.2.f & Table 4.8-1 Re Testing of 125 Volt DC Station Batteries & Applicable TS Bases ML20155E0721998-10-27027 October 1998 Proposed Tech Specs Revising 3/4.3.1.1 Re RPS Instrumentation & 3/4.3.2.3 Re ARTS Instrumentation,To Provide Potential Reduction in Spurious Trip Rate for Potential Cost Savings in Excess of $50,000 ML20151W3071998-09-0808 September 1998 Proposed Tech Specs Permitting Use of Framatome Cogema Fuels M5 Advanced Alloy for Fuel Rod Cladding & Fuel Assembly Spacer Grids ML20151W2991998-09-0808 September 1998 Proposed Tech Specs Revising Section 3/4.7.6, Plant Systems - CREVS & Associated Bases ML20206D2721998-08-28028 August 1998 Rev 11,change 1 to Odcm ML20217P8351998-04-24024 April 1998 Proposed Tech Specs Clarifying Discussion of Margin Between RPS High Pressure Trip Setpoint & Lift Setting for Pressurizer Code Safety Valves ML20217P8811998-04-24024 April 1998 Proposed Tech Specs 3/4.3.1.1,3/4.3.2.1,3/4.3.2.2 & Associated Bases Relocating Tables of Response Time Limits to Plant USAR Technical Requirements Manual ML20217C4881998-03-20020 March 1998 Proposed Tech Specs SR 4.4.5.3.c.1,providing Greater Specificity as to Location of Addl Insps in Unaffected SG ML20217N4471998-02-27027 February 1998 Proposed Tech Specs Pages Provided to Modify Proposed New Action 3.7.6.1.b to Make More Consistent w/NUREG-1431 ML20203L1111998-02-26026 February 1998 Proposed Tech Specs Pages Re Amend to License NPF-3 Involving Incorporation of New Repair Roll Process for SG Tubes W/Defects in Upper Tube Sheet ML20197J2621997-12-23023 December 1997 Proposed Tech Specs Pages Re Changes to TS Definition 1.2, TS 3/4/9.5 & New TS 3.0.6 & Associated Bases.Ts Index Rev to Reflect Change to TS 3/4.9.5,included ML20197J5971997-12-23023 December 1997 Proposed Tech Specs Pages,Revising TS Surveillance Requirements for ISI Requirements of Internal Auxiliary Feedwater Header,Header to Shroud Attachment Welds & External Header Thermal Sleeves ML20217M5601997-09-0505 September 1997 Rev 11.0 to Davis-Besse Odcm ML20217R2821997-08-26026 August 1997 Proposed Tech Specs,Clarifying LCO 3.6.1.3.a & Revising Surveillance Requirement 4.6.1.3.c ML20217R2871997-08-26026 August 1997 Proposed Tech Specs,Modifying TS 3.2.5 Action Statement to Require Power Reduction to Less than 5% of Rated Thermal Power within Four Hrs If RCS Flow Rate Is Less than Specified Limit for Greater than Two Hrs ML20217G5981997-07-29029 July 1997 Proposed Tech Specs 3/4.4.3 Re Safety Valves & Pilot Operated Relief valve-operating ML20141F1101997-06-24024 June 1997 Proposed Tech Specs,Deleting Requirements for Safety Features Actuation Sys Containment High Radiation Monitors ML20138C3261997-04-18018 April 1997 Proposed Tech Specs 3/4.7.6 Revising Limiting Condition for Operation to Include New Required Actions in Event That One or Both Channels of Radiation Monitoring Instrumentation Becomes Inoperable ML20138A6891997-04-18018 April 1997 Proposed Tech Specs 3/4.5.3.2.1 & 3/4.5.2 Modifying Presently Specified 18-month Surveillance Frequencies to New Specified Frequencies of Once Each 24-months ML20140D9481997-04-0909 April 1997 ODCM, Rev 10 ML20138M1281997-02-14014 February 1997 Proposed Tech Specs 3.5.2 Re Emergency Core Cooling Systems & 4.5.2.f Re Surveillance Requirements ML20134L0561997-02-13013 February 1997 Proposed Tech Specs Re Changes Made Concerning Decay Heat Removal Sys Valve ML20134F1811997-01-30030 January 1997 Proposed Tech Specs Re Possession & Use of SNM as Reactor Fuel ML20134D7621997-01-30030 January 1997 Proposed Tech Specs Revising SR Intervals from 18 to 24 Months Based on Results of DBNPS Instrument Drift Study & TS 2.2, Limiting Safety Sys Settings, Based on Results of Revised Framatome RPS Instrument String Error ML20134B0591997-01-20020 January 1997 Proposed Tech Specs 3/4.5.3 Re ECCS Subsystems ML20132B7031996-12-11011 December 1996 Proposed Tech Specs Revising TS Definitions,Instrumentation TS & ECCS TS for Conversion to 24 Month Fuel Cycle for License NPF-3 ML20134F1891996-10-28028 October 1996 Proposed Tech Specs 3/4.8 Re Electrical Power Systems ML20117P5311996-09-17017 September 1996 Proposed Tech Specs,Supporting Conversion of DBNPS from 18 Month to 24 Month Fuel Cycle ML20117N8531996-09-12012 September 1996 Proposed Tech Specs Re Reactivity Control Systems & Emergency Core Cooling Systems ML20117M2201996-09-0404 September 1996 Proposed Tech Specs 6.2.3,removing Specific Overtime Limits & Working Hours ML20116K2631996-08-0707 August 1996 Proposed Tech Specs Re Definitions,Applicability Bases, Containment Spray Sys & Containment Isolation Valve for Conversion to 24 Month Fuel Cycle ML20117K1911996-05-28028 May 1996 Proposed Tech Specs 3/4.3.1.1 - RPS Instrumentation & TS 3/4.3.2.3 - Anticipatory RTS Instrumentation Increasing Trip Device Test Interval ML20101M1921996-03-29029 March 1996 Proposed Tech Specs 3/4.6.4.4 - HPS,3/4.6.5.1 - Shield Building Evs & 3.4.7.6.1 - CREVS Re Changing Surveillance Requirements for Charcoal Filter Lab Testing to Revise Methodology Used to Determine Operability in ESF AHUs ML20101C6961996-03-0606 March 1996 Proposed Tech Specs,Allowing Deferment of SR 4.5.2.b for ECCS Flowpath Containing HPI Pump 1-2 Until 10th Refueling Outage,Scheduled to Begin 960408 ML20100E0101996-02-0505 February 1996 Proposed TS 3/4.3.2.1,Table 3.3-3,safety Features Actuation Sys Instrumentation,Reflecting Design & Actuation Logic of Plant Sequencers & Essential Bus Undervoltage Relays ML20107C3101995-12-21021 December 1995 Rev 9 to Odcm 1999-09-07
[Table view] |
Text
._ __ _.__ .._ _ _. _ _ . _
I. Change to Davis-Besse Nuclear Power Station, Unit No. 1 Technical Specifications; Appendix A, Section 6 and Appendix B, Section 5 - see proposed changes attached.
A. Time Required to Implement This change is to be effective upon NRC approval.
B. Reason for Change (Facility Change Request 79-426)
This change is requested to reflect organizational changes within the Toledo Edison Company.
C. Safety Evaluation This change reflects an organizational alteration within the Toledo Edison Company. There has been no plant design effects which would constitute -
an unreviewed safety question as per 10CFR50.59.
v 162'1 070 gg
f
, ADMINISTRATIVE CONTROLS
- c. Review of all proposed changes to Appendix "A" Technical Specifications.
- d. Review of all proposed changes or mcdifications to plant systems or equipment that affect nuclear safety.
e.
Investigation of all violations of the Technical Specifications including preparation and forwarding of reports covering evalua-tion and recommendations to prevent recurrence to the Vice President - Cn:c;; Eu-^1 Nuclear Review Board. k ; p g yand to the Chainnan of the / C f.
Review of events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification to the Commission.
g.
Review of facility operations to det'ect potential safety hazards, h.
Performance of speciai reviews, investigations and analyses
- and reports thereon as requested by the Chairman o,f the Company Nuclear Review Board.
i.
Revie.i of the Plant Security Plan and implementing procedures and shall submit reccmmended changes to the Chairman of the Company Nuclear Review Board.
j.
Review of the Emergency Plan and implementing procedures and
- shal~ submit reccmmended changes to the Chairman of the Company Nuclear Review Board.
AUTHORITY 6.5.1.;7 the Station Review Board shall:
a.
Recommend to the Station Superintendent written approval or disapproval of items considered under 6.5.1.6(a) through (d) above. -
b.
Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question.
c.
~
Provide writtgn notjfication within 24 hcurs to the Vice President, En;fl]Im3 ply and the Company Nuclear Review Board of disagreenent between the SRB and the Station Superintendent; 4
(
however, the Station Superintendent shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.
OAVIS-BESSE, UNIT 1 6-7 * .
7 , ,
ADMINISTRATIVE CONTROLS RECORDS 6.5.1.8 The Station Review Board shall maintain written minutes of each meeting and copies shall be provided to the Vice President, E : 3; N0cleehr- '
Sepp 4y and Chairman of the Company Nuclear Review Board.
6.5.2 COMPANY NUCLEAR REVIEW 30ARD (CNRB)
FUNCTION
.s 6.5.2.1 The Company Nuclear Review Board (CNRB) shall function to provide areas of:independent review and audit of designated activities in the
- a. Nuclear pcwer plant operations,
- b. Nuclear engineering,
- c. Chemistry and radiochemistry,
- d. Metallurgy,
- e. Instrumentati.on and centrol,
- f. Radiological safety,
.g.
Mechanical and electrical engineering, and
- h. Quality assurance practices.
I
,4 DAVIS-BESS E. UNIT 1 6-8 1621. 072
ADMINISTRATIVE CONTROLS COMPOSITION 6.5.2.2 The Company Muclear Review Board shall be composed of the:
C h ir m Gu u<ISapu.' M cd ,De w Lfseu:n *d M s % cb**\
MMChc . .cca: Vice President. .Fec P 'de:-Bevekpmen t4 w c. lev l Member: Vice President, Energy Supply
":mbar- heref--Super t 4Mende6ar Eq' ee dag j eM.-Gons t rJ. . w, Pember: General Superintendent, Transmission and Substations Member: Superintendent, Davis-Besse Station .
Member: .
.Geper4r.4 ender 4,1 A ercm Sec r4ce> b'Kedoe s Nude *r EpJ
.- Member: Nuclear Project Engineer, Power Engineering T Member: Nuclear Encineer, Power Engineering Director,QualityAssurance Member:
Member:
General Superintendent, Fossil pegggggg A
~~-
Member: Others as deemed advisable by the CNRB Chaint.an*
ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the CNRS Chairman to serve on a temporary basis; however, no more than two alter-nates shall participate as voting members in CNRB activities at any one time.
CONSULTANTS 6.5.2.4 Consultants shall be utili:ed as determined by the CNRS Chairman to provide expert advice to the CNRB.
MEETING FREQUENCY 6.5.2.5 The CNRB shall meet at least once per calendar quarter during the initial : car of unit operation following fuel loading and at least once per 21x months thereafter.
OUORUM 6.5.2.6 A quorum of CNRB shall consist of the Chairman or his designated alternate and at least half of the appointed CNRS members or their alternates. No more/than a minority of the quorum shall have line responsibility for operation of the facility.
"Otners as ceemed advisable by the CNRS chairman, who are appointed to the Company Nuclear Review Boarc shall have an acacemic decree in an Engineering or Physical Science Field; and in addition, shall have a minimum of five years of technical experience,,of which a minimum of three years shall be in one or more of the areas specified in Spedification 6.5.2.1. ,
DAVIS-BESSE, UNIT 1 4
. - - . . _ . _ . . . . . { {)2 ]._ 07 3
1
. ADP.INISTRATIVE CONTROLS AUDITS 6.5.2.8 Audits of facility activities shall be perfomed under the cognizance of the CNRB. These audits shall encompass :
- a. The confomance of unit operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months. -
- b. The performance, training and qualifications of the entire
. station staff at least once per 12 months.
- c. The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months.
- d. The perfomance of activities required by the Quality Assurance program to meet the criteria of Appendix "B",10 CFR 50, at least once per 24 months,
- e. The Station Emergency Plan and implementing procedures at least once per 24 months.
f.
The Station Security Plan and implementing procedures at
, least once per 24 months.
g".
Any other area of facility operation considered appropriate by the CNRB.
~
h.. The Facility Fire Protection Program and implementing procedures at least once per 24 months.
i.
An independent fire protection and loss prevention program inspection and audit shall be perfomed at least once per
'12 months utilizing either qualified offsite licensee per-sonnel or an outside fire protection firm.
j.
An inspection and audit of the fire protection and loss pre-vention program shall be performed by a qualified outside fire consulant at least once per 36 months.
AUTHORITY
' 6.5.2.9 The Company Nuclear Review Board shall report to and advise the 4*ec t . ; 7 ? ; ; ' . . . L.1; , W W :-% on those areas of responsibility I specified in Sections 6.5.2.7 and 6.5.2.8.
- h t$ bQb ce d CC,e h OperaNq O fCOcr DAVI,S-BESSE, UNIT 1 6-11 Amendment No.
/ -
5 1621 074
ADMINISTRATIVE CONTROLS RECORDS 6.5.2.10 Records of Company Nuclear Review Board activities shall be prepared, approved and distributed as indicated below:
- a. Minutes of each CNRS meeting shall be prepared, approved and forwarded to the Ex: = ti : 'l % . T. . d de - t , pera m n + !
. and CNRB members within 14 days following each meeting.
- b. Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the S:=ti .: " "A Asident , OpwcMon#and CNRS members within 14 days following j completion of the review.
- c. Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Exct:ti .: 'li::--Fr:'A & ra , Op" =31c d and CNRS l members and to the management positions responsible for the 2 areas audited within 30 days after completion of the audit.
6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for REPORTABLE OCCURRENCES:
- a. The Comission shall be notified and/or a report submittec pursuant to the requirements of Specification 6.9.
- b. Each REPORTABLE OCCURRENCE requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Cor:raission shall be reviewed by the SRB and submitted
- to the CNRB. .
(Ql ace. uJ i'"A Pre 4 der.h c d Ckie[ oggJ.,*
OWeer
- DAVI5-BESSE, UNIT l 6-12 Amendment No.
. T624-075
o ADMINISTRATIVE CONTROLS 6.7- SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit
. is violated: ..
." a. The facility shall be placed in at least HOT STANDBY within one hour. .
. I
- b. The Safety Limit violation shall be reported to the Commission. (
- the Vice President,J:Wre %./rfandtotheCNRSwithin24.
. #- hours. - f $4r-
- c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the SRB. This report shall describe
- (1) applicable circumstances preceding the violation, (2) effects of. the violation upon facility components, systems or
- structures, and (3) corrective action taken to prevent recurrence.
~
- d. The Safety Limit Commission, theViolation CNRB and Report shallPresident,4~
the Vice be submittedutoL;,$.the-/fvc/ var-within 14 days of the violation.
'( .
6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and main-tained covering the activities referenced below:
The applicable procedures recommended in Appendix "A" of
. ~
a.
Regulatory Guide 1.33, November, 1972.
- b. Refueling operations.
- c. Surveillance and test activities of safety related equipment.
- d. Security Plan implementation.
- e. Emergency Plan implementation. ,
- f. Fire Protection Program i6plementa tion. .
,a 6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed by the SRB and approved by the Station Superintendent prior to implementation and,, reviewed periodically as set forth in administrative
{ procedures. .
~
.; DAVIS-8 ESSE, UNIT 1
~
6-13 fadndmentNo.6 L ,
. J. Q [._ g
. e
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5.0 ADMINISTRATIVE CONTROLS 5.1 Review and Audit i
j Review and audit of environniental matters and complianca.with these Environmental Technical Specifications in particular shall be provided by the Station Revig Bo,ard, the Company Nuclear Review Board, and the g Quality Assurance Manascr- This activity shall be controlled in accordance l with QAP 5000 of the Toledo Edison Nuclear Quality Assurance Manual.
' ".. 5.1.1 Station Review Board A Station Review Board, composeo of technically qualified station personnel has been established to perform timely and continuing reviews of unit Operation. The makeup of the Board, specification of quorum, and meeting frequency are set forth in Section 6.0 of the Unit's Appendix "A" Technical Specifications. The Board's review responsibility will include all new
/ or revised unit environmental procedures, proposed changes or modifications to unit structures or equipment, reported violations of the unit's Environmental Technical Specifications, proposed changes to the unit's
. Environmental Technical Specifications, results of the Environmental Monitoring Programs prior to their submission in each Environmental Operating Report, anu any occurance of a safety limit being exceeded.
5.1.2 Company Nuclear Review Board A Company Nuclear Review Board, composed of technically qualified personnel, has been appointed ';- + i : :Jr -
=-2m L . _ l +..m . At o f perform independent reviews of unit operation. The makeup of the Scard,
. specification of quorum and meeting frequency are set forth in Section 6.0 of the Unit's Appendix "A" Technical Specifications. The Boards independ-ent review responsibility will include all new or revised un'it environ-mental' procedures, proposed changes or modifications to unit structures or equipment, reported violations of the unit's Environmental Technical Specifications, proposed changes to the unit's Environmental Technical Specifications, station operation, and minutes of the Station Review Board meeting.
5.1.3 Quality Assurance % ;ger-CI"eC """
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The Quality Assurance Maneter shall be responsible for verification of compliance with the Environmental Technical Specifications. Planned periodic reviews and audits will be conducted in accordance with the provisions of the quality assurance program for unit operation described in the unit's Final Safety Analysis Report. The Quality Assurance p oecra. {
Yans;cr shall also be responsible for reviewing all nonconfor=ance reports concerning Environmental Technical Specifications including corrective actions taken to prevent any recurrence of the sage nonconformance. ,
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