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| {{#Wiki_filter:ADMINISTRATIVE CONTROLSCOMPOSITION ALTERNATES least'i-ktbeefmodmorc.+htea+ace(yc.T"eSRO>>ellbecomposedofbb~~stcebeym~~bb toUtytUlshallmeetorexceedtherequirements ofANSI3.1-1981, Section4.7.TheChairman, ViceChairmanandallmembersshallbeappointed inwritingbytheSeniorVicePresident-Nuclear. | | {{#Wiki_filter:ADMINISTRATIVE CONTROLS COMPOSITION least'i- kt beef mod morc. +htea +ace(yc. |
| 6.5.2.3Allalternate. | | T"e SRO>>ell be composed of bb~~stcebeym~~bb toUtytU l shall meet or exceed the requirements of ANSI 3.1-1981, Section 4.7. The Chairman, Vice Chairman and all members shall be appointed in writing by the Senior Vice President-Nuclear. |
| membersshallbeappointed inwritingbytheSRCChairmantoserveonatemporary basis;however,nomorethantwoalternates shallparticipate asvotingmembersinSRCactivities atanyonetime.CONSULTANTS 6.5.2.4Consultants shallbeutilizedasdetermined bytheSRCChairmantoprovideexpertadvicetotheSRC.HEETINGFREUENCY6.5.2.5TheSRCshallmeetatleastoncepercalendarquarterduringtheinitialyearofunitoperation following fuelloadingandatleastoncepersixmonthsthereafter.
| | ALTERNATES |
| gUORUN6.5.2.6The+~sum-quorumoftheSRCnecessary fortheperformance oftheSRCreviewandauditfunctions oftheseTechnical Specifications shallconsistofes+gadmorethanaminorityofthequorumshallhavelineresponsibility foropera'onoftheunit.6.5.2.7TheSRCshallreview:a.Thesafetyevaluations for1)changestoprocedures, equipment orsystemsand2)testsorexperiments completed undertheprovision ofSection50.59,10CFR,toverifythatsuchactionsdidaotconstitute anunreviewed safetyquestion.
| | : 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. |
| b.Proposedchangestoprocedures, equipment orsystemswhichinvolve~anunreviewed safetyquestionasdefinedinSection50.59,10CFR.c.Proposedtestsorexperiments whichinvolveanunreviewed safetyquestionasdefinedinSection50.59,10CFR.less'hana.m'ajofety ofaltW~4ersbrdesigh~e~ | | CONSULTANTS |
| +~+~~~iesp ghoul(be.Su.bJec+4o+4cWotloutg~drains-WgcChalrma+, | | : 6. 5. 2.4 Consultants shall be utilized as determined by the SRC Chairman to provide expert advice to the SRC. |
| orhispie<<yetcJarne(e<<aafe shallhe[reseafd'ormt(4oprsa(meek(lseacncetaoSUSQUEHANNA
| | HEETING FRE UENCY |
| -UNIT1850a<4OhO4 8SO2S>6-10~PDRADOCK05OOOS87PPDR a4'(W trJFoLHATOJ o4~g:FfloqPRePosEgQCdnekdig7~g<&CSAA&~<bra@ui~4R.~AOMINISTRATIVE CONTROLSCOMPOSITION gln~6.5.2.2TheSRCshallbecomposedofindividuals who,shall,meetorexceedtherequirements ofANSI3.1-1981,Section4.7.TheChairman, ViceChairmanandallmembersshallbeappointed inwritingbytheSeni.orVicePresident-Nuclear. | | : 6. 5. 2. 5 The SRC shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least once per six months thereafter. |
| | gUORUN 6.5.2.6 The +~sum- quorum of the SRC necessary for the performance of the SRC review and audit functions of these Technical Specifications shall consist of es+g ad more than a minority of the quorum shall have line responsibility for opera 'on of the unit. |
| | 6.5.2.7 The SRC shall review: |
| | : a. The safety evaluations for 1) changes to procedures, equipment or systems and 2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did aot constitute an unreviewed safety question. |
| | : b. Proposed changes to procedures, equipment or systems which involve |
| | ~ |
| | an unreviewed safety question as defined in Section 50.59, 10 CFR. |
| | : c. Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CFR. |
| | less'han a. m'ajofety of a lt W~4ers br desigh~e~ +~+~~~iesp ghoul( be. Su.bJec+ 4o +4c Wotloutg ~drains - Wgc Chalrma+, or his pie<<y etc J arne(e<<aafe shall he [reseaf d'or mt( 4oprsa( meek( ls e acncet a o |
| | - 850a<4OhO4 8SO2S> |
| | SUSQUEHANNA UNIT 1 6-10 ~ |
| | PDR ADOCK 05OOOS87 P PDR |
| | |
| | a4 |
| | '( |
| | W |
| | |
| | trJFoLHATOJ o4~g: Ffloq PRePosEg QCdnekd i g7 |
| | ~g<&CS AA& ~<bra@ ui~ 4 R.~ |
| | AOMINISTRATIVE CONTROLS COMPOSITION gl n~ |
| | 6.5.2.2 The SRC shall be composed of individuals who |
| | , shall, meet or exceed the requirements of ANSI 3. 1-1981, Section 4.7. The Chairman, Vice Chairman and all members shall be appointed in writing by the Seni.or Vice President-Nuclear. |
| ALTERNATES'. | | ALTERNATES'. |
| 5';2.3.Allalternate membersshallbeappointed inwritingbytheSRCChairmantoserveonatemporary basis;however,nomorethantwoalternates shallparticipate asvotingmembersinSRCactivities atanyonetime.CONSULTANTS 6.5.2.4Consultants shallbeutilizedasdetermined bytheSRCChairmantoprovideexpertadvicetotheSRC,MEETINGFREUENCY6.5.2.5TheSRCshallmeetatleastoncepercalendarquarterduringtheinitialyearofunitoperationfollowing fuelloadingandatleastoncepersixmonthsthereafter. | | 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. |
| QUORUM6.5.2.6Theekrrin~Wquorum oftheSRCnecessary fortheperformance oftheSRCreviewandauditfunctions oftheseTechnical Specifications shallconsistoftheChairmanorhisdesignated alternate andatleast~SRCmembers'ncluding alternates.
| | CONSULTANTS |
| Nomorethanaminorityofthequorumshallhaveline.responsibility foroperation oftheunit.REVIEW4~r',gcpcs(oh~i6(c.4I+4.pcvlctdot6.5.2.7TheSRCsha11~~c.a.Thesafetyevaluations for1)changestoprocedures, equipment orsystemsand2).testsorexperiments completed undertheprovision oftoverifythatsuchactionsdidnotconstitute
| | : 6. 5.2.4 Consultants shall be utilized as determined by the SRC Chairman to provide expert advice to the SRC, MEETING FRE UENCY |
| />CFR5o.5g anunreviewed safetyquestion. | | : 6. 5.2.5 The SRC shall meet at least once per calendar quarter during the initial year of unit oper ation following fuel loading and at least once per six months thereafter. |
| b.Proposedchangestoprocedures, equipment orsystemswhichinvolveanunreviewed safetyquestionasdefinedin(oCFg.So.S'9c.Proposedtestsorexperiments whichinvolveanunreviewed safetyquestion'as definedinhlocFeso.sySUSQUEHANNA | | QUORUM 6.5.2.6 The ekrrin~Wquorum 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 ~SRC alternates. No more than a minority of the quorum shall have line members'ncluding |
| -UNIT16-10 | | . responsibility for operation of the unit. |
| ~I0ADMINISTRATIVE CONTROLSCOMPOSITION J'c)ig~g(7f~of'~+QQnQWelY~6.5.2.2TheSRCshallbecomposedof@+acindividuals whoshallmeetorexceedtherequirements ofANSI3.1-1981,Section4.7.TheChairman, ViceChairmanandallmembersshallbeappointed inwritingbytheSeniorVicePresident-Nuclear.'LTERNATES 6.5.2.3Allalternate membersshallbeappointed inwritingbytheSRC-Chairmantoserveonatemporary basis;ho~ever,nomorethantwoalternates shallparticipate asvotingmembersinSRCactivities atanyonetime.CONSULTANTS 6.5.2.4Consultants shallbeutilizedasdetermined bytheSRCChairmantoprovideexpertadvicetotheSRC.MEETINGFREUENCY6.5.2.5TheSRCshallmeetatleastoncepercalendarquarterduringtheinitialyearofunitoperationfollowing fuelloadingandatleastonceper6monthsthereafter. | | REVIEW 4~r ', |
| OUORUM6.5.2.6ThequorumoftheSRCnecessary fortheperformance oitneSRCreviewandauditfunctions oftheseTechnical Specifica~',ons shallcc.".s'.s.
| | gc pcs(oh~i 6(c. 4I +4. pcvlctd ot |
| responsibility foroperaonoftheunit.REYIEW6.5'.7a~TheSRCshallberesponsible forthereviewof:Thesafetyevaluations for(1)changestoprocedures, equipment orsystemsand(2)testsorexperiments completed underthe.provisions of10CFR50.59toverifythatsuchactionsdidnotconstitute anunreviewed safetyquestion. | | : 6. 5. 2. 7 The SRC sha 1 1 ~~c. |
| b.C.Proposedchangestoprocedures, equipment orsystemswhichinvolveanunreviewed safetyquestionasdefinedin10CFR50.59Proposedtestsorexperiments whichinvolvean-unreviewed safetyquestionasdefinedin10CFR50.59..go~leSS44Oh4h1QJbrE'F)oI'-A.((~QMberSOrG(eS<cnaked a(kernafCS IJShat,tlLe,Sub)cO-4'4,+t~oulgCoii'ral4;-theC4El.(r~a orRigdes<)rQeJcl.4ernake'5~a.t~Ile$f'e<c<tfor4(l4(~a.'teecfigs"'othoSUSQUEHANNA | | : a. The safety evaluations for 1) changes to procedures, equipment or systems and 2). tests or experiments completed under the provision of to verify that such actions did not constitute |
| -UNIT26-11 0(~7}} | | />CFR5o.5g an unreviewed safety question. |
| | : b. Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in (o CF g. So.S'9 |
| | : c. Proposed tests or experiments which involve an unreviewed safety question'as defined in h |
| | lo cFe so.sy SUSQUEHANNA - UNIT 1 6-10 |
| | |
| | ~ I 0 |
| | ADMINISTRATIVE CONTROLS COMPOSITION J c ) i g~ g(7f ~o f'~+QQ n QWelY~ |
| | 6.5.2.2 The SRC shall be composed of @+ac individuals who shall meet or exceed the requirements of ANSI 3. 1-1981, Section 4.7. The Chairman, Vice Chairman and all members shall be appointed in writing by the Senior Vice President-Nuclear.'LTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the SRC- Chairman to serve on a temporary basis; ho~ever, 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 as determined by the SRC Chairman to provide expert advice to the SRC. |
| | MEETING FRE UENCY 6.5.2.5 The SRC shall meet at least once per calendar quarter during the initial year of unit oper ation following fuel loading and at least once per 6 months thereafter. |
| | OUORUM 6.5.2.6 The quorum of the SRC necessary for the performance oi tne SRC review and audit functions of these Technical Specifica~',ons shall cc.".s'.s. |
| | responsibility for opera on of the unit. |
| | REYIEW 6.5 '.7 The SRC shall be responsible for the review of: |
| | a~ The safety evaluations for (1) changes to procedures, equipment or systems and (2) tests or experiments completed under the. provisions of 10 CFR 50.59 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 10 CFR 50.59 C. Proposed tests or experiments which involve an-unreviewed safety question as defined in 10 CFR 50.59. |
| | .go~ leSS 44Oh 4 h1QJbr E'F) oI'- A.(( ~QMberS Or G(eS<cnaked a(kernafCS I J Shat,tl Le, Sub)cO- 4'4, +t~oulg Co ii'ral 4; -the C4El.(r~a or Rig des<)r Qe J cl. 4ernake '5 ~a.t~ Ile f'e<c<t for 4( l 4(~a.'t eec f i gs" ' ot ho SUSQUEHANNA - UNIT 2 6-11 |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML18040B2891999-03-12012 March 1999 Proposed Tech Specs Including Rev 0 to EMF-1997(P)(A) Into TS Section 5.6.5 & Including Revised MCPR Safety Limits in TS Section 2.1.1.2 ML18040B2881999-01-12012 January 1999 Proposed Tech Specs Re ANFB-10 Critical Power Correlation & MCPR Safety Limits ML17164A6711998-07-0808 July 1998 Proposed Tech Specs,Implementing Improved Tech Specs of NUREG-1433.Page B3.8-1 of Incoming Submittal Not Included ML17159A3261998-05-12012 May 1998 Proposed Tech Specs Re Removal of Fire Protection Program ML18026A4711997-02-11011 February 1997 Proposed Tech Specs Requesting Improved TSs LCO 3.10.3 & LCO 3.10.4 Be Approved for Use During Susquehanna Ses Unit 2 Eighth Refueling & Insp Outage Scheduled for 970315 ML20129D7851996-09-23023 September 1996 Proposed Tech Specs Re MSIVs Leakage Testing ML20116K3491996-08-0909 August 1996 Proposed Tech Specs Re Battery Load Profiles ML17158B5581996-03-20020 March 1996 Proposed Tech Specs,Changing Open Logic for HPCI Suction Valve HV-155/255-F042 in Order to Eliminate HPCI Pump auto- Transfer on High Suppression Pool Level ML20115A8171996-02-29029 February 1996 Proposed Tech Specs,Relocating Spec 3/4.9.6, Refueling Platform to Document Which Is Controlled Under Requirements of 10CFR50.59 ML20115A8211996-02-29029 February 1996 Proposed Tech Specs,Removing Rod Block Monitor Requirements from TS by Reducing Number of Rod Movements During Power Maneuvers ML17158B1071996-02-12012 February 1996 Proposed Tech Specs to Implement 10CFR50,App J,Option B & Establish New Spec 6.8.5, Primary Containment Leakage Rate Testing Program. ML17164A5801995-02-10010 February 1995 Proposed Tech Specs for Aot/Sti Extensions ML17164A4351994-11-21021 November 1994 Proposed Tech Specs Increasing MSIV Leakage Rate & Deleting MSIV-LCS ML17158A5441994-10-28028 October 1994 Proposed Tech Specs,Incorporating Administrative Changes ML20058F8281993-11-24024 November 1993 Proposed Tech Specs Re Power Uprate W/Increased Flow ML17157C2741993-04-0202 April 1993 Proposed TS 3.4.1.1.2 Re LCO for Recirculation Loops,Single Loop Operation ML20082P1871991-09-0404 September 1991 Proposed Tech Specs for HPCI Sys Low Pressure Surveillance Test Acceptance Criteria ML17157A3371990-09-24024 September 1990 Proposed Tech Specs in Support of Facility Cycle 5 Reload ML17157A2441990-07-0202 July 1990 Proposed Tech Specs to Support Cycle 6 Reload ML19325D7491989-10-19019 October 1989 Proposed Tech Specs 3.2.2 Eliminating Certain Requirements on One Time Basis for 3 Months ML17156B1101989-04-14014 April 1989 Proposed Tech Specs,Making Changes to Emergency Svc Water Sys,Per 10CFR50,App R ML17156A7291988-08-10010 August 1988 Proposed Tech Specs,Extending Operation During Cycle 4 W/ One Recirculation Loop Out of Svc ML18040A8741988-04-0606 April 1988 Proposed Tech Specs Re Radiation Monitoring Instrumentation ML17146B0891987-12-23023 December 1987 Proposed Tech Specs Index & Sections 3/4.2.1,3/4.2.2, 3/4.2.3,3/4.2.4,3/4.3.6,3/4.4.1,B 2.1,B 3/4.2.1,B 3/4.2.2, B 3/4.2.3 & B 3/4.4.1,to Support Cycle 3 Reload ML18040A8421987-06-10010 June 1987 Proposed Tech Specs,Increasing Load Profile for Batteries 1D612 & 1D622 ML18040A8341987-04-16016 April 1987 Proposed Tech Spec 4.1.3.1.4(a) Changing Requirements for Surveillance of Scram Discharge Vol Vent & Drain Valves ML18040A8261987-02-0909 February 1987 Proposed Tech Specs,Allowing Alternate Method of post-accident Drywell Gaseous Sampling & Providing Relief for Unnecessarily Restrictive Action Statement on Drywell Oxygen Analyzer ML20215C1291986-12-0909 December 1986 Proposed Tech Spec Tables 3.6.3-1 & 3.8.4.2-1,supporting Mods to Improve Containment Isolation Function & Testability of Feedwater Sys ML17146A4811986-08-0505 August 1986 Proposed Administrative Changes to Tech Specs ML20206J9471986-06-23023 June 1986 Proposed Tech Specs Changing Main Steam Line Radiation High Setpoint from Three Times Background to Seven Times Background ML17146A4161986-06-19019 June 1986 Proposed Tech Specs Re Cycle 2 Reload.Nshc Encl ML17146A3111986-03-27027 March 1986 Proposed Tech Spec Changes Providing Editorial Correction to Previously Approved Change for Unit 1 & Supporting Mods Which Enhance Capability of Drywell Cooling Sys for Unit 2 ML20141C9281986-03-27027 March 1986 Proposed Tech Specs Re Recirculation Sys W/One & Two Loop Operation,Supporting Operation W/One Recirculation Loop Out of Svc ML17146A2681986-02-10010 February 1986 Proposed Tech Specs,Reflecting Incorporation of Fifth Diesel Generator Into Plant Design ML20137G5781985-11-26026 November 1985 Proposed Tech Specs,Deleting Requirement for Operability of Refueling Floor Wall & High Exhaust Ducts & Railroad Access Exhaust Duct Radiation Monitoring Sys for Conditions 1,2 & 3 ML17156A1261985-04-11011 April 1985 Proposed Tech Spec Changes Re Single Loop Operation Requirement ML18040A7701985-02-11011 February 1985 Proposed Tech Specs Re Util Review Committee Membership ML17139C7431984-12-0606 December 1984 Proposed Tech Specs Separating Unit 1 from Unit 2 Battery Loads to Avoid Forced Shutdown of Unit 2 During Unit 1 Refueling Outage ML18040A7421984-09-24024 September 1984 Proposed Tech Specs,Revising Table 3.3.7.1-1, Radiation Monitoring Instrumentation. ML18040A7411984-09-0707 September 1984 Proposed Tech Specs Re Primary Containment Isolation Valves & Containment Sys Limiting Condition for Operation & Bases ML20078M6531983-10-20020 October 1983 Proposed Changes to Tech Spec Table 4.8.1.1.2-2 Re Settings for Emergency Svc Water Pump Timers ML17139B3301983-02-0303 February 1983 Proposed Tech Specs 2.2.1.1,3.2.2,4.2.2 & 3.3.6-2 Re Reactor Protection Sys Instrumentation,Average Power Range Monitor & Control Rod Block Instrumentation Setpoints ML17139B3311983-02-0303 February 1983 Proposed Tech Specs 3.4.3 & 4.4.3 Re RCS Leakage Detection Sys ML18031A4031982-10-19019 October 1982 Proposed Changes to Tech Spec Table 3.8.4.1-1 to Include More Conservative Type 2 Molded Case Circuit Breakers & to Add Previously Omitted Type 3 Molded Case Circuit Breakers 1999-03-12
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML18040B2891999-03-12012 March 1999 Proposed Tech Specs Including Rev 0 to EMF-1997(P)(A) Into TS Section 5.6.5 & Including Revised MCPR Safety Limits in TS Section 2.1.1.2 ML18040B2881999-01-12012 January 1999 Proposed Tech Specs Re ANFB-10 Critical Power Correlation & MCPR Safety Limits ML17164A6711998-07-0808 July 1998 Proposed Tech Specs,Implementing Improved Tech Specs of NUREG-1433.Page B3.8-1 of Incoming Submittal Not Included ML17159A3261998-05-12012 May 1998 Proposed Tech Specs Re Removal of Fire Protection Program ML20199C8741997-10-22022 October 1997 Rev 0 to NASI-00-507, Corrective Action Process Effectiveness Assessment ML18026A4711997-02-11011 February 1997 Proposed Tech Specs Requesting Improved TSs LCO 3.10.3 & LCO 3.10.4 Be Approved for Use During Susquehanna Ses Unit 2 Eighth Refueling & Insp Outage Scheduled for 970315 ML17158C0321997-01-0808 January 1997 Rev 4, Solid Radwaste Pcp. ML20129D7851996-09-23023 September 1996 Proposed Tech Specs Re MSIVs Leakage Testing ML20116K3491996-08-0909 August 1996 Proposed Tech Specs Re Battery Load Profiles ML17158B5581996-03-20020 March 1996 Proposed Tech Specs,Changing Open Logic for HPCI Suction Valve HV-155/255-F042 in Order to Eliminate HPCI Pump auto- Transfer on High Suppression Pool Level ML20115A8211996-02-29029 February 1996 Proposed Tech Specs,Removing Rod Block Monitor Requirements from TS by Reducing Number of Rod Movements During Power Maneuvers ML20115A8171996-02-29029 February 1996 Proposed Tech Specs,Relocating Spec 3/4.9.6, Refueling Platform to Document Which Is Controlled Under Requirements of 10CFR50.59 ML17158B1071996-02-12012 February 1996 Proposed Tech Specs to Implement 10CFR50,App J,Option B & Establish New Spec 6.8.5, Primary Containment Leakage Rate Testing Program. ML17158A6821995-04-26026 April 1995 Rev 3 to Nuclear Dept Procedure ON-100-009, Control Room Evacuation. ML17158A6841995-04-13013 April 1995 Rev 3 to Nuclear Dept Procedure ON-200-009, Control Room Evacuation. ML20081L9151995-03-14014 March 1995 Rev 1 to NS-ST-002, Security Training & Crucial Security Task Certification ML17164A5801995-02-10010 February 1995 Proposed Tech Specs for Aot/Sti Extensions ML17164A5891995-01-20020 January 1995 Rev 2 to PP&L SSES Odcm. ML17164A4351994-11-21021 November 1994 Proposed Tech Specs Increasing MSIV Leakage Rate & Deleting MSIV-LCS ML17158A5441994-10-28028 October 1994 Proposed Tech Specs,Incorporating Administrative Changes ML20058F8281993-11-24024 November 1993 Proposed Tech Specs Re Power Uprate W/Increased Flow ML17157C3881993-05-31031 May 1993 Rev 8 to ISI-T-100.0, ISI Program Plan for Pump & Valve Operational Testing. ML17157C3901993-05-31031 May 1993 Rev 5 to ISI-T-200.0, ISI Program Plan for Pump & Valve Operational Testing. ML18017A2671993-04-20020 April 1993 Exercise Manual. ML17157C2741993-04-0202 April 1993 Proposed TS 3.4.1.1.2 Re LCO for Recirculation Loops,Single Loop Operation ML18017A2631992-05-0606 May 1992 Emergency Exercise Std for Conduct in Performance of 920219 NRC Graded Exercise ML20113G9881992-02-19019 February 1992 Package Providing Basis for Conduct of Simulated Radiological Accident at Plant ML17157B0101991-12-31031 December 1991 Rev 4 to ISI-T-200.0, Sses,Unit 2,ISI Program Plan for Pump & Valve Operational Testing, Per Generic Ltr 89-04 ML17157B0081991-12-31031 December 1991 Rev 7 to ISI-T-100.0, Sses,Unit 1,ISI Program Plan for Pump & Valve Operational Testing, Per Generic Ltr 89-04 ML18017A2591991-10-16016 October 1991 Exercise Manual, Approved by Util as Std for Conduct in Performance of 911016 NRC Graded Exercise ML20082P1871991-09-0404 September 1991 Proposed Tech Specs for HPCI Sys Low Pressure Surveillance Test Acceptance Criteria ML17157A3381990-09-30030 September 1990 Cycle 5 Reload Summary Rept. ML17157A3371990-09-24024 September 1990 Proposed Tech Specs in Support of Facility Cycle 5 Reload ML17157A2441990-07-0202 July 1990 Proposed Tech Specs to Support Cycle 6 Reload ML17157A0891990-03-19019 March 1990 Rev 0 to Procedure MT-024-024, Diesel Engine Analysis & Load Balancing. ML17157A0871990-03-19019 March 1990 Rev 0 to Procedure TP-024-087, Data Collection for E Diesel Generator Combustion Intake Air Temp Test. ML20127B4271990-01-19019 January 1990 Rev 8 to Procedure MT-GE-008, 480 Volt & Under Circuit Breaker High Current Testing ML19325D7491989-10-19019 October 1989 Proposed Tech Specs 3.2.2 Eliminating Certain Requirements on One Time Basis for 3 Months ML20082C4101989-08-16016 August 1989 Spec Change Notice 7 to Rev 4 to TS F1000, TS for Design & Installation of Electrical Raceway Fire Barriers ML17156B1101989-04-14014 April 1989 Proposed Tech Specs,Making Changes to Emergency Svc Water Sys,Per 10CFR50,App R ML17156B0651989-03-31031 March 1989 Rev 6 to ISI-T-100.0, Pump & Valve Inservice Insp Testing Program. ML17156B0671989-03-31031 March 1989 Rev 3 to ISI-T-200.0, Pump & Valve Inservice Insp Testing Program. ML20082C4071989-03-23023 March 1989 Spec Change Notice 6 to Rev 4 to F1000, TS for Design & Installation of Electrical Raceway Fire Barriers ML17156B1391989-02-22022 February 1989 Rev 12 to EO-100-009, Plant Shutdown from Outside Control Room. ML20082B2771989-01-0404 January 1989 Rev 4 to TS F1000, TS for Design & Installation of Electrical Raceway Fire Barriers ML20082C3731988-11-0707 November 1988 Spec Change Notice 5 to Rev 3 to TS F1000, TS for Design & Installation of Electrical Raceway Fire Barriers ML20082C3711988-11-0101 November 1988 Spec Change Notice 4 to Rev 3 to TS F1000, TS for Design & Installation of Electrical Raceway Fire Barriers ML20082C3641988-10-14014 October 1988 Spec Change Notice 3 to Rev 3 to TS F1000, TS for Design & Installation of Electrical Raceway Fire Barriers ML17156A7291988-08-10010 August 1988 Proposed Tech Specs,Extending Operation During Cycle 4 W/ One Recirculation Loop Out of Svc ML20082B2911988-07-11011 July 1988 Rev 3 to TS F1000, TS for Design & Installation of Electrical Raceway Fire Barriers 1999-03-12
[Table view] |
Text
ADMINISTRATIVE CONTROLS COMPOSITION least'i- kt beef mod morc. +htea +ace(yc.
T"e SRO>>ell be composed of bb~~stcebeym~~bb toUtytU l shall meet or exceed the requirements of ANSI 3.1-1981, Section 4.7. The Chairman, Vice Chairman and all members shall be appointed in writing by the Senior Vice President-Nuclear.
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 as determined by the SRC Chairman to provide expert advice to the SRC.
HEETING FRE UENCY
- 6. 5. 2. 5 The SRC shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least once per six months thereafter.
gUORUN 6.5.2.6 The +~sum- quorum of the SRC necessary for the performance of the SRC review and audit functions of these Technical Specifications shall consist of es+g ad more than a minority of the quorum shall have line responsibility for opera 'on of the unit.
6.5.2.7 The SRC shall review:
- a. The safety evaluations for 1) changes to procedures, equipment or systems and 2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did aot constitute an unreviewed safety question.
- b. Proposed changes to procedures, equipment or systems which involve
~
an unreviewed safety question as defined in Section 50.59, 10 CFR.
- c. Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.
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AOMINISTRATIVE CONTROLS COMPOSITION gl n~
6.5.2.2 The SRC shall be composed of individuals who
, shall, meet or exceed the requirements of ANSI 3. 1-1981, Section 4.7. The Chairman, Vice Chairman and all members shall be appointed in writing by the Seni.or Vice President-Nuclear.
ALTERNATES'.
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 as determined by the SRC Chairman to provide expert advice to the SRC, MEETING FRE UENCY
- 6. 5.2.5 The SRC shall meet at least once per calendar quarter during the initial year of unit oper ation following fuel loading and at least once per six months thereafter.
QUORUM 6.5.2.6 The ekrrin~Wquorum 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 ~SRC alternates. No more than a minority of the quorum shall have line members'ncluding
. responsibility for operation of the unit.
REVIEW 4~r ',
gc pcs(oh~i 6(c. 4I +4. pcvlctd ot
- 6. 5. 2. 7 The SRC sha 1 1 ~~c.
- a. The safety evaluations for 1) changes to procedures, equipment or systems and 2). tests or experiments completed under the provision of to verify that such actions did not constitute
/>CFR5o.5g an unreviewed safety question.
- b. Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in (o CF g. So.S'9
- c. Proposed tests or experiments which involve an unreviewed safety question'as defined in h
lo cFe so.sy SUSQUEHANNA - UNIT 1 6-10
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ADMINISTRATIVE CONTROLS COMPOSITION J c ) i g~ g(7f ~o f'~+QQ n QWelY~
6.5.2.2 The SRC shall be composed of @+ac individuals who shall meet or exceed the requirements of ANSI 3. 1-1981, Section 4.7. The Chairman, Vice Chairman and all members shall be appointed in writing by the Senior Vice President-Nuclear.'LTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the SRC- Chairman to serve on a temporary basis; ho~ever, 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 as determined by the SRC Chairman to provide expert advice to the SRC.
MEETING FRE UENCY 6.5.2.5 The SRC shall meet at least once per calendar quarter during the initial year of unit oper ation following fuel loading and at least once per 6 months thereafter.
OUORUM 6.5.2.6 The quorum of the SRC necessary for the performance oi tne SRC review and audit functions of these Technical Specifica~',ons shall cc.".s'.s.
responsibility for opera on of the unit.
REYIEW 6.5 '.7 The SRC shall be responsible for the review of:
a~ The safety evaluations for (1) changes to procedures, equipment or systems and (2) tests or experiments completed under the. provisions of 10 CFR 50.59 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 10 CFR 50.59 C. Proposed tests or experiments which involve an-unreviewed safety question as defined in 10 CFR 50.59.
.go~ leSS 44Oh 4 h1QJbr E'F) oI'- A.(( ~QMberS Or G(eS<cnaked a(kernafCS I J Shat,tl Le, Sub)cO- 4'4, +t~oulg Co ii'ral 4; -the C4El.(r~a or Rig des<)r Qe J cl. 4ernake '5 ~a.t~ Ile f'e<c<t for 4( l 4(~a.'t eec f i gs" ' ot ho SUSQUEHANNA - UNIT 2 6-11
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