|
---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217F3481999-10-15015 October 1999 Marked-up & Reprinted TS Pages,Changing TS Requirements for Insp of RCP Flywheels ML20212E7851999-09-16016 September 1999 Proposed Tech Specs Pages,Modifying Surveillance Requirements 3.8.4.8,3.8.4.9 & 3.8.4.8 Bases to Allow Testing of DC Channel Batteries with Units on Line ML20216E6601999-09-13013 September 1999 Marked-up & Revised TS Pages,Making Permanent One Time Only Changes Incorporated Into TS 3.7.9 Allowing Up to 24 Hours to Restore Control Room Pressure Boundary to Operable Status When Two Cravs Trains Inoperable ML20211G6711999-08-27027 August 1999 Proposed Tech Specs 3.1.4 Re Rod Group Alignment Limits ML20210R0131999-08-10010 August 1999 Revised Tech Specs Bases Pages B 3.4.14-2 & B 3.4.14-6, RCS PIV Leakage ML20210N3151999-08-0404 August 1999 Proposed Tech Specs Changing TSs 3.3.2, ESFAS Instrumentation, 3.3.3, Post Accident Monitoring Instrumentation, 3.4.14, RCS Loops - Test & 5.3, Unit Staff Qualifications ML20196H7551999-06-24024 June 1999 Proposed Tech Specs 2.0, Safety Limits, TS 3.3.1, Reactor Trip Sys Instrumentation & TS 3.4.1, RCS Pressure,Temp & Flow Departure from Nucleate Boiling (DNB) Limits ML20195F2941999-06-10010 June 1999 Proposed Tech Specs,Facilitating one-time Addition of Condition G & Administrative Controls Note to TS 3.7.9, Cravs ML20206M9391999-05-0606 May 1999 Proposed Tech Specs,Revising List of Referenced Documents in TS 5.6.5b Re COLR Requirements ML20206B0761999-04-0606 April 1999 Proposed Tech Specs Expanding Allowable Values for Interlocks P-6 (Intermediate Range Neutron Flux) & P-10 (Power Range Neutron Flux) in TS 3.3.1,Table 3.3.1-1, Function 16 ML20205L2251999-04-0505 April 1999 Proposed Tech Specs,Providing Revised SFP Storage Configuration,Revised SFP Storage Criteria & Revised Fuel Enrichment & Burnup Requirements ML20205C6901999-03-25025 March 1999 Proposed TS Facilitating Treatment of RTS Instrumentation, ESFAS Instrumentation,Lop DG Start Instrumentation,Cp & Exhaust Isolation Instrumentation & LTOP PORV TS Trip Setpoints as Nominal Values ML20205B6231999-03-23023 March 1999 Proposed Tech Specs Pages Mark Ups for Unit 1,changing Record for FOL NPF-9 Amend Submittal ML20204F6761999-03-18018 March 1999 Marked-up Tech Spec Pages Re License Bases Record Change to License Amend Submittals ML20204E5281999-03-15015 March 1999 Proposed Tech Specs Deleting TS for Cravs & Auxiliary Bldg Filtered Ventilation Exhaust Sys Actuation Instrumentation & Adding Note to TS for Cravs Re Chlorine Protection Function ML20204F6931999-03-11011 March 1999 Proposed Tech Specs 3.3.7 & 3.3.8 Re CR Area Ventilation Sys & Auxiliary Bldg Filtered Ventilation,Exhaust Sys Actuation Instrumentation ML20207C6921999-02-22022 February 1999 Proposed Tech Specs Bases,Reflecting Removal of SI Signal on Low Steamline Pressure on Page B 3.3.2-16 & Adding Clarification for Increasing Hydrogen Recombiner Power During Testing on Page B 3.6.7-4 ML20203A3331999-01-28028 January 1999 Proposed Tech Specs Modifying Flowrate Specified for SR 3.7.13.4 from Value Representative of One Filter Unit/Fan to Value Representative of Entire Fhves Train ML20198B9671998-12-0909 December 1998 Revised TS 3.7.11 LCO Bases to Specify That AB Filtered Ventilation Exhaust Sys Is Considered Operable When Associated Two Fans,Filters,Ductwork,Valves & Dampers Are Operable ML20197G8991998-12-0707 December 1998 Proposed ITS 3.8.3,modifying Inventory Requirements for DG Lube Oil Sys ML20195D6481998-11-11011 November 1998 Proposed Tech Specs,Modifying Details of SRs 3.6.11.6 & 3.6.11.7 to Be Consistent with Design of Containment Pressure Control Sys at Plant ML20155B2111998-10-22022 October 1998 Proposed Revs to Improved Tech Specs,Implementing W Fuel as Described in TRs DPC-NE-2009 & DPC-NE-2009P ML20151Y2461998-09-15015 September 1998 Proposed Improved Tss,Resolving Items Identified by Util During Review ML20151Y1821998-09-15015 September 1998 Proposed Improved TSs Providing Changes Necessary to Resolve Items Identified by Util During Review ML20151U3521998-09-0808 September 1998 Proposed Tech Specs & Bases Converting to Improved Tech Specs ML20151T9491998-09-0808 September 1998 Proposed Tech Specs & Bases Re Relocation from Current TS & Scheduling of New More Restrictive Surveillance Requirements ML20237B6241998-08-14014 August 1998 Proposed Tech Specs 4.6.5.1.b.2 & 4.6.5.1b.3 Relating to Ice Condenser Ice Bed Changing Portion of Surveillances Pertaining to Lower Inlet Plenum Support Structures & Turning Vanes from 9-month Frequency to 18-month Frequency ML20237B5751998-08-12012 August 1998 Proposed Tech Specs 4.6.5.1b.2 Re Ice Condenser Sys Components W/Respect to Accumulation of Frost or Ice ML20237B5721998-08-12012 August 1998 Proposed Tech Specs 4.6.5.1b.3 Re Ice Condenser Sys Components W/Respect to Accumulation of Frost or Ice ML20237A6571998-08-0606 August 1998 TS Page 3/4 8-9 Re Notice of Enforcement Discretion Request from Enforcing TS Surveillance Requirement 4.8.1.1.2i.2 ML20237A9341998-08-0606 August 1998 Proposed Tech Specs,Deleting SR 4.8.1.1.2i.2 for Pressure Test of DG Fuel Oil Sys ML20237A0411998-08-0505 August 1998 Suppl 8 to Improved TS Noting Differences Between Two Units. Proposed Changes Require That Specs & Surveillances Apply to Each Unit Individually,Unless Otherwise Noted,Consistent W/Version of Current TS Prior to Amends 166 & 148 ML20237A0361998-08-0505 August 1998 Suppl 8 to Improved TS (Its),Combining Units ITS Pages to Facilitate Ease of Use & Significantly Reduce Vol of Paper That Must Be Processed & Controlled ML20236U1531998-07-22022 July 1998 Proposed Revised Improved Tech Specs,Implementing W Fuel as Described in TRs DPC-NE-2009P & DPC-NE-2009 ML20236G5301998-06-29029 June 1998 Rev to Bases of TS 3/4.6/3,correcting Editorial Errors ML20249B3961998-06-15015 June 1998 Proposed Tech Specs Affecting Requirements for low-temp Overpressure Protection ML20248B5741998-05-22022 May 1998 Proposed Tech Specs Modifying SR 4.4.3.3 for Pressurizer Heaters to Be Consistent W/Plant Design & W/Ts Requirement as Delineated in Improved Tech Specs ML20247E3891998-05-0808 May 1998 Proposed Tech Specs,Revising Power Range Neutron Flux High Trip Setpoints in Event of Inoperable MSSVs & Deleting References to 3-loop Operation in Current TS Section 3.7.1.1(b) & Table 3.7-2 ML20217E6531998-04-20020 April 1998 Proposed Improved Tech Specs Re Section 1.0,2.0,3.0 & 4.0 ML20217E9521998-04-20020 April 1998 Proposed Tech Specs Revising Requirements for Automatic Actuation Logic & Actuation Relays Associated W/Cravs Operation Function,Which Is Part of ESFAS ML20217E9831998-04-20020 April 1998 Proposed Improved Tech Specs Sections 1.0,2.0,3.0 & 4.0 ML20216B9721998-04-0808 April 1998 Proposed Tech Specs 3/4.6.5 Re Ice Condenser Reduction of Required Ice Weight ML20217C7121998-03-20020 March 1998 Proposed Improved TS Section 3.6 Re Containment Sys ML20217B7871998-03-20020 March 1998 Marked-up Proposed Improved TS 3.6 & 5.5.2 ML20216B7691998-03-0909 March 1998 Proposed Tech Specs Pages Responding to 980116 RAI Re Improved TS Sections 3.1 & 3.2.Suppl Changes to Improved TS Also Included ML20217N9311998-03-0303 March 1998 Proposed Tech Specs 5.5 Re Meteorological Tower Location ML20217Q3741998-03-0303 March 1998 Proposed Tech Specs Re Catawba Safety Review Group ML20216B9851998-03-0202 March 1998 Proposed Tech Specs Responding to 980116 RAI Re Improved TS Sections 3.1 & 3.2.Suppl Changes to Improved TS Encl ML20197G4391997-12-17017 December 1997 Proposed Tech Specs Referencing Updated or Recently Approved Methodologies Used to Calculate cycle-specific Limits Contained in COLR ML20198H5361997-12-17017 December 1997 Tech Spec Pages for TS 3/4.7.8 for Use in Lieu of ASME Section XI Requirements 1999-09-16
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217F3481999-10-15015 October 1999 Marked-up & Reprinted TS Pages,Changing TS Requirements for Insp of RCP Flywheels ML20217J6401999-10-0606 October 1999 Revised Pages to McGuire Nuclear Station Selected Licensee Commitments Manual ML20212E7851999-09-16016 September 1999 Proposed Tech Specs Pages,Modifying Surveillance Requirements 3.8.4.8,3.8.4.9 & 3.8.4.8 Bases to Allow Testing of DC Channel Batteries with Units on Line ML20216E6601999-09-13013 September 1999 Marked-up & Revised TS Pages,Making Permanent One Time Only Changes Incorporated Into TS 3.7.9 Allowing Up to 24 Hours to Restore Control Room Pressure Boundary to Operable Status When Two Cravs Trains Inoperable ML20211G6711999-08-27027 August 1999 Proposed Tech Specs 3.1.4 Re Rod Group Alignment Limits ML20211A9881999-08-18018 August 1999 Rev 5 to DPC Nuclear Security Training & Qualification Plan ML20210R0131999-08-10010 August 1999 Revised Tech Specs Bases Pages B 3.4.14-2 & B 3.4.14-6, RCS PIV Leakage ML20210N3151999-08-0404 August 1999 Proposed Tech Specs Changing TSs 3.3.2, ESFAS Instrumentation, 3.3.3, Post Accident Monitoring Instrumentation, 3.4.14, RCS Loops - Test & 5.3, Unit Staff Qualifications ML20210N9641999-07-26026 July 1999 Revised Catawba Nuclear Station Selected Licensee Commitments Manual ML20211C3731999-07-26026 July 1999 Revs to Catawba Nuclear Station Selected Licensee Commitments Manual & List of Effective Pages ML20196H7551999-06-24024 June 1999 Proposed Tech Specs 2.0, Safety Limits, TS 3.3.1, Reactor Trip Sys Instrumentation & TS 3.4.1, RCS Pressure,Temp & Flow Departure from Nucleate Boiling (DNB) Limits ML20210A5911999-06-10010 June 1999 Revised Catawba Nuclear Station Selected Licensee Commitments Manual ML20216D4061999-06-10010 June 1999 Revised Catawba Nuclear Station Selected Licensee Commitment Manual, List of Effective Pages ML20195F2941999-06-10010 June 1999 Proposed Tech Specs,Facilitating one-time Addition of Condition G & Administrative Controls Note to TS 3.7.9, Cravs ML20212A2701999-05-28028 May 1999 Rev 25 to McGuire Nuclear Station,Units 1 & 2 Pump & Valves Inservice Testing Program ML20211C3751999-05-19019 May 1999 5 to Catawba Nuclear Station Units 1 & 2 Pump & Valve Inservice Testing Program. Page 1 of 15 in Section 4.1 of Incoming Submittal Not Included ML20195B4181999-05-18018 May 1999 Revised Pages to Catawba Nuclear Station Selected Licensee Commitments Manual ML20206M9391999-05-0606 May 1999 Proposed Tech Specs,Revising List of Referenced Documents in TS 5.6.5b Re COLR Requirements ML20206T0571999-05-0505 May 1999 Revised Catawba Nuclear Station Selected Licensee Commitments Manual. with List of Effective Pages ML20206Q9311999-05-0404 May 1999 Rev 29 to List of Effective Pages for Chapter 16 & Page 16.11-66 to McGuire Selected Licensee Commitment Manual. with ML20206S9401999-04-30030 April 1999 Rev 29 to McGuire Nuclear Station Selected Licensee Commitments. with List of Effective Pages ML20206K3621999-04-30030 April 1999 Revised McGuire Nuclear Station Selected Licensee Commitments (SLC) Manual ML20206J4531999-04-22022 April 1999 Revs to Catawba Nuclear Station Selected Licensee Commitments Manual ML20206Q8741999-04-22022 April 1999 Revs to CNS Selected Licensee Commitments Manual,Including Page 5 of List of Effective Pages & Pages 1-11 to Chapter 16.9-13.With ML20206B1271999-04-15015 April 1999 CNS Selected Licensee Commitments Manual, List of Effective Pages ML20206C0391999-04-15015 April 1999 Revs to Catawba Nuclear Station Selected Licensee Commitments Manual ML20206B0761999-04-0606 April 1999 Proposed Tech Specs Expanding Allowable Values for Interlocks P-6 (Intermediate Range Neutron Flux) & P-10 (Power Range Neutron Flux) in TS 3.3.1,Table 3.3.1-1, Function 16 ML20205L2251999-04-0505 April 1999 Proposed Tech Specs,Providing Revised SFP Storage Configuration,Revised SFP Storage Criteria & Revised Fuel Enrichment & Burnup Requirements ML20205L2431999-04-0505 April 1999 SFP Soluble Boron Credit Dilution Analysis (Summary of Applicable Portions) ML20205L2531999-04-0505 April 1999 Boraflex Degradation Analysis ML20205C6901999-03-25025 March 1999 Proposed TS Facilitating Treatment of RTS Instrumentation, ESFAS Instrumentation,Lop DG Start Instrumentation,Cp & Exhaust Isolation Instrumentation & LTOP PORV TS Trip Setpoints as Nominal Values ML20205B6231999-03-23023 March 1999 Proposed Tech Specs Pages Mark Ups for Unit 1,changing Record for FOL NPF-9 Amend Submittal ML20204F6761999-03-18018 March 1999 Marked-up Tech Spec Pages Re License Bases Record Change to License Amend Submittals ML20204G2541999-03-16016 March 1999 Revised Pages to Catawba Nuclear Station Licensee Commitments Manual ML20204E5281999-03-15015 March 1999 Proposed Tech Specs Deleting TS for Cravs & Auxiliary Bldg Filtered Ventilation Exhaust Sys Actuation Instrumentation & Adding Note to TS for Cravs Re Chlorine Protection Function ML20204F6931999-03-11011 March 1999 Proposed Tech Specs 3.3.7 & 3.3.8 Re CR Area Ventilation Sys & Auxiliary Bldg Filtered Ventilation,Exhaust Sys Actuation Instrumentation ML20205B1341999-03-11011 March 1999 Revs to Catawba Nuclear Station Selected Licensee Commitments Manual ML20204E7271999-03-0808 March 1999 Chapter 16.5-2,page 1-3 to CNS Selected Licensee Commitments Manual. with List of Effective Pages ML20207C6921999-02-22022 February 1999 Proposed Tech Specs Bases,Reflecting Removal of SI Signal on Low Steamline Pressure on Page B 3.3.2-16 & Adding Clarification for Increasing Hydrogen Recombiner Power During Testing on Page B 3.6.7-4 ML20203A3331999-01-28028 January 1999 Proposed Tech Specs Modifying Flowrate Specified for SR 3.7.13.4 from Value Representative of One Filter Unit/Fan to Value Representative of Entire Fhves Train ML20199H4061999-01-16016 January 1999 Revised CNS Selected Licensee Commitments Manual ML20198A4691998-12-0909 December 1998 Rev 14 to DPC McGuire Nuclear Station Process Control Program ML20198B9671998-12-0909 December 1998 Revised TS 3.7.11 LCO Bases to Specify That AB Filtered Ventilation Exhaust Sys Is Considered Operable When Associated Two Fans,Filters,Ductwork,Valves & Dampers Are Operable ML20197G8991998-12-0707 December 1998 Proposed ITS 3.8.3,modifying Inventory Requirements for DG Lube Oil Sys ML20196G6891998-11-23023 November 1998 Rev 26 to Selected Licensee Commitments (SLC) Manual ML20196C9211998-11-14014 November 1998 Rev 26 to Selected Licensee Commitments Manual. with Update Instructions ML20195D6481998-11-11011 November 1998 Proposed Tech Specs,Modifying Details of SRs 3.6.11.6 & 3.6.11.7 to Be Consistent with Design of Containment Pressure Control Sys at Plant ML20155B2111998-10-22022 October 1998 Proposed Revs to Improved Tech Specs,Implementing W Fuel as Described in TRs DPC-NE-2009 & DPC-NE-2009P ML20154L7191998-10-0505 October 1998 Rev 8 to DPC Nuclear Security & Contingency Plan, for Oconee,Mcguire & Catawba Nuclear Stations ML20151Y1821998-09-15015 September 1998 Proposed Improved TSs Providing Changes Necessary to Resolve Items Identified by Util During Review 1999-09-16
[Table view] |
Text
- - - _ _ _ - - - - - - _ - _ _ _ _
3
\ '.,
l I
DUKE POWER COMPANY i McGUIRE NUCLEAR STATION ATTACHMENT NO. 1A PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS i
I
~
SG12070027 PDR 8S11?8ADOCK FDC 05000369 P
l ADMINISTRATIVE CONTROLS Ma6 wig 6.2.3 ST 9 ^"-SAFETY REVIEW GROUP FUNCTION -
WGo'M M yres.L 7" p . 2. 3.1 The * * " ' a=
6 4 fety Review Group (KSRG) shall function to ex: ', :
rima + aperating che-actecietics , "C i cusaces ,n i dertry adef: rin, '.f:en:=
4, :nd Oth:r : urcee '84 8 my indicate areas for i.coroving-p4*r, y g.cl @ [<nury E..nt. W e n :
COMPOSITION M
6.2.3.2 The ASRG shall be composed of at least five dedicated, full-time i S,, r,ss,c t e m m 4 - e r , ime,+.a an.4t._
. I RESPONSIBILITIES 2.3.3 ThehSRG shall be responsible fortesi"'i 'ng :urvei'!:nc: Of ;1:nt
- " " *'4 6aeM*iti e: t: ;r:;id: '.d:p:nd:nt v:r d 'icatica* **et +*=ss ecti"4+4es e*e
'c ' _p.ernre.a enee.rtty end that w e 3- er-e 3.. educed 3 ue w :: p r::tica h
,Mt AUTHORITf M es 4f ed p-ecedu es ,
g # g 6.2.3.4 The D,
-owia ent e/SRG shall aa4-deh444-m:
_i 'i s444+#'er-e 9:ndations-r O th r 9 In: Of 'm?r0V'9; f e-t the
? l ant Saf0ty
'. W h / Oire:t:r, Scla:r Sen ty ":^eine S;;rd.
RECORDS, 3 ,, L ,I6.2.3.5 Re;ords of activities performed by-t'e SS3-4ha!' b: pr:;: red,
-aiate'e d md ' m sded ee-- ci!cnd r cath te t*e 04escro.c Muc! ear $3f4sy s 6, y re yfr 9e rd.
Yr.jyP4 6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor shall serve in an acvisory capacity to i the Shift Supervisor.
6.3 UNIT STAFF CUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifica-tions of ANSI N18.1-1971 for ccmparable positions and the supplemental require ~
ments specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, except for the Padiation Protection Hanager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1575.
6.4 TRAINING 6.4.1 A retrair.ing and replacement training program for the unit staff shall be maintained under the direction of the Station Manager and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix A of IV CFR Part 55 and the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, and shall include familiari:ation with relevant industry operational experience identified oy the SSRG.
' Not responsible for sign-ofi f unction.
McGUIRE - UNITS 1 and 0 6-7
1 9 4
A. Insert Under Function
- the review of plant design and operating experience for potential
- opportunities to improve plant safety; evalua'aon of plant operations and maintenance activities; and, to advise management on the overall quality
, and safety of plant operations. The MSRG shall make recommendations for
] revised procedures, equipment modifications, or other means of improving plant safety to appropriate station / corporate management.
i B. Insert Under Composition at least five dedicated, full-time engineering / technical personnel, located on-site. MSRG engineering / technical personnel shall have at i
least six years of technical experience with a minimum of two of these six years being nuclear station related experience. A maximum of four years of the six years may be fulfilled by academic or related technical training.
C. Insert Under Responsibilities
- a. Review of selected plant operating characteristics and other i appropriate sources of plant design and operating experience
! i' formation for awareness and incorporation into the 4 performance of other duties.
1 j b. Review of the effectiveness of corrective actt:,ns taken as a result 4 of the evaluation of selected plant operating characteristics and
- other appropriate sources of plant design and operating experience
- information.
! c. Review of selected programs, procedures, and plant activities, including maintenance, modification, operatie # .n e M e :, and 3
operational analysis.
j d. Surveillance of selected plant operations and maintenance l
activities to provide independent verification
- that they are performed correctly and that human errors are reduced to as low as j practicable.
1 4
- e. Investigation of selected unusual events and other occurrences as assigned by Station Management or the Maneger of Nuclear Safety Assurance, j
O. AUTHORITY f
- 6.2.3.4 The MSRG shall report to and advise the Manager of Nuclear Safety Assurance, on those areas of responsibility specified in Seccion 6.2.3.
E. Records i
l 6.2.3.5 Records of activities performed by the MSRG shall be prepared i and maintained for the life of the station. Summary reports of j activities performed by the MSRG shall be forwarded each calendar month i to the Manager of Nuclear Safety Assurence.
J 4
- - , - ern nn ,,-,-c.~.,,- w,---- -vn-m-o--~~,m---ww- _
e 6
I DUKE POWER COMPANY CATAWBA NUCLEAR STATION ATTACHMENT NO. 1B PROPOSED CHANGES TO TECHNICAL $PECIFICATIONS ,
k l
f l
I P
I
'1 l J
l i
I i
ACHINISTRATIVE CONTROLS 6.2.3 CATAWBA SAFETY REVIEW GROUP, <
FUNCTION revsla.'.
The Catawba Safety Review Group (CSRG) shall function to ( : t4e-33 y 4 ,.i" 6.2.3.1 p':-* 'w444ag-45:r::ter t: tic:, 'oC i r s u nc^e , 'adestry ad"'sw4*.
'A' g Qj 9EPCP""LE E'!E"TE, :nd :th:r ::;r :: ; H e m:y 'ndt::t: :re:: f:r bpr: wing p unt eefetj. The 00"O shell make d;teihd r;;;rmnd ti:n; f:r r;vf::d pu-cedu- : :';uf; :nt ::dif h:ti:n:,-cr :th:r e::n: :f ' pr: A ; p hnt ::fety u + u n < ,- . ,
uges e3 g3fety ow .u m 3-e.
4 COMPOSITION "m:n and at M::t f:e d:dk t;d, 6.2.3.2 The CSRG shall be composed of L .nu , +
, g, fe"-t - aus!"Ed i divide:h 4 n !eceted :n:ite_
-0 (h+ k , RESPONSIBILITIES 6.2.3.3 The CSRG shall be responsible forl-ad ats'a'c; sumi!'! z: ef ;unt
. ... ....<~,.... -
g,7, . , w u. .. . ~<a. us.... ... ~..ur...u.....
,46%, n u--e cy4ciiiine iEi- iL :;i~ifi' diiejil iGiaiih.
~
< re,a .rmid -- RECORDS A tter T f :! -
M+'
- p .U.ucY' 6.2.3.W
_tziaed, and Records of::kactivities fe m::d:d :::P nd:r monthperformed
- th: Otr :::r, by +"" CSSC Pe!' b^
'.';;her
- fety
'E' g 9M hu "^ 2M.
MS 6.2.4 SHIFT TECHNICAL ADVISOR j 6.2.4.1 The Shift Technical Advisor shall serve in an advisory capacity to the Shift Supervisor.
I y
63 UNIT STAFF QUAltFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifi-l cations of ANSI N18.1-1971 for comparable positions, except for the Radiation l Protection Manager, who shall meet or exceed the qualifications of Regulatory l j
! Cuide 1.8, Septt.mber 1975. The licensed Operators and Senior Operators shall also meet or exceed the minimum qualifications of the supplemental require-ments specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC 4
letter to all licensee 4.**
6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall j be maintained under the direction of the Station Manager and shall meet or t
exceed the requirements and recommendatiens of Section 5.5 of ANSI N18.1 1971 l and Appendix A of 10 CFR Part 55 and the s'applemental requirements specified j in Sections A and C of Enclosure 1 of the March 29, 1980 NRC letter to all licensees, and shall include fas.iliari:ation with relevan* industry operational l
axperience identified by the LSRG.
t "Not responsible for sign-off function, i
- Except that the experience and other censiderati:ns described in Ouke Power 5, Company's letters dated August 28, 1985, and July 8. 1986, are acceptable for $l the six and two applicants for SRO licenses ider.tified therein, respectively. l-0-6 Mencunr. No, Munit 1)
CATAWBA - UNITS 1 & 2 /vnd ent N:. X(Unit 2)
I A. Insert Under Functicn 4
the review of plant design and operating experience for potential opportunities to improve plant safety; evaluation of plant operations and maintenance activities; and, to advise management on the overall quality and safety of plant operations. The CSRG shall make recommendations for i revised procedures, equipment modifications, or other means of improving
- plant safety to appropriate station / corporate management.
B. Insert Under Composition at least five dedicated, full-time engineering / technical personnel, located on-site. CSRG engineering / technical personnel shall have at least six years of technical experience with a minimum of two of these six years being nuclear station related experience. A maximum of four i i years of the six years may be fulfilled by academic or related technical !
i training.
3 C. Insert Under Responsibilities i
a
- a. Review of selected plant operating characteristics and other !
l appropriate sources of plant design and operating experience a information for awareness and incorporation into the performance of other duties.
- b. Review of the effectiveness of corrective actions taken as a result [
i of the evaluation of selected plant operating characteristics and
! other appropriate sources of plant design and opersting experience ,
information. l
- c. Review of selected programs, procedures, and plant activities, s
including maintenance, modification, operational problems, and f
operational analysis. 6
- d. Surveillance of selected plant operations and maintenance !
j activities to provide independent verification
- that they are performed correctly and that human errors are reduced to as low as ;
practicable. ;
i I
- e. Investigation of selected unusual events and other occurrences as ;
j assigned by Station Management or the Manager of Nuclear Safety l j Assurance.
l l D. AUTHORITY
' i l 6.2.3.4 The CSRG shall report to and advise the Manager of Nuclear Safety Assurance, on those areas of responsibility specified in Section I
6.2.3. f l E. Records i
- 6.2.3.5 Records of activities performed by the CSRG shall be prepared !
I and maintained for the life o' the station. Summary reports of j
! activities performed by the CSRG shall be forwarded each calendar month to the Manager of Nuclear Safety Assurance.
i
-