Proposed Tech Specs Change for Tech Specs 6.0-6.8 Re Reorganization in Generation & Const Dept,Plant Organization & Safety Review Committee MembersML19320A298 |
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Arkansas Nuclear |
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Issue date: |
01/20/1978 |
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From: |
ARKANSAS POWER & LIGHT CO. |
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To: |
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Shared Package |
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ML19320A291 |
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References |
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NUDOCS 8004210578 |
Download: ML19320A298 (10) |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20216G0881999-09-19019 September 1999 Proposed Tech Specs Pages,Changing TS 4.18.5.a.9 & Associated Bases for One Cycle of Operation Through End of Cycle 16 for Suppl Use of OTSG Repair Roll Technology ML20216G0721999-09-17017 September 1999 Proposed Tech Specs,Revising Once Through SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Volumetric Integranular Attack ML20212F5851999-09-17017 September 1999 Proposed Tech Specs Pages,Changing TS by Revising Curie Limits for Radioactive Gas Storage Tanks ML20211P0061999-09-0707 September 1999 Proposed TS in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria ML20211B3291999-08-19019 August 1999 Proposed TS 4.18.3.a.4 Clarification Supporting Tube End Cracking Alternative Repair Criteria ML20211C1701999-08-18018 August 1999 Proposed Tech Specs Revising ESAS Low RCS Pressure Setpoint to Ensure That TS Adequately Bounds Safety Analysis ML20211C4101999-08-18018 August 1999 Proposed Tech Specs Removing Requiremets for Tube Repair (Sleeving) & Clarifying Requirements for Preservice & ISI of Tubes to Facilitate Replacement of Original SGs ML20210K5121999-07-29029 July 1999 Proposed Tech Specs,Revising Requirements Associated with Plant Station Batteries & DC Sources to 125 Vdc Switchyard Distribution Sys ML20210K3571999-07-29029 July 1999 Proposed Tech Specs Revising SRs Pertaining to ISI Requirements for SG Tube Circumferential Cracking at top-of-tubesheet During 2P99 Planned mid-cycle Outage ML20209H5811999-07-14014 July 1999 Proposed Tech Specs Revising RB Structural Integrity Requirements Re ISI Reporting for Containment Structures, Tendons & Anchorages ML20209H8701999-07-14014 July 1999 Proposed Tech Specs 6.2.2 & 6.2.2.h,replacing Functional Description of Operations Staff Middle Manager with Ref to Functional Description Assistant Operations Manager & Revising TS Table 6.2-1 Item 5 & TS 6.2.2.f ML20209H9721999-07-14014 July 1999 Proposed Tech Specs Changes for Elimination of Programmatic Requirements Associated with PASS & Regulatory Relief from PASS Requirements of NUREG-0737 & RG 1.97 ML20195D2371999-06-0101 June 1999 Proposed Tech Specs Re Surveillance Requirements & Applicable Bases Relevant to ISI Requirements for Portions of once-through SG (OTSG) Tubes Adjacent to Primary Cladding Region of tube-to Tubesheet Roll ML20206T2651999-05-14014 May 1999 Proposed Tech Specs Revising SG Tubing SRs ML20206Q1281999-05-10010 May 1999 Proposed Tech Specs Bases,Page B 2-2,discussing Guidance to Be Used When Applying Later Editions & Addendas of ASME Code to RCS Components ML20205P4081999-04-0909 April 1999 Proposed Tech Specs Changes,Revising Reactor Bldg Structural Integrity Requirements ML20205P6291999-04-0909 April 1999 Proposed Tech Specs Changes,Revising Battery Requirements ML20205P3731999-04-0909 April 1999 Revised Proposed TS Page 5-1 Re Design Features Conversion ML20205P6931999-04-0909 April 1999 Proposed Tech Specs Change,Adding Specification 3.0.6 & Associated Bases to ANO-2 ML20207C0631999-02-25025 February 1999 Proposed Tech Specs Change Revising Action 2 Associated with Table 3.3-1, Reactor Protective Instrumentation. Change Adds Footnote to Action 2 Allowing Startup with Functional Units Associated with Channel D Excore Inoperable ML20207M7561999-02-24024 February 1999 Proposed Tech Specs,Allowing Startup & Continued Operation of Plant with Channel D Detector Until New Detector Is Installed During mid-cycle Outage Scheduled for Nov 1999 ML20198K1341998-12-17017 December 1998 Corrected Tech Specs Pages to 980629 Application for Amend to License NPF-6 ML20198A3661998-12-0808 December 1998 Proposed Tech Specs B3/4 6-3 & B3/4 6-4,deleting All Requirements Associated with Sodium H Addition Sys & Adding New Requirements for Trisodium Phosphate to Be Stored in Containers Located on Floor of Cb ML20196B4381998-11-24024 November 1998 Proposed Tech Specs Pages,Changing Administrative Controls Section to Implement Consolidated QA Plan Manual & Clarifying Responsibilities on STA Position on Shift ML20153D8491998-09-17017 September 1998 Proposed Tech Specs 2.2.1,3.3.1.1 & 3.3.2.1 Re Operating Bypass Setpoint ML20236Y5081998-08-0606 August 1998 Proposed Tech Specs Section 3.3.4.B Re Sodium Hydroxide Tank Limits ML20236Y5251998-08-0606 August 1998 Proposed Tech Specs Section 3.1.3.2,revising Action Requirements for CEA Position Indicator Channels ML20236Y5951998-08-0606 August 1998 Proposed Tech Specs,Revising Requirements Associated W/Units 1 & 2 Control Room Emergency Ventilation Sys ML20236Q2781998-07-13013 July 1998 Proposed Tech Specs Re Safety Limits & Limiting Safety Settings ML20236G6921998-06-29029 June 1998 Proposed Tech Specs,Revising TS 3.4.2 & TS 3.4.12 Re Reactor Coolant Sys Safety Valves & Low Temp Overpressure Protection ML20236G5421998-06-29029 June 1998 Proposed Tech Specs,Revising Surveillance Testing Requirements for Unit 2 Direct Current Electrical Distribution Sys ML20236G4911998-06-29029 June 1998 Proposed Tech Specs Re MSSVs & Pressurizer Safety Valves ML20236G5631998-06-29029 June 1998 Proposed Tech Specs,Revising Table 3.3-4 to Provide Range of Acceptable Values for 4160 Volt Bus Loss of Voltage Values ML20217M2621998-04-30030 April 1998 Proposed Tech Specs Re DG Load Rejection Testing ML20217N6141998-04-30030 April 1998 Proposed Tech Specs 1.6.1,revising Definition of Quadrant Power Tilt ML20217M4871998-04-28028 April 1998 Proposed Tech Specs Changing Order of Channel Rotation During Outage for Scheduling Flexibility,While Still Requiring Rotation Schedule to Be Established for Operating Cycle ML20217P8141998-04-0101 April 1998 Proposed Tech Specs Re Upper Tubesheet Volumetric Indications to Remain in Svc for Cycle 15 ML20216J7841998-03-17017 March 1998 Proposed Tech Specs Bases Change Concerning Plant Protection Sys Matrix Logic Testing ML20203D1061998-02-18018 February 1998 Proposed Tech Specs Revising Surveillance Testing Requirements for Emergency Feedwater Sys ML20202G9771998-02-0909 February 1998 Proposed Tech Specs Pages,Allowing Use of Repair Roll Technology (Reroll) for Upper Tubesheet Region of SGs ML20197A8421997-12-12012 December 1997 Proposed Tech Specs Re Establishment of Alternate Repair Criteria for Outer Diameter Intergranular Attack in Upper Tubesheet of Unit 1 SGs ML20211C6441997-09-23023 September 1997 Proposed Tech Specs,Modifying RPS & ESFAS Trip Setpoint & Allowable Values for SG Low Pressure ML20211C8911997-09-23023 September 1997 Proposed Tech Specs Reducing Min Required Reactor Coolant Sys Flow Rate Requirements Until ANO-2 SGs Are Replaced ML20151J3371997-07-28028 July 1997 Proposed Tech Specs,Modifying Actions Associated W/Ts Table 3.3-1 for Reactor Protective Instrumentation & Table 3.3-3 for Esfa Sys Instrumentation ML20149K0551997-07-21021 July 1997 Proposed Tech Specs,Revising Surveillance Testing Requirements for Facility EFW Sys as Specified in Specification 4.7.1.2 ML20141C5641997-06-18018 June 1997 Proposed Tech Specs Changes Restoring Table 2 to Table II & Revision to One of Offsite Dose Calculation Manual, Pages Previously Submitted.Also Includes Amended Pages Modified to Amends Issued Since Change Request Submitted ML20141A8001997-05-0808 May 1997 Proposed Tech Specs 3/4.3.1 & 3/4.3.2 Requesting Removal of Reference to CE NPSD-576 ML20138H8521997-05-0202 May 1997 Proposed Tech Specs,Submitting Rev to Original TS Change Request to Reduce Limit Specified in Section 3.1.6.3.b for Leakage Through SG Tubes of Any One Sg,Per SG Tube Insp Surveillance Requirements ML20138D6411997-04-24024 April 1997 Proposed Tech Specs Revising Requirements for Sample Scope Initial Size & Expansion for Inservice Insp of Steam Generator Tube Sleeves ML20141H2621997-04-18018 April 1997 Proposed Tech Specs,Permitting Delay of Scheduled three-yr Inspections of Flywheels on All Four RCPs Until Completion of 2R13 Refueling Outage,Scheduled for Winter of 1998-99 1999-09-07
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217N3171999-10-19019 October 1999 Rev 1,change 024-01-0 to OP-1903.011, Emergency Response Notifications ML20217J7641999-10-0505 October 1999 Rev 1 to Unit 1 Technical Requirement Manual, Replacing Index Page ML20216G0881999-09-19019 September 1999 Proposed Tech Specs Pages,Changing TS 4.18.5.a.9 & Associated Bases for One Cycle of Operation Through End of Cycle 16 for Suppl Use of OTSG Repair Roll Technology ML20212F5851999-09-17017 September 1999 Proposed Tech Specs Pages,Changing TS by Revising Curie Limits for Radioactive Gas Storage Tanks ML20216G0721999-09-17017 September 1999 Proposed Tech Specs,Revising Once Through SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Volumetric Integranular Attack ML20211P0061999-09-0707 September 1999 Proposed TS in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria ML20211B3291999-08-19019 August 1999 Proposed TS 4.18.3.a.4 Clarification Supporting Tube End Cracking Alternative Repair Criteria ML20211C4101999-08-18018 August 1999 Proposed Tech Specs Removing Requiremets for Tube Repair (Sleeving) & Clarifying Requirements for Preservice & ISI of Tubes to Facilitate Replacement of Original SGs ML20211C1701999-08-18018 August 1999 Proposed Tech Specs Revising ESAS Low RCS Pressure Setpoint to Ensure That TS Adequately Bounds Safety Analysis ML20210N5541999-08-0404 August 1999 Rev 28,Permanent Change 4 to OP-1903.061, Communication Equipment Test ML20210N5571999-08-0404 August 1999 Rev 23,Permanent Change 5 to OP-1903.011, Emergency Response/Notifications ML20210K5121999-07-29029 July 1999 Proposed Tech Specs,Revising Requirements Associated with Plant Station Batteries & DC Sources to 125 Vdc Switchyard Distribution Sys ML20210K3571999-07-29029 July 1999 Proposed Tech Specs Revising SRs Pertaining to ISI Requirements for SG Tube Circumferential Cracking at top-of-tubesheet During 2P99 Planned mid-cycle Outage ML20209H5811999-07-14014 July 1999 Proposed Tech Specs Revising RB Structural Integrity Requirements Re ISI Reporting for Containment Structures, Tendons & Anchorages ML20209H8701999-07-14014 July 1999 Proposed Tech Specs 6.2.2 & 6.2.2.h,replacing Functional Description of Operations Staff Middle Manager with Ref to Functional Description Assistant Operations Manager & Revising TS Table 6.2-1 Item 5 & TS 6.2.2.f ML20209H9721999-07-14014 July 1999 Proposed Tech Specs Changes for Elimination of Programmatic Requirements Associated with PASS & Regulatory Relief from PASS Requirements of NUREG-0737 & RG 1.97 ML20195D2371999-06-0101 June 1999 Proposed Tech Specs Re Surveillance Requirements & Applicable Bases Relevant to ISI Requirements for Portions of once-through SG (OTSG) Tubes Adjacent to Primary Cladding Region of tube-to Tubesheet Roll ML20206T2651999-05-14014 May 1999 Proposed Tech Specs Revising SG Tubing SRs ML20206Q1281999-05-10010 May 1999 Proposed Tech Specs Bases,Page B 2-2,discussing Guidance to Be Used When Applying Later Editions & Addendas of ASME Code to RCS Components ML20206J8021999-05-0404 May 1999 PC-03 to Procedure/Work Plan 1904-002, Offsite Dose Projections Rdacs Computer Method ML20205P6931999-04-0909 April 1999 Proposed Tech Specs Change,Adding Specification 3.0.6 & Associated Bases to ANO-2 ML20205P3731999-04-0909 April 1999 Revised Proposed TS Page 5-1 Re Design Features Conversion ML20205P6431999-04-0909 April 1999 Revised Proposed Technical Requirement Manual Pages ML20205P4081999-04-0909 April 1999 Proposed Tech Specs Changes,Revising Reactor Bldg Structural Integrity Requirements ML20205P6291999-04-0909 April 1999 Proposed Tech Specs Changes,Revising Battery Requirements ML20207C0631999-02-25025 February 1999 Proposed Tech Specs Change Revising Action 2 Associated with Table 3.3-1, Reactor Protective Instrumentation. Change Adds Footnote to Action 2 Allowing Startup with Functional Units Associated with Channel D Excore Inoperable ML20207M7561999-02-24024 February 1999 Proposed Tech Specs,Allowing Startup & Continued Operation of Plant with Channel D Detector Until New Detector Is Installed During mid-cycle Outage Scheduled for Nov 1999 ML20198K1341998-12-17017 December 1998 Corrected Tech Specs Pages to 980629 Application for Amend to License NPF-6 ML20198A3661998-12-0808 December 1998 Proposed Tech Specs B3/4 6-3 & B3/4 6-4,deleting All Requirements Associated with Sodium H Addition Sys & Adding New Requirements for Trisodium Phosphate to Be Stored in Containers Located on Floor of Cb ML20196B4381998-11-24024 November 1998 Proposed Tech Specs Pages,Changing Administrative Controls Section to Implement Consolidated QA Plan Manual & Clarifying Responsibilities on STA Position on Shift ML20196C9761998-11-24024 November 1998 Rev 1 to Unit 2 Technical Requirements Manual ML20154D6681998-10-0101 October 1998 Rev 28 to Procedure/Work Plan 1904.002, Offsite Dose Projections Rdacs Computer Method ML20153D8491998-09-17017 September 1998 Proposed Tech Specs 2.2.1,3.3.1.1 & 3.3.2.1 Re Operating Bypass Setpoint ML20153H1651998-08-12012 August 1998 Rev 0 to ANO Units 1 & 2 Technical Requirements Manual ML20236Y5251998-08-0606 August 1998 Proposed Tech Specs Section 3.1.3.2,revising Action Requirements for CEA Position Indicator Channels ML20236Y5081998-08-0606 August 1998 Proposed Tech Specs Section 3.3.4.B Re Sodium Hydroxide Tank Limits ML20236Y5951998-08-0606 August 1998 Proposed Tech Specs,Revising Requirements Associated W/Units 1 & 2 Control Room Emergency Ventilation Sys ML20236Q2781998-07-13013 July 1998 Proposed Tech Specs Re Safety Limits & Limiting Safety Settings ML20236G6921998-06-29029 June 1998 Proposed Tech Specs,Revising TS 3.4.2 & TS 3.4.12 Re Reactor Coolant Sys Safety Valves & Low Temp Overpressure Protection ML20236G5421998-06-29029 June 1998 Proposed Tech Specs,Revising Surveillance Testing Requirements for Unit 2 Direct Current Electrical Distribution Sys ML20236G5631998-06-29029 June 1998 Proposed Tech Specs,Revising Table 3.3-4 to Provide Range of Acceptable Values for 4160 Volt Bus Loss of Voltage Values ML20236G4911998-06-29029 June 1998 Proposed Tech Specs Re MSSVs & Pressurizer Safety Valves ML20199F7211998-05-22022 May 1998 Rev 8 to Simulator Mod Control,Training Desk Guide 6.3 ML20217N6141998-04-30030 April 1998 Proposed Tech Specs 1.6.1,revising Definition of Quadrant Power Tilt ML20217M2621998-04-30030 April 1998 Proposed Tech Specs Re DG Load Rejection Testing ML20217M4871998-04-28028 April 1998 Proposed Tech Specs Changing Order of Channel Rotation During Outage for Scheduling Flexibility,While Still Requiring Rotation Schedule to Be Established for Operating Cycle ML20217P8141998-04-0101 April 1998 Proposed Tech Specs Re Upper Tubesheet Volumetric Indications to Remain in Svc for Cycle 15 ML20216J7841998-03-17017 March 1998 Proposed Tech Specs Bases Change Concerning Plant Protection Sys Matrix Logic Testing ML20203D1061998-02-18018 February 1998 Proposed Tech Specs Revising Surveillance Testing Requirements for Emergency Feedwater Sys ML20202G9771998-02-0909 February 1998 Proposed Tech Specs Pages,Allowing Use of Repair Roll Technology (Reroll) for Upper Tubesheet Region of SGs 1999-09-07
[Table view] |
Text
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6.0- ADMINISTRATIVE CONTROLS 6.i RESPONSIBILITY .
6.1.1 The Plant Manager shall be responsible for overall facility operation. in his absence, the Assistant Plant Manager of Power Plant shall assume all responsiisility and perform all dutics of the Plant Manager- If both the Plant Manager and his assistant are, absent, these respon-sibilities and duties are assu:aed by the Operations Superintendent
-followed by the Technical Support Engineer.
6.2 ORCANIZATION OFFSITE 6.2.1 The of fsite organi:ation for facility management and technical support shall be as shown on Figure 6.2-1.
FACILITY STAFF 6.2.2 The Facility organi:ation shall be as shown on Figurc 6.2-2A and 6.2-2B and each on dut y shift shall be composed of at least the minimum shift crew composition shown in Tabic 6.2-1.
6.3 FACIL1'IY STAFF QUALIFICATIONS L.a 6.3.1 Each member of the facility staff shall meet or exceed the minimum .
qualifications of ANSI NIS.1-1971 for comparabic position, except
' for the llcalth Physics Supervtsor who shall meet or exceed the qualifications of Regulatory Guide 1.3, September 1975.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained
~
and shall meet or exceed the requirements ,
and recommendat tons of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFis Part 55.
6.5 REVIEW AND AUDIT 6.5.1 Plant Safety Corr.ittee (PSC) Function 6.5.1.1 The. Plant Safet y Co:ait tee shall functicn to advise the Plant -
Manager on all matters related to nuclear safety.
COMPOSITION 6.5.1.2 The Plant Safety Co.c.tttee shall be composed of the:
O Amendment No.16 -
117 ggo4210 7 %
EXECUTIVE DIRECTOR GENERATION 6 CONSTRUCTION SAFETY ._
REVIEW C0kt!I1 TEE v
~
}
DIRECTOR DIRECTOR DIRECTOR DIRECTOR DIRECTOR DIRECTOR GENERATION GENERATION GENERATION PROJECTS TECilNICAL 4 AD5!INISTRATIVE TECllNOLOGY OPERATIONS ENGINEEhlNG ?!ANAGEPIENT ENVIRONBIENTAI. SERVICES 6 PROJECT SERVICES SUPPORT U
,e PLANT PLANT SAFETY -
FIANAGER C0bS!ITTEE T
.. . -... It ArsT CE M t' 'ER 5
E 9 * '. ' NUC E AR O
l'L/.N T MM4AGLR ADMIN.
SEE FIGURE 6.2-2B SE CURI T Y ACM. BLOC. RECORDS
( CCt. JANITOR A 0) SUPVR.
m OPF RAT!ON TR AININ G PRODUCTION E NG!NEERS SOLOGIST SUPT. SUPVR, STORE -
LSO KEEPER ASST. T R AINING OPER. COOac.
SUPTi LSC l These positions are for infornation UNITI UNIT 2
- only and should be treated as such SHIFT SHIF T for this Technical Specification. .
SUPVR. SUPVR.
_LSO LSO UNIT I UNII 2*
PL AN T PLAN T OPER. OPER.
LO LO ASdi. ASST.
LO LO M.S T E WASTE
CONT OPEAATOR h J'l e
- t. v '9 E R A;lA Gi E.i -- --
-120-i AFtK ANSAS POWER . S LIGH T Co. FI G U!1 E
~
AkK ANSAS NUCLE AR ONE - UNIT l 6. 2 - 2 A
'O O .
~
2 l
ASS:STAN T PLANT MANAGER
SEE FIGURE
~6.2-2A
_C - Dsgree or Equivalent Required CE - Engineering Degree or Equivalent Required ,
M^
SU
!.50 - Sanior Operator License Required LO - Operator License Required l
. );- D2sirable but not Required ELEC. PLANT MECH. l M AIN T. SERVICE M A.'N T.
i SUPVR SUPVR SUPVR tNS T Raf.'E NTS tt CON T R "'L S ASST ASST
' (CE)SUPvs i ELECT YECH ,
- - .- J M AIN T. MAINT SUPvRS SUPVRS l _L AsSr IaC '
SUPVRS i
i 1 I l l
TECH OVALITY PLANNING NUCLEAR SUPPORT CONTROL 8 SCHEO. ENGINEER ENGINEER ENGR. COORD (CE) (CE)
HEALTH' RADt0 CHEM rFRrORM CUALITY ASST PL AN. REACTOR COMPUTEA PHYSICS --CHEM 6 ENVid ENGR- CC'd TROL 8 SCHED ENGR $ ENGR.
SUPVR' SUPVR. SUPVR SUPVR INSPECTS COOROS
_]._ (CE )
ASST HEALTH bA
PHYS 3CS O (,OVouTER
- SUPVRS c #
ow - -'
ENGRS
-121-A% KANSAS POWER S LIGHT CO.
FUP4CTIONAL OhGANIZ ATION FOR PLANT OPE R ATIO N FIGURE A! KANSAS NUCLE AR JONE- UNIT I ' _
G.2 - 2 9
- ~
9 9 '4~s -,
7 Chairman: Assistant Plant Manager
' t Member: Technical Support En,:incer b Member: Instrumentation 6 Controls Supervisor
. Member: Operations Superintendent a Member: Maintenance Superintendent Member: Nuclear Engineer Member: !!calth Physics Supervisor The Plant Manager shall appoint an acting chair-
. man in the absence of the Assistant Plant Manager ALTERNATES 6.5.l.3 All alternate mecers shall be appointed in writing by the PSC Chaiman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in PSC activities at any one time.
MEETING FREQUENCY 6.5.1.4 The PSC shall meet at Icast once per calendar month and as con-vened by the PSC Chai=an or. his designated alternate.
~
QUORUM -
6.5.1.5 A quorum of the PSC shall consist of the chairman and three members including alternates.
h RESPONSIBILITIES 6.5.1.6 The Plant Safety Cccatttee shall be responsible for:
- a. Review of 1) all procedures required by Specification 6.8 and revisions thereto, 2) any other proposed procedures or revisions thereto as detet ained by the Plant Manager to affect nuclear safety. l
^
- b. Review of all preposed tests and experiments that affect -
nuclear safety.
-c. Review of all proposed changes to the Appendix "A" Tech-nical Specifications.
- d. Revice of all propared changes or modifications to plant systems or equipment that af fect nuclear safety.
e, .
Investigation of all violations of the Technical Specificatio,s including the preparation and forwarding of reports covering l evaluation and recommendations to prevent recurrence to the l
- Plant Manager. l 1
- f. Review of those Reportable Occurrences requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
n0tif!Catton of the Conntsston.
Amendment No. 16 - 122 -
es % e
, .c ,,
g.- Revi~cw of' facility operations to detect potential nucicar safety ha:ards.
- h. Perfomance of .special reviews and investigations and reports thercon as requested by the Plant Stanager l
- i. Review of the Plant Security Plan and impicmenting procedures and shall submit recomended changes to the Plant blanager l
- j. Review of the Emer,;cacy Plan and impicmenting procedures and shall submit recomended changes to the Plant'llanager Alm!ORITY 6.5.1.7.1 The Plant Safety Committee shall:
- a. Recommend to the Plant ?!anager. 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 cach item considered under 6.5.1.b(a) through (c) above constitutes an unreviewed safety question.
- 6. 5.1. 7. 2 In the event of a disagreement between the recommendations of
(# the Plant Safety Comittee and the actions contemplated by the Plant stanager , the course detemined by the Plant Flana--
ger to be more conservative will be followed. Records of l .
the disagreement will be sent for review to the Dirdctor, Generation Operations, or 5 tanager, Nuelcar Operations and the Chairman of the Safety Review Committee by the Plant Planager on the next working day.
RECORDS ,
6.5.1.8 The Plant safety Comittee shall maintain written minutes of each '
meeting and copics shall be provided to the Chaiman of the Safety Rcview Comittee by the Plant Flanager l
6.5.2 Safety Review Cc=ittee (SRC) l FUNCTION l 6.5.2.1 The Safety Review Committee shall function to provide independent review and audit of designated activities in the areas of:
- a. nucicar power plant operations
- b. nuclear engineering b y c. . chemistry and radiochemistry Amend.T.ent No. 16 123 -
i e -
L ta
r-g
,.m l' i REVIEW 6.5.2.7 The SRC shall review:
- a. The safety evaluations for 1) changes to procedures, equip-ment or systems and 2) tests or experinents completed under the provision of Section 50.39, 10 CFR, to verify that such actions did not ecnstitute an unreviewed safety question.
- b. Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as .lefined 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.
- d. Proposed changes in Technical Specifications or licenses.
- c. Violations of applicable statutes, codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.
- f. Significant operating abnormalitics or deviations from notr.a1 and expected perfomance of plar.t equipment that affect nucitar safety.
- g. Reportable occurrences requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission.
U
- h. Reports and meeting minutes of the PSC. -
AUDITS
~
6.5.2.8 Audits of facility activities shall be perfomed under the cogni:ance of the SRC. These audits shall encompass: i
, a. The conformance of facility operation to provisions contained within the Technical Specifications and applicabic - ,
f license conditions at Icast once per year,
- b. The perfomance and retraining of all members of the plant l management and operations staff, and the perfomance, training, and qualificat. ions of ne.< members of the entire plant staff at least once per year.
- c. The results of all actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation tnat affect nuclear safety at least once per six months.
- d. The Facility Energency Plan and implementing procedures at Icast I once per two years.
v om- m -
l Amendment No. Ic - 125 - ow w . :2 1
I-
. ,. . -s s
- d. metallurgy
- . c. instrumentation and control
- f. radiological' safety *
- g. . mechanical and cicctrical engineering
- h. environmental considerations i, other appropriate ficid:, required by the. unique characteristics of the nuclear pcwcr plant COMPOSITION 6.5.2.2 The SRC shall be composed of the:
Chaiman: . Direction, Generation Operations Member: Director, Generation Technology Member: Director, Technical 6 Environmental Services Member: Manager of Safety Member: Arkansa -
Member:
Manager,s Nuclear One technical . Plant Manager Analysis Member: Arkansas Nuclear One Nucicar lingineer Member: Director, Generation Engineering Member: Radiation and ifcalth Physics Censultant Member: Nuclear Safety Consultant ,
f V
In his absence, the Chaiman shall appoint an Acting Chairman. ~
ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the SRC Chaiman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in SRC 1 activities at any one time. I 1
CONSULTANTS 6.5.2.4 Consultants shall be utili:cd as determined by the SRC Chaiman !
to provide expert advice to the SRC. '
l b'EETING FREQUENCY 0
99 0 F gg D3NA Mb c i
6 I 6.5.2.5 The SRC shall meet at least once per ca'lendar quarter during the iaitial year of factlity operation following fuel loading and at least once per six months thereaf ter.
-QUORUM 6.5.2.6 A quorum of SRC thall consist of the Chaiman or his designated i alternate and four .cmbers including alternates. No more than l G a minority of the queram shall have line responsibility for l
I cperation of the factlity, k.endment No. 16 - 124 -
f
t\
- >[ c. Th; Facility Security Plan and impicmenting procedurcs at W least once per two years.
h f. Any other arca of facility operation considered appropriate by the SRC or the Executive Director Generation 6 Construction j
(EDG6C).
AUTHORITY 6'.S.2.9 The SRC shall report to and advise the Executive Director, Generation 5 Construction (EDGSC) within~ 30 days following each meeting. ~
RECORDS 6.5.2.10 Records of SRC _ activities shall be prepared, approved and dis-
, tributed as indicated below:
- a. Minutes of each SRC meeting shall be prepared, approved and forwarded to the Executive' Director, Gene ration G Construction (EDGGC)within 30 days'following ea'ch meeting.
- b. Reports of reviews encompassed by Section 6.S.2.7 e, f, g and h above, shall be prepared, approved and forwarded to ,
the Executive Director, Generation & Construction (EDGSC)
Githin 30 days followi.sg ' completion of the review.
- c. Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Etecutivo Director, Generation 6 Construction l (EDGr,C) and to the management tvositions respon'sible for the areas audited within 30 days aftpr completion of the. audit. .
6.6 REPORTABl.E OCCURRENCE ACTION 6.6.1 The following actions shall be taken for Reportable Occurrences: ,
- a. The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.12.
- b. Each Reportabic 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. Commission shall be reviewed by the PSC and submitted to the '
SRC and the Manager,. Nuclear Operations by the Plant Manager 6.7 SAFETY LIMIT VIOL \ TION J 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 shutdown within one hour,
- b. The Nucicar Regulatory Ccr.ission shall be notified and a report subnit ted pursuant to the requirements of 10 CFR 50.36 y and-Specificatten o.12.3.1
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6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:
- a. The applicable procedures recommended in Appendix "A" of 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.
6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed by the PSC and approved by the Plant blanager prior to implementation and reviewe 2 periodically as set forth in administrative procedures.
6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided: .
b' a. The intent of the original procedure is not altered.
- b. The change is approved by two members of the plant staff, at least one of wnom holds a Senior Reactor Operator's i, License on the unit affected.
- c. Tne e.hange is documented, reviewed by the PSC and approved l by the Plant >Ianager within 14 days of l implemensation.
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