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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20209E0551999-07-0606 July 1999 1999 Business Plan ML20206F2231999-04-27027 April 1999 NRC Manual Chapter 0350 Restart Action Plan for Clinton Power Station ML20199H2771999-01-20020 January 1999 Proposed Tech Specs Changing Table 3.3.8.1-1 to Revise Allowable Values for Degraded Voltage Relay Reset & Dropout Setpoints as Specified Per Items 1.c,1.d,2.c & 2.d ML20206E6281998-12-31031 December 1998 Rev 17 to ODCM for Clinton Power Station ML20196A0941998-11-20020 November 1998 Proposed Tech Specs Re Div 3 Diesel Generator Droop Issue ML20196A1501998-11-20020 November 1998 Revised Pages Constituting Rev 3 to CPS TS Bases,Consisting of Pages Annotated with Rev Numbers 3-1,3-2,3-3,3-4 & 3-5. Changes to Text Identified with Rev Bars.No Rev Bars Included for Changes to Format ML20155A5631998-10-23023 October 1998 Proposed Tech Specs LCO 3.6.1.9, FW LCS (FWLCS) for Implementation of FWLCS Mode of RHR Sys U-603088, Proposed Tech Specs Section 5.5.13,allowing Next Scheduled Performance of LLRT of Primary Containment Penetration for RPV Head Spray Piping (IMC-042) to Be Deferred Until Seventh Refueling Outage (RF-7)1998-10-0505 October 1998 Proposed Tech Specs Section 5.5.13,allowing Next Scheduled Performance of LLRT of Primary Containment Penetration for RPV Head Spray Piping (IMC-042) to Be Deferred Until Seventh Refueling Outage (RF-7) ML20153F4201998-09-23023 September 1998 Corrected Proposed Tech Specs Bases Page B 3.8-94 Re SVC Protection Sys ML20237E4191998-08-24024 August 1998 Proposed Tech Specs SR 3.8.1.17,revising Acceptance Criteria for Meeting ready-to-load Requirement for Division 3 DG ML20237C3501998-08-17017 August 1998 Proposed Tech Specs Partially Reducing Load at Which DGs Are Required to Be Tested Per Affected SRs in Order to Reduce Stress & Wear on Machines While Still Sufficiently Challenging Machines to Confirm Operability ML20236X0071998-07-31031 July 1998 Proposed Tech Specs,Revising Acceptance Criteria of SRs 3.8.1.7,3.8.1.12,3.8.1.15 & 3.8.1.20 ML20236Q4661998-07-17017 July 1998 Rev 0 to Procedure 2800.93, Emergency Reserve Auxiliary Transformer Integrated Test ML20236Q4651998-07-17017 July 1998 Rev 0 to Procedure 2800.92, Emergency Reserve Auxiliary Transformer Integrated Test ML20236Q4571998-07-17017 July 1998 Rev 0 to Procedure 2800.91, Emergency Reserve Auxiliary Transformer Test ML20216B1511998-05-0404 May 1998 Proposed Tech Specs Pages,Incorporating Requirements for Static Var Compensator (SVC) Protection Sys Under New TS ML20217M3351998-04-27027 April 1998 Proposed Tech Specs Re Mgt Changes Occurring in Operations Organization at Plant ML20203D5651998-02-19019 February 1998 Plan for Excellence ML20212C6951997-10-23023 October 1997 Proposed Tech Specs,Constituting Rev 2 to CPS TS Bases.Rev Consists of Pages Annotated W/Rev Numbers 2-1 Through 2-14 ML20149J1701997-07-22022 July 1997 Proposed Tech Specs Requesting Exemption to 10CFR50,App a, General Design Criteria to Allow Operation W/Identified Offsite Circuit Condition ML20149H8991997-06-30030 June 1997 CPS Long Term Improvement Plan U-602714, Proposed Tech Specs Table 3.3.8.1-1 Re Loss of Power Instrumentation1997-04-0101 April 1997 Proposed Tech Specs Table 3.3.8.1-1 Re Loss of Power Instrumentation ML20133F2051997-01-0707 January 1997 Proposed Tech Specs 2.0 Re Safety Limits ML20133A5951996-12-13013 December 1996 Proposed TSs Re Transfer of Minority Ownership ML20134M3181996-11-19019 November 1996 Proposed Tech Specs Revising Table 3.3.8.1-1, Loss of Power Instrumentation, by Dividing Function, Degraded Voltage - 4.16 Kv Basis & Degraded Voltage Dropout - 4.16 Kv Basis, re-numbering Items in Table & Revising Associated Notes ML20128K0711996-10-0404 October 1996 Proposed Tech Specs 3.3.8.1,adding Action Statement & Note Requiring Restoration of Inoperable Degraded Voltage Relays, Rev to Table 3.3.8.1-1 ML20134C1631996-09-20020 September 1996 Proposed Tech Specs,Revising TS 3.3.4.1, End of Cycle Recirculation Pump Trip Instrumentation, to Delete SR 3.3.4.1.6 Which Requires RPT Breaker Interruption Time to Be Determined at Least Once Per 60 Months ML20116N1101996-08-15015 August 1996 Proposed Tech Specs 2.0, Safety Limits, Changing TS to Incorporate Revised SLMCPR as Calculated by GE for CPS Cycle 7 U-602619, Proposed Tech Specs 5.0, Administrative Controls, Deleting Examples Currently Included in Parentheses1996-08-15015 August 1996 Proposed Tech Specs 5.0, Administrative Controls, Deleting Examples Currently Included in Parentheses U-602623, Proposed Tech Specs 3.10.10, Single Control Rod Withdrawal- Refueling1996-08-15015 August 1996 Proposed Tech Specs 3.10.10, Single Control Rod Withdrawal- Refueling ML20137A1101996-08-14014 August 1996 Rev 19 to App V Second 10-Yr Interval Pump & Valve Testing Program Plan ML20137A1021996-07-10010 July 1996 Rev 5 to App IV Second 10-Yr Interval Inservice Exam Plan ML20113E7261996-06-28028 June 1996 Proposed Tech Specs,Allowing Removal of Inclined Fuel Transfer Sys Primary Containment Blind Flange While Primary Containment Required to Be Operable U-602591, Proposed Tech Specs,Allowing Utilization of RWP or Equivalent to Control Entry Into High Radiation Area, Clarifying Example Given in TS of Individuals Qualified in Radiation Protection Procedures1996-06-21021 June 1996 Proposed Tech Specs,Allowing Utilization of RWP or Equivalent to Control Entry Into High Radiation Area, Clarifying Example Given in TS of Individuals Qualified in Radiation Protection Procedures ML20108C9431996-05-0101 May 1996 Proposed Tech Specs,Implementing 10CFR50,App J - Option B ML20107L0011996-04-19019 April 1996 Proposed Tech Specs,Revising Listed TS to Eliminate Core Alterations as Applicable Condition for Which Associated LCO Must Be Met ML20100H8411996-02-22022 February 1996 Proposed Tech Specs,Changing TS 3.3.4.1, End of Cycle Recirculation Pump Trip Instrumentation, to Delete SR 3.3.4.1.6 Which Requires RPT Breaker Interruption Time to Be Determined at Least Once Per 60 Months ML20100H7901996-02-22022 February 1996 Proposed Tech Specs,Deleting SR 3.3.8.1.1 Which Requires Channel Check for Loss of Power Instrumentation & Changing TS Table 3.3.8.1-1 to Change Allowable Value for Degraded Voltage Function from 3762V & 3832V to 3876V ML20100H8171996-02-22022 February 1996 Proposed Tech Specs,Changing TS 3.4.11, RCS P/T Limits, to Incorporate Specific P/T Limits for Bottom Head Region of Rv Separate & Apart from Core Beltline Region of Rv ML20100H7741996-02-22022 February 1996 Proposed Tech Specs,Proposing to Revise TS 3.6.5.1, Drywell, to Allow Drywell Bypass Leakage Tests to Be Performed at Intervals of Up to Ten Yrs Based on Demonstrated Performance of Drywell Barrier ML20095G5141995-12-14014 December 1995 Proposed Tech Specs 3.3.1.1, RPS Instrumentation & TS 3.3.6.1, Primary Containment Dwl Isolation Instrumentation to Eliminate Periodic Response Time Testing of Analog Trip Modules ML20095G6401995-12-14014 December 1995 Proposed Tech Specs Instrumentation Associated W/High Pressure Core Spray Sys,Reactor Core Isolation Cooling Sys & Residual Heat Removal Sys ML20095G4791995-12-14014 December 1995 Proposed Tech Specs 3.4.2, Flow Control Valves Re Proposed Deletion of Average Rate of Movement Verification Requirement ML20117E3001995-11-0606 November 1995 Rev 18 to App V Pump & Valve Testing Program Plan ML20094D2031995-10-27027 October 1995 Proposed Tech Specs,Consiting of Changes to TS 3.1.3 to Include 25% Surveillance Overrun Allowed by LCO 3.0.2 Into Allowances of Surveillance Notes for Control Rod Notch Testing Per SR 3.1.3.2 & SR 3.1.3.3 ML20094D2141995-10-27027 October 1995 Proposed Tech Specs,Consisting of Changes to TS 5.2.2.e to Revise Requirements for Controls on Working Hs of Unit Staff That Perform SR Functions ML20085N0621995-06-23023 June 1995 Proposed Tech Specs Bases,Per TS 5.5.11, TS Bases Control Program ML20085F5961995-06-0909 June 1995 Proposed Tech Specs,Incorporating Description of Exclusion Area Boundary ML20087J5691995-05-17017 May 1995 Rev 17 to App V, Pump & Valve Testing Program Plan of CPS ISI Program Manual ML20085J9701995-02-16016 February 1995 Proposed Tech Specs Reflecting Enforcement Discretion Re TS LCO for Div 2 DC Electrical Power Sources 1999-07-06
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20209E0551999-07-0606 July 1999 1999 Business Plan ML20206F2231999-04-27027 April 1999 NRC Manual Chapter 0350 Restart Action Plan for Clinton Power Station ML20206E6281998-12-31031 December 1998 Rev 17 to ODCM for Clinton Power Station ML20236Q4661998-07-17017 July 1998 Rev 0 to Procedure 2800.93, Emergency Reserve Auxiliary Transformer Integrated Test ML20236Q4651998-07-17017 July 1998 Rev 0 to Procedure 2800.92, Emergency Reserve Auxiliary Transformer Integrated Test ML20236Q4571998-07-17017 July 1998 Rev 0 to Procedure 2800.91, Emergency Reserve Auxiliary Transformer Test ML20203D5651998-02-19019 February 1998 Plan for Excellence ML20149H8991997-06-30030 June 1997 CPS Long Term Improvement Plan ML20137A1101996-08-14014 August 1996 Rev 19 to App V Second 10-Yr Interval Pump & Valve Testing Program Plan ML20137A1021996-07-10010 July 1996 Rev 5 to App IV Second 10-Yr Interval Inservice Exam Plan ML20117E3001995-11-0606 November 1995 Rev 18 to App V Pump & Valve Testing Program Plan ML20087J5691995-05-17017 May 1995 Rev 17 to App V, Pump & Valve Testing Program Plan of CPS ISI Program Manual ML20064K5141993-10-11011 October 1993 Rev 16 to Apps Iii,Iv & V of Clinton Power Station ISI Program Manual ML20249A6601993-04-14014 April 1993 Revised ESA-102, Electrical Engineering Std for Electrical & Physical Characteristics of Class B Electrical Cables ML20126E4581992-11-30030 November 1992 Rev 13 to CPS IST Program,App III ML20096G5031992-04-30030 April 1992 Rev 0 to Clinton Power Station Raw Water Treatment & Enhancement Program ML20058L3371991-07-10010 July 1991 Rev 2 to Procedure Nragp 101-1, Nuclear Review & Audit Group Charter ML20082J1991991-02-28028 February 1991 Rev 7 to Odcm ML20059N2201990-08-31031 August 1990 Rev 8 to, Pump & Valve Testing Program Plan ML20006C2071989-12-31031 December 1989 Rev 6 to Odcm. ML20006A8321989-10-20020 October 1989 Rev 3 to Inservice Exam Plan. ML20236A5281989-02-28028 February 1989 Rev 5 to Odcm ML20151M7611988-07-29029 July 1988 Rev 2 to Inservice Exam Program Plan ML20196J5731988-03-0101 March 1988 Pump & Valve Testing Program Plan U-601006, Rev 3 to Pump & Valve Testing Program Plan & Summary of Changes1987-08-20020 August 1987 Rev 3 to Pump & Valve Testing Program Plan & Summary of Changes ML20234E0931987-06-30030 June 1987 Rev 2 to Pump & Valve Testing Program Plan ML20215M3511987-06-22022 June 1987 Revised Inservice Exam Program Plan for First 10-yr Interval ML20215K5701987-02-23023 February 1987 Rev 0 to Procedure Dcrdr 5.2, Verification of Implemented Human Engineering Discrepancy Corrections ML20212E9701987-02-0606 February 1987 Rev 8 to Station Operating Manual Maint Procedure 8451.02, Testing of Motor-Operated Valves Using Movats MOV Signature Analysis Sys ML20212E9611987-02-0606 February 1987 Rev 10 to Station Operating Manual Maint Procedure 8451.01, Preventive Maint for Motor-Operated Valves ML20213F3631986-10-31031 October 1986 Long-Term Inservice Exam Plan for Class 1,Class 2 & Class 3 Component Supports for Clinton Power Station,Unit 1, First 10-yr Interval Final Plan ML20213F3861986-09-30030 September 1986 Vols I & II to Long-Term Inservice Exam Plan for Class 1, Class 2 & Class 3 Piping & Components for Clinton Power Station,Unit 1, First 10-yr Interval Final Plan ML20213F3761986-09-30030 September 1986 Inservice Exam Program Plan ML20214P1141986-08-15015 August 1986 Rev 7 to Operating Manual Maint Procedure 8451.02, Testing of Motor-Operated Valves Using Movats Motor-Operated Valve Signature Analysis Sys U-600481, Rev 2 to Administrative Procedure 1888.00, Process Control Program1986-03-21021 March 1986 Rev 2 to Administrative Procedure 1888.00, Process Control Program U-600487, Rev 1 to Clinton Power Station Inservice Insp - Pump & Valve Testing Program1986-03-18018 March 1986 Rev 1 to Clinton Power Station Inservice Insp - Pump & Valve Testing Program ML20198S5391986-02-21021 February 1986 Rev 2 to Nuclear Station Engineering Instruction Nsei CS-4, UHS Monitoring. W/860522 Advance Instruction Change 1 ML20138Q0911985-11-30030 November 1985 Rev 1 to Offsite Dose Calculation Manual ML20138Q9831985-11-30030 November 1985 Inservice Insp Pump & Valve Testing Program ML20209H1541985-10-29029 October 1985 Rev 2 to Instruction PI-CP-079, Preparation,Review & Approval of Pump & Valve Operability Packages ML20209H1611985-10-29029 October 1985 Rev 3 to Nuclear Station Engineering Dept Procedure D.22, Engineering Interdisciplinary Review & Impact Assessment for Plant Mode ML20133N0461985-08-0707 August 1985 Rev 3 to Record Verification Program Plan,Clinton Power Station ML20134L8921985-07-31031 July 1985 Program for Compliance W/Tmi Action Plan Item I.G.1, `Training During Low Power Testing.' ML20134P8821985-07-0808 July 1985 Rev 1 to Procedure 1888.00, Process Control Sys. Addl Info Re ATI-VR-001-P-A, Associated Technologies,Inc Vol Reduction & Bitument Solidification Sys, Encl ML20133N7171985-06-28028 June 1985 Revised Emergency Plan Implementing Procedures,Including Rev 1 to AP-01, Organization & Preparation of Controlled Documents & Rev 1 to Document Control ML20128M0021985-06-14014 June 1985 Rev 0 to Procedure SPDS-DST-001, SPDS Dynamic Simulation Test Plan ML20126C5081985-04-30030 April 1985 Offsite Dose Calculation Manual ML20126B6741985-04-20020 April 1985 Emergency Plan Implementing Procedure EC-13, Reactor Core Damage Estimation ML20108B4601985-02-28028 February 1985 Preservice Insp Program ML20116M7781985-02-27027 February 1985 Rev 8 to Radiation Safety Program Augmentation CPS-1, Instructions for Augmenting United States Testing Co Radiation Safety Program at Clinton Power Station 1999-07-06
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I ILLINOIS POWER COMPANY CLINTON POWER STATION CPS No. 0AP1895.02N Revision No. 1 TITLE: ALARA CO WITTEE Scope of Revision:
Rev. 1: Clarified application of economic costs in ALARA cost-benefit reviews, Corrected titles of personnel. Changed membership of ALARA Cor:mittee to include Assistant Power Plant Manager, and NSE representative.
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SIGNATURES
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Department Head / / -
Groun Surervisor -
gbtW2C Assistant Power //
Plant Manager {/ /i s'/' 4 MM]f,Ee Compliance Surerviser .
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Date of Issue , j,,
8204120261 820407 PDR ADOCK 03000461 A PDR
ILLINOIS POWER CCMPANY CLINTCN PCWER STATICN CPS No. 0AP1695.02N Revision No. O i
TITLE: ALARA COMMITTEE Scope of Revision:
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Quality Control .
Suoervisor UE'kLU(M Department Head Accroval
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Submittal ) f ,ML !b'( -
Plant Manager i Accroval -
Date of Issue g gg
c?s No. 0AP1895.02N LIST OF EFFECTI'E PAGES Page No. Rev. No.
i 1 11 1 1 1 .
2 1 3 1 4 1 5 1 6 0 7 0 Anoendix Rev. No.
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1 CPS No. 0APlS95.02N TABLE OF CONTENTS 1.0 Furpose 2.0 Discussion / Definitions 3.0 Responsibility 4.0 Precautions - None 5.0 Prerequisites - None 6.0 Limitations and Actions - None
/.0 Materials and/or Test Equipment - None 8.0 Procedure 8.1 Composition of the ALARA Ccemittee -
8.2 Authority and Responsibilities 8.3 ALARA Co=ittee Meetings 8.4 Comittee Approval and Records 9.0 Acceptance Criteria - None 10.0 Final Conditions - None 11.0 References 12.0 Appendices 13.0 Documents - None i
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Pace No.
Rev. No. 1
c?S No. 0AP1895.02N 1.0 PURPOSE The purpose of this procedure is to establish the ALARA Committee and to provide a charter for the conduct of its activities.
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2.0 DIS CUSSION/ DEFINITIONS -i vi P i ! ;5 T. ! 'l >-
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2.1 Discussion The ALARA Committee is the group designed to ensure the development and implementation of principles that shall ensure that occupational exposures to ionizing radiation and contamination will be "as low as reasonably achievable" ( ALARA) .
2.2 Definitions 2.2.1 ALARA principles - ALARA principles refer to a design or conduct of operation that will allow cperations, maintenance, inspec-tions, and decommissioning of a nuclear facility with the consequent radiation expo-sure to personnel as low as reasonably achievable.
2.2.2 Reasonably achievable - Peasonably achiev-able is judged by considering the state of the technology and the economics of improve-ments in relation to all of the benefits from these improvements.
In assessing the economic portion of potential modifications or programs the following guidelines should be used. tihen l only the health benefits to the zeneral 1
pub'lic or plant radiation workeri need be considered the 10CFR50 value of $1000 (1975 dollars) per man-rem, integrated over the period of exposure, should be used.
When a potential dose reduction affects plant radiation workers because of the added cost of replacement workers, a dollar value of $6000 (1975 dollars) per man-ren i
Pace No. 1 Rev. No. 1
CPS No. 0AP1895.02N i
per year, averaged dose rate reduction, should be used. This figure represents an economic ecuivalent of a dose rate reduction (dose per year) and cannot be integrated 1
over the perio~d of exposure. However, an additional value of $1000 per man-rem.
integrated over the period of exposure, should be added to this calculation to account for the health benefits to the radiation workers.
It should be emphasized that a dollar value, as calculated above, is not sufficient 1
justification alone in deciding on the merits of a given modification. Instead, careful consideration of all factors followed by prudent judgment related to this consid-eration will dictate the final decision.
3.0 RESPONSIBILITY The Power Plant Manager is responsible for ensuring the proper implementation of this procedure. The Supervisor -
RadChem is responsible for review of this procedure. The Supervisor - Radiation Protection (SRP) is responsible for providing technical guidance and assistance to persons 1
involved in compliance with the ALARA program.
4.0 PRECAUTIONS None s,nm--
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5.0 P REREOUISITES 4
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None l
1 6.0 LISETATIONS AND ACTIONS None Page No. 2 Rev. No. 1 i
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9 c?s No. 0AP1895.02N 7.O PATERIALS AND/OR TEST EOUIPMENT None
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8.0 PROCEDURS '- J IIV s v i ~1 f .
8.1 Comoosition of the ALARA Committee 3.1.1 The ALARA Committee shall be composed of the following personnel:
Pcwer Plant Manager Assistant Power Plant Manager Supervisor - RadChem 1 Supervisor - Radiation Protection Member-at-Large Nuclear Station Engineering Representative 8.1.2 The Power Plant Manager shall select the Member-at-Large and selection should 1 n rmally be from the Facility Review Group.
Selection shall be based on the expertise required at the ALARA Committee meeting.
The Member-at-Large and the Nuclear Station Engineeriry representative should be so noted
- in the meeting minutes.
1 8.1.3 The Power Plant Manager or designee shall act as chairperson of the ALARA Committee.
8.1.4 Alternates to the designated member shall be appointed by the designated member with concurrence by the Chairperson. The Alter-nate should be so noted in the meeting I
minutes.
8.1.5 A quorum of the ALARA Ccomittee consists of 1
the Power Plant Manager or designee and any three additional members.
l Pace no. 3 I
Rev. No. 1
c?s No. 0AP1895.02N 8.2 Authority and Responsibilities 8.2.1 In accordance with the directive by the Vice- ,
President of Illinois Powc r Company (letter, L. J. Koch to T. F. Plunsett, Apri' 27, 1978; see Appendix A of this procedure) , the ALARA Committee shall have the authority and responsibilities as delineated in 1l CPS No. 0AP1895. 00N , ALARA PROGRAM.
8.2.2 The ALARA Committee should be awcre of matters relating to ALARA principles at Clinton Power Station.
8.2.3 Each member of the ALARA Committee should be familiar with the documents and informa-tion provided, preparatory to ALARA review or an area.
8.2.4 Each member of the ALARA Committee should ensure that all areas of concern are brought to the attention of the ALARA Committee Chairperson.
8.2.5 Members of the ALARA Committee are respon-sible for attending ALARA Committee meetings, particularly if areas in their expertise are to be discussed.
8.3 ALARA Committee Meetines S.3.1 During design and construction activities, the ALARA Committee shall meet at least twice a year and/or whenever two or more ALARA Committee members request a meeting.
NOTE l Requested meetings may satisfy the recuire-I ment of the two meetings per year.
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8.3.2 During operational activities the ALARA Committee shall meet at least twice a year, within 30 days prier to a refueling and/or major planned maintenance shutdown (greater than 21 days), and whenever two or more ALARA Committee members request a meeting.
8.3.3 Approximately one week prior to a normally scheduled ALARA Committee meeting, the
' 1l Supervisor - Radiation Protection shall sub-1 mit to the committee members the meeting agenda, status of "open " items and a copy of all ALARA Reviews generated since the last meeting.
8.4 Committee Accroval and Records 8.4.1 A majority vote by ALARA Committee members (or alternates) present or polled shall constitute the ALARA Committee position. The chairperson shall sign for the ALARA i
committee.
8.4.2 If all ALARA Committee members are not available, it is the chairperson's pre-rogative to allow voting by poll.
8.4.3 It is the prerogative of the chairperson to table all or any business conducted during the committee meeting to the next regularly scheduled meeting or to a date specified which is prior to the next regularly scheduled meeting.
8.4.4 The ALARA Committee shall provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Director of the Nuclear Review and Audit Group (NRAG) if a disagreement occurs between a majority of the ALARA Committee and the Pcwer Plant 1 Manager; however, the Pcwer Plant Manager shall have the responsiblity for resolution of such disagreements pursuant to CPS Technical Specification 6.5.1.7.
Pace no. 5 Rev. No. 1
cps No. 0AP1895.023 8.4.5 The ALARA Committee shall maintain written minutes of each meeting. These minutes, as a minimum, shall contain:
- a. Date and time of meeting
- b. Persons attending meeting.
- c. Summary of items discussed and reso-lutions reached.
- d. Votes taken by the ALARA Committee.
- e. Open and Action items.
8.4.6 ALARA Committee minutes shall be distributed, as a minimum, to all ALARA Committee members, and the Director of the Nuclear Review and i Audit Group (NRAG) .
8.4.7 The ALARA Committee minutes shall be retained for the duration of the facility operating license.
9.0 ,
ACCEPTANCE CRITERIA None 10.0 FINAL CONDITIONS None
11.0 REFERENCES
11.1 CPS Technical Specification - Section 6 11.2 Regulatory Guide 8. 8 Rev. 3 (June, 1978),
"Information Relevant to Ensuring that Occupationcl Exposure at Nuclear Power Stations Will Be As Ecw As Is Reasonably Achievable".
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gg 3,, OAP1895.02N 2
12.0 APPENDICES i
A. Implenentation of the ALAPA Program for Clinton Power Station, Letter, L.J. Koch to T.F. Plunkett, i April 27, 1978.
13.O DOCUI'ENTS None I
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i N72-PY-73(04-27)-0 CPS No. 0Apl395. 02:I April 27, 1978 T. F. Plunkett, F-33 Implementation of the ALARA Program for Clinton Power Station The U.S. Nuclear Regulatory Commission (NRC) has established requirements that nuclear power plant licensees implement a program to achieve radiation exposure both operationally and to the general public, "as low as reasonably achievable (ALARA)."
The attached document describes Illinois Power Company's plans to ensure that all aspects of our ongoing nuclear plant design and eventual operation be conducted in a manner such that radiation exposure will be as low as reasonably achievable.
You are hereby directed to fully develop and implement the ALARA program at the Clinton Power Station. By copy of this memorandum, I am directing that the Power Production and Genera-tion Engineering Departments participate in the ALARA program as their specific responsibilities so relate.
, /)/
f ,y L J. Koch Att.
cc: W. C. Gerstner J. D. Geier, F-33 T. W. Schroeder, A-05 B. L. Blackburn, A-05 1 .
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