Rev 3 to Administrative Procedure NG-IS-00002, General Nuclear Security Requirements. Pages 7,9,10 & 15 OnlyML20217C366 |
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Site: |
Davis Besse ![Cleveland Electric icon.png](/w/images/7/78/Cleveland_Electric_icon.png) |
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Issue date: |
07/08/1991 |
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From: |
CENTERIOR ENERGY |
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To: |
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Shared Package |
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ML20217C290 |
List: |
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References |
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NG-IS-00002, NG-IS-2, NUDOCS 9107150244 |
Download: ML20217C366 (5) |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20216E6111999-09-0707 September 1999 Proposed Tech Specs 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation & Associated Bases ML20210H0731999-07-28028 July 1999 Proposed Tech Specs 3/4.7.5.1, Ultimate Heat Sink, Allowing Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F ML20210G4311999-07-27027 July 1999 Proposed Tech Specs,Changing TSs 6.4, Training, 6.5.2.8, Audits, 6.10, Record Retention, 6.14, Process Control Program & 6.15, Odcm ML20210G4801999-07-26026 July 1999 Proposed Tech Specs 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation & Associated Bases ML20210G9161999-07-26026 July 1999 Proposed Tech Specs 3/4.3.3.1, Radiation Monitoring Instrumentation, 3/4.3.3.2, Instrumentation - Incore Detectors & 3/4.3.3.9, Instrumentation - Waste Gas Sys Oxygen Monitor ML20210G5391999-07-26026 July 1999 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B for Type B & C Containment Leakage Rate Testing ML20195F9351999-06-10010 June 1999 Proposed Tech Specs,Revising TS 3/4.6.4.4, Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.6.5.1, Crevs ML20207E7941999-05-21021 May 1999 Proposed Tech Specs Allowing Use of Expanded Spent Fuel Storage Capability ML20205E5031999-03-19019 March 1999 Proposed Tech Specs Withdrawing Proposed New Action B, Previously Submitted in 981027 Application ML20204F1821999-03-0909 March 1999 Proposed Tech Specs,Adopting Changes in Frequency & Scope of Volumetric & Surface Exams Justified by W TR WCAP-14535A ML20155E4971998-10-28028 October 1998 Proposed Tech Specs 4.0.2 Re Applicability of 25% Surveillance Interval Extension Allowance ML20197G5521998-10-28028 October 1998 Rev 8 to Dbnps,Unit 1 Technical Requirements Manual ML20155E3231998-10-28028 October 1998 Proposed Tech Specs Revising Various Sections of 6.0, Administrative Controls, Including Relocation of 6.11 Contents to Plant Ufsar,Per NUREG-1430,Rev 1 ML20155D7791998-10-27027 October 1998 Proposed Tech Specs Relocating TS SR 4.6.5.1.d.4 Re Evs Negative Pressure Testing to TS 3/4.6.5.2,deleting TS Definition 1.24 & Making Related Changes Associated with Deletion of Subject Definition ML20155D8521998-10-27027 October 1998 Proposed Tech Specs Revising SRs 4.8.2.3.2.d,4.8.2.3.2.e, 4.8.2.3.2.f & Table 4.8-1 Re Testing of 125 Volt DC Station Batteries & Applicable TS Bases ML20155E0721998-10-27027 October 1998 Proposed Tech Specs Revising 3/4.3.1.1 Re RPS Instrumentation & 3/4.3.2.3 Re ARTS Instrumentation,To Provide Potential Reduction in Spurious Trip Rate for Potential Cost Savings in Excess of $50,000 ML20151W3071998-09-0808 September 1998 Proposed Tech Specs Permitting Use of Framatome Cogema Fuels M5 Advanced Alloy for Fuel Rod Cladding & Fuel Assembly Spacer Grids ML20151W2991998-09-0808 September 1998 Proposed Tech Specs Revising Section 3/4.7.6, Plant Systems - CREVS & Associated Bases ML20206D2721998-08-28028 August 1998 Rev 11,change 1 to Odcm ML20217P8351998-04-24024 April 1998 Proposed Tech Specs Clarifying Discussion of Margin Between RPS High Pressure Trip Setpoint & Lift Setting for Pressurizer Code Safety Valves ML20217P8811998-04-24024 April 1998 Proposed Tech Specs 3/4.3.1.1,3/4.3.2.1,3/4.3.2.2 & Associated Bases Relocating Tables of Response Time Limits to Plant USAR Technical Requirements Manual ML20217C4881998-03-20020 March 1998 Proposed Tech Specs SR 4.4.5.3.c.1,providing Greater Specificity as to Location of Addl Insps in Unaffected SG ML20217N4471998-02-27027 February 1998 Proposed Tech Specs Pages Provided to Modify Proposed New Action 3.7.6.1.b to Make More Consistent w/NUREG-1431 ML20203L1111998-02-26026 February 1998 Proposed Tech Specs Pages Re Amend to License NPF-3 Involving Incorporation of New Repair Roll Process for SG Tubes W/Defects in Upper Tube Sheet ML20197J2621997-12-23023 December 1997 Proposed Tech Specs Pages Re Changes to TS Definition 1.2, TS 3/4/9.5 & New TS 3.0.6 & Associated Bases.Ts Index Rev to Reflect Change to TS 3/4.9.5,included ML20197J5971997-12-23023 December 1997 Proposed Tech Specs Pages,Revising TS Surveillance Requirements for ISI Requirements of Internal Auxiliary Feedwater Header,Header to Shroud Attachment Welds & External Header Thermal Sleeves ML20217M5601997-09-0505 September 1997 Rev 11.0 to Davis-Besse Odcm ML20217R2821997-08-26026 August 1997 Proposed Tech Specs,Clarifying LCO 3.6.1.3.a & Revising Surveillance Requirement 4.6.1.3.c ML20217R2871997-08-26026 August 1997 Proposed Tech Specs,Modifying TS 3.2.5 Action Statement to Require Power Reduction to Less than 5% of Rated Thermal Power within Four Hrs If RCS Flow Rate Is Less than Specified Limit for Greater than Two Hrs ML20217G5981997-07-29029 July 1997 Proposed Tech Specs 3/4.4.3 Re Safety Valves & Pilot Operated Relief valve-operating ML20141F1101997-06-24024 June 1997 Proposed Tech Specs,Deleting Requirements for Safety Features Actuation Sys Containment High Radiation Monitors ML20138C3261997-04-18018 April 1997 Proposed Tech Specs 3/4.7.6 Revising Limiting Condition for Operation to Include New Required Actions in Event That One or Both Channels of Radiation Monitoring Instrumentation Becomes Inoperable ML20138A6891997-04-18018 April 1997 Proposed Tech Specs 3/4.5.3.2.1 & 3/4.5.2 Modifying Presently Specified 18-month Surveillance Frequencies to New Specified Frequencies of Once Each 24-months ML20140D9481997-04-0909 April 1997 ODCM, Rev 10 ML20138M1281997-02-14014 February 1997 Proposed Tech Specs 3.5.2 Re Emergency Core Cooling Systems & 4.5.2.f Re Surveillance Requirements ML20134L0561997-02-13013 February 1997 Proposed Tech Specs Re Changes Made Concerning Decay Heat Removal Sys Valve ML20134F1811997-01-30030 January 1997 Proposed Tech Specs Re Possession & Use of SNM as Reactor Fuel ML20134D7621997-01-30030 January 1997 Proposed Tech Specs Revising SR Intervals from 18 to 24 Months Based on Results of DBNPS Instrument Drift Study & TS 2.2, Limiting Safety Sys Settings, Based on Results of Revised Framatome RPS Instrument String Error ML20134B0591997-01-20020 January 1997 Proposed Tech Specs 3/4.5.3 Re ECCS Subsystems ML20132B7031996-12-11011 December 1996 Proposed Tech Specs Revising TS Definitions,Instrumentation TS & ECCS TS for Conversion to 24 Month Fuel Cycle for License NPF-3 ML20134F1891996-10-28028 October 1996 Proposed Tech Specs 3/4.8 Re Electrical Power Systems ML20117P5311996-09-17017 September 1996 Proposed Tech Specs,Supporting Conversion of DBNPS from 18 Month to 24 Month Fuel Cycle ML20117N8531996-09-12012 September 1996 Proposed Tech Specs Re Reactivity Control Systems & Emergency Core Cooling Systems ML20117M2201996-09-0404 September 1996 Proposed Tech Specs 6.2.3,removing Specific Overtime Limits & Working Hours ML20116K2631996-08-0707 August 1996 Proposed Tech Specs Re Definitions,Applicability Bases, Containment Spray Sys & Containment Isolation Valve for Conversion to 24 Month Fuel Cycle ML20117K1911996-05-28028 May 1996 Proposed Tech Specs 3/4.3.1.1 - RPS Instrumentation & TS 3/4.3.2.3 - Anticipatory RTS Instrumentation Increasing Trip Device Test Interval ML20101M1921996-03-29029 March 1996 Proposed Tech Specs 3/4.6.4.4 - HPS,3/4.6.5.1 - Shield Building Evs & 3.4.7.6.1 - CREVS Re Changing Surveillance Requirements for Charcoal Filter Lab Testing to Revise Methodology Used to Determine Operability in ESF AHUs ML20101C6961996-03-0606 March 1996 Proposed Tech Specs,Allowing Deferment of SR 4.5.2.b for ECCS Flowpath Containing HPI Pump 1-2 Until 10th Refueling Outage,Scheduled to Begin 960408 ML20100E0101996-02-0505 February 1996 Proposed TS 3/4.3.2.1,Table 3.3-3,safety Features Actuation Sys Instrumentation,Reflecting Design & Actuation Logic of Plant Sequencers & Essential Bus Undervoltage Relays ML20107C3101995-12-21021 December 1995 Rev 9 to Odcm 1999-09-07
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20197G5521998-10-28028 October 1998 Rev 8 to Dbnps,Unit 1 Technical Requirements Manual ML20206D2721998-08-28028 August 1998 Rev 11,change 1 to Odcm ML20217M5601997-09-0505 September 1997 Rev 11.0 to Davis-Besse Odcm ML20140D9481997-04-0909 April 1997 ODCM, Rev 10 ML20107C3101995-12-21021 December 1995 Rev 9 to Odcm ML20107C3021995-10-16016 October 1995 Rev 8 to Odcm ML20199L1821995-09-0909 September 1995 Rev 3 to DB-OP-00000, Conduct of Operations ML20082V4071995-02-0303 February 1995 Offsite Dose Calculation Manual Rev 7 ML20072S8611994-06-22022 June 1994 Rev 6 to Davis-Besse Offsite Dose Calculation Manual ML20056F3071993-08-0808 August 1993 Rev 3 to Emergency Plan Off Normal (Epon) Occurrence Procedure HS-EP-02820, Earthquake. W/Rev 23 to Epon Occurrence Procedures Manual Table of Contents ML20072S8401992-12-18018 December 1992 Rev 5 to Davis-Besse Process Control Program ML20072S8501992-12-18018 December 1992 Rev 5.2 to Davis-Besse Offsite Dose Calculation Manual, Reflecting Rev 5,Change 2 to ODCM ML20101R1721992-06-11011 June 1992 Rev 1 to Vol I of Inservice Insp Plan,Second 10-Yr Nuclear Interval Pump & Valve Inservice Testing Program ML20114C6321992-05-19019 May 1992 Change 1 to Rev 5 to ODCM ML20114C6301992-03-0606 March 1992 Rev 5 to ODCM ML20217C3661991-07-0808 July 1991 Rev 3 to Administrative Procedure NG-IS-00002, General Nuclear Security Requirements. Pages 7,9,10 & 15 Only ML20084U5911991-02-22022 February 1991 Rev 4 to ODCM ML20217C3481990-12-18018 December 1990 Rev 1 to Security Dept Procedure IS-DP-04007, Performance Test for Alco-Sensor ML20059D4181990-08-28028 August 1990 Second 10-Yr Interval Pump & Valve Inservice Testing Program ML20217C3001990-08-23023 August 1990 Rev 5 to Security Dept Procedure IS-AC-00011, Protected & Vital Area Badge Issuance & Control ML20217C3571990-08-0909 August 1990 Rev 3 to Security Implementing Procedure IS-AC-00516, Unescorted Access Requirements ML20217C3071990-07-27027 July 1990 Rev 2 to Security Dept Procedure IS-AC-00015, Fingerprint Processing & Controls ML20217C3201990-06-27027 June 1990 Rev 1 to Security Dept Procedure IS-AC-00018, Drug & Alcohol Testing Process ML20217C3811990-06-22022 June 1990 Rev 4 to Nuclear Group Procedure NG-IS-00004, Fitness for Duty Program ML20217C4001990-04-0202 April 1990 Corporate Ref Manual - Nuclear NU-102, Fitness for Duty ML20217C3401990-01-12012 January 1990 Rev 1 to Security Dept Procedure IS-DP-00101, Bac Simulation ML20217C3281989-11-0909 November 1989 Rev 1 to Security Dept Procedure IS-DP-00100, Bac Exams ML20217C3141989-10-25025 October 1989 Rev 2 to Security Dept Procedure IS-AC-00017, Denied Access List Control ML20217C3941989-08-0101 August 1989 Corporate Ref Manual - Human Resource HR-604, Drug & Alcohol Policy ML20244A8421989-05-31031 May 1989 Pressurizer Surge Line Thermal Stratification Phase I Program ML20213A0311987-03-31031 March 1987 Rev 2 to Vol IV of Procedure Writers Manual:Operation Procedures Guidelines ML20213A0361987-03-31031 March 1987 Rev 1 to Davis Besse Emergency Procedure Verification & Validation Program ML20212D1621987-01-27027 January 1987 Rev 1 to Maint Procedure MP 1411.06, Preventive Maint for Type Smb & Smc Valve Operators ML20198D2551986-12-27027 December 1986 Rev 2 to Maint Procedure MP 1411.04, Maint & Repair of Limitorque Valve Operators Type SMB-000 & SMB-00. Temporary Mod Request T-9969,indicating Rewiring of Fcr 85-302 MU-11 to Torque Out in Open Direction,Encl ML20212B5721986-12-15015 December 1986 Rev 0 to Security Training & Qualification Plan, Superseding Rev 24 to App B of ISP AD1808.00.W/o Revised Pages ML20212C9481986-11-21021 November 1986 Rev 8 to Maint Procedure Mpo 1410.32, Testing of Motor- Operated Valves Using Movats ML20212D3131986-10-28028 October 1986 Change 3 to Temporary Mods T10161 & T10144 to Rev 0 to Maint Procedure MP 1411.07, Maint & Repair of Limitorque Valve Opr Smc 04, Incorporating Fcr 86-0092,Rev a Re Removal & Installation of Limiter Plate ML20212D1091986-10-21021 October 1986 Change 1 to Rev 2 to Maint Procedure MP 1411.04, Maint & Repair of Limitorque Valve Operators Type SMB-000 & Smb 00, Addressing Need for Procedure to Address Replacement of Defectrive Parts ML20212D1471986-10-0303 October 1986 Rev 1 to Maint Procedure MP 1411.05, Maint & Repair of Limitorque Valve Operators Types SMB-0 Through SMB-4 ML20212C9181986-09-22022 September 1986 Rev 1 to Procedure NEP-092, Establishing D/P Limits & Tests for Q Motor Operated Valves ML20203M0201986-08-21021 August 1986 Specs for Mist Continuous - Venting Tests ML20210V1131986-08-20020 August 1986 Rev 0 to Emergency Plan Implementing Procedure EP-2320, Emergency Technical Assessment ML20206P6511986-06-30030 June 1986 GE Owners Group Action Plan as Result of Davis-Besse Event, June 1986 ML20198D2361986-05-0202 May 1986 Rev 5 to Maint Procedure MP 1410.32, Testing of Motor- Operated Valves Using Movats ML20141J5231986-04-18018 April 1986 Human Engineering Discrepancy Review & Closeout Process for Davis-Besse Dcrdr Program ML20205M6981986-04-0707 April 1986 Rev 0 to Nuclear Engineering Procedure NEP-092, Establish Differential Pressure Limits & Tests for Motor-Operated Valves ML20205M7031986-03-25025 March 1986 Rev 0 to Nuclear Engineering Procedure NEP-091, Motor- Operated Valve (MOV) Data Evaluation ML20141N1501986-02-26026 February 1986 Procedure Fcr 85-227, Main Feedwater Block Valve Interlock ML20141N1561986-02-26026 February 1986 Procedure Fcr 85-200, Main Feedwater Pumps Rapid Feedwater Reduction Speed Setpoint ML20141N1531986-02-26026 February 1986 Procedure Fcr 85-201, Steam Generator Level Setpoint 1998-08-28
[Table view] |
Text
E i s e i
I NG-IS-00002, REVISION 03 PAGES 7, 9, 10, 15 ONLY' "INFORMATION ONLY" l
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l 91071;O244 w 10799 PDR ADOCK OT;OOO346 l
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g NG-IS-00002, REVISION 03 PAGES 7, 9, 10, 15 ONLY "INFORMATION ONLY" l
l 910715G244 91070g PDR A DOC r'. 03000346 F POR I
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.'s- 80 ?S?S DAVS SESsg T1VE PROCEDURE ___ FAGE f.EVISION . PMoCEDURE NUMGER ,
Guncrc uclcor Security- 7 03 NG-IS-00002 Requirements- .
4 . 7. - OWNER-CONTROLLED AR3A - Land owned'or controlled by Toledo Edison Company, including the wildlife refuge, and excluding
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~ths Protected and Vital Areas.
4.8- OWNER-CONTROLLED AREA BADGES - Photo identification' badges 1 issued by Security and required for access to the Owner- '
controlled Area _upon successful completion of the requirements specified in NG-IS-00003. I' 4.9- .PPF - Personnel-Processing Facility 4.~10'- PROTECTED ~ AREA - The fenced araa within the owner-controlled t.ree:containing major plant buildings _and structures.=
4.11 PROTECTED / VITAL AREA BADGES - Photo identification badges and keycards issued by Security'and required for access to l_
the-Protected and Vital Areas (for authorized individuals) upon successful completion of the requirements-specified in
-IS-AC-00516. l
-4.12 SPONSOR - Personnel. responsible for.the conduct and who arel 1 cognizant of the location of-individuals who are visiting--l
- on the-Davis-Besse site. I 4.13 TAII4ATING - Entry into:a Protected / Vital Area without- l proper access authorization or properly badging in. I i
_ _4 .14 TLD:- Thermoluminescent Dosimeter 4.15 UNAUTHORIZED. ITEMS- Unauthorized. items' include weapons, firearms, explosives, large knives-(unauthorized knives. l
-with blades over-3 1/2 inches long), incendiary devices, . l alcohol,:and illegal drugs. l 4.16 . VISITORS --Personnel who request access-to-DBNPS for i periods:of 14 consecutiveidays or-lese.
4.17- VITAL AREAS -'. Areas within the Protected' Area that contain.
equipment vital to safe operation of the plant.
"i .' O' RESPONSIBILITIES 5.1 -The Manager:- Industrial Security and-the Plant Manager l_
shall be responsible for ensuring the overall implementation of this' procedure.
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L DAVIS-BESSE ADMINLSTRATIVE PftOCEDURE FAGE r.EYlSION PROCEDUZE NUMBER G:ncral NuclOOr S curity 9 03 R quirCCOnto NG-IS-00002 5.4.5 Ensuring personnel are processed for access to the Pr';ected and Vital Areas according to IS-AC-00516.
5.5 The Supes or - Nuclear Security Support shall be responsibo. for: l 5.5.1 Administrative control of this procedure.
5.5.2 Ensuring compliance with the DBNPS Industrial Security Plan.
5.5.3 Controlling locks and keys. l 5.6 The General Supervisor be responsible for: ~ Nuclear Security Operations shall l 5.6.1 Operational control of the Nuclear Security Section.
5.6.2 Ensuring that personnel and vehicles are searched for unauthorized items in accordance with IS-DP-00511 and IS-DP-08512. l 5.6.3 Ensuring. personnel are observed as they enter the Protected Area for indications of alcohol or drug use.
5.6.4 Initiating security investigations.
5.6.5 Authorizing camera permits in the Protected and Vital Areas.
5.6.6 Co-authorization of access to the Security Data Management System Computer.
5.7 The Supervisor-Security Shift shall be responsible for: l 5.7.1 Implementing the requiremencu of NG-IS-00004. l 5.7.2 Ensuring Plan.
compliance with DENPS Industrial Security i i
5.7.3 Ensuring gate passos are verified and initialed according to IS-DF-00006.
5.7.4 Authorizing temporary key assignments from the !
master key cabinet during a backshift. ;
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ie ,m l PAGE r.EVIStota PROCEDUZE NUMBER DAVIS-SESSE ADMINISTRATTVE PROCEDUZE G2n0rel Nuclocr Sccurity 10 03 NG-IS-00002 R quiremento: .
5.8 TheNuclearGroupSupervisorsshA((beresponsiblefor:
5.8.1 observing personnel under their direct supervision for any indications of drug or alcohol use.
5.8.2 Completing Visitor Tour and Visitor Work Permits.
5.9 Sponsors and/or project coordinators shall be responsible for ensuring that visitors who are vendors, field -
representatives, or consultants, going into the Protected / Vital Areas to assist in the resolution of equipment problems or testing, have any material or parts j verified at the Warehouse and/or any Measuring-and Test i Equipment (M&TE) processed through the Metrology Laboratory I before entering the Protected / Vital Areas. l 5.10 Escorts shall be respcnsible for:
5.10.1 -Maintaining Fitness For Duty escort qualification. l 5.10.2 - Escorting visitors and personnel who have been granted escorted access to the Protected and/or Vital Areas. l 5.10.3 Maintaining the correct visitor escort ratio for the Protected / Vital Areas. l 5.11 The Tool Room Foreman shall be responsible for approving ,
gate passes for tools and/or materials to be removed from L their arca of responsibility.
l 5.12 Nuclear Materials Management Personnel shall be responsible i I
for:
l 1 5.12.1 Approving Gate Passes for tools and/or materials to be removed from their area of responsibility.
5.12.2 Ensuring that any material taken into the Protected / Vital Areas by a sponsored vendor, field representative, or consultant, is approved in accordance with NG-NP-00400. l I
l 5.14 -The Nuclear Training Manager shall be responsible for i providing Fitness for Duty Training,-General Employee l L Training (GET) and Radiation Controle Training (RCT) for
! -Nuclecr Group personnel according to NG-NT-00600. 1 I ;
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PAGE REVISloN PAOCEDURE NUM8ER DAVIS-8 ESSE ADMINISTRATIVE PGOCEDURE General Nuclear Sccurity 15 03 NG-IS-00002 Requirements .
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- f. In the event of an emergency, Visitor assembly, accountability, and evacuation shall be accomplished in accordance with HS-EP-02520 and] ;
HS-EP-02530.
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6.3.4 Protected Area Exit Process
- a. The Protected Area shall be exited through the ;
PPF according to the guidelines in Attachment i 2, Protected Area Exit Process.
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- b. The individual shall pass through the radiation portal monitor when exiting. If this monitor alarms, security shall ask the person to step I '
through the monitor again to verify the alarm.
- 1. If the alarm is verified, the person shall be delayed and Radiological Control l Section shall be informed. Further action is specified in DB-HP-01701.
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- 2. In the event of a power failure or a loss of portal monitors for any reason, security shall contact Radiological Control Section to provida an alternate means of monitoring all exits from the Protected Area.
- c. Protected / Vital Area badges shall be left with l security upon exiting the Protected Area.
6.3.5 Any breaches of the Protected Area perimeter barrier such as a hole in or under the fence, an open gate with no cecurity officar present, a ladder near the fence, or anything suspicious that may be a breach i _
of security, shall be reported to the CAS Operator immediately. l 6.3.6 Any Security related problam shall be reported to l Security immediately for a reportability I
( determination in accordance with IS-DP-00518. I 6.3.7 Employaa Observation
- a. Esa General Supervisor - Nuclear Security I operations shall ensure that personnel entering the Protected Area are observed for indications of alcohol or drug use in accordance with NG-IS-00004. I
o y NG-IS-00003, REVISION 04 PAGES 6, 18 ONLY "INFORMATION ONLY" I
s <
tO7178 DAVic-BESSE ADMINISTRATIVE PROCEDURE PAGE REVISION PZOCEDURE NUMBER l
Owner Controlled Access 6 of 25 04 NG-IS-00003 4.0 DEFINITIONS 4.1 BUILDING ACCESS KEYCARDS - Keycards issued by Security and required for access to buildings outside the Protected Area.
4.2 COMPANY PERSONNEL - Individuals employed by Centerior Energy Corporation or its subsidiaries.
4.3 NON-COMPANY PEkSONNEL - Individuals not employed by Centerior Energy Corporation or its subsidiaries.
4.4 OWNER CONTROLLED AREA - Land owned, or controlled, by Toledo Edison including the wildlife refuge. The Owner Controlled Area excludes the Protected and Vital Areas.
4.5 OWNER CONTROLLED AREA BADGES - Photo identification badges or visitor badges, issund by Access Control which are required to be displayed for access to be granted to the Owner Controlled Area.
4.6 PICKUP / DELIVERY PERSONNEL - Individuals requiring access to the owner-Controlled Area periodically (e.g., servicemen, repairman, oil deliveries, Federal Express, spouses picking up paychecks). l 4.7 SPONSOR - As pertains to this procedure, a sponsor is the Company person assigned responsibility for a visitor while inside the ownc.r-Controlled Area.
4.8 UNAUTHORIZED ITEMS - Unauthorized items include weapons, firearms, explosives, switchblades, knives with blades over 3 1/2 inches long, incendiary devices, alcohol, and illegal drugs. l 4.9 VISITORS - Individuals requiring access to DBNPS for less than 14 consecutive days.
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DAVIS.CESSE ADMINISTRAT1VE PROCEDURE PAGE ' REVISION PROC (0VRE NUYBER Owner Controlled Access 18 of is 04 NG-IS-00003 NOTE 6.9 Information pertaining to access denial shall be handled in strictest confidence. This information shall be disseminated to only those individuals who have a need to know the information in detersining whether to grant access.
6.9 Access _ Denial 6.9.1 The Supervisor Accese Control may deny access to the owner controlled Area and place the individual on the DBNPS Danied Access List for the following reasonst
- a. Criminal History Check results
- b. Failure tu meet minimum screening requirements
- c. Pitness for Duty incidents e d. Violation of cuapany procedures and policies
- e. Possession of unauthorized items
- f. Other circumstances which, in the opinion of the Supervisor - Access Control and the Manager
. Industrial Security, cast doubt upon the individual's security reliability and
=
trustworthiness.
6.9.2 individuals denied access to the owner Controlled Ataa may appeal the access denial decision in '
accordance with Section 6.10, Access Denial Appeal.
6.10 Access _ Denial _Acceal 6.10.1 Individuals requesting reinstatement of access eligibility to DBNPS shall notify the Supervisor - l Access control in writing.
6.10.2 The Industrial Security Committee shall review the j situation in accordance with IS.AC 00017, Denied Access List Control.
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