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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML18017A9271999-10-21021 October 1999 Proposed Tech Specs Implementing Selected Improvements as Described in GL 93-05 ML18017A8531999-08-26026 August 1999 Proposed Tech Specs Pages,Revising TS 3/4.9.4 to Allow Penetrations Which Provide Direct Access from Containment Atmosphere to Outside Atmosphere to Remain Open During Refueling Operations ML18016B0521999-08-0404 August 1999 Proposed Tech Specs,Incorporating Analytical Methodology in TS 6.9.1.6.2 Which Are Used to Determine Core Operating Limits ML18016B0451999-08-0202 August 1999 Proposed Tech Specs 6.2.2.e Re Operations Mgt License Requirements ML18016B0101999-07-0909 July 1999 Proposed Tech Specs 3/4.2.2,3/4.2.3 & 3/4.2.5,providing Clarification & Reducing Burden of Addl License Amend Process by Implementing Guidance in GL 88-16 & NUREG-1431, Rev 1, Std Ts,W Plants. ML18016B0131999-07-0909 July 1999 Proposed Tech Specs,Relocating 3/4.3.3.3,3/43.3.4,3/4.3.3.9 & 3/4.3.3.11 to Plant Procedure PLP-114, Relocated Tech Specs & Design Basis, IAW GL 95-10 ML18016A9911999-06-15015 June 1999 Proposed Tech Specs Incorporating performance-based 10CFR50,App J,Option B for Type a Tests (Containment Integrated Leakage Rate Tests) ML18016A9781999-06-0202 June 1999 Proposed Tech Specs Revising TS 6.5 & TS 6.8 ML18016A8401999-02-26026 February 1999 Proposed Tech Specs Revising Table Notations for TS Table 3.3-4, ESFAS Instrumentation Trip Setpoints, Specifically Time Constants Utilized in lead-lag Controller for Steam Line Pressure Low (Table Item 1.e.) ML18016A7701998-12-23023 December 1998 Proposed Tech Specs 5.6, Fuel Storage, Increasing Spent Fuel Storage Capacity by Adding Rack Modules to Pools 'C' & 'D.' ML18016A9341998-12-15015 December 1998 Rev 11 to ODCM, for Shnpp ML18016A7531998-12-0707 December 1998 Proposed Retyped Tech Specs Page 3/4 7-5,incorporating Changes Resulting from Issuance of Amend 77 Re Afs SRs ML18016A7561998-12-0707 December 1998 Proposed Retyped Tech Specs Page 3/4 9-13,incorporating Changes Resulting from Issuance of Amend 84 Re SFP Water Level & Revised Fuel Handling Accident Analyses ML18016A7591998-12-0707 December 1998 Retyped Tech Specs Pages 3/4 6-4 & 3/4 6-4a,incorporating Changes Resulting from Issuance of Amend 84 Re Containment Air Locks ML18016A6571998-10-28028 October 1998 Corrected TS Pages 6-5 & 6-27 Re 970612 Request for Amend to License NPF-63 Re Proposed Changes to TS 6.0.Original Submittal Contained Editorial Errors ML18016A6261998-10-15015 October 1998 Proposed Tech Specs 3/4.5.1 Re Accumulators & Associated Bases ML18016A6051998-10-0101 October 1998 Proposed Tech Specs 3.0.4 Concerning Applicability of Limiting Conditions for Operation & SR to Be Consistent with GL 87-09 ML18016A5941998-09-23023 September 1998 Proposed Tech Specs 3/4.6.3, Containment Air Locks for Consistency with NUREG-1431,Rev 1 & Clarifying Requirements for Locking Air Lock Door Shut ML18016A5461998-09-0101 September 1998 Proposed Tech Specs Section 3/4.9.11,requiring 23 Feet of Water Above Top of Fuel Rods within Irradiated Fuel Assemblies Seated in Storage Racks ML18016A5411998-08-27027 August 1998 Proposed Tech Specs Re Applicability of LCO & Surveillance Requirements ML18016A5381998-08-27027 August 1998 Proposed Tech Specs,Revising Section 6.0, Administrative Controls. ML18016A5311998-08-24024 August 1998 Proposed Tech Specs Re Use of SG Sleeves Designed by ABB-CE ML18016A4301998-05-15015 May 1998 Revised Proposed TS Pages Which More Closely Reflect Generic TS Wording Contained in Std TS W Plants ML18016A4021998-04-24024 April 1998 Proposed Tech Specs 3/4.3.2,allowing Two Hour Surveillance Interval to Facilitate Testing of 6.9 Kv Emergency Bus Undervoltage Relays ML18016A3881998-04-13013 April 1998 Proposed Tech Specs Bases Section 4.0.2,clarifying Guidance Related to Safety Performing Surveillance Testing at Power ML18016A3481998-03-12012 March 1998 Proposed Tech Specs Deleting SR 4.9.12.d.4 Which Requires Verifying That Filter Cooling Bypass Valve for Fhb EES Is Locked in Balanced Position at Least Once Per 18 Months ML18016A3051998-01-29029 January 1998 Rev 0 to HNP-IST-002, Shearon Harris Nuclear Power Plant, IST Program Plan - 2nd Interval. ML18022B0351998-01-26026 January 1998 Rev 0 to Procedure HNP-ISI-002, Shearon Harris Nuclear Power Plant,Isi Program Plan,2nd Interval. ML18016A4131997-12-18018 December 1997 Rev 10 to ODCM for Shearon Harris Nuclear Power Plant. ML18016A2591997-12-16016 December 1997 Proposed Tech Specs Pages,Revising TS 4.7.1.2.1.a.2.a to Change Differential Pressure & Flow Requirements of Steam turbine-driven AFW Pump to Allow Testing of Pump at Lower Speed than Is Currently Performed ML18016A2241997-10-29029 October 1997 Proposed Tech Specs Revising TS 3/4.8.1, AC Sources - Operating & Associated Bases to Clarify Intent of TS ML18012A8121997-06-12012 June 1997 Proposed Tech Specs 6.0 Amending Administrative Controls. ML18012A7991997-05-23023 May 1997 Proposed Tech Specs,Providing Retyped TS Pages Re Revised Action & Surveillance for ECCS Accumulators ML18012A7861997-05-16016 May 1997 Proposed Tech Specs,Informing That TS 4.6.2.3 a.2 Requires Verification at Least Once Per 31 Days of Cw Flow Rate of Greater than or Equal to 1425 Gpm to Each Containment Fan Cooler ML18012A6361997-04-23023 April 1997 Proposed Tech Specs,Incorporating Enhancements to TS Identified in Plant Review Performed IAW GL 96-01.Changes Affected Specs 4.3.2.1.1.a,4.3.2.1.4.b,4.3.2.1.6.g, 4.3.2.1.10.a,4.3.2.1.10.b & 4.7.3.b.3 ML18012A5811997-03-17017 March 1997 Proposed Tech Specs Surveillances 4.1.2.2c,4.5.2.e, 4.6.2.1c,4.6.2.2.c,4.6.3.2,4.7.1.2.1.b,4.7.3.b & 4.7.4.b to Delete Specific Restrictions in Text of Surveillances ML18022B0041997-03-14014 March 1997 Proposed Tech Specs,Increasing AOT for Refueling Water Storage Tank to Twelve Hs While Performing TS Surveillance 4.4.6.2.2 ML18022B0071997-03-10010 March 1997 Proposed Tech Specs 3/4.5 Re Emergency Core Cooling Systems ML18012A5361997-02-27027 February 1997 Proposed Tech Specs,Amending TS 3/4.4.5, Sgs, & Associated Bases,To Add Sleeve Installation as Alternative to Tube Plugging for Repairing Degraded SG Tubes ML18012A5351997-02-21021 February 1997 Proposed Tech Specs Revising TS 3.3.2 in Action 16 of Table 3.3-3 to Add Specific Time Interval of Six H to Place an Inoperable Channel in Bypassed Condition ML18012A5281997-02-21021 February 1997 Proposed Tech Specs 3.0.5 Re Exception to TS 3.0.1 to Permit Equipment to Be Placed Into Svc in Order to Perform Testing to Demonstrate Operability ML18012A5311997-02-18018 February 1997 Proposed Tech Specs 3/4.7.1, Turbine Cycle Safety Valves. ML18012A5101997-02-13013 February 1997 Proposed Tech Specs 3.2.3 Re Rated Thermal Power ML18012A5011997-02-0606 February 1997 Proposed Tech Specs 3/4.0,adding New Entry 3.0.5 to Provide Specific Guidance for Returning Equipment to Svc Under Adminstrative Control for Sole Purpose of Performing Testing to Demonstrate Operability ML18012A4961997-01-29029 January 1997 Proposed Tech Specs 3/4.0 Re Applicability ML18012A4641997-01-10010 January 1997 Proposed Tech Specs 4.8.1.1.2 Re AC Sources - Operating Surveillance Requirements ML18012A4531996-12-30030 December 1996 Proposed Tech Specs 3/4.4.9 Re Pressure/Temp Limits ML18012A4161996-10-31031 October 1996 Proposed Tech Specs Re Ultimate Heat Sink Level & Temp ML18012A3981996-10-0808 October 1996 Proposed Tech Specs Bases Change to 3/4.6.1.4 & 3/4.6.1.6 Changing Calculated Peak Pressure for MSLB Event ML18012A3721996-09-18018 September 1996 Proposed Tech Specs 4.8.1.1.2 Re Surveillance Requirements for Diesel Fuel Oil Sys Pressure Testing 1999-08-04
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML18016A9341998-12-15015 December 1998 Rev 11 to ODCM, for Shnpp ML18016A3051998-01-29029 January 1998 Rev 0 to HNP-IST-002, Shearon Harris Nuclear Power Plant, IST Program Plan - 2nd Interval. ML18022B0351998-01-26026 January 1998 Rev 0 to Procedure HNP-ISI-002, Shearon Harris Nuclear Power Plant,Isi Program Plan,2nd Interval. ML18016A4131997-12-18018 December 1997 Rev 10 to ODCM for Shearon Harris Nuclear Power Plant. ML18011A8031994-08-31031 August 1994 Rev 5 to Odcm. ML18011A5631994-07-0101 July 1994 Rev 4 to Odcm. ML18011A1111993-07-0707 July 1993 Rev 8 of ISI Program ISI-203, ASME Section XI Pump & Valve Program Plan. ML20044G6131993-05-11011 May 1993 Rev 5 to Design Guide DG-II.20, Design Guide for Civil/Structural Operability Reviews. ML18011A1181993-01-0606 January 1993 Rev 3 to Odcm. ML18010A8491992-09-23023 September 1992 Change 1,Rev 5 to Vol 3,Part 9 of Plant Operating Manual Procedure OST-1825, Safety Injection:Esf Response Time, Train a 18 Month Interval on Staggered Test Basis Mode 5 - 6. ML20116D2961992-08-31031 August 1992 Rev 2 to Nuclear Generation Group Manual 305-05, Prioritization Process ML18010A8361992-08-28028 August 1992 Change 2,Rev 2 to Vol 4,Part 7 of Plant Operating Manual Procedure MST-I0080, RCS Wide Range Pressure P-0402, Reflecting Case Level Change to Case III ML20044G6141992-07-31031 July 1992 Rev 0 to 92C1737A, Recommended Operability Review Criteria for Piping Sys Subj to Level D Svc Loadings for Carolina Power & Light Nuclear Stations. ML18010A8371992-05-0404 May 1992 Rev 3 to Vol 3,Part 9 of Plant Operating Manual Procedure OST-1083, ESFAS Train 'A' Slave Relay Test 18 Months Interval Modes 5 & 6. ML18010A5471991-12-18018 December 1991 Rev 3 to Odcm. ML18005B0231989-08-29029 August 1989 Rev 3 to Odcm. ML18005A9061989-03-27027 March 1989 Rev 6 to Vol 6,Part 7 to Inservice Insp Program ISI-203, ASME Section XI Pump & Valve Program Plan. ML18005A3461988-02-26026 February 1988 Rev 1 to Plant Program Procedure PLP-108, Environ Qualification Program (10CFR50.49). ML18005A3441988-02-18018 February 1988 Rev 1 to Technical Support Mgt Manual TMM-402, Equipment Qualification Coordinator Responsibilities. Related Info Encl ML18005A3641988-02-18018 February 1988 Rev 4 to Technical Support Mgt Manual TMM-104, Determination of Technical & QA Requirements for Procurement Document. ML18005A3521988-02-11011 February 1988 Rev 0 to Ned Design Guide DG-VIII.19, Shearon Harris Equipment Qualification Documentation Review. ML18005A3471988-02-10010 February 1988 Rev 0 to Ned Design Guide DG-VIII.34, Preparation & Control of Shearon Harris Environ Qualification Master List. ML18005A3371988-01-29029 January 1988 Rev 14 to Coporate QA Dept Procedure Cqad 80-1, Procedure for Corporate QA Audits. ML18022A6141988-01-28028 January 1988 Inservice Insp 10-Yr Plan of Shearon Harris Nuclear Power Plant Unit 1, Vols 1 & 2 ML18005A3581988-01-13013 January 1988 Rev 0 to Maint Mgt Manual MMM-025, Maint Environ Qualification Program. ML18022A7961987-10-31031 October 1987 Master Plan for Wakesouth Regional Airport Phase I. ML18005A3391987-09-24024 September 1987 Rev 1 to Operations Qa/Qc Procedure OQA-201, Surveillance Program. ML18005A3431987-09-0101 September 1987 Rev 4 to Administrative Procedure AP-600, Plant Change Request Initiation. ML20235G5241987-08-28028 August 1987 Revised Plant Emergency Procedures,Including Rev 2 to Change 5 to PEP-101, Emergency Classification & Initial Emergency Actions, & Rev 2 to PEP-221, Technical Analysis Manager. W/One Oversize Drawing ML18005A3481987-08-24024 August 1987 Rev 8 to Mod Procedure MOD-103, Engineering Evaluations. ML18005A3501987-06-23023 June 1987 Rev 5 to Administrative Procedure AP-014, Criteria for Qualified Safety Reviewers. ML18005A3511987-04-24024 April 1987 Rev 0 to Administrative Procedure AP-618, Justification for Continued Operation. ML18022A5011987-04-14014 April 1987 Rev 1 to Procedures Generation Package. W/Emergency Operating Procedures Writing Guide,Verification & Validation Program & 870414 Ltr ML18005A3651987-02-12012 February 1987 Rev 1 to Technical Support Mgt Manual TMM-110, Receiving Packaging,Storage & Maint Requirements for Spare Parts,Matl & Components. Equipment Qualification Master List & Other Related Documents Encl ML18005A3421986-12-18018 December 1986 Rev 1 to Administrative Procedure AP-610, Processing Vendor Recommendations,Vendor Manual Revs & Equipment Technical Info. ML18022A4991986-12-0909 December 1986 Change 1 to Rev 1 to Emergency Procedure PEP-401, Record Keeping & Documentation, Deleting Prohibition of Use of Felt Tip Pens & Clarifying Type of Facility & Equipment Records to Be Maintained ML18005A3531986-10-27027 October 1986 Rev 1 to Administrative Procedure AP-609, Review of Incoming Nrc/Inpo Correspondence. ML18005A3571986-10-24024 October 1986 Rev 1 to Administrative Procedure AP-026, Corrective Action Program. ML18022A4691986-07-0303 July 1986 Rev 0 to Procedure 1-9103-S-27,Turbine Overspeed Trip Test. ML18004A2861986-05-20020 May 1986 Change 3 to North Carolina Emergency Response Plan in Support of Shearon Harris Nuclear Power Plant, Including Revs to Annex E, Emergency Broadcast Sys Procedures for Shearon Harris Nuclear Power Plant Operational Area. ML20212C0611986-04-0707 April 1986 Rev 2 to Operations Mgt Manual Procedure OMM-006, Emergency Operating Procedure Writers Guide ML18005A3561986-03-20020 March 1986 Rev 1 to Administrative Procedure AP-031, Operational Experience Feedback. ML18019A5891986-02-14014 February 1986 Revised Plant Emergency Procedures,Including Rev 2 to PEP-223, Radiological Control Manager & Rev 1 to PEP-103, Site Emergency Coordinator - Technical Support Ctr. W/One Oversize Drawing ML18019B0451985-12-17017 December 1985 Rev 1 to Plant Program Procedure PLP-610, Equipment Identification & Numbering Sys. ML18003B2961985-12-14014 December 1985 Rev 3 to Technical Support Mgt Procedure TMM-104, Determination of Technical & QA Requirements for Procurement Documents. ML18003B2921985-11-21021 November 1985 Rev 2 to Maint Mgt Procedure MMM-020, Operation Testing, Maint & Insp of Cranes & Matl Handling Equipment. ML18003B2891985-11-20020 November 1985 Rev 1 to Procedure CRC-827, Post-Accident Sample Boron Analysis by Fluoroborate Specific Ion Electrode. ML18019A5861985-11-0404 November 1985 Vol 6 of Part 7 of Plant Operating Manual,Consisting of Rev 1 to Inservice Insp Program ISI-203, ASME Section XI Pump & Valve Program Plan. ML18003B2951985-09-0909 September 1985 Rev 2 to Procurement & Matl Control Procedure PMC-001, Procurement & Cataloging of Parts,Matl,Equipment & Svcs. ML18019A3921985-08-30030 August 1985 Rev 2 to Inservice Insp Program ISI-201, ASME Preservice Insp Program Plan (Except Reactor Vessel). 1998-12-15
[Table view] |
Text
..
>o Carolina Power & Light Company
'84 FEB 21 El:31 SHEARON HARRIS NUCLEAR POWER PLANT, ..
TECHNICAL SUPPORT CENTER (TSC)
SUMMARY
OF DESIGN STANDARDS AND CRITERIA IOR THE TSC ENCOMPASSING HUMAN FACTORS ENGINEERING I. Introduction Human factors engineering is the science of designing machines and the immediate physical surroundings of the workplace to fit human physical and mental limitations, and to ensure comfort and well being in order to maximize human abilities. The design for the Technical Support Center (TSC) has been based on widely recognized industry and technical standards and building codes which encompass many aspects of good human factors engineering principles. The standards and specific considerations used for the TSC which relate to human factors engineering are described below.
II. Applicable Standards The primary standard governing the design of the TSC is the NUREG-0696, Functional Criteria for Engineering Response 8402220269 840217 PDR ADOCK 05000400 0 PDR 411 Fayetteville Street
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Facilitie's, which identifies various parameters for physical laycut, staffing, size requirements, habitability, communicatons, data systems and operational capabilities.
Structural and internal features were based on the Uniform Building Code and the North Carolina State Building Code, Volumes I, II, and III. The American Institute of Architects Architectural Graphic Standards was used for sizes, clearances, and features not specifically covered in the codes. Seismic design considerations, safe and sufficient layout parameters, requirements for construction materials and installation are some of the areas covered by these particular codes and standards.
Heating, air conditioning, and ventilation were designed utilizing the American Society of Heating, Refrigeration and Air Conditioning Engineering Handbook and the Industrial Ventilation Handbook.
Power and lighting design conform to the National Electrical Code and the Illuminating Engineering Society standards.
Safety and equipment systems were based on National Fire Protection Association and Occupational Health and Safety Administration l
standards.
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A, III. Specific Considerations In designing the TSC, the physical arrangement, interior, noise control, data display systems and computers, environmental charac-teristics, communications and protective / emergency systems specifically incorporate good human factors engineering principles.
A. Physical Layout and Location The physical layout of the TSC is designed for optimum grouping of employees to accomplish the functions that will be performed therein. A copy of the TSC floor plan is attached. Rooms and personnel are logically arranged according to work functions for an orderly flow and interaction of task to ensure efficient and expedient response for decision-making purposes. Adequate working area for personnel and equipment has been provided.
The amount of partitioned and open plan work areas allows flexible use of space and personnel. For example, in th,e Site Emergency Coordinators Staff room, the use of low-height movable partitions allows quick functional rearrangement or addition of personnel. Open-plan areas are used to accom-modate team functions. Adjoining partitioned rooms having view windows where necessary to permit observation of work activities in the open-plan areas, but maintain privacy when required. Circulation patterns provide sufficient and convenient access to services and work areas.
The interior features have been finished in a manner suitable to an office environment. Finish surface colors are to be consistent throughout and light in value, glare-free, and relatively neutral so as not to create visual contrast and confusion with surrounding display charts and equipment. The location of the TSC in a concrete structure provides seismic (earthquake) protection in addition to direct radiation shielding.
B. Noise Control Measures to control noise have been incorporated into the TSC design to ensure proper acoustics and to preclude interference with the work of support personnel. External noise is blocked by the dense concrete envelope of the TSC. Built-in equipment, such as air-handling units, fans, pumps, piping systems, and ductwork, has design features to isolate vibration and, thus, to attenuate background noises. Partitions are sufficiently constructed and sealed to reduce sound transmission between walls. Individual rooms and particularly large spaces will have length, width, and height proportions that avoid long, narrow rooms with high ceilings which can cause objectionable reverberations (echoes). Speech, phones, movement of people, equipment printers, keyboard punching, and other internally-generated noise is dampened by an absorbent acoustical ceiling system throughout the TSC.
C. Display Systems and Computers Anthropometric design features have been incorporated into the display systems equipment and computers. These features are intended to optimize human, physical motion and perceptual capabilities relative to equipment control methods and sequences, motion and time manipulations, and display quality.
The ultimate purpose is to ensure efficient, accurate, and expedient use of essent-;al display equipment. Two such display systems, the Emergency Response Facility Information System (ERFIS) and Safety Parameter Display System (SPDS),
monitor plant instrumentation for various critical safety functions, such as pressures, temperatures, fluid levels, valve status and other critical readout data. The equipment and computers for these vital display systems have glare-free screens, large-character graphic displays, logical and easily operated controls, and require minimum arm-and-head movement to manipulate and view equipment.
D. Heating, Cooling, and Ventilation System The heating, cooling, and ventilation system is designed to provide complete habitability of the TSC in the event of a release of airborne radioactivity from in plant sources. A microprocessor-based, programmable thermostat regulates
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constant air comfort for the heating and cooling cycle:
Humidity control is provided for both human ecmfort and optimum operation of essential computer equipment. Air within the TSC is maintained at a positive pressure to prevent any infiltration of contamination. Nuclear grade, high-efficiency particulate air (HEPA) and charcoal filter systems protect the TSC air supply from airborne radiation. These filter systems are designed to remove essentially all of the particulates, gases, iodine, and other impurities from the air supply.
E. Electrical System
, The electrical system is designed to provide a wide range of services for the TSC. In addition to providing adequate service for the mechanical systems, communications equipment.
ano computer systems, the electrical system will provide sufficient space lighting and convenient outlets. Office area lighting will be eve.aly distributed and maintain a minimum illumination of 75 footcandles. Some work areas will have a dimmer switch for light-level control. Other light levels in the TSC are designed in conformity with Illuminating Engineering Society-recommended standards for each particular space use.
The electrical system has an emergency back-up system in case of a loss of normal power.
b F. Communications In designing the TSC, consideration was given to providing adequate communications equipment and procedures for expeditious interfacing, transfer of vital information, and problem solving. Automatic ring down (ARD) phones, for example, are provided from the control room to the TSC and from the TSC to the NRC and other off-site agencies, such as state and local organizations with emergency preparedness responsibilities. This communications feature gives a hotline capability to key emergency response personnel for use in making prompt notifications of emergency conditions and pos-sible recommendations for protective actions. Regular tele-phones will be located throughout work areas to ensure adequate numbers. Display status boards, in ddition to the ERFIS/SPDS systems, were designed for the purpose of expediting the communication of vital information among the TSC, the plant, and the CP&L corporate office. This_will enhance command, control, and decision making. These large graphic displays present such information as Time / Event Logs, Vital Equipment Out-of-Service, Organization / Assignment Charts and Radiological Status Charts. The design of these displays takes into con-sideration size, location, visibility, readability, acces-sibility, and need for data.
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G. Protective / Emergency Systems I
Protective / emergency systems have been incorporated into the j design to ensure habitability and reliability of the TSC. A smoke detection system has been design.rd to alarm in the event of smoke in the TSC. A fire sprinkler system protects the TSC in case of fire. A Halon system, using a nontoxic gas fire suppressant that prevents damage to sensitive electronic equipment, will protect the communications equipment room. An automatic radiation detector at the air intake to the TSC will activate the flow of outside make-up air to the HEPA and charcoal filter systems. The filter systems will have an integral fire alarm and deluge system to protect them in the event of fire. To determine radiation dose rates and airborne radioactivity concentrations in the TSC on a continuous basis, portable radiation monitoring equipment will be maintained.
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- .f J e EMERGENCY PEPSONNEL KEY LEGEND AATt, - ACCtDENT ASSEZMENT TEkA LEACER l l STANDARD OMICE CE4K CGTL - DOSE PROJECTION TEAIA LEADER l l SJNGLE PEDESTAL UCs EC r EMEF<,ENCY COMMUNICATIONS g
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EMERGENCf PLANNING SPECALIST REFERENCE TABLE ERD - DAERGENCY REPAIR 0; RECTOR O OrFiCE SwivE' C ^iR FATL- ARST A30 TEAM LEACER O OFFICE SCE CHAIR LSD - LOGISTICS SUPPORT OtRECTOR BOOKCASE
. FILE CARNET .+
NRC - NUCLEAR REGULATORY COMMISSION 8 - 2 STEELCASE SHELVES PtJ7L* PLANT NONiTORINC, TEAM LLADER DOUBLE DOOR METAL STORACE CABINET i JO - PLANT OPERATIONS DIRECTER PP t0TL PERSONNEL PROTECTION (
ll l FOLOING TABLE" LECONTAtAINATION TEAM LEADER IC l CONSOLE
. CLOTH PARTITIONS RCD - RADIOLOGICAL CONTROL OtREC TOR
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, _ WALL CLOCK SEC - EITE EMERGENCY COORDINATCM SSC - SUPPORT SERVICES COORDINATOR O w^5te s" lA l APERTURE CARD REACCR / PKit t TCH STL- SECURIT( TEAN LEAOCR lwl DRAWING FILE 8 WATER COCLER
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- r SERVICE LIST
'84 FE3 21 All 31 James L. Kelley, Esquire John D. Runkle, Esquire 4
Atomic Safety and Licensing Board Conservation Council.of North Carolina U. S. Nuclear Regulatory Commission 307 Granville RoadC'C$Oif.GT $$via Washington, D. C. 20555 Chapel Hill, North CarolissN27514
- Mr. Glenn O. Bright M. Travis Payne, Esquire Atomic Safety and Licensing Board Edelstein and Payne U. S. Nuclear Regulatory Commission Post Office Box 12643
- Washington, D. C. 20555 Raleigh, North Carolina 27605 Dr. James H.' Carpenter Dr. Richard D. Wilson Atomic Safety and Licensing Board 729 Hunter Street
- U. S. Nuclear Regulatory Commission Apex, North Carolina 27502 Washington, D. C. 20555 Mr. Wells Eddleman
'. Charles A. Barth, Esquire 718-A Iredell Street Myron Karman, Esquire Durham, North Carolina 27705 Office of Executive Legal Director U. S. Nuclear Regulatory Commission Thomas A. Baxter, Esquire Washington, D. C. 20555 John H. O'Neill, Jr., Esquire Shaw, Pittman, Potts & Trowbridge _
. Docketing and Service Section 1800 M Street, N.W.
Office of the Secretary Washington, D. C. 20036 U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Dr. Phyllis Lotchin 108 Bridle Run Mr. Daniel F. Read, President Chapel Hill, North Carolina 27514 Chapel Hill Anti-Nuclear Group Effort Bradley W. Jones, Esquire 5707 Waycross Street U. S. Nuclear Regulatory Commission Raleigh, North Carolina 27606 Region 11 101 Marietta Street Dr. Linda Little Atlanta, Georgia 30303 Governor's Waste Management Board 513 Albemarle Building Robert P. Gruber 325 Salisbury Street Executive Director
- Raleigh, North Carolina 27611 Public Staff North Carolina Utilities Commission Ruthanne G. Miller, Esquire Post Office Box 991 Atomic Safety and Licensing Raleigh, North Carolina 27602 Board Panel U. S. Nuclear Regulatory Commission Washington, D. C. 20555 i
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