ML20004C802
| ML20004C802 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 06/01/1981 |
| From: | Burstein S WISCONSIN ELECTRIC POWER CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.A.1, TASK-TM GL-81-10, NUDOCS 8106050319 | |
| Download: ML20004C802 (60) | |
Text
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O Wisconsin Electnc ma cwar 231 W. MICHIGAN, P.O. BOX 2046. MILWAUKEE. WI 53201 June 1, 1981 1
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Mr. Harold R. Denton, Director G 'A Of fice of Nuclear Reactor Regulation W U. S. NUCLEAR REGULATORY COMMISSION g Og l
! Washington, D. C. 20555 m .( Mg y- n Gentlemen: uh
- DOCKET NOS. 50-266 AND 50-301 cu f >s /
POINT BEACH NUCLEAR PLANT UNITS 1 AND 2 /4; g M '
EMERGENCY RESPONSE FACILITIES l
In accordance with the requirements of NUREG-0737, Item II.A.1.2, as clarified in a letter to all licensees of February 18, 1981, (Generic Letter
- 81-10) from Mr. Eisenhut, we are herewith submitting the conceptual design l information for the emergency response facilities at Point Beach Nuclear Plant. Tne design information for the emergency response facilities appears on Attachment "A". The Emergency Organization and task functions appear in Attachment "B".
We are proceeding with construction of a technical support center
, (TSC) building as described in Attachment "A". We believe that the TSC and I
its ventilation, instrumentation and communications design will be completely satisfactory to the NRC. The building and its ventilation and electrical systems will be operable by January 1, 1982. Temporary instrumentation will be available at that time. The permanent safety parameter dispiry system will not be operational until approximately August, 1983.
The emergency support center as described in Attachment "A" (the
! emergency operating facility at Point Beach Nuclear Plant) is the existing Energy Information Center which will include a modified communications system.
The emergency support center modifications will be completed by January 1,1982.
Data Display and the Safety Parameter Display System conceptual design is provided in Attachment "C".
Three copies of this submittal have been provided to Mr. J. G. Keppler, Director, Region III Office of Inspection and Enforcement. .
Very truly yours,
^ (
Sol Burstein Executive Vice President %
I cc: NRC Resident Inspector Point Beach Nuclear Plant i(
8106 050 3 l}
ATTACHMENT "A" POINT BEACH NUCLEAR-PLANT EMERGENCY RESPONSE FACILITIES Items identified with_a single asterisk (*) correlate on a numerical basis with the " Documentation Required" section of Generic Letter 81-10,'while items identified with a double asterisk correlate to NUREG-0696 sections.
1.* The' task functions for the individuals in'the emergency organizatica listed in our Emergency Plan are independent of emergency classifi-cation. However, the number of. individuals who report to the emergency response facilities changes from emergency classification to emergency classification. This is reflected in the emergency organization charts which appear in our Emergency Plan Manual as Figure 5-3, Emergency Organization - Unusua) Event; Figure 5-4, Emergency Organiza-tion - Alert; Figure 5-5, Emergency Organization - Site Emergency; and Figure 5-6, Emergency Organization - General Emergency.
As the emergency becomes more severe, the emergency organization-becomes expanded.
Copies.of Figures 5-3', 5-4, 5-5,'and 5-6 have been attached as Attachment "B" to this letter. These figures also list the emer-gency response facilities to whi.:h each of the members of the i
emergency organization is required to report in a given emergency classification.
Also attached to this letter as part of Attachment B is a copy of Appendix A, " Emergency Response Organization Personnel Function and Responsibilities" of our Emergency Plan Manual. Appendix A includes charts listing the emergency response facilities, emergency response organization, and all the subgroups within the emergency organization. Appendix A also includes a nescription of functions, responsibilities and principal working relationships for all members of the emerger.cy organization.
2.1** Our general concept of location, design and operation of the l
emergency response facilities was outlined in a letter to the
- Secretary of the Commission dated February 18, 1981. By a letter l dated March 16, 1981, Mr. Stello acknowledged receipt of .our comment letter and indicated that our proposal would meet the criteria of NUREG-0696.
l At the Point Beach Nuclear Plant there are three physical facilities
( which we believe will meet the requirements of NUREG-0696. We now have under construction a building containing 18,000 square feet of floor space which will contain the - technical support center (TSC). Approximately one-half of this sqaure footage is below-l l
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grade, allowing habitation at any time after an accident. The rest of the building floor space is above grade and there is a remote possibility that it may not be habitable for a very short time during an accident when direct radiation could limit the time-of.
stay.
The technical support center will be the emergency operations work area for technical, engineering and senior mana;tment personnel.
The TSC will be the primary communications center for the emergency organization.
TSC personnel will, during an emergency, use the TSC data system to
- analyze plant, environmental and radiological parameters. This includes most of those functions described as emergency operating facility (EOF) functions in the criteria listed in NUREG-0696.
Portions of the TSC will be used for administrative, engineering and training purposes during normal operation. These normal operating.
functions will not degrade, but.will enhance the emergency prepared-ness and system reliability of the TSC. This normal operation use of the TSC will increase personnel familiarity with and normal upkeep of the systems, locations and operations of the TSC.
2.2** The walking distance between the control room and the TSC is about 90 seconds. The only security barrier between the TSC and the control room is the cardkey access door into the control room. The emergency support center (ESC) (the emergency operating facility for Poi'nt Beach Nuclear Plant), is a three-minute walk from the TSC .
including passing through the major security checkpoint for the, plant entrance. Anti-contamination clothing, respiratory protection equipment, and other protective gear will be kept in the TSC for use in travel from the TSC to the control room or the ESC, or during times that the TSC is deemed to have radiological conditions requiring protective equipment; although this is not anticipated.
The TSC areg for management, display, assessment, and persongel will-have 869 ft ; the NRC " private office" area will hgve 240 ft ; the records office area will have approximately 800 ft of-space which will be used for the recordkeeping, c3mmunications coordination, and administrative personnel. The 800 ft records office does not meet the habitability criteria immediately following a severe release but will, however, be habitable under almost. any emergency scenario.
Since the TSC building has 18,000 ft2 , the space available for use as a TSC'can be expanded by including other parts of the building.
3.1** A portion of the TSC tailding will be used for the on-site operations support center (OSC) as well. The OSC area will be separate from
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but on the same floor as the operations area of the TSC. The OSC is a staging area for personnel ccming to the site. The OSC provides s' an area'where the new arrivals can be briefed on current and' historical
- conditions of the plant prior to going on the job or being assigned to a new job.
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The TSC building also includes a backup health' physics station.for-analysis of environmental and plaut. samples for radiologiccl contasi-nagionorradioactivitylevels. The health phygics. station has 448- -
ft of floar spacei a count handlingfacilityof122ft{ngroomwith390.ft,andasmallsample' 2.4** Sufficient space will be available for'tts TSC data system, its use, j and its maintenance. Sufficient space will be available for unhindered ,
i use and maintenance of the communication and data transmission-equipment.
A separate room adequate for consultation by three people will be
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provided'for NRC personnel during an emergency. ,
2.5** The TSC building is a reinforced concrete' structure and has been designed to withstand 100 year-recurren- winds and 50 year floods. ,
l 2.6** The TSC will meet the same radiological' habitability criteria as the.
control room. The ventilation system will' function in a manner comparable to _the control rcom ventil ?. ion system. The ventilation -;
, - system' includes HEPA and charcoal filters. - Sufficient potassium ,
iodide is'available for use by TSC and OSC personnel. The. potassium iodide will be used only in accordance with our Emergency Plan Implementing Procedure EPIP.1.6, "Radioiodine Blocking and Thyroid.
Exposure Accounting."
The TSC will have air sampling equipment'with alarms for the purpose e of providing advance warning of a radiation hazard in the TSC: This equipment will have tye capability of detecting radiciodine in -
concentrations of 10 pCi/cc or more.
The Emergency Plan Implementing Procedures provide for transfer of the Management personnel of the TSC to the control room if for some unforeseen reason the TSC might become uninhabitable.
- 2.7** The TSC will be the primary communications center for the plant in the event of an emergency. The switchboarn for the in-plant. telephone.
system and outside normal and emergency telephone-line will be located in the TSC building. Reliable communications can be maintained l between the emergency response facilities and offsite agencies. In all cases, there are at least two methods of communication.
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3.* The existing switching equipment-in the plant has a battery backup j power supply and can therefore operate under power failure conditions.
I The TSC communications systems will include:
- Direct, dedicated line to NRC Operations Center in Bethesda, MD (red phone). This line will be in the TSC not in the NRC i
consultation room unless NRC will be responsible for all red phone communications whenever the TSC is activated.
! - Health physics network line for NRC use and contact with the individual responsible for making offsite dose projections.
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In-plant extensions designated as the lines to be used expressly for management direct communications between the TSC and the control room, and the ESC.
- Dial phones in an adequate number to provide access to onsite locations and offsite agencies.
A Gai-tronics system with handsets at all work stations provides intercommunications to'all areas of the plant including the TSC and OSC.
- Radio communications capability for communications with mobile monitoring teams, both onsite and offsite.
- Telephone, and NAWAS telephone lines to connect the TSC with the emergency operating centers in Manitowoc and Kewaunee counties.
Plant extension lines wit .. cess to outside lines available in the TSC for h u; use during an emergency.
- Facsimile transmission from the TSC building to NRC Operations. Facsimile transmission is not necessary between the TSC and the ESC. The walking time between the TSC abd ESC is such that the time to operate the machine for trar smission is longer than the walking time. Therefore, no provisions for facsimile trans-
. mission or receipt will be made in the ESC.
- Telephone jack for access to the dedicated line to the NRC Operations Center in Bethesda, MD.
Equipment, including sensors, data storage units, computers, and display systems have or will be installed.at Point Beach Nuclear Plant such that plant conditions can be analyzed. Some of the equipment such as sensors, data receipt and storage will be in the plant computer room in the control room building.
l The display systems will be located in the control room and TSC.
l i Signals for TSC use from sensors which provide signals to safety equipment will be isolated such that the performance of the safety equipment will not be compromised or degraded. The TSC electrical load will not degrade the capability or reliability of any safety-related power source.
The data storage systems are such that any power supply failure to the TSC or data storage system will not cause the loss of historical data which would be vital to the analysis of plant conditions.
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3.* A backup power supply for the TSC will be provided which allows for _
continuity of TSC functions after manual transfer to the backup supply fs made. The communications system has a-battey backup and alternate power supply. The acquisition and storage portion of the data system will have its own redundant power supplies separate .from the TSC power supply.
The design. availability goal for the data system including sensors, storage, computers, and displays is 0.99. Human factors engineering will be incorporated into the' data display systems.
4.* The techical data provided by the data display system as described in Attachment C will include.the following:
- Historical data on parameters sufficient'to provide the
- steady-state cperating conditions prior to the accident. This data storage and recall capability will be able-to reconstruct *
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the conditions of the plant for up to two hours prior to the event.
Parameters in sufficient detail'and real time such that the transient conditions producing the initiating event can be watched and analyzed in a timely manner.
- The storage capacity and data acquisition capacity-will be such -
that plant system dynamic behavior throughout the ce'.rse of an event up to-12 hours after the event can be recorded and maintained.
i The maximum sample frequency on any particular parameter will be one sample per second. The peak will be recorded at that maximum sample rate. The peak valve of.a very fast changing parameter can be inferred from the data on either side of the peak.
The TSC display system will er tain in alphanumeric or graphical form those plant system variables which are necessary to analyze plant conditions prior to, during and after an emergency event.
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These displays will include as parameters, in-plant radiological variables at various in-plant locations, meteorological information-and offsite radiological projections 'obtained from the first two parameters.
Where applicable, trend information and time / history displays will be included for some variables.
A complete and up-to-date set of design, technical, administrative
- and operational records are .ad will be maintained in the TSC i building. Since this set of records is in use during normal operation, familiarity by the plant staff, who compose the emergency organization, will be the norm.
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L Up-to-date, as-built drawings of.the plant are and will be maintained-in the TSC building ~readily accessible to
, emergency organization personnel.
Up-to-date records and documents available in the '
TSC building include:
- Technical Specifications Plast operating procedures Emergency operating procedures.
- Final Fccility Design & Safety Analysis Report Plant operating records Plant operations reactor safety committee (Manager's Supervisory Staff) records and reports 1
- As-built plant plans, schematics and diagrams showing
! conditions of plant structures and systems. : and in plant
, locations of systems 3.2** Habitability nf the OSC is the same as the TSC. The OSC and TSC 4
are both below grada and share a ventilating system.
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3.3** Communications systems will'be provided via a designated-plant telephone extension to the TSC. The OSC isiclose to 3
the TSC where plant supervision will be evaluating plant l conditions. .Due to the closeness of OSC personnel, plant management in the TSC will be able to easily communicate with first line supervision and workers with respect to their
. tasks and debrief them :following their work.
- . Communications between the OSC and the control room are
[ not necessary since the work direction and duty assign-ments for OSC personnel come from the'TSC. :The Gai-tronics will provide voice intercommunications to the control room, TSC and all other. areas of the plant
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and will provide a. backup to the telephone system.
l 4.1**- Due to the large size of the TSC building and proximity l
of the ESC to the TSC, the ESC will serve a lesser role
- than outlined in NUREG-0696.
At Point Beach Nuclear Plant there are an all-brick structure l
about 1/8 mile south of the plant used as the Energy Information l Center (EIC) and a small wooden building. located approximately one mile southwest of the plant at the site boundary,. called the site boundary control center'(SBCC). The emergency operations facility (EOF) functions at Point Beach Nuclear.
Plant will be done at the emergency support center.(ESC),
known during normal operation as the EIC and at an enlarged 4 and improved site boundary control center to be located adjacent to the existing SBCC.
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The ESC will serve as the primary meeting point for Federal,
' State, Local, and Corporate' officials. The upgraded SBCC will serve as a health physics and security control point at the normal site entrance during an emergency. The SBCC~would
~ house emergency materials and a basic health physics laboratory '
for screening of environmental samples. Space will also be provided for protective clothing and other health physics supplies. ESC personnel, in conjunction with TSC personnel assigned to dose assessment, will coordinate the radiological and environmental assessment.
6.* Personnel assigned to the .TSC will make a determination as to what public protective actions should be recommended. ESC personnel will provide the TSC recommendations to offsite
- peuonnel.
The ESC will not have technical data display systems or SPDS.
Personnel in the TSC will be making the technical decisions and providing recommendations to the ESC. People in the ESC may not have the familiarity with the display systems to make appropriate evaluations. It is the responsibility of the Site Manager assigned to the TSC to relay the important informa-tion and recommendations to the ESC. For the same reaons, the keeping of up-to-date plant records in the ESC is not imoortant to the operation of the ESC. The control of records in the TSC can minimize the potential for abuse or misuse of confidential and/or proprietary information. Also, minimizing the numbers of documents reduces, the probability of, incorrect use of superceded records.
t The primary function of ESC personnel is the enordination of
- l. corporate and offsite emergency response. The facilities
! for performance of this essential function are the communi-I caticus systems. This system will be provided.
The ESC will have space available for liaison personnel from offsite agencies. Limited communications facilities will be provided to the offsite agencies.
Normal industrial security exists at the ESC during normal operation. During an emergency, increased security will be l
established at the site boundary to limit access to the site i and restrict unauthorized personnel from the ESC.
For low severity emergencies, the ESC can be used for limited numbers of media personnel. For more severe a.mergencies, arrangements have been made for an emergency news center in the city of Two Rivers, nine miles to the south of the plant.
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4.2** As mentioned above, the ESC is located close to the plant and the SBCC is near the south site boundary. The location of the ESC provides for easy availability of all plant personnel for face-to-face discussions with ESC staff and easy data transmittal, if necessary. This allcws for easy access to all data and records within a five-minute walk from the ESC j
. Eto TSC. Management in the TSC and ESC can easily have l face-to-face conferences on any plant or environmental matter. l The SBCC allows for easy access to the offsite and onsita environment for sampling by the health physics survey _te 5s.
The SBCC also provides space for increased security personnel during an emergency situation. '
I The ESC and SBCC will not have habitability as a design criteria.
The backup for the ESC, if it oecomes uninhabitable, will be the SBCC. If the SBCC is unir. habitable, the Two Creeks Town Hall, two miles west /corthwest of the plant, will provide the functional capabilities of the ESC and some of the functions of the SBCC.
Guidance for habitability of an emergency response facility is contained in the Point Beach Nuclear Plant Emergency Plan Manual.
The ESC is a well-engineered, reinforced concrete building which will withstand the most adverse conditions reasonably expected to occur during the design life of the plant.
The heati. ,and ventilating system will not be fitted with HEPA filters. The area of the building in which communi-cations and decision-making will take place is in a,part of the building which is totally below grade, or. slightly exposed above grade in a direction facing away from the plant.
Therefore, the ESC function will not have to be-interrupted for most cases for which protective actions might be required.
TheSBCCwillbeabuilgingoflightindustrialdesign.
It will have about 3000 ft floor space.- This will include facilities for security, health physics, management, health physics survey teams, and a basic health physics laboratory for the screening of environmental samples.
The location of the SBCC provides space in the optimum location for performance of the functions of the SBCC.
The SBCC is not designed to meet the 100-year occurrence criteria for ssvere weather. The functions of people assigned to the SBCC can be transferred to the ESC or the Two Creeks Town Hall in the event of the loss of use of the SBCC.
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l' 4.5** - The ESC will be staffed to coordinate onsite and offsite activities
't; to effact Federal, State and Local offsite emergency plans..
The SBCC will be-staffed with: security personnel to augment security.
measures in and around the plant, to control-ingress to-and egress from the plant and to coordiaate personnel accountability. .The SBCC
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will. also be. staffed with health physics management and personnel.to l assess offsite and onsite_(exterior to the plant) radiologicalL conditions of the environment. The offsite dose projections will be ,
done in the TSC. SBCC field survey teams'will be used to confirm the conservatism in the projections.
-4.4** The-floor, space of the ESC }s divided into.three levels. The upper-most, ground . level (1045" ft -) is designated for ESC management' and NRC personnel. The' lower two levels sill be used for offsite agency personnel and communications yith onsite and offsite personnel. The' lowest level provides 1200 ft for offgite t.gencf.es and corporate management. The middle level (1180 ft ) at-the ESC has facilities ;
for the handling of a limited. number of media personnel (4.7**).
The ESC will not have a data displayfsystem.or a SPDS (4.8**). -The functions of personnel in the ESC do not require the immediate l- availability of-the parameters cantained in these-display systems
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(4.7**). If there is any need.for the data displayed on the data.
- l. display system of SPDS, the information can be obtained via the phone systems or by walking to the TSC. The walk from=the ESC to the TSC takes. around three minutes including going through the security system at the. entrance gatG to the plant.
l 4.5** The ESC and SBCC will have' portable monitoring systems available for use as a radiation monitor. These systems.will be ab l levelsofradioactivematerialintheairdown;to10}e.to-detect pCi/cc.
l 4.6** The ESC.will have telephone communications available to the TSC, thel L
control room, the NRC, and the State and Local emergency operations centers. The ESC will also have radio consunications available to I. the TSC and the control' room. The backup communications system'to the State and Local emergency operations center is via the NAWAS intercommunications netwock in the TSC. The.NRC can be reached on the NRC emergency notification system in the TSC and via the'NRC health physics network in the TSC. Communications with the SBCC is-via private telephone lines and a radio backup. The SBCC can j.
communicate with the control room, the TSC and ESC via prvate I telephone lines. SBCC personnel maintain radio communications with ,
onsite and offsite monitoring teams.
4.9* Records and drawings will not be stored in the ESC; however, if required, they will be available in the ESC by a walk to the TSC.
The ESC also has a copy of the Emergency. Plan Manual and Emergency.
Plan Implementing Procedures- The Emergency Plau has offsite population distribution data and evacuation plans included in Appendix J.
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8.0** The emergency response facilities will work as an' integrated team during the emergency situations. The primary operational control of' the plant and its systems will take place in the control room. The TSC will provide technical support for the control room, the ESC and the SBCC. The TSC will provide onsite and offsite coordination and information dissemination in an emergency of the Alert classifi-cation and prior to the activation of the ESC and SBCC in any -
' e~ergency which would be either a Site Emergency or General-Emergency.
Upon activation, the ESC would take over the'respecsibility for coordination of communications with onsite, offstte igencier, and the corporate headquarters. The purpose of this cootdination is.the overall function of the emergency organization and its response to the emergency. The operation of the SBCC will augment the radiological assessment being done in the TSC and t' e security response to the emergency. It must be emphasized that it is the intention of Wisconsin Eeletric that, although the capability exists, normally, communications will not take place between the control room and the ESC or SBCC. Control room personnel cannot be bothered with requests for information from many sources. Nor, should any question arise as to who is responsible for issuing directives to the control room. Senior plant management who are familiar with the plant, its operating characteristics, its. Tech-nical Specifications, to whom control room personnel are normally responsible, and who have'all important parameters available will be in the TSC. It is the function of the TSC to serve as the single source of information of plant. status to non-plant personnel and the single source of directives for plant personnel. This interface is:
essential to minimize confusion which may arise from reports of data
.. collected at different times or from different methods of measurement or suggestions or recommendations for actions from several sources.
The operation of the emergency response facility systems will not degrade the. performance or reliability of any reactor safety or control system, or any safety-related displays in the control room.
The ERFs will provide the technical and administrative augmentation necessary for the expeditious mitigation of any emergency situation and protection of health and safety of the offsite population.
Actions of the control room will not degrade any functional operation of the ERF systems.
9.0** The Quality Assurance Division of Wisconsin Electric will verify and-valioate the design development, qualification, and installation of-
- i. the SPDS, TSC and ESC facilities. The issue of Technical Specifications for the specification of compensating actions to be t? ken when the SPDS, TSC and ESC are not operational will be 4
addressed upon completion of the buildings and data systems. These specifications will include surveillance requirements for determination of the ERF facilities.
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ATTACIDENT "B" 3
This attachment includes copies of the emergency organization charts for each. emergency classification. The attachment also includes i descriptions of responsibilities and functions for each of the personnel listed in the emergency organizations. .
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Page A-1 APPENDIX A EMEEGENCY RESPONSE ORGANIZATION PERSONNEL WNCTION AND RESPONSIBILITIES INDEX
! age I. Emergency Facilities A-3 II. Emergency Response Organization A-4 III. Emergency Director A-5 IV. Emergency Support Manager A-6 V. Administrative and Logistics Manager A-8 VI. Emergency News Center Director A-9 VII. Site Manager A-10
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- VIII. Plant Operations Group (diagram) A-12 IX. Plant Operations Manager A-13 f
X. Shift Supervisor A-15 j
i XI. Shift Support Coordinator A-16 XII. Maintenance Supervisor A-17 XIII. Training Supervisor A-18 XIV. Security Supervisor A-19 XV. Technical Support Group (diagram) A-20 XVI. Technical Support Manager A-21 XVII. Instrument rnd Control Supervisor A-23 XVIII. Chemistry / Health Physics Supervisor A-24 XIX. ' Systems Analysis and Procedural Support A-25 Coordinator
P Page A-2 APPENDIX A (Cont'd)
INDEX P_ age 1
XX. Core Physics Coordinator 'A-26 XXI. Administrative Supervisor A-27 XXII. Data Processing Coordinator A XXIII. RadCon/ Waste Management Group (diagram) A-29 XXIV. ~ RadCon/ Waste Manager A-30 XXV. Health Physics Director A-31 XXVI. Licensing Support Coordinator A-32 XXVII. Radwaste Technical Support Coordinator A-33.
XXVIII. Design, Construction, and Planning Support Group _A-35
- (diagram)
XXIX. Design, Construction, and Planning Manager A-36
. XXX. Director, Quality Control A-37 XXXI. Utility Engineering Director .A-38 I .
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I Page A 3 CONTROL ROCH TECID ICAL PROTECTED SUPPORT CENTER AREA Sm BOUNDW EMELENCY OPERAIIONS ON SITE C0h""ROL CENTER SUPPORT CENTER SUPPORT CENTER EMr. asst.wx NEAR SITE NEWS CENTER CORPORATE HEADQUARTZRS - 0FFSITE NSSS SUPPLIER ARCHITECT
' EIGINEER OTHER SUPPORT l
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APPENDIX A.I 1
Page A-4 ENEMENCY DIRECTOR EMEEENCY ENEMENCY AIMINISTRATIVE NEWS CENTER SUPPORT AND I4GISTICS DIRECTOR MANAGER MANAGE 7 SITE DESIGN, MANAGER CWSTRUCTION, AND .
PIANNIE MANAGER TECHNICAL PIANT RADCON/ WASTE SUPPORT OPERATIONS MANAGER MANAGER MANAGER l
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Appendix A-III Emergency Director REPORTS TO: President, Wisconsin Electric Power Company LOCATION: Corporate Headquarters SUPERVISES: WEPCO General Office emergency response and. recovery management-BASIC FUNCTIONS:
Responsible for the overall canagement of_ WEPCO General Office emergency response and Recovery Operations; with the primary objective of providing the necessary management and technical support for the PBNP emergency response and recovery effort.
PRIMARY RESPONSIBILITIES:
- 1. Coordinates WEPCO General Office emergency response and Recovery Operations in support of the plant's emergency r + and recovery effort.
~
' 2. Provides the supervision for the administrative and technical support of the emergency response and Recovery Operations.
PRINCIPAL WORKING RELATIONSHIPS:
- 1. The Emergency Support Manager for the overall direction and coordination of the emergency response and Recovery Operations to assist PBNP resources.
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Page A-6 APPENDIX A - IV EMERGENCY SUPPORT MANAGER -)
( REPORTS'TO: Emergency Director LOCATION- Emergency Support Center
.s SUPERVISES: Operation of the Emergency Support Center
, BASIC FUNCTIONS:
1 % s Coordinates the PBNP Emergency Plan, with respect tx> both offsite radiological consequence assessment and the interaction with the remainder of Emergency. Plan arrangements specific to the plant.
PRIMARY RESPONSIBILITIES:
, 1. Establishes communications with che Technical Support Center and
! obtains information on the diagnosis and prognosis of the accident condition, the estimates of radioactive material releases, and -
the prevailing meteorological.ccaditions-. 'A communications channel is to remain in use for this information-as long as is
, ,. necessary.
- 2. Maintains commun'ications with the offsite authorities designated ~
I in the Emergency Plan and relates the accident diagnosis and prognosis information necessary for the offsite authorities to
~
implement their emergency plans.
- 3. Assists in organizing and dispatching onsite and offsite radio-logical monitoring teams as required.
- 4. Interprets the offsite radiological data obtained and updates the ..
Technical Support Center and offsite authorities with the results, in terms of both real-time measurements and, to the extent possible, projected radiological exposures.
- 5. Arranges for any further onsite and offsite radiological evaluations as required.
- 6. Arranges for and dispatch any special assistance or service required (e.g., radiological measurement or protection equipment, onsite emergency medical treatment, etc).
- 7. Maintains con' trol over personnel assembled at the Emergency Suppott Center and assesses and provides for any considerations necessary for their rafety.
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Page A-7
- 8. Maintains communications with the Emergency News Center and coordinates the flow of information between the Plant and Corporate Headquarters.
- 9. Receives any responding representatives from offsite emergency agencies and assists in their information and communications needs.
- 10. Relates all of these actions to the remainder of the emergency response organization.
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e Page A-8 APPENDIX A-V ADMINISTRATIVE AND LOGISTICS MANAGER REPORTS TO: Emergency Support Manager LOCATION: Eastgency Support Center COORDINATES: Administration and Logistics BASIC FUNCTIONS:
Provides administrativa, logistic, communications, and personnel support for the emergency response and Recovery Operations.
PRIMARY RESPONSIBILITIES:
- 1. Administration - Provides the general office support functions including typing, . reproduction, office supplies, and office furniture. Special items like photography services and facility /
area maps may also be required.
- 2. Accommodations - Handles the arrangements for motel, airline,' and f- trailer. Performs the functions of registration and general personnel orientation. ,
- 3. Communications - Leets the telephone requirements of the overall l
emergency and recovery organization and provides special radio l requirements such as mobile units and radio pagers. An emergency /
l recovery organization telephone directory will be maintained.
- 4. Purchasing - Functions as the emergency and recovery organization purchasing a-ent with responsibility for contract negotiation /
l administration and material control.
I l S. Finance - Administers the petty c' ash fund and expense accountc.
l Provides for handling of payroll matters.
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- 6. Commissary - Provides for food deliveries, operation of the field kitchen, and for trash disposal.
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- 7. Human Resources - Meets the manpower request needs of the emergency and recovery organization both in the technical and craft disci-plines. Ensures that clerical support is available and provides labor relations assistance as required.
- 8. Transportation - Staffs the motor pool facility and provides vehicles for the emergency and recovery organization. Maintains shuttle services between surrounding motels and airports. Supplies l special transportation (helicopters, buses), as required.
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Page A-9 APPENDIX A-VI EMERGENT:Y NEWS CENTER DIRECTOR REPORTS T_0: Emergency Support Manager LOCATION: Emergency News Center COORDINATES: Personnel assigned to Public Affairs and Information
, PRIMARY RESPONSIBILITIES:
- 1. The Emergency News Center Director is the ranking public information representative at the Emergency News Center who relays information to other employees at the center, supervises all communications operations at the center, and distributes all news releases and statements. He coordinates information at the Emergency News Center with his counterparts from local, State, and Federal agencies and with other companies involved with the Emergency, and provides a means of meeting the media's needs.
i j 2. The Emergency News Center Direc:or is identified as the official company spokesman for the Emergency, with the responsibility for
- arranging interviews, statements quoted in press releases or ot,her announcements, and for presiding at forma'. press couferences.
- 3. The Emergency News Center Director assures that accurate inforiination is distributed to the nuclear power industry through the Atomic Industrial Forum.
PRINCIPAL WORKING RELATIONSHIPS
- 1. The Emergency Support Manager for information on all press statements.
- 2. The Site Manager as available for up-to-date technical information on the plant snd plant operations.
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I' Page A-10 APPENDIX A-VII .,
SI'IT MANAGER REPORTS TO: Emergency Support Manager LOCATION: Emergency Support Center / Technical Support Center SUPERVISES: Plant Operations, Technical' Support, and RadCon/ Waste Managers BASIC FUNCTIONS:
Responsible for-implementation and management of overall plant emergency-
. response and Recovery Operations; with.the primary objective of placing the plant in a scfe shutdown condition, and then recovering the plant in a manner which minimizes any adverse health and safety effects on-the public, employees and contractors.
PRIMARY RESPONSIBILITIES:
- 1. Responsible for overall management of all in-plant operating and Emergency Plan Implementing Procedures in support of the objectives of the emergency response and Recovery Operation. -
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- 2. Approves changes in the emergency classification assessments based on plant conditions, site meteorology and radiological data.
l l 3. Appears at press conferences as available in support of the Emergency News Center Director to handle technical que.stions raised by the press.
- 4. A., proves the analysis and the development of plans and procedures which are conducted in direct support of plant operations personnel.
- 5. Reviews and approves plans and procedures to process and control liquid, gaseous, and solid wastes in a manner consistent with overall emergency response and Recovery Operations.
- 6. Serves as chairman of any plant review committee established for ,
l the emergency response and Recovery Operations. !
PRINCIPAL WORKING RELATIONSHIPS:
- 1. Emergency Support Manager for coordination and direction of implementation of the PBNP Energency Plan and Emergency Plan
, Implementing Procedures, particularly with respect to offsite l radiological consequence assessment as a result of Recovery
- Operations.
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Page A-11
.2. Emergency News Center Director to provide technical assistance for press conferences.
- 3. Design, Construction, and Planning Manager for coordination of any design, construction, and planning activities required by-emergency response and Recovery Operations.
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APPENDIX A-II PLANT OPERATIONS MANAGER REPORTS TO: Site Manager LOCATION: Technical Support Center / Control Room SUPERVISES: Plant Operations Support Staff, Jhift Supervisor, Shift Support Coordinator, Maintenance Supervisor, Security Supervisor, and the Training Supervisor.
BASIC FUNCTIONS:
Responsible for implementation of in-plant emergency response and recovery activities with the objective of taking the plant to a safe shutdown condition in a manner which minimizes any adverse health and safety effects on the public, employees and contractors.
PRIMARY RESPONSIBILITIES:
- 1. Responsible for the implementation of all in-plant operating and Emergency Plan Implementing Procedures in support of the objec-tives of the emergency response operation.
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- 2. Implements emergency classification procedures by assessing plant conditions, site meteorology, and radiologicsl data.
- 3. Responrlble for all in plant maintenance activities utilizing normal plant maintenance and support personnel.
- 4. Maintaint an effective in plant security program in support of the emer gency response and Recosary Operations.
- 5. Responsible for training of in-plant personnel on the required emer- Icy operating and maintenance plan and procedures in support of the emergency response and Recovery Oparations.
- 6. Provides licensed personnel in direct support of plant shift operations personnel.
l
- 7. Implements in plant plans and schedules to meet the objectives of l
the emergency response and Recovery Operations.
l 8. Provides informstion and recommendations to the Site Manager concerning future operations that could affect the plant or the environment.
i i _ _ ,
l Page A-14 PRINCIPAL WORKING R2LATIONSHIPS:
- 1. - Technical Support Manage concerning review and approval of proposed modifications to procedures, systems, and equipment.
- 2. RadCon/ Waste Manager concerning plans and procedures to process and control liquid, gaseous, and solid wastes.
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_Page A-15 APPENDIX A-X SHIFT SUPERVISOR REPORTS TO: Plant Operations Manager LOCATION: Control Room SUPERVISES: Normal plant operations personnel and the emergency response organization shift support personnel.
BASIC FUNCTIONS:
Responsi*:le for the safe operation of the plant including implementation of normal and emergency procedures and instructions to safely place and maintain the plant in a rafe shutdown condition.
PRIMARY RESPONSIBI,LITIES:
- 1. Directs the activities of the normal plant operations personnel and the emergency response organization shift support personnel.
- 2. Operation of the plant in compliance with all normal plant procedures,
- directives, technical specifications, and emergency procedures.
- 3. Provides information and recommendations -on accident response t o the Plant Operations Manager.
- 4. Responsible for monitoring plant parameters and plant conditions.
- 5. Responsible for system valve alignment and equipment operations.
- 6. Responsible for interfacing with the emergency response crganiza-tion in support of the emergency response operations.
l l PRINCIPAL WORKING RELATIONSHIPS:
- 1. Maintenance, Instrument and Control, Training Engineer, and Security Supervise .s in support of the emergency response and Recovery Operatir:.s.
- 2. Shift Support Coordinator regarding effective utilization of the i shift support personnel.
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' Page A-16 APPENDIX A-XI SHUT SUPPORT COORDINATOR .
REPORTS'TO: ~ Plant Operations Manager F ATION: Technical. Support Center COORDINATES: Emergency support personnel assigned to the plant operations group.
BASIC FUNCTIONS:
Coordinates with the Shift Supervisor effective utilization of the emergency support personnel assigned to the plant operations group.
PRIMARY RESPONSIBILITIES:
- 1. Provides support to plant operations in monitoring plant-parameters and analyzing plant conditions.
- i. 2. Provides support to plant operations in system valve alignment and equipment operations.
'( e 3. Assists in coordinating the emergency response and recovery organization" objectives requirids implementation by the plant operations group.
PRINCIPAL WORKING RELATIONSHIPS:
- 1. Shift Sepervisor regarding the most effeccive utilization of support personnel.
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Page A-17 APPENDIX A-XII MAINTENANCE SUPERVISOR i
REPORTS TO: Plant Operations Manager LOCATION: Technical Support Center SUPERVISES: Maintenance personnel in support of repair, installation, and modification of maintenance equipment.
BASIC FUNCTIONS:
Responsible for the repair of installed equipment (other than instru-ment and control equipment), and the installation of modifications to existing equipment in support of the emergency response and Recovery Operations.
PRIMARY RESPONSIBILITIES:
Directs maintenance personnel in the repair of defective equipment I
! 1.
in support of the emergency response and Recovery Operations.
,h 2'. Directs the normal maintenance personnel in the installation of modifications to existing equipment in support of the emergency lN response and Recovery Operations.
- 3. Secures necessary electrical power and' mechanical equipment to assist emergency _ response and Recovery Operations.
PRINCIPAL WORKING RELATIONSHIPS:
- 1. Shift Supervisor in the repair of maintenance equipment and regarding the installation of modifications in the maintenance.
j area.
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Page A-18 APPENDIX A-XIII TRAINING SUPERVISOR REPORTS 'IO: Plant Operations Manager-
, IIV'ATION: Technical Support Center SUPERVISES: Training persor.nel responsible for procedural and other i training in support of the emergency response and Recovery l Operations.
l BASIC FUNCTIONS:
Responsible for coordinating the training requirements of all in-plant personnel associated with the emergency response and Recovery Operations.
PRIMARY RESPONSIBILITIES:
- 1. Directs the plant training personnel to provide training in direct support of the emergency response and Recovery Operations.
- 2. Provides the necessary training equipment and facilities to effectively support the training needs of the plant.
i PRINCIPAL WORKING RELATIONSHIPS:
i
! 1. Shift Supervisor regarding the training needs of the shift personnel
! in support of the emergency response and Recovery Operations.
- 2. I&C Supervisor, Maintenance Supervisor, Chemistry / Health Physics Cupervisor, Security Supervisor regarding training needs on out-of-normal procedures in their areas.
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Page A APPENDIX A-XIV SECURITY SUPERVISOR REPORTS To: Plant Operations Manager LOCATION: Technical Support Center / Security duilding SUPERVISES: Plant Security Personnel f
BASIC FUNCTIONS:
l Directs the normal plant security personnel to provide required in-plant security.
I PRIMARY RESPONSIBILITIES:
- 1. Directs the normal in plant security personnel in maintaining the plant security system in support of the emergency response and Recovery Operations. ,
- 2. Responsible for coordinating onsite personnel accountability with assistance from plant supervision during emergency situations.
I 3. Responsible for personnel evacuation and restricting access.to secured areas.
i PRINCIPAL WORKING RELATIONSHIPS:
l 1. All in plant supervisors regarding emergency response and recovery activities requiring security protection.
- 2. All emergency response organization groups regarding security requirements for personnel requiring access to the plant.
- 3. Coordinate onsite evacuation routes with Chemistry / Health Physics Supervisor.
4 Law enforcement agency personnel to oaintain control of potential trespassers and to establish sppropriate roadblocks. ,
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Page A-21 APPENDIX A-XVI TECHNICAL SUPPORT MANAGER REPORTS TO: Site Manager LOCATION: Technical Support Center SUPERVISES: Technical Support Group Personnel BASIC FUNCTIONS:
Responsible for analysis and the development of plans and procedures in direct support of plant operations personnel with the objective of placing the plant in a safe shutdown condition in a manner which minimizes any adverse health and safety effects on the public, employee and contractors.
He provides a central facility for the collection, retention, retrieval, and transmitting of plant and local environmental parameters.
PRIMARY RESPONSIBILITIES:
- l. Analyzes instrument and control problems, determines alternates, and designs and coordinates the installation of short-term instrument and control modifications.
- 2. Responsible for all chemistry and health physics activities onsite by coordination of onsite sampling programs, dose assess-ment, dose management and radiation protection programs.
- 3. Analyzes problems, determines alternatives, and develops plans in the area of system operations.
- 4. Analyzes conditions and develops guidance for plant shift opera-tions personnel for the protection of the core.
- 5. Develops out-of-normal operating and emergency procedures in direct support of plant shift operations personnel.
- 6. Provides a central facility for the collection, retention, re-trieval, and transmitting of plant and local environmental pare-meters.
I i 7. Helps resolve questions concerning plant licensing requirements with h7C representatives.
PRINCIPAL WORKING RELATIONSHIPS:
- 1. Plant Operations Manager regarding implementation of the Emer-gency Plan and Emergency Plan-Implementing Procedures.
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Page A-22
- 2. RadCon/ Waste Manager regarding any plant manipulations that might affect in-plant radiation or waste inventory levels.
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Page A-23 APPENDIX A-XVII .
d INS 11tLHENT AND CONTROL SUPERVISOR REPORTS T0_: Technical Support Manager IDCATION: Technical Support Center SUPERVISES: Plant Instrument and Control personnel BASIC FUNCTIONS:
Responsible for analyzing problems, determining alternatives, develop- ~
ing emergency plans and the repairing of installed instrument and control equipment, and for the design and installation of modifica-tions to existing equipment in support of the emergency response and Recovery Operations.
PRIMARY RESPONSIBILITIES:
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- 1. Analyzes instrument and control problems and develops plans for how the plant operations personnel can continue to monitor and' control plant parameters.
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- 2. Designs and coordinates the installation of modifications required to allow continued monitoring and control of plant parameters.
- 3. Directs the normal instrument and control personnel in the repair of defective equipment in support of the emergency response and Recovery Operations.
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- 4. Directs the normal instrument and control personnel in the installa-tion of modifications to existing equipment in support of the i emergency response and Recovery Operations.
PRINCIPAL WORKING RELATIONSHIPS:
- 1. Shift Supervisor in the repair of instrument and control equipment.
- 2. Systems Analysis and Procedural Support Coordinator regarding required instrument and control procedure development.
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Page A-24 APPENDIX A-XVIII CHEMISTRY / HEALTH PHYSICS SUPERVISCR
_ REPORTS 'IV: Technical Support Manager LOCATIg{: Technical Support Center SUPERVI9E_S: Plant Chemisti, 'iealth Physics personnal in support of -
health physics / chemistry / meteorology and procedures during l
the emergency response and Recovery Operations.
BASIC FUNCTIONS:
i Responsible for directing the Chemistry / Health Physics Staff in accumulat-~
ing onsite radiation / chemical data, dose assessments and radiation ,
protection programs-in support of the emergency response and Recovery Operations.
PRIMARY RESPONSIBILITIES:
- 1. Directs the normal in-plant Chemistry / Health Physics personnel in monitoring, controlling, and evaluating plant chemical, radiological,
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and meteorological conditions.
- j. 2. Provides radiation protection and ALARA training, respiratory
' equipment training, and in-plant whole body counting,.-and de-contamination. .
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l 3. Performs radiation protection activities as required in support of the emergency response and Recovery Operations.
- 4. Responsible for procedures for reentry into potentially highly contaminated areas or areas with high radiation levels.
PRINCIPAL WORKING RELATIONSHIPS:
l l 1. Health Physics Director in satters affecting offsite rt.diation measurement data, dose assessment and wate management processing.
- 2. Maintenance and I&C Supervisors in support of mainteuance/ instrument and control repair / modifications with radiological implications i
affecting the normal emergency response and Recovery Operations.
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- 3. Security Supervisor in providing radiological monitoring in i support of ev'acuation efforts.
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Page A-25 APPENDIX A-XIX SYSTEMS ANALYSIS AND PROCEDURAL SUPPORT C00RDINA11)R REPORTS TO: Technical Support Manager LOCATION: Technical Support Center COORDINATES: Support personnel analyzing problems and developing plans in the area of systess and equipment operations. Support personnel developing operating and emergency procedures.
BASIC FUNCTIONS:
l Analyzes probleu and develops plans associated with the operation of plant systems and equipment. Develops out-of-normal operating andi emergency procedures for plant operations personnel.
PRIMARY RESPONSIBILITIES: e
- 1. Analyzes problems associated with the operations of plant systems and equipment and develops plans to mitigate those problems.
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- 2. Revises or rewrites existing ' operating and emergency procedures as required to reflect existing accident conditions.
- 3. Converts plant recovery plans into clear, concise, out-of-normal operating and energency procedures for use by.the plant operations group.
PRINCIPAL WORKING RELATIONSHIPS:
- 1. Shift Support Coordinator regarding systems and equipment problems that need resolution.
- 2. Technical Support Manager regarding recommendations on how to contend with systems and equipment problems.
j
- 3. Shift Support Coordinator regarding required out-of-normal operating and energency procedures.
- 4. Core Physics Coordinator regarding required operati2g procedures to protect the core.
- 5. I&C Supervisor regarding procedures on use of modified controls, F alternate ins'truments, and out-of-normal monitoring and control ,
requitements, i
Page A-26 APPENDIX A-XX CORE PHYSICS COORDINATOR REPORTS TO: Technical Support Manager LOCATION: Technical Support Center BASIC FUNCTIONS:
t l Analyzes core parameters and develops guidance for the plant shift operations personnel on protection of the core.
PRIMARY RESPONSIBILITIES:
- 1. Analyzes core parameters to determine current conditions of the Core.
- 2. Reviews proposed plant operations with respect to the effect on core conditions.
- 3. Develops recommendations for plant operations that would effect safer core conditions.
r-PRINCIPAL
- WORKING RELATIONSHIPS:
l
- 1. Technical Support Manager and Site Manager regarding proposed plant operations to effect safer core conditions.
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Page A-27 APPENDIX A-XXI ADetINISTRATIVE SUPERVISOR REPORTS TO: Technical Support Manager LOCATION. Technical Support Center BASIC FUNCTIONS:
Supervises clerical personnel assigned to the Technical Support Group and coordinates the Technical Support Group needs for communications, office supplies, personnel, and office equipment with the Administrat.4 ' -
and Logistics Manager.
PRIMARY RESPONSIBILITIES
- 1. Provides typing, filing, and office equipment operation to all areas within the Technical Support Group.
- 2. Coordinates with the Administration and Logistics Manager the Technical Snoport Group needs for additional communications, equipment, office supplies, office equipment, etc.
PRINCIPAL WORKING RELATlt.,. SHIPS: . ,
i
- 1. Technical Support Manager and all Technical Support Group Staff regarding administrative support needs and staffing needs.
- 2. Administration and Logistics Manager regarding filling of the Technical Support Group administrative and <3taffing needs.
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Page A-28 APPENDIX A-XXII DATA PROCESSING COORDINATOR REPORTS TO: Technical Support Manager LOCATION: Technical Support Center COORDINATES: Data Processing BASIC FUNCTIONS:
Accumulation, retention, retrieval, and retransmittal of information-needed by the emergency responsa organization.
PRIMARY RESPONSIBILIT.ES:
- 1. Provides for the accumulation, retention .and retrieval of plant information and local environmental parameters.
- 2. Transmits inforattion needed by the emergency response organization.
- 3. Serve- *= a single location for the acquisition of data resulting I in mi- --*arence with plant operations.
t PRINCIPAL WORKING nr.m . .odIPS: >
- 1. Plant Operations Manager regarding accuisition of needed plant information and environmental parameters.
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- RADCON/WASfE l MANAGER 1
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PH SICS SUPPORE TECHNICAL i DIRECTOR COORDINATOR SUPIORT j COORDINATOR a
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i APPENDIX A-XXIII l
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i Page A-30 f
.1PPENDIX A-XXIV RADCON/ WASTE MANAGER REPORTS TO: Site Manager-LOCATION: Emergency Support Center SUPERVISES: Waste Systems and the R'dCon/ a Waste Management Group BASIC FUNCTIONS:
i Responsible for the development of plans and procedures to process and
- control liquid, gaseous, and solid wastes in a manner consistent with the emersucy response and recovery organization objectives and to minimize any adverse health and safety effects on the public.
PRIMARY RESPONSIBILITIES:
- 1. Develops plans and procedures for sampling and processing liquid, gaseous, and solid wastes.
. 2. Develops any required modifications to plant wasta systems and
, conceptual designs of new systems and equipment.
w
- 3. Provides health physics support offsite by coordination of offsite
, sampl'ing programs, dose assessments, dose management, and r d iation protection and ALARA programs.
- 4. Provides information and recommendations to the Site Manager concerning future operations that could affect the plant or the environment.
PRINCIPAL WORKING RELATIONSHIPS:
1
- 1. Site Manager and Technical Support Manager regarding implementa-tion of plans to obtain samples and process liquid, gaseous, and solid wastes, and to obtain data on plant waste systems status.
- 2. Design, Construction and Planning Manager for drawings and construc-l-
tion of systems and equipment and regarding planned and scheduled activities of the RadCon/ Waste Management Group.
- 3. Technical Support Manager concerning review and approval of l proposed modifications to procedures, systems, and equipment.
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l Page A-31 l APPENDIX A-XXV HEALTH PHYSICS DIRECTUR REPORTS T0i RadCon/ Waste Manager'(out of plant responsibilities) and Chemistry / Health Physics Supervisor (in-plant responsibilities)
IDCATION: Site Boundary Control Center i
} SUPERVISES: .lth Physics Personnel BASIC FUNCTIONS:
Responsible for directing assigned Health Physics personnel in accumulat-i ing offsite radiatior. measurement data, performing dose assessments, and providing radiation protection assistance as directed to meet the i needs of the emergency response and Recovery Operations..
PRIMARY RESPONSIBILITIES:
- 1. Implementation of offsite radiological survey procedures.
- -- 2. Evaluate. Sfsite doses based on radiation monitoring performed -
by health physics personnel. ,
~
, 3. Provides radiation protection training for support-personnel.
- 4. Provides respirator training, fitting, and whole body counting-services.
i
- 5. ' Develops plans for plant radiation surveys, sampling, shielding, and special tools in support of waste systems processing and design modification activities.
- 6. Performs radiation protection activities as requested by the plant Chemistry / Health Physics Supervisor.
PRINCIPAL WORKING RELATIONSHIPS
- 1. Chemistry / Health Physics Supervisor regarding radiation protection
- support, dose evaluation, and dose management.
1
- 2. Radwaste Technical Support Coordinator regarding sampling and radiation measurements needed as well-as protective clothing requirements to perform the work.
- 3. Waste group tec'anical support personnel for recommendations regarding methods to reduce exposure.
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Page A-32 APPENDIX A-XXVI LICENSING SUPPORT COORDINATOR
_ REPORTS TO: RadCon/Vaste Managm LOCATION: Emergency Support Center COORDINATES: ALARA review, plant operations review, and resolution of license requirements with NRC representatives.
BASIC FUNCTIONS:
Resolves questions of FFDSAR and Technical Specification commitments, abnormal operating modes, and other license requirements wfQ NRC representatives.
PRIMARY RESPONSIBILITIES:
- 1. Works with NRC representatives to resolve questions concerning FFDSAR and Technic , :pecification commitments in light of exist-ing plant conditions.
' 2. Works with NRC representatives to resolve license requirements associated with proposed abnormal operating modes or plant modifica-tions.
- 3. Provides ALARA review of proposed emergency response organization activities.
PRINCIPAL WORKING RELATIONSHIPS:
- 1. NRC representatives regarding all license requirement areas.
- 2. Technical Support Manager regarding out-of-normal operating modes and acdifications to the plant.
- 3. Design, Construction and Planning Manager regarding modifications to the plant.
- 4. RadCon/Vaste Manager regarding ALARA review.
. , _ . - . _ _ . . , . - . . , . - . ~ . . . - . . - . - . - , . . - - - . , . . .-
Page A-33 APPENDIX A-XXVII
_RADWASTE TECHNICAL SUPPORT COORDINATOR
~
REPORTS TO: RadCon/ Waste Manager LOCATION: Emergency Support Center SUPERVISES: Radwaste technical support BASIC FUNCTIONS:
Responsible for tne development of plans and procedures to process and' control liquid, gaseous, and solid wastes in support of the emergency response and Recovery Operations. Other responsibil':les include =
developing decontamination plans in support of plac . operations; conceptual design of systems and equipment to acco mdate waste process-ing needs and to reduce plant and offsite dose rat s; and for reviewing the plans and procedures and modifications developed by the RadCon/
Waste Management Group to evaluate their effectiveness in achieving the objectives of expediting waste processing and reducing plant and-offsite dose rates.
' PRIMARY RESPONSIBILITIES: .
- 1. Maintains an updated status of the liquid storage tank, gas system, and solid waste system inventories.
f
- 2. Develops plans and procedures to process liquid wastes.
- 3. Develops plans and procedures for processing gaseous wastes and maintain in plant charcoal filter exhaust systems.
I j 4. Develops plans and procedures for solid waste processing, i
S. Assists in development of decontamination plans for affected plant areas.
- 6. Develops plans to reduce all liquid, gaseous _and solid waste levels to a normal inventory.
j 7. Provides recommendations to the plant operating organization on chemistry and radiochemistry problems.
PRINCIPAL WORKING RELATIONSHIPS:
- 1. Technical Support Manager and the Health Physics Director in regard to technical feasibility of processing plans and their effects on the plant and environment.
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4 Page A-34
- 2. Chemistry / Health Physics Supervisor with regard to implementation--
of plans and procedures for processing wastes and to obtain the status of radweste volumes.
- 3. Health Physics Director regarding in plant and offsite dose rates and radiation protection and clothing requirements for waste l
processing; shielding, special tools, and monitoring instrumenta-
! tion needed in the modification package;.and assessment of the effects of waste processing.
- 4. Technical Support Manager for technical advice concerning the adequacy and feasibility of the proposed modifications.
- 5. Chamistry/ Health Physics Supervisor as requested for recocaenda-tions conterning plant chemistry and radiochemistry.
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2 f DESIGN, CONSTRUCTION, AND PIANNING MANAGER i
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UTTT.T'lY ARCHITECT- NSS OTIER DIRECTOR, ENGINEERING EIIGIIEER SUPPLIER SUBCONTRACTORS QtRLITY i DIRECTOR CONSTIUCTOR AND SUPPLIERS CONTROL ,
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DESIGN, CONSTRUCTION, AND PLANNING SUPPORT GROUP j
APIENDIX A-XXVIII f.
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Page A-36
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APPENDIX A-YYYY DESIGN. CONS 11EX"rION. AND PIMMING MANAGER l
REPORTS TO: Emergency Support Manager LOCATION: Corporation Headquarters SUPERVISES: Design, Construction,~and Planning Group BASIC FUNCTIONS:
Coordinates the design, construction, and p1'=aning activities of the utility, A/E, NSSS Supplier, construction forces, and outside vendors.
PRIMARY RESPONSIBILITIES:
- 1. Provides the direct contact between the utility and the A/E, NSSS Supplier, and Corstructor, on administrative matters.
- 2. Determines the need for and provides engineering and technical sp.ecialists assigned on a preplanned basis to the Technical .
Support, Plant Operations, and RadCon/ Waste Managers, and the Eeergency Support Manager, if required. Ensure.s that these specialists are present, or their alternates are available. Is prepared to provide additional support as required.
! 3. Ensures that any design and construction activities are adequately _
staffed and equipped to provide timely support.
- 4. Directs, coordinates, and approves other engineering, design, and construction activities onsite.
S. Establishes which engineering, design, and construction activi-ties, if any, shall conform to utility formal specifications or be documented by utility quality assurance procedures.
- 6. Assists in the planning, scheduling, and expediting of Recovery Operations.
PRINCIPAL WORKING RELATIONSHIPS:
1
^
- 1. Site Manager regarding plans for modifications to systems and equipment'in plant.
- 2. Technical Support Manager regarding review and approval of pro-posed modifications to systems and equipment in plant. {
- 3. RadCon/Vaste Manager regarding modifications to systems and equipment and support of activities in the waste management area.
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l Page A-37 APPENDIX A-XXX DIRECTOR. QUALITY CONTROL REPORTS 'IT): Design, Construction, and Planning Manager LOCATION: Emergency Support Center SUPERVISES: Quality Control BASIC PUNCTIONS:
- 1. Responsible for directing and executing the. quality control program for soch construction tasks that the Design Construction and Planning Manager may direct to meet the requirements of emergency response and Recovery-Operations.
PRIMARY RESPONSIBILITIES:
- l. Ensures that the quality control activity is adequately staffed and equipped to provide timely support.
- 2. Directs and coordinates the implementation of the quality control program for approved construction tasks.
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Page A-38 APPENDIX A-XXXI ITTILITY ENGINEERING DIRECTOR REPORTS 10: Design, Construction, and Planning Manager IDCATION: Emergency Support Center SUPERVISES: Utility Engineering BASIC FUNCTIONS:
Responsible for directing and administrative 1y controlling and performing.
such engineering and design tasks that the Design, Construction and Planning Manager may direct to meet the requirements of the emergency response and Recovery Operations.
PRIMARY RESPONSIBILITIES:
- 1. Provides the administrative and technical control of any engineers and designers assigned to him.
- 2. Ensures that his engineering and design activity is adequately staffed and equipped to provide timely support.
- 3. Establishes for the Design, Construction and Planning Manager which engineering, design, and construction activities, if any, fs -shall conform to the utility's formal technical requires ents. .
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' DATA DISPLAY AND SAFETY PARAMETER DISPLAY SYSTEMS
[ 1.0 SAFETY ASSESSMENT SYSTEM CONCEPTUAL DESIGN DESCRIPTION L i
1 ~.1 GErERAL CONSIDERATIONS
~
4 . The Safety Assessment System (SAS) meets the requirements c the Safety Parameter Display System (SPDS). This section describes th. .~ portion 2 of the SAS which meets the SPDS. requirements of.NUREG-0696. It provides-a centralized, flexible, camputer-based. data and display ~ system:to ,
assist control room personnel'in evaluating the safety status of:the
- plant. This assistance is accomplished by providing the operators and i the Technical Support Center a high-level graphical display containing a minimum set of key plant parameters representative of the plant 1 safety.
I status. More detailed plant information is provided by several secondary l displays. 1All graphical displays are presented to the control roma~ ,
operator on a high resolution multiple-color CRT.
h All data displayed by the SAS is validated by comparing redundant sensors, j checking the value.against reasonable limits,.calculcating rates of change, and/or checking temperature;versus pressure curves.
i All displays of the SAS have been carefully designed by persons with plant. operating experience'and evaluated against human factors design.
U criteria. The concepts used in the SAS design.will'be verified using_ ,
l data recorded from a similar power plant simulator. The intent'of the.
j, SAS is to present to the control room personnel.a few easily _under-L standable displays which use color coding and pattern . recognition techniques L
to indicate off-normal values. Tbene displays are updated and1 validated.
on an essentially real-time basis.
f The SAS will be operable during normal'and abnormal plant operating
! conditions. The SAS will operate during all SPDS required modes of plant operation. The " Normal Operation" mode will encompass all plant conditions at or above normal operating pressure and temperature. When the reactor coolant system is intentionally cooled below normal operating values, the operator will select the Heatup-Cooldown mode .which alters the limit ' checking algorithm for.the key parameters. An~ additional mode may. be provided to address concerns of cold shutdown plant conditions.
1.2 DISPLAY HARDWARE LOCATIONS AND OPERATION i
The SPDS portion of the SAS may be Laplemented 'on a single CRT. located
~
in a central location of the control roon visible to the control room operator and the Senior Reactor Operator. This CRT'contains the high -
level display from which the overall safety status of the plant may bei
-assessed. A dedicated function button panel allows' operator. selection lL of several predetermined second level (trend) displays at'any time.
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I The SAS has been designed such that control room personnel can utilize-f- its features without' requiring additional operations personnel.
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The SAS displays will be provided to the Technical Support Center.
Refer to Figure C.1 for the configuration of the SAS and the data' display system for the control room and the TSC.
. 1.3 DISPLAY CONTENTS The primary display consists of bar graphs of selected parameter _ values, digital status indicators for important safety system parameters and digital values. The parameters indicated by bar graphs and digital values include: RCS pressure, RCS temperature, pressurizer level, steam '
generator levels and steam generator pressures. Status indicators are provided for containment environment and secondary system radiation.
Reactor vessel level (if available), core exit temperature, amount of subcooling and containment radiation are indicated by digital values.
In addition, there is a message area wh> ' vill be usedoto indicate that an appropriate secondary display provides further information in case an off-normal value is detected or an event is occurring.
Each of the bar graphs indicates wide-range values. If a parameter's value is outside the normal range, the bar color will turn red. Arrows next to the bar will indicate the trend direction (increasing or decreasing) based on data smoothing algorithms.
During normal operation, the message area will.be.used to display
- average power, reactor core average temperature, data, time, and unit.
These messages may be displaced by higher priority messages as required.
Secondary d'isplays may be selebted by the operator Trend graph groups of selected parameters, showing the last thirty. minutes of plant operation are available. These trend groupings were chosen to'kaep like parameters or related parameters on one display "page".
1.4 HUMAN FACTORS CONSIDERATIONS Human factors engineering and industrial design techniques have been l effectively combined to establish man-machine interface design require-ments, maximize system effectiveness, reduce training and skill demands, and minimize operator error.
The CRT color graphic formats and functional key board designs have been developed through an interdiscipliancy team of senior operational, human factors, industrial design and computer interface personnel.
Minimum use of color combined with simplified format throughout the CRT presentation have key design features to provide both normr.1 and off-normal pattern recognition. The operator, who is the end user, has been directly involved from the conception.to insure that man-machine.
1 interface goals of SAS have been satisfied. Human factor engineering standards and testing verification have been used which are consistent with accepted practices.
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- 1. 5 - VALIDATION ~AND VERIFICATION ,
The SAS is. implemented on a' digital computer system which includes a_.
peripheral display generator computer for color graphic displays. The software that controls the' sensor data validation, key parameter construc-tion, and display formats has been developed'under strict' quality
- assurance procedures. -The original development of the SAS. software began with a functional specification that was developed over a period of 18 months by_a technical committee comprised of. members from a number '
of utilities and consultants, These functional specifications are .
transformed into a design specification. Reviews of the' design specification will assure conformance of the SPDS portion of the~SAS to those functions 1 discussed in NUREG-0696. The basis .for selection of the primary display -
parameters will be a part of the final project documentation. -
During the course of' software development, . a set of static test cases will be developed which test the key features of each software module.
Furthermore, static system test cases will be developed and used to verify the correct. operability of the total system. A set of dynamic test cases will-be. generated by recording nuclear plant simulator. data on magnetic tape from a number of different plant transients which test the dynamic behavior of the system under "real" conditions. A design-review that compares these test results to the original functional and-4 design specifications will be performed. A-selected number of the 4
static test cases will be " frozen" such that they could be used to j' verify future changes to the software. In, summary, verification and. j validation was addressed and designed into the'SAS software from the beginning to provide a highly reliable product and a mechanism for i identifying and controlling future changes.
2.0 SYSTEM C0hTIGURATION ,
2.1 GENERAL The Data Display and SPDS configuration is shown in Figure C.1. The i system consists of four input multiplexers, two SAS computers, two
> Plant Process Computer Systems (PPCS), control room displays, TSC displays i
and computer room equipment. The overall system has been carefully -1 l_
designed to provide a highly reliable system using a common data base.
4 l 2.2 DATA ACQUISITION SYSTEM
- i. The Data Acquisition System consists of four multiplexer input units
' which collect analog and digital information from both units and sends this information to the computers as indicated in Figure C.l. Each-I mu3tiplexer will be supplied by a different _IE power supply. The input-signals will be separated such that their power supplies will match or i
be siallar to the multiplexer power supply. Thus, a power supply failure.
should not reduce the data input by more than one redundant channel of sensors. The multiplexers will be seismically qualified. Input signals coming from' safety systems will be isolated by an isolation device
- i. prior to connection to the multiplexer.
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2.3 SAS COMPUTERS Dual SAS computers are provided and each computer receives inputs from all four MUXs. Plant data from other sources, such as radiological monitor system (RMS) and meteorological data (MET),- is also received by each'SAS computer. This results in each SAS computer receiving the total input data base for both units. For both units, each SAS computer organizes the data base, performs its SAS functions, sends the appropriate data to the SAS display CRTs, and passes the total data base on to the PPCS computers. The SAS functions include redundant parameter verification and averaging, derivation of the historical data base for the SAS (SPDS)
- rend displays and derivation of the parameter attributes for.the SAS (SPDS) displays. The SAS computers will utilize only core resident memory such that seismic qualification may be feasible. Each computer will be powered by an IE power supply.
2.4 PLANT PROCESS COMPUTER SYSTEM Dual PPCS computers are provided and each computer is capabi. of receiving the total two-unit data base from each SAS computer. For both units, each PPCS computer will perform its normal plant process computer functions and the data handling for display in the control room and TSC. The total computer system data base will be available to the control room and the TSC. This includes the Regulatory Guide 1.97 parameters except as described'in Section 3.0 of Attachment "C". The PPCS will cottbe seismically designed because it uses rotating memory but it is.likely l
that data may not be lose during a seismic event because the data is stored in core resident memory before transfer for longer term storage on disk or tape. The PPCS computers will be powered by IE power sources.
l 2.5 CONTROL ROOM DISPLAYS Each unit will have at least one SAS (SPDS) display CRT. Each SAS CRT is capable of receiving input from either SAS computer as shown in Figure C.1. Only the Itmited number of SAS displays will be shown on the SAS CRTs.
Each unit will have two PPCS display CRTs. Each master PPCS CRT is l
capable of receiving input from either PPCS computer as shown in Figure C.l. These CRTs will have the capability to display all of the plant process computer functions and the total data base.
A line printer associated with each unit is provided in the control room.
2.6 TECHNICAL SUPPORT CENTER DISPLAYS A single SAS display CRT is provided in the TSC. It is catable of being connected to either unit's master SAS CRT and can display either unit's SAS displays quickly. The TSC can select its own S/S display but it will be chosen from the same set of displays availa' ale in the l~ control room.
-Two master PPCS display CRTs are provided-in the TSC. Each CRT is capable of being connected to either PPCS computer. These CRTs will have the same capability as the control room CRTs for displaying all of the plant process computer functions and the total-data-base.
A line printer similar to that in the control room will~ be provided in the TSC.
2.7 -COMPUTER ROOM EQUIPMENT The equipment located in the computer room is shown in Figure C.l.
2.8 AVAILABILITY ANALYSIS A detailed availability analysis will be performed to verify that the availability goal of NUREG-0696 is met.
2.9 NUCLEAR DATA LINK (NDL)
- No provisions for a NDL are being provided. . Transmittal of information to NRC headquarters via the NDL need not be real ti.me as suggested by NUREG-0696, as no "real time" management function exists. This infor-
. mation transmittal will be limited to dedicated voice communication links.
2.10 SEISMICALLY QUALIFIED SPDS AND CONCENTRATED (SEISMIC) BACKUP The function of the SPDS does not warrant seismic qualification because of the low probability of a seismic event' concurrent with the need for l- the SPDS function, given the availability of seismically qualified.
l displays for key safety parameters in the control room. Further, a l separate additional concentrated display is not required as a backup-for a non-seismic SPDS and is conceptually contrary to good human engineering practices.
Indicators are available and with proper training of the operators they i are adequate for controlling the plant under all conditions. Future control room reviews will identify human factors deficiencies in the control room and improvements will be'made as required. The~ require-ment to install separate additional seismic displays compounds the human factors problem and is also in conflict with the design' criteria of Regulatory Guide 1.97 which encourag.; that the operator use normal operating displays during accidents. This use of existing displays is most desirable since the operator will always get information to perform critical and normal operating functions from the same location. The SPDS, by definition, is intended to concentr ae a minimum set of plant parameters to aid the operator in the rapid .etection of abnormal operating events. However, it is reasonable to use the normal displays as a backup for this purpose.
The existing instrumentation in a well human engineered control room can fulfill the functions required for the SPDS backup. The. ongoing controt room reviews-to improve human factors considerations will assure P
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that the requested functions for an SPDS backup will be satisfied by the existing control room displays. A separate concentrated seismically qualified backup SPDS in the control. room is unnecessary, and Jhould-
~
not be required.
3.0 REGULATORY GUIDE 1.97 PARAMETERS Revision 2* of Regulatory Guide 1.97 (R. G.1.97) dated December 1980 was issued by the NRC Staff to provide guidance on the instrumentation-parameters to be displayed in the control-room to assess plant and environs conditions during and following a design basis accident. R. G.
1.97 represents one acceptable way to meet General Design Criteria 13, 19, and.64 of Appendix A of 10 CFR 50. R. G. 1.97 states, however, that " Regulatory Guides are not substitutes for regulations and compliance with them is not required." NUREG-0696, which references R. G. 1.97, was issued to licensees as an enclosure-to NRC Generic Letter No. 17 dated March 5, 1.'81. The Generic Letter states that NUREG-0696 "provides general guidance only, is an acceptable way to meet the NRC rules and regulations, and that compliance with NUREG-0696 is not a requirement."
NUREG-0696 states that "the minimum data set that shall be available for display and use in the TSC and EOF shall include . . . Type A, B, C, D, and E variables specified in R. G. 1.97." It continues that " acquisition and transmission of . . . variables- to the TSC and EOF need not meet the Regulatory Guide design and qualification criteria for display _of that data in the control room."
Wisconsin Electric does not believe that impleme'tation n of R. G. 1.97 for control room, TSC and EOF displays is mandatory. We have, however, conducted a detailed evaluation of the R. G. 1.97 instrumentation design and qualification criteria as compared to the Point Beach Nuclear Plant
, design. A number of instruments are being added or upgraded to meet l the requirements of the TMI Action Plan or IE Bulletin 7901B. The R.
l G. 1.97 design criteria are being factored into these additions and upgrades. In addition, several instruments are being added or upgraded strictly to meet the objectives ofR. G. 1.97.
Wisconsin Electric takes exception to a number of the R. G. 1.97 design criteria. The reasons include the adequacy of the present design, unavailability of reliable, qualified equipment, and/or the lack of a safety function requirement for that instrument in the Point Beach Nuclear Plant design. The present instrumentation already meets the
( requirements of General Design Criteria 13, 19 and 64. Wisconsin Electric l
does not intend to upgrade the following instrumentation for the reasons
! given:
i j
VARIABLE DISCREPANCIES JUSTIFICATION
- 1. Neutron Flux.(Source Seismic and Environmental Boron Sampling and Rod and Intermediate Qualification Position Indication Range) Adequate; Qualified System Not Available
- 2. RCS Soluable Boron No Instrumentation Installed Boron Sampling and Rod Content Position Adequate; Qualified System Not Available
- 3. Containment Isolation Seismic and Environmental Mild Environments Only; Valve Position Qualification (Outside Seismic Will Be Containment only); Single' Addressed Later:
Failure Criteria Redundant Valves Provide Redundancy No Instrumentation RCS Samples Adequate;
- 4. RCS Radioactivity Concentration Installed Qualified System Not Available
- 5. Pressurizer Heater No Electric Current; Meter Breaker Position Status Installed Adequate; Pzt. Temp, and Press. Are Backups
- 6. Quench Tank (Pzr. Range Required Range Relief Tank)
- Physically Unrealistic Temperature
- 7. Heat Removal by Seismic and Environmental Containment Temperature
. Cor ninment Fan Qualification will be Qualified and Coolers Is Adequate-
- 8. CVCS Makeup Environmental Qualification Not Safety-Related (Charging) Flow
- 9. CVCS Letdown Flow Environmental Qualification Not Safety-Related I
- 10. Volume Control Tank Environmental Qualification Not Safety-Related Level l
- 11. Status of Standby Seismic and Environmental Mild Environments-j Power Sources Qualification Only; Seismic Will Be l Addressed Later; Numerous
! Indications Available for Backup f'
l
- 12. Radiation Exposure Range (Some Areas); No Portable Survey Meters Rate (Inside Instrumentation Installed Are Primary Source of l
Building) (Some Areas); Environmental Data and are Adequate j
- Qualification l I
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v-1 VARIABLE DISCREPANCIES , JUSTIFICATION
- 13. Airborne Radioactive Seismic and Environmental Portable Sampling and Material Released Qualification Onsite Analysis is from Plant-(Noble-- Adequate Backup; Gas Radioactivity) Qualified System Not Available
- 14. Environs Radiation No-Instrumentation Installed ~ Portable Survey Meters Exposure Meters Are Primar; Source of-
-Data;-TLDs Are Backup
- 15. Primary Coolant Gross Activity Range; Activity Range Adequate Sampling- Dissolve Oxygen; Onsite for PBNP; Oxygen and Analyses Capability for Chlorides Not Required Chlorides for Safety
- 16. Containment Air Oxygen Content Cxygen Not Required for Sampling Safety e
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