ML20024A748
| ML20024A748 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 05/01/1983 |
| From: | Murray T TOLEDO EDISON CO. |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20024A745 | List: |
| References | |
| PROC-830501, NUDOCS 8306220263 | |
| Download: ML20024A748 (424) | |
Text
.
DAVIS-BESSE NUCLEAR POWER STATION TE TOLEDO EDISON COMPANY EERGENCY PLAN IMPLEENTING PROCEDURES THIS MANUAL IS TE SOLE PROPERTY OF THE TOLEDO EDISON COMPANY.
IT MAY BE RECALLED AT TE OPTION OF TOLEDO EDISON. THIS MANUAL MAY NOT BE REPRODUCED.
CONTROL COPY NO.: SOA ISSUED T0: NRC - NUCLEAR REACTOR REGULATION I
DATE: MAY 1, 1983 ISSUED BY: STATION SUPERINTENDENT /EE31GENCY PLANNING e M 263 830607 PDR ADOCK 05000346 F ..PDR
.~
DAVIS-BESSE NUCLEAR POWER STATION EMERGCICY PLAN DTLEerrrfG PRCCCL"AES TOLEO EDISON
%e
% e S "
se i
l he I
L 1
=_
4
- i. .
1 l
l THE TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDUES
' REVISION INDEX.
PACE REVISION PROCEDURES REVISION TEMPORARY ICDITICATIONS
' 1 0 EI 1300.00 4 EI 1300.01 5 3
EI 1300.02 3 T-6938 .
EI 1300.03 3 EI 1300.04 3 EI 1300.05 3 EI 1300.06 3
, EI 1300.07 4 T-7104
. EI 1300.08 5-EI 1300.09 1
, EI 1300.10 1
- EI 1300.11 1 EI 1300.12 2 T-6820 i
Revision 28 April, 1983 e ge e
6B
_l
__ e_- _ . _ . _ . . - . _ _... _ . _ _ . _
4 i
EMERCE' ICY PT AN IMPI.EMENTING PROCEDURES
- 1. Station Response to E=ergencies (EI 1300.00)
- 2. Emergency Plan Activation (EI 1300.01) l l 3. Unusual Event (EI 1300.02) -
l
- 4. Alert (EI 1300.03)
- 5. Site Emergency (EI 1300.04)
. 6. General Emergency (EI 1300.05) f
- 7. Operations Support Center Activation (EI 1300.06)
Technical Support Center Activation (EI 1300.07) 8.
- 9. Emergencf Control Center Activation (EI 1300.08)
- 10. Emergency Support Center Activation (EI 1300.09) i -
- 11. Reentry (EI 1300.10)
- 12. Recovery (EI 1300.11) -
1.
- 13. Administrative Controls (EI 1300,12) f s .,
1 L
I L
I~ '; _.
L.
L i
J
~
, Revision 2 December, 1982 b>.
EI 1300.00.0 Davis-Besse Nuclear Power S'tation Unit No. 1 Emergency Plan Implementing Procedure EI 1300.00 Station Response to Emergencies Record of Approval and Changas Prepared by C. J. Reed 5/30/80 Date Submitted by C. E. tJells 6/13/80 Section Head Date Recommended by /e b. 8 PD
- SR3 Chathan Date QA Approved 8 -
Quality Assurance Manager Date Approved by D ./ @ // SF/@
StationSuperintendeur[ Date L
, Revision SR3 QA Sta.' Supt.
No. Recommendation Date Approved- Date Approved pace
\
f hYA$f* Y YN
$ f3 s -=f l l ~~ O t- -
7/' / P~
Lll5f6L.
3 p - a e)<>ln J/r _
'" y'M 'YW"~
p s 3 sl1sjes MA W' *#
l 1
a a - - - -,-w
1 EI 1300.00.2
- 1. PURPOSE To present a summary of the DENPS Emergency Plen.
- 2. SCOPE To present a summary of Station actions during an emergency and to outline the interface between Station procedures and Emergency Implementing Procedures (EI 1300 series).
- 3. REFERENCES 3.1 Davis-Besse Nuclear Power Station Emsrgency Plan 3.2 Davis-Besse Nuclear Power Station Emergency Plan Telephone Directory 3.3 TECo Corporate Radiological Emergency Response Procedure 3.4 Emergency Implementing Procedures EI 1300 series 3.5 Administrative Procedures AD 1827 series 3.6 EP 1202.35 Fire Emergency 2 3.7 HP 1604.01 Personnel Decontamination 3.8 Admin Memos 38, 39, 40
- 4. DEFINITIONS
- 4. l' Dose Projection - The calculated estimate of a radiation dose to individuals at a given location (usually offsite),
determined frem the quantity of radioactive material released and the appropriate meteorological transport and dispersion parameters.
4.2 Emergency Action Levels - Radiological dose rates, specific concentrations of radioactive materials; or specific instrument readings and indications (including their rate of change) that may be used as thresholds for initiating-such specific emergency measures as designating a partic-ular classification of emergency, initiating a notifica-tion procedure, or initiating a particular protective action.
4.3 Emergency Control Center (ECC) - A specifically designated location which is equipped to facilitate the control and coordination of emergency activities and asse.ssments.
4 i
l l
EI 1300.00.3 2 s ,
4.4 Emergency Duty Of ficer (EDO) - An assigned individual responsible for direction and coordination of activities during an emergency situation at the Station.
4.5 Emergency Ocerations Center (EOC) - An offsite location utilized by State, County, and other government agencies and organizations to perform assessments of radiological conditions and to coordinate offsite activities (access,
)
evacuation, etc.). ,
i 4.6 Emergency Planning Zones (EPZ) - Two zones that EPA recommends be established around all nuclear power stations.
One zone with a radius of 10 miles (16090 meters) for plume exposure pathway, and the other with a radius of 50 l miles (80450 meters) for food ingestion pathway. I i
In these zones, predetermined protective action plans are needed.
4.7 Ooerations Supeort Center (OSC) - An area in the Station in close proximity to the Control Room to which Station 3 support personnel report and await Lastructions from the Shift Supervisor, Emergency Duty Officer or Station Operations Manager.
4.8 Projected Excosure Time (PET) - The estimated period of )
time that the population in the area surrounding DBNPS may be exposed to radiation as a result of an accidental airborne radioactive release. PET starts when the air-borne radioactivity release is estimated to cross the Owner-Controlled Area, and ends when the radiation levels offsite are expected to return to normal.
4.9 Protective Action Guides (PAG's) - Projected radiological dose or dose commitment values to individuals in the
. general population that warrant protective action follow-ing a release of radioactive material. Protective' actions would be warranted provided the reduction in individual dose is NOT offset by excessive risks to individual safety in taking the protective action. The PAG does NOT include the dose that has unavoidably occurred prior to the assessment.
4.10 Technical Support Center (TSC) - An~ area within the owner controlled area, which has the capabilities to display and transmit station status information to individuals who are knowledgeable of and responsible for engineering and management support of reactor operations in the event of an emergency situation.
m -
3 EI 1300.00.2
- 5. EMERGENCY PLAN SLTfARY 5.1 The DBNPS Emergency Plan establishes the concepts, evalu-ation and assessment criteria, and protective actions that are necessary in order to limit and mitigate the consequences of potential or actual radiological emergencies. The plan provides the necessary prearrangements, directions, and organization so that all Station emergencies can be effectively and efficiently resolved in order to safeguard
. Station personnel, property and the general public.
- 6. STATION RESP 0NSE 6.1 The Statioz. Superintendent is ultimately responsible for the assignment of responsibilities in the onsite Emergency Organization. However, the onsite Emergency Organization is predefined, and alternate assignments specified. ,
6.2 When an emetgency condition is declared, the members of the normal plant organization assume duties in the onsite Emergency Organization.
6.2.1 The Shift Supervisor's primary responsibility is maintaining the plant in a safe condition as well as carrying out the initial steps of the EDO:
- a. Verify the existence of an emergency condition.
- b. Notify Station personnel, the Station Superin-tendent, EDO, and offsite support groups as required.
- c. Activate emergency teams.
2 d. Control access of personnel to Control Room.
- e. Initiate immediate protective measures as required. .
- f. Verify operating status of the Plant and Station.
6.2.2 The Shift Supervisor assumes the role as EDO until properly relieved by the on-call EDO or his alternate.
6.2.3 The Control Room, during an emergency, will control the power plant to mitigate the effects 1 of the emergency conditions. '
. I
4 EI 1300.00.2 sg 6.2.4 The Assistant Station Superintendent, Operations, or his alternate, the Operations Engineer, becomes the Plant Operations Manager. He is responsible for keeping the Station Operations Manager advised of plant operations. He may assist the Shift Supervisor in directing plant activities and damage control efforts, however, ultimate authority for directing all chases of plant operations lies with the Shif t Supervisor.
6.2.5 The Radeon Opeations Manager is the Chemist and Health Physicist or the Chemical and Radiation Protection Engineer. He directs and coordinates the radioactive vaste and radiological controls aspects of the recovery operation.
6.2.6 The Operations Engineer, or the Operations Supervisor, becomes the Plant Operations Engineer.
He supervises Control Room activities, and
, 2 performs on-the-spot operation analysis as required by the Shift Supervisor. The Shift Supervisor, and through him the operating shift, reports to the Operations Engineer.
6.2.7 Plant Maintenance, during an emergency, is directed by the Maintenance Engineer, or his ,)
alternate, the Lead Maintenance Support Engineer, or Lead Instrumentation and Control Engineer.
6.3 The ED0's . responsibilities include:
- a. Implements appropriate protective actions to mitigate the effects of the incident. The Implementing Procedures for the plan shall provide necessary guidance. The judgment of the EDO plays a vital role in any emurgency and in some cases, may take precedence over previously preplanned actions.
- b. The safety and well-being of Station personnel,
- c. Determination as to necessity to evacuate the Station and/or the local area.
- d. Provides projected dose Laformation.
- e. Recommends to offsite emergency. organizations for implementing effective protective measures for the -
general public.
2
- ,-v -
7 m- --me - ,-- , -v - - -
5 EI 1300.00.2 6.4 Onsite Assessment Teams (OAT) 6.4.1 The Onsite Assessment Team is headed by the Nuclear Engineering Manager or his alternate, the Plant Nuclear Systems Engineer.
6.4.2 The Team Manager supervises the analysis efforts of Company engineers , NSSS vendors , and other plant staff.
6.4.3 The location of the OAT is the TSC.
2 6.4.4 The Technical Engineer or his alternate, the Nuclear and Performance Engineer, will be in :he TSC to analyze vital plant parameters and plant response.
6.5 Other emergency response personnel provide specialized support:
6.3.1 Radiation Monitoring teams (Admin Memo 42) 6.5.2 First Aid Team (Admin Memo 38) 6.5.3 Fire Brigade (Admin Memo 39) 6.5.4 Emergency Facility Personnel
- a. ECC (EI 1300.08)
- b. TSC (EI 1300.07)
- c. OSC (EI l'300.06) 6.6 When required, additional support is provided by the TED Corporate Emergency Organization in the form of technical, administrative, and logistical support to the onsite Emergency Organization.
- 7. EMERGENCY PLAN STEPS In general, the Emergency Plan encompasses the following basic steps.
- a. Detection of the emergency -
- b. Classification of the emergency
- c. Activation of the responding organization (s)
~
6 EI 1300.00.2 s
- d. Assassment of the situation
- e. Initiation of protective actions
- f. Initiation of corrective actions
- g. Aid to affected persons
- h. Periodic dissemination of updated information 2 1. Reentry and recovery 7.1 Detection of the Emergency This step of the Emergency Plan relies on the Operating Shift Crew to determine whether an abnormal situation exists based on all plant parameters, visual sitings of problems or sound engineering judgement. This step may also include ~ actions required by Emergency Procedures, Alarm Procedures, or Abnormal Procedures, etc.
7.2 Classification of the Emergency 7.2.1 Emergencies are grouped into four (4) class-ifications listed below in order of increasing
, severity: )
- a. Unusual-Event The occurrence of an event or events which indicate a potential degradation of the level of safety of the plant. Unusual Event emer-gencies involve minor situations.that have the potential to escalate to more serious emergencies.
- b. Alert The occurrence of an event or events which involve an actual or potential substantial degradation of the level of safety of the plant. The consideration is, as in an Unusual Event, to prepare to cope with potentially more serious emergencies. Alert emergencies may involve limited release of radioactive material.
- c. Site Emergency
-m
7 EI 1300.00.0 The occurrence of an event or events which involve actual or IJkely major failures of plant functions needed for protection of the public. The potential for a situation hazardous to the genersi public is the major concern of the Site Emergency classification. There also exists a significant actual or potential release of radiocctive material.
- d. General Emergency The occurrence of an event or events which involve actual or imminent core degradation with the potential for loss of containment integrity. Large amounts of radioactive material, immediately hazardous to the general public, could be released during a General Emergency.
7.2.2 The classification of the emergency is determined by comparing plant conditions with the Emergency Action Levels described in Emergency Plan Activa-tion Procedure EI 1300.01.
7.2.3 The Shift Supervisor is responsible for determin-ing the initial classification of the emergency.
7.3 Activation of the Responsible Organization (s) 7.3.1 Upon determination of the appropriate emergency class, the Shift Supervisor shall then refer to the appropriate emergency classification procedures:
- a. Unusual Event EI 1300.02
- b. Alert EI 1300.03
- c. Site Emergency EI 1300.04
- d. General Emergency EI 1300.0S 7.3.2 The Shift Supervisor. assumes the duties as interim Emergency Duty Officer and proceeds with the actions outlined in the EDO check lists provided with the above procedures. He remains the interim EDO until relieved by the assigned EDO or until the emergency is terminated.
l
8 EI 1300.00.2 'e 7.3.3 Part of each checklist is ensuring that proper, timely notifications are made in the event of an emergency.
For example:
2 a. Notification should be made to State / Local authorities (via Ottawa County Sheriff) as soon as possible (normally within 15 minutes) following the declaration of an emergency classification, as identified in 10 CFR 50 Appendix E, Section IV.D.3., Domestic Licensing of Production and Utilization Facilities.
i
- b. Notification should be made to the NRC as soon -
as possible and in all cases within one hour of the occurrence of any significant event as identified in 10 CFR 50.72, Licensing of Production and Utilization Facilities.
7.3.4 The EDO has some options as to which organiza-tions and/or individuals should be activated.
These decisions should be based on obtaining the best sources of information, experience and advice available. ;
7.3.5 The expected degree of involvement of partici-pating organizations is shown in Table 1.
7.3.6 The Emergency Organization response to amer-gencies is shown in Table 2.
7.3.7 The Emergency Organization is shown.in Figures 1 and 2.
7.3.8 The DBNPS Emergency Call Syst'em is shown in Figure 13.
7.4 Assessment of the Situation Effective coordination and direction of all elements of the emergency organization requires continuing accident assessment throughout an emergency situation. Each emergency class shall invoke similar assessment methods, however each classification imposes a different magnitude of assessment effort. In the following subsections, assessment actions to be taken for each emergency class-ification are outlined.
.)
9 EI 1300.00.0 7.4.1 Assessment Actions for Unusual Events I i
The continuing assessment actions to be performed for this classification consist of the normal monitoring of Control Room anc other plant instrumentation and status indication until the situation is resolved. If a fire is the reason for the declaration of an Unusual Event, the Fire Brigade Captain, upon reporting to the fire location will make continuing assessments based on his knowledge and experience and report his findings to the Shift Supervisor on whether offsite fire fighting support is required. In the case of personnel injury and/or illness, the utilization of offsite medical assistance may be cause to declare an Unusual Event if the injury involves personnel contamination.
7.4.2 Assessment Actions for Alerts The assessment actions for an Alert shall include:
- a. Increased surveillance of in-plant instru-mentation.
- b. If possible, the dispatching of shift per-sonnel to the identified problem area for confirmation and visual assessment of the problem.
- c. The dispatch of onsite Radiation . Monitoring Team's (RMT's) to monitor for possible releases and to provide confirmation of correct accident classification,
- d. If a radiological accident is occurring, the.
in-plant instrumentation necessary to obtain meteorological and radiological data for
. calculating or estimating projected doses will be monitored. This dose assessment activity shall continua until termination of the emergency in order that the updating of initial assessments may be provided to all concerned offsite agencies and to the EDO.
6 e
10 EI 1300.00.0 -
7.4.3 Assessment Actions for Site Emergencies The assessment actions for the Site Emergency classification are similar to the actions for an Alert, however due to the increased magnitude of the possible release of radioactive material, a significantly larger assessment activity shall occur. The necessary personnel for this assess-ment effort shall be provided by mobilization of the onsite and offsite emergency organizations.
Specifically:
' a. An increased amount of plant instrumentation shall be monitored. In particular, indica-tions of core status (e.g., incore thermo-couple readings, etc.) shall be monitored.
- b. Monitoring efforts shall be greatly increased.
Onsite and offsite monitoring teams shall be dispatched. In addition to beta-gamma field measurements, the change-out of thermolum-inescent dosimeters (TLD's) at frequent intervals may be performed; air sampling and collection of other environmental media for assessment of material transport and deposition shall be performed.
- c. Dose assessment activities shall be conducted more frequently, with an' increased emphasis on dose projection for use as a factor in determin-ing the necessity for protective actions.
Radiological and meteorological instrumentation readings shall be used to project the. dose race various distances ' from the Station, and to determine the integrated dose received. In reporting the dose projections to the EDO or to offsite agencies, the dose rate, dose, and the basis for the time used for the dose estimate shall always be'provided. Any confirmation of dose rates by offsite RMI's shall be reflected in reporting and/or revising dose estimate information provided to offsite and internal organizations.
7.4.4 Assessment Actions for General Emergencies Assessment actions for the General Emergency.
i
.s
7., -. - .
3%, __ .
- z. s- -- .-
_ .. _A \ s
( w '; __
- ),
, i s
, \ , ; i p %
v.
'.. g s .
- s. 6 *N ,*
+1 , , y <
u._,-
x . _.
11 EI 1300.00.3 classification shall be the same as for the Site
.' Emergency with a shift of'eltphasis to greater _ j offsite) efforts monitoring wtanding to ef'ortss and dose projection ,
plant. 'A'dditionally,{distancesfurtherfromthe since the projected doses are likely to be much closer to the EPA PAG's, t greater ,e.nphasis' shall be placed on the, assess-ment Of release duration. Judgementsf ind assump- - s , ,. .
tions usedifor dose assessment shall dlways be ,]
reported. , q ,, 4 ' ,
~
s 7.5 Initiation of.Protectiva, Actions ( *
- , , - i ,- ,
Protectivsactions pra esargency, measures taken duriny; or [
after an emergency situation that are intended to minimize '
orel'iminatethehazardtoths].salthandsafetyofthe
4, generel public aal/or Station peysonaal. Protective s actiots include the following: (- N . . ,
! .\
')'
3 s 7.5.1 Protectivs Cover,, Evacuation, Fersons.el Account-ability "^
[ s1 s
_ . x
' During an emergency, sheltering may be the most offective protective action. The relocation of personnel may also ba required 'it order to pre- '
i vent or minimize exposure to radiacion and radio- -
In any event, p'ersonnel
~
, active materials.
accountability is very importe.st during this time. The following subsections present infermation \
, ton policies applicable to such situations.
- a. Plant Site All persons onsite at the time of an Alert, ,
Site, or General Emergency, who do NOT have emergency assignments (nonessential personnel) shall be notified of the emergency classifica-tion by announcement over the public address 3 system. These persona.1 may be required to report to assembly areas for accountability, monitoring and possible evacuation. At the assembly area, members of the emergency organization shall direct and conduct accountability, monitoring and evacuation efforts.
- b. Offsite Areas The responsibility for actions to protect persons in offsite areas rests with the State I
y .. .
@y,p ^ . ,
ys ^ j)e' S';j* 5 j(-
k.A g
{f.' S
~ Y,' -
- 12 EI 1300.00.3 s, of Ohio and Ottawa County officials. Respon-sibilities are described in detail in the-State Plan and implemented in conjunction with i the County Plan. The means to warn or advise persons involved in taking protective actions s is the responsibility of the Ottawa County 3; , . , , ,* * ~
s ',
Disaster Services Agency (DSA) Coordinator and i
the Ottava County emergency organization.
4' g , %y Ottawa County is responsible, according to the
~,f, t-s ]1 State Plan, for the preparation and dissemina-0 3
' tion of information material on protective "i actions for the general public.
< 7.5.2 Use of Onsite Protective Equipment and Supplies '
The following onsite locations have been designated as areas where emergency teams can be assembled and ,
equipped.
- a. Operations Support Center / Turbine Deck
'\ '
N 3 b. Health Physics Monitor Room
- c. Radiological Testing Laboratory u
- d. Emergency Control Center i
1 7.5.2.1 Emergency equipment and supplies shall be stored in close
, proximity to the assembly points .
7.3.2.2 A complete list of emergency equipment and supplies can be found in appropriate procedures ,
if the Emergency Plan.
1 7.5.2.3 Emergency response team members have been trained in the use of specific emergency equipment.
7.3.2.4 Emergency equipment and supplies will be used in accordance with Emergency Flan Implementing Procedures or as directed by.'-
the Emergency Duty Officer, Shift Supervisor, or emergency team leaders.
l d i" c
-l I
I
)
3 . . - -4< ,. ., , , _, . . . , - - ;,m ~,- ,, .- - m. ~, . - '
13 EI 1300.00.0
-7.5.3 Contamination Control Measures This section describes provisions for praventing or minimizing direct or subsequent ingestion exposure to radioactive materials deposited on the ground or other surfaces.
- a. Station Area Access to the owner-controlled area is con-trolled. In addition, there are no areas for producing agriculturcl products within the
- owner-controlled area. Station contamination control shall be exercised in accordance with approved procedures.
- b. Offsite Areas It is the responsibility of the State Depart-
,, ment of Agriculture, in conjunction with the Department of Health and Environmental Pro-taction, to issae guidance and coordinate i actions to control contaminated agricultural j products offsite. The State of Ohio has the responsibility to act on TECo recommendations and to develop their own course of action.
7.6 Initiation of Corrective Actions
. 7.6.1 Detailed operating procedures are available to i the operators for use during emergencies as well as during normal operations. Specific Emergency Procedures are provided to assist the operators in placing the plant in a safe condition and
, taking the necessary supplemental corrective actions. In addition, operations personnel are a
capable of taking appropriate corrective actions
] based on their training, knowledge and experience.
7.6.2 Selected Davis-Besse Nuclear Power Station Staff personnel, including operation, health physics, chemistry and radiochemistry, and maintenance personnel are assigned to emergency teams.
These teams are capable of responding to situa-tions in order to assess conditions and take any applicable corrective actions. Maintenance personnel shall provide the necessary crafts L expertise to effect repair and damage control
, functions.
i l
O n m n -
~
14 EI 1300.00.1 ~
7.6.3 Corrective actions shall normally be planned events that are taken to mitigate the consequences of, or terminate the emergency situation.
Planned radioactive releases or corrective actions that may re-ult in a radioactive release shall be evaluated by the Emergency Duty Officer, and his staff, as far in advance of the event as is possible. Such events and data pertaining to the release shall be reported to the appropriate offsite emergency response organization and/or agencies prior to any controlled release during an emergency or post emergency situation. ,,
7.7 Aid to Affected Persons 7.7.1 Emergency Personnel Exposure Emergency measures may warrant the acceptance of
~
above-normal radiation exposures. Saving a life, measures to circumvent substantial exposures to population groups, or even preservation of valuable installations, may all be sufficient cause for above normal exposures. The following are the guidelines for these emergency activities:
- a. Life-saving action 100 rem ,
- b. Corrective action 25 rem Personnel involved in any of the above actions must be volunteers.
1 The senior Toledo Edison Management. individual present shall authorize the above exposures and
. is responsible for maintaining exposures below these values. He shall seek advice from the Radeon Operations Manager (Chemist and Health Physicist) or members of the C&HP staff. He shall assure that measures are taken to minimize
- other exposures (such as internal exposure) during the conduct of emergency operations.
7.7.2 Thyroid Blocking A ready supply of suitable thyroid blocking agent will be maintained and available for use by Toledo Edison employees. Guidance for admin-istration of the blocking agent will be provided t by medical advisors and it will be distributed as per AD 1827.12.
v e
15 EI 1300.00.2 7.7.3 Decontamination and First Aid Personnel found to be contaminated shall undergo decontamination by Health Physics personnel (or other qualified personnel as specified in HP Procedures). It is preferred that personnel decontamination be performed by trained Heal,th Physica personnel, however other TECo personnel are Lastructed in both decontamination and first aid procedures. Measures shall be taken to prevent the spread of contamination. -
Emergency first aid and medical treatment shall be given to injured personnel who are contaminated.
Station personnel, trained Ln first aid, shall assist contaminated personnel either at the scene
! of ths accident or La the First Aid Room.
Provisions have been made to ensure contaminated and injured personnel receive specialized medical treatment if necessary. The Magruder Memorial Hospital has agreed to accept contaminated -
patients for emergency medical and surgical treatment and/or observation. If affected personnel must be transported, measures shall be taken to prevent the spread of contamination.
7.7.4 Medical Transportation Ambulance service for Davis-Besse is provided for by the Carroll Township Emergency Medical Service.
7.7.5 Medical Treatment -
Arrangements for hospital and medical services for injured or contaminated /over-exposed per-sonnel are provided for by the Magruder Memorial 2 Hospital, REMS Corporation, the Peter Bent Brigham Memorial Hospital in Boston, Mass. , and local physicians.
7.8 Reentry and Recovery l
7.8.1 The Emergency Duty Officer and the Station Opera-tions Manager hav. the joint responsibility Jor determining and declaring when an emergency situation is stable and the Station is ready to enter the reentry and recovery phase.
_.n . ~ _ . - _ - - _ . _ _ _ _ _ - - _ _ ~ _ _ _ _ . _ _ _ - - _ - _
y .
- l. .
L' 16 EI 1300.00.0 - s_ .
7.8.2 The reentry and recovery phase of the Emergency Plan consists of planned and deliberate actions taken to return the plant to pre-accident levels
[ of rsdiat' ion and contamination or to conditions L' which are acceptable and controllable for an '
extended period of time.
i l
I I -
r.
h i
l-l ',-
( I l
I
[. -
l l
t f.
l, l-
4 17 EI 1300.00.1 Table 1 EMERGENCY CLASSIFICATIONS AND TE DEGREE OF INVOLVEMENT BY PARTICIPATING GROUPS Necessity for Necessity Degree of Participation Emergency Protective Actions for By Various Organizations Classification Corrective TECo Offsite Onsite Offsite. Actions *** Onsite Offsite Agencies Notifi- Notifica- Notifica-1 Unusual Event None None Possible cation tion tion Status
- Status Status **
Alert Possible None Possible Standby Standby Standby Status ** Status Status i Site Emergency Probable Possible Probable Action Action Action General Emer-gency Probable Probable Required Action Action Action
- Notification Status: Organization informed of situation onsite.
- - Standby Status: Organization staffs preplanned centers, establishes communications, and assembles emergency teams.
- Action might include local fire support, ambulance service, medical assistance, or radiological assessment.
e e
s
- _, _1 u__ > w - ~
Y ' T
~ ' ' '
9
-e
- g. . .
3, . . . . ! .
3 G=
.. -3. .
m I
- 8.1 3
- 3* 4 :E.3 .
3 I g ." 3 :.
A 5
. . . I2 * .* ;
3 6
.4 o - .2 2 o
g 4
...g. --......
. . . 3 .
. . . .e al
.F h.
3.. ..
5 . *t e t . t ., .
4 **
u
. u. t.... . -.
I
- ex m:-
. t i. :4 , 42: g.: 4 :. ::: c: 1 ***
" t' J. : J*.d t .: ... : c.
.. . 14:'F c.:r i t. . t : I':d j Cd
. - . . fiA
- g= .. l
- 1. ;;. g.
2: . i ". 3 g g
- 21.
- 2 1 :
iy.t **:.:.". 5 *
,12.4.2.
. **:ii.as m..
dA ..
.a4
.8If dk 2....-
8:...w.J 2 . .r
. .t. .J
.a
. , .w.. =1 .".
2.
- 1. . .. d
- 43. 81 a. ..
=.-
8.F 4. ..
,. , = ,. . . .
.. . . ..1
.= . -
. ..I. ..
.2 3- . . . ..
l3
,.4. ..
3 t,,
g
.I.
.I 2 e
3
- &3
.2.
2 .o . . .
2
.2 2 3
- g . .
g,
........=
M g
- ::: = ::
..~g .2 2 .: .:.:.: : : ~:::
w .
..=.=.=.=.=.:..
=,
y -: ,
.s 51 t .
d 5 ..
t._..t.8 1..
.. 51 . ...
.Ow.
E.:. . .
.a . .. .t ., .
m 4 .
u
.t. s d m.3t-4,. . .4 s
2
- c. . ..... u.t .. 1 i .si . . .........
3i .
El . -.3 . .
Es.2 ,. .
. .u
., a . . .
. .. 'J 1 .
. ,. t o.... . .
..e 4.3-:
5 .A. . 21 .. 2.. -! .
. I s
. 4
. . . .- . .i.I. .t .t . .. -. . .. . .
. .u.
s
. . ... w.*
..d- dE1 ..
r.
s
. Q.. .-. . 28 c..W.d m.e 5.
.. s a. .d . a .3. .... , 28 a. ; a. -. 3 7,,, - \
.s I !}
.a .i
. . . . =
8
. . g
< ,= .. ,.
.=.
3.! .
p . .- ... .
_ :3 :. : : 3. . .- . 3 :=
=. .= 2. 3. .: $ .1 .:: :.. =. 2.
.-.. .h .-
g
.gS 3
e
.g. .*
3 -gg.
. 3
.. e3
-g**
.e i -
I A 5 -I :. 2 2.e.
A 3 .
... A 3 :?
- : : :
- 3
- .=
..... :::= *c.: : ::.: : :
. . ,... ::::,~..
- ~
~
. . I -: .
. t 1 :
. 3 .
3 W 3. 3t .mi.
.,i. .
44 u. . . m u .. . .t... u 4.. 1
..t 4... ... . ...
. . . g.i 3...
d 9 .'
I> .~3 ..
r.!&
- s. t. . : g .
. f -.&..
3l A . . 1 .
. . . A . ! !. t . t .. .. .
- . . . . . ... 4.I E..
.E.
...14 .: 4 A!......a.J
. . .. ! u. cid1 L.-
- 1. s m .
. 1. :.. 1 L...&.
2::..:
.sl.
z . . ... . 5... .
. 1. . ... 11 . 5,3 eE s. .g, SI:f
.:32 oId Jid::tt ti:: w :2 :;ss:Ad:d:::s .g.is
,.m..
I ,- ..
.. l.
. . .F l * .
- :::: . :. . . =
I i . ....
m
- 1 I. .
I
- S S.t. .
} .
y'- us .
I .. .f g 4..g : n
- I a.t 2
.t
..i
.m..
bt
.T'3 t
=
3,..t. 4
...-.-.... ....a.....
.. 2
.. ... .. .....,.1.. . S .F .t . .
. 2i t
.. d..
J.
. .. . id wg.
. I g$
$ 23id::tt k::v: 2 . S:
ie 5-l mse msuo I
I
l
__l 19
] EI 1300.00.2 i
i I .I I I-vil a , -
c p4 I .2 j }1 3
b i i* '
a j g il 1 ,
h.
l 1: ,
t i
}.
I J
1 i $I I .i ..
1 c l l..
} ,
I l .. l ;; - -
t
- g o
f } I A l - - -- l l ! I I l -
};
c : t i I 3 3 b
!)
r-I- 3 _ 3 i ql} a : I So,1 I l i I I l i r ii 1]'1l
,. .t ,
3 }
., I ,
I da d q- g g. 2 4
}
1 9 I jjlil I: . ! <I }}::fkt ! Figura 1 f.N :d,} 1 l ON SITE EMERGENCY ORGANIZATION l I
l
~._ --
20 -
, EI 1300.00.2 1 '
. } .! .!
' *,~
l s sa n a T j . ]l i I
, :r.
.:] j j __ ';
ji I y i . j l 8 11 r- 3 ' j; I l'
- i {
s
~
I g
* 'j' I I I J<t ,
~~
l
~
5 l n,' l li! < .j! ' j 11 . 1 l I ((
; ss 1 1 II iI t ,
i s is ; I j - t ] i I i ,.n. 3 } . _____, i: H. . g j {: j. , 1 j g-
- .).
j , f ; i
. i i
i j !..., i j-: pI l I
. i l -l 31 i .
I '{!! jel} i ,, l I i ' l ii I 21 i I j!f o r 3 i j 1, 1 i i ' r }.1 I j- s.j l. -
}
1 i l' 1 l
'1 la
' 1 r -
t a,
}1].
---- a i
j .3.!! j'd li l i
} 2I i
" } -{ l 1
5 t} I i}t < l g} il l !
~~ l I :: : Eg
,1
- i l
l i
, , - =
, i .
-l I
i l I ll 11 - l d .' I-
,5 i t, _
1 1: _ _ _ _l _ _l 1i i e i i IrI <. 1 il . It ji
~
! jl
' ~
j j] l
) .
f.! . ,
!$ - } } ,l l
( 1 j; 3 :.l l h, Ij l t j l j r:
- t . i
' j n .. j l -
j-
-- I j j,s ..
_____q r } l I 1l UU I I I 2 i
- : )
l - I 1 :1 1 19 1 . j.;. _ l j jr. _____ l 3 ,n i,E 1 J.
] .
a ,r
- s. .
2 kl '
, l'
' ~" '*' "
Fi m 2 l OFF SITE EMERGENCY ORGANIZATION l
i I l
)
i 1 l 21 : 13co.co.4 ,
- 1
\
,./ i.
f
,....J I
)l-3:e l 7---i i
i 5 5 y / / ; i : -
~
a a
/,/
4,
= ,! -! t' it 4:
'/ / .. l l l53 j *8 f!Ef
.E
.ar_ r 2 .
i I. : , s- iw . s
- c. .5 =-.
i I..sa: ss. s . ggi - - - . - - - ' I **
'. .53 i
=
N.
**.g" e l
- T 1
\
's % ' = . . i, . :I l s.:
5 s.* s. - l 3. 4.:5
' :ys i.
.3 1s*: ===.t
;p.
;a s 50
\ -
'.....: j==
a=
\, l t
.. !b ._._ _ - _ - : -
u!
.:=:1
' = I. I
- t 5 ,;._ .!g:: sea ,
i i e
- +
- y. >~ s
_h: :. g , .saa a i - Ilg;1 ; 2 l
. 1.t .
i a f v..= g I . ._ . :s
- A led.
,::. - eEi I :. - l
,i.
l 2! 3:
' lg!"
;g i
3 Ig s,. l..::
=-i i
1
.- i. .
w . , [.. l Il st-r -i a
=4
!e
'. .'E!! --:I.:le 3
.-e
. s .s.
i
=
t.3i t i.g-;
- .e; .:j:
- -s in 1 EEll :E!Esi las
' ; g}gj,1, g; gjaj ,
c:
; l.se , ! .
1 I!= - ;
-_ :: i Eag
!:i l . jg i, g-l u.,. ig;c s3 lldil i
- b. .,
*=
; !sE ~3a.i Id"g*
i.s
-at :s tausg
- a:-
;e 3 s!::> .
3 i t.: 3:56 ~ 8 l 343 . d t ]g l"gd. 2 g I _ ,, ,,f li, 1g: :1 ez. l g4 6 p g 58 I 4 I I I .. =x... . Si.- l6 1
- 1 *dT A !
- t g ', '
' '= !!! . ' gs. ] { ' . 9,l 5 * ~I':] *'
- s ,
, ::: . 3: ::: as i
k 5
.i
-i =
.u e.
t j is i - i a 1; .I aff I 3
' *
- 5
' 'I N,
=
3 l . .- $.N zm :: 5
.'! .h
=r-i e .5 :.g
- x. :: :I j,
e ,i ,i i . s
- .n! .a = .
. sa a.m n
- as
{ i
's . I ! I
. ' i i
i i
* !.eE. l$!g=
l Ell -l3=3]
=v ,
e 1 1 i ; "--- l .! I, N----------------------,' l N!:l.ld!!]..I
- }
- i. li. r1 - =. s .:-
1 i
.a 1 an l
Y Y N e
El 1300. 01.0 Davia-Besse Nuclear Power Station Unic No. 1 Emergency Plan Implementing Procedure EI 1300.01 Emergency Plan Activation Record of Approval and Changes Prepared by_ ' G. J. Reed 5/30/80 Submitted by. Date C. E. Wells l Section Head _ 6/13/80 I Date Recommended by M 8 e_s /3!N SRB Chair:stan ~ Date
~
QA Approved _ , A/ A . Quality Assurance Manager ~ _ Approved.by
^
Date N T'> W= ~ Sta'tionSuperintende@
\
~ _
/ k$C Date t- ;
Revision SRB
}
No. QA Recommendation Date Approved Sta. Supt. j b, t,). Q AhotsI Date Approved Ng W Daty p p e = A ,1= & s */'02 o i 3 /ddr 'N/* jJir # W M ]/*,'y'n ; I 7 +.p n .f( g o Im g p = -g al1=-ln I I i I _ _________. ___-__-____-________-_--.__._.-_m__ . _
1 EI 1300.01.3
- 1. PURPOSE To provide guidelines for conditions at which specific emergency 3 classifications must be declared.
- 2. SCOPE 3 To specify emergency action levels and personnel judgments that are consistent with the emergency classification scheme depicted in Appendix 1 of NUREG-0654, Rev. 1.
- 3. REFERENCES 3.1 The Davis-Besse Nuclear Power Station Emergency Plan 3.2 Final Safety Analysis Report, DBNPS 3.3 Technical Specifications, DBNPS Unit No. 1, Appendix A and B to License No. NPF3
( 3.4 Station Response to Emergencies, EI 1300.00 l
- 4. DEFINITIONS 4.1 Unusual Event - Event (s) are in progress or which have occurred that indicate a potential degradation of the level of safety of DBNPS.
4.2 Alert - Events are in progress or have occurred which involve an actual or substantial degradation of the level of safety of DBNPS. 4.3 Site Emergency - Events are in progress or have occurred which involve actual or likely major failures of DBNPS functions needed for the protection of the public. There als.o exists a significant actual or potential release of radioactive material.
-4.4 General Emergency - Events are in progress or have occurred which invo.!ve actualaor imminent substantial core degrada-tion or melting with the potential for loss of containment integrity, and/or involve the potential for a release of radioactive particulates or gases offsite of a magnitude to exceed regulatory limits.
4.5 Emergency Action Levels (EAL's) - Radiological dose rates, specific contamination levels of airborne, waterborne, or surface-deposited concentrations of radioactive materials; or specific instrument readings and indications (including their rate of change) that may be used as thresholds for initiating such specific emergency measures as designating
2 EI 1300.01.3 a particular classification of emergency, initiating a notification procedure, or initiating a particular protec-tive action.
- 5. EMERGENCY MEASLTES 5.1 The Shift Supervisor, when informed that abnormal or emer-gency conditions (real or potential) have arisen, shall 3 perform the necessary actions in the priority listed below:
5.1.1 Ensure that the immediate actions (e.g., use of Emergency Procedures) are taken for the safe and proper operation of the plant. 5.1.2 Assess the information available from valid indication and using Table 1, initially classify the situation with the following considerations: 3
- a. The specific emergency action levels described in Table 1 are not all inclusive. The Shift Supervisor or Emergency Duty Officer shall declare an appropriate emergency classification whenever, in his judgment, the station status warrants such a declaration. (Refer to Step 5.2.2 for guidance.)
' b. Reaching these levels over a period of days , rather than hours is not sufficient to declare the appropriate classification.
l c. Some of the emergency action levels described are not, by their very nature, intended to be used during maintenance and/or testing situa-tions where abnormal temperature, pressure, equipment status, etc. is expected.
- d. All of the emergency action levels shall be considered if the plant is, or was (immediately prior to the emergency condition) in Mode 1 operating at a high power level, except for those conditions noted in the Index of Emer-gency Action Level Conditions, Page 4.
5.1.3 Use the appropriate checklist from either the Unusual Event (EI 1300.02), Alert (EI 1300.03), Site Emergency (EI 1300.04), or' General Emergency 3 (EI 1300.05) procedure to ensure that immediate notification requirements are met and the proper Emergency Plan response is taken. 1 l l
3 EI 1300.01.3 3 5.1.4 Perform additional emergency actions as time and conditions permit. 5.2 Operator judgment plays an important role in ensuring that during any specific event the appropriate actions are performed.
5.2.1 Examples
- a. For an abnormally high lake level, operator judgment should take into consideration the lake level, wind direction, weather con-ditions, etc., before announcing a flood warning and initiating personnel evacuation.
During a previous incident, personnel were evacuated during flood warning conditions, however it was found that this was unnecessary since the weather then cleared and no flood or hazardous situation occurred.
- b. For localized incidents that may affect only small areas, operator judgment should take into consideration that an alarm, when sounded, could be followed by some amplifying instruc-tions to aid personnel response. During a previous incident, an individual was injured
" requiring medical assistance. The Initiate
' Emergency Procedures alarm was sounded, however verbal instructions via the gai-tronics system could have been used to prevent unneeded personnel involvement and assembly.
3 5.2.2 For abnormal plant conditions that are not specifically covered in the Table 1 emergency action levels, the following criteria shall be used to assist the Shift Supervisor or Emergency Duty Officer in classifying the event based on their judgment.
- a. Unusual Event - Other plant conditions exist that warrant increased awareness on the part of the plant operations staff or State and/or local offsite authorities which are not covered under any other existing station procedure.
- b. Alert - Other plant conditions exist that warrant precautionary activation of the Technical Support Center and Emergency Control Center and placing other key emergency per-sonnel on standby.
T
, -, r war
4 EI 1300.01.3
- c. Site Emergency - Other plant conditions exist that warrant activation of emergency centers and monitoring teams or a precautionary notification to the public near the site.
- d. General Emergency - Other plant conditions exist, from whatever source, that make release of large amounts of radioactivity in a short time period possible, e.g., any core melt situation.
5.3 Plant conditions should be continually evaluated to ensure the proper emergency classification is being utilized and the classification upgraded or downgraded by the Shift Supervisor and Emergency Duty Officer as conditions dictate 3 per Table 1 and Steps 5.1.x and 5.2.2 above. f I 4 9 i
-=,r w w-V e -W -
5 El 1300.01.3 INDEX OF EMERGENCY ACTION LEVEL CONDITIONS Condition Page No(s). 3l
- Safety System Functions 6-7 Plant Shutdown Functions 8 Coolant Pump Seizure 9 Loss of Assessment Functions 10 Control Room Evacuation 11
*Abnorraal Coolant Temperatures 12 3
- Abnormal Primary Leak Rate 13-14 Abnormal to Primary / Secondary Leak Rate 15-16 3l
- Core Fuel Damage 17-18 Loss of Fission Product Barriers 19
- Fuel Handling Accident 20 Abnormal Containment Atmosphere 21
- Abnormal Effluent Release 22
*High Radiation Levels in Plant 23
- Abnormal Radiation Levels at Site Boundary 24-26
- Contaminated Personnel 27 Major Steam Leak. 28-29 l
Major Electrical Failures 30 l
- Fire 31 1
- Security Threat 32 l
- Hazards to Station Operation 33-35
- Natural Events (Within Ottawa County) 36-38 3
- NOTE: When evaluating the EAL's in Table 1, the plant must be in Mode 1 or had been in Mode 1 operating at a high power level when the event initiated, except for those annotated conditions above which have been broken down and noted, as applicable, in their respective sections of Table 1.
l l 6 EI 1300.01.3 TABLE 1 SAFETY SYSTEM FUNCTIONS Emergency Condition Indication (s) Classification 3l Unplanned Initiation Any three of the four fol- Unusual Event
- of ECCS with Flow into lowing with flow indicated: (EI 1300.02)
Core Indicated 1. HPI low flow alarm and/or LPI low flow alarm (on then off)
- 2. HPI and/or LPI pump status lights indicate pump (s) running
- 3. HPI and/or LPI pump current meters indicate pump (s) running
- 4. HPI and/or LPI pump discharge valves indicate open Loss of Containment Any 09- of the four following Unusual Event Integrity requiring plant shutdown per (EI 1300.02)
T.S. 3.6.1.1:
- 1. Any penetrations required to be closed during accident conditions that are not:
A. Capable of being closed by the Safety Features Actuation System, OR B. Closed by manual valves, blind flanges, or de-activated automatic valves secured in their closed position except as provided in T.S. 3.6.3.1 Table 3.6-2
- 2. An equipment hatch is not closed and sealed
- 3. An airlock is not operable per T.S. 3.6.1.3
- 4. A sealing mechanism assoc-iated with a penetration (e.g., welds, bellows, or 0-rings) becomes inoperable 3 -NOTE: For the above asterisked (*) classification (s) the plant can be in any Mode for the listed EAL's to be applicable.
l l
7 EI 1300.01.4 TABLE 1 SAFETY SYSTEM FUNCTIONS (Con't) Emergency
- Condition Indication (s) Classification Loss of Engineered 1. A Safety Features Unusual Event Safety Feature Actuation System (SFAS) (EI 1300.02) functional unit shown in T.S. Table 3.3-3 becomes inoperable per T.S.
3.3.2.1 and requires plant shutdown OR
- 2. The Boron Injection Flow Path (operating) or Borated Water Sources (operating) become in-operable and require plant shutdown per T.S. 3.1.2.2 and 3.1.2.9 Failure of Safety 1. Reactor Coolant System: Unusual Event Related Safety or Relief A. Indication of flow (EI 1300.02)
Valve to Close through Pressurizer Reliefs (red light on Panel C5798 or C5799) AND B. RCS Pressure drop to <1600 psig
- 2. Main Steam System:
(any 2 of 3) A. Rapid and continuing decrease in Steam Gen-- erator pressure to <500 Psig B. Rapid RCS cooldown rate C. Audible steam relief noise in the Control Room lasting >10 minutes 4 Loss of Steam Feed 1. A Steam Feed' Rupture Con- Unusual Event Rupture Control System trol System (SFRCS) Func- (EI 1300.02) l tional Unit as shown in ] T.S. Table 3.3-11 becomes inoperable per T.S. 3.3.2.2
- and requires plant shutdown I
( y o w - . , - - ,c - - y , - ,
I i 1 8 EI 1300.01.1 TABLE 1 PLANT SHUTDOWN FUNCTION Emergency Condition Indication (s) Classification Loss of any system which 1. Any of the following Alert precludes placing the systems become inoperable: (EI 1300.03) 1 plant in cold shutdown A. Service Water System (botn trains) B. Decay Heat System (both trains) C. Component Cooling Water (both trains) Loss of any system which 1. The following systems Site Emergency precludes placing the become inoperable: (EI 1300.04) plant in hot shutdown A. Makeup System and HPI System OR B. Main Feedwater System and Auxiliary Feed-water System Failure of Reactor Pro- 1. Any time plant parameters Alert tection System to in'tiate meet conditions requiring (EI 1300.03) and complete a trip a trip and RPS fails to initiate and complete a trip which brings the reactor suberitical e 9 o l l 1 1
1 i l l 9 EI 1300.01.0 TABLE 1 COOLANT PUMP SEIZURE Emergency Condition Indication (s) Classification Coolant pump seizure with 1. Reactor Coolant System Alert fuel damage indicated flow indication decreases (EI 1300.03) by Iodine sample > T.S. rapidly 3.4.8 AND
- 2. Confirmed Primary Coolant sample results indicate
>1.0 pCi/ Gram dose equiv-alent I-131
*- w- eon,- , ,
10 EI 1300.01.3 TABLE 1 LOSS OF ASSESSMENT FUNCTIONS Emergency Condition Indication (s) Classification Control Room Indications Any of the Following: Unusual Event or Alarms on Process or 1. Radiation monitoring (EI 1300.02) Effluent Parameters NOT instrumentation < min-functional to an extent imum channels operable requiring plant shutdown requiring shutdown per T.S. or other significant loss requirements 3 of assessment or communica- OR tion capability 2. RE2024A, B & C, RE2025A ,B
& C and Backup Grab Sample capability become in-operable OR
- 3. Meteorological monitoring instrumentation < min-imum necessary to perform affsite dose calculations
'i.e. wind speed, wind direction, and stability class)
OR
- 4. Post-accident instrument-ation < minimum channels operable requiring plant shutdown per T.S.
requirements (T.S. 3.3.3.6) OR
- 5. Complete failure of the plant telephone system and Gai-tronics system All annunciator alarms 1. Any simultaneous loss Alert and station computer of all annunciator (EI 1300.03) lost alarms and the station computer All annunciator alarms 1. Complete loss of all Site Emergency and station computer lost annunciator alarms (EI 1300.04)
>15 minutes during plant and station computer transient lasting more than 15 minutes AND
- 2. Plant transient initiated or in progress i
1 l l l l
11 EI 1300.01.0 TABLE 1 CONTROL ROOM EVACUATION Emergency Condition Indication (s) Classification Evacuation of Control Room 1. Any evacuation of the Alert required Control Room with shut- (EI 1300.03) down coctrol established locally within 15 minutes
. Evacuation of Control Room 1. Any evacuation of the Site Emergency and Control NOT estab-
- Control Room with shut- (EI 1300.04) lished locally within down control NOT estab-15 minutes lished locally within 15 minutes
12 EI 1300.01.3 TABLE 1 ABNORMAL COOLANT TEMPERATURES Emergency Condition Indication (s) Classification 3 Core Subcooling is 1. As determined by Sub- Unusual Event
- Determined to be less Cooling graph or T,,g (EI 1300.02) than normal (10') Meter Indication (TD14950 or TD14951)
AND
- 2. As indicated by the difference between Pres-surizer Temperature and 3
Th (use incore thermo-couples temperature if. Th meter is off-scale) 3 Coolant Temperatures 1. As determined by the Unusual Event
- and/or pressures outside combination of Reactor (EI 1300.02) of Technical Specification Coolant Core Outlet limits Pressure and/or Outlet
- _ Temperature es
- ceeding the safety limits of T.S. 2.1.1 3 NOTE: For the above asterisked (*) classification (s), the plant can be in any mode for the listed EAL's to be applicable.
4 J s i s esw e- e w s .< - e u -w - e--
s 'I 13 EI 1300.01.3 TABLE 1 ABNORMAL PRIMARY LEAK RATE Emergency Condition Indication (s) Classification Leak Rate Requiring 1. RCS Water Iaventory Unusual Event Plant Shutdown by Balance indicates (EI 1300.02) TS Section 3.4.6.2 >l GPM unidentified leakage or >10 GPM ' identified leakage OR
- 2. Measurement of controlled leakage from the Reactor Coolant Pump seals is.>10 GPM total OR 3 3. Leakage from any RCS pres-
- sure isolation valve >5 gpm as listed in TS Table 4
3.4-2 i Leak Rate >50 GPM but Any Two of the Four Following: Alert
- 3 within High Pressure 1. Makeup Tank level (EI 1300.03)
Injection' system decreasing approximately t capacity two inches per minute while RCS temperature remains steady
- 2. Increased activity on Con-tainment Vessel Airborne Monitor (s) RE 4597AAA, AAB
,. AAC, or RE 4597BAA, BAB, . j BAC 3
- 3. Increase in Normal Sump level on level instruments LI 1546 A or B
- -4. RCS Water Inventory Balance indicates
>50 GPM leakage Loss of Coolant ~ Accident 1. Pressurizer level and Site Emergency
, > High Pressure Injection pressure decreasing' (EI 1300.04) system capacity . rapidly without an associated change in RCS temperature (RCS tempera-ture/ pressure reach saturation conditions) OR l
" ~~
_._.z,
i 14 EI 1300.01.3 TABLE 1 _ ABNORMAL PRIMARY LEAK RATE Emergency ' Condition Indication (s) Classification
- 2. Containment pressure >38.4 psia and Reactor Coolant System pressure <400 psig
. 3 NOTE: For: the above asterisked (*) classification (s), the plant can be in any Mode for the listed EAL's to be applicable.
/
i
- - , v-v. ,
i a 15 EI 1300.01.3 TABLE 1 ABNORMAL PRIMARY TO SECONDARY LEAK RATE Emergency Condition indication (s) Classification Leak Rate Requiring RCS Water Inventory
- Unusual Event Plant Shutdown by Balance indicates >l (EI 1300.02)
TS 3.4.6.2 GPM total Primary to Secondary leakage And the Following:
- 1. Main Steam Line Radiation monitor (s) (RE 600 and/or 3 RE 609) in the " Analyze Mode" to detect N-16 indicate increased activity OR
- 2. Condenser Vacuum dis-charge radiation monitor (s)
(RE 1003A (B)) indicate increased activity AND
- 3. Unexplained Makeup tank level decrease while Reactor Coolant System temperature remains constant 3 Rapid failure of Steam Main Steam Line Radiation . Alert Generator tubes (e.g., monitor (s) (RE 600 and/or (EI 1300.03) several hundred gpm RE 609) in the " Analyze Mode" primary to secondary to detect N-16 indicate leak rate!) increased activity, or Con-denser Vacuum discharge radia-tion monitor (s) (RE 1003 A (B)) indicate increased activity
, And One of the Following:
- 1. Rapid drop in RCS pressure
- 2. Rapid decrease in Pres-surizer and Makeup Tank levels
- 3. Safety Features Actuation System (SFAS) Level 2 activates I
16 EI 1300.01.3 TABLE 1 1 ABNORMAL PRIMARY TO SECO EARY LEAK RATE Emergency Condition Indication (s) Classification 3 4. Main Steam line radiation monitors in the " Gross Mode" indicating more than 15000 ' cpm net; background equals 1000 cpm Rapid failure of one Steam 1. Noticable drop in Alert Generator tube and loss of RCS pressure and pres- (EI 1300.03) offsite power surizer level , , AND
- 2. The 13.8 KV RUSES are.
deenergized AND 3 3. Main Steam line radia-tion monitors in the
" Gross Mode" indicating more than 15000 cpm net; background equals 1000 cpm 3 Rapid failure of Steam 1. Indications for leak Site Emergency Generator tubes (several rate of 400-700 GPM (EI 1300.04) hundred GPM leak rate AND indicated) and loss of 2. The 13.8 KV BUSES are offsite power deenergized m ,. ..- - ,- , . . ~ , , - , , ._- ..
17 EI 1300.01.3 TABLE 1 CORE FUEL DAMAGE Emergency Condition Indication (s) Classification 3 High Coolant activity 1. Failed Fuel Detector (RSH Unusual Event sample Requiring Plant 1998) alarm with confirmed (EI 1300.02) Shutdown by Technical sample results indicating Specifications for Iodine >1.0 pCi/ Gram Dose Equiv-(1.S. 3.4.8) alent I-131 AND
- 2. Plant Shutdown required -
3 Very High Coolant 1. Failed Fuel Detector (RSH Alert activity 1998) "RC Letdown Activity (EI 1300.03) High" alarm AND
- 2. Confirmed sample results indicate >300 pCi/ Gram I-131 Core damage with in- 1. Confirmed primary coolant Site Emergency adequate core cooling sample results indicate: (EI 1300.04) determined A. >1.0 pCi/ Gram Dose equivalent I-131, and B. >100/E pCi/ Gram specific activity, AND
- 2. Reactor Coolant System Hot Leg temperature >620*F OR
- 3. Incore thermocouple temper-atures increasing to >700*F Core damage with other 1. Confirmed primary coolant General Emergency plant conditions making sample results indicate (EI 1300.05) 3l a release of large >300 pCi/ Gram I-131 amounts of radioactivity AND possible 2. Incore thermocouple temper-atures indicate >2000*F AND
- 3. Containment radiation level !
3 is > 104 R/hr ' OR
- 4. Containment pressure is
>40 psia i
I i ,. , . , . . . . . . . .. .-
. _ _ . - - - - - - . _ _ . _ - - - - - - - - - - - - - - - - - - - - - - - ^ - - - - - - - - - - - - - - -
l 1 1 18 EI 1300.01.3 TABLE 1 CORE FUEL DAMAGE Emergency Condition Indication (s) Classification 3 Core melt situations Any one of the following General Emergency sequences occurs with a concurrent likely failure of (EI 1300.05) containment imminent:
- 1. Either a small or large LOCA occurs with a con-current failure of the ECCS to perform leading to severe core degradation or melting
- 2. A transient is initiated by a loss of the main feedwater system followed by a failure of the emer-gency feedwater system for an extended period with core melting resulting
- 3. A transient occurs requiring operation of shutdown systems with failure to trip which results in core damage, or additional failures of core cooling and makeup systems occur which lead to a core melt
- 4. A failure of offsite and onsite power along
, with total loss of emer- ! gency feedwater makeup capability occurs for several hours which leads to a core melt
- 5. A small LOCA occurs with initially successful ECCS, however a subsequent fail-ure of RCS heat removal systems over a period of several hours leads to a core melt 1
w m w e-
19 EI 1300.01.3 TABLE 1 LOSS OF FISSION PRODUCT BARRIERS Emergency Condition Indication (s) Classification Loss of 2 of 3 fission Anv Two of the following General Em.rgency product barriers with a conditions exist and the (EI 1300.05) potential loss of the Third is imminent: 3rd barrier 1. Fuel clad is ruptured as indicated by grab sample results . 2. A rupture of the RCS has been confirmed
- 3. Containment integrity has been breached and cannot be restored 3 NOTE: Other sections of Table I can be used for guidance in determining the above three conditions, as follows:
- a. For item 1, refer to " Core Fuel Damage" at the Alert and Site Emergency levels for sample result values and indi-cations.
- b. For ites 2, refer to " Abnormal Primary Leak Rate" at the Alert and Site Emergency levels for indications of a loss of primary coolant.
- c. For item 3, refer to " Safety System Functions" a Loss of Containment Integrity condition at the Unusual Event level for indications of a breach in Containment integrity.
t
+ r-, . - - + - -
d 20 EI 1300.01.3 TABLE 1 FUEL HANDLING ACCIDENT 4 Emergency Condition Indication (s) Classification )- Fuel Handling Accident 1. Direct information from Alert * ! which results in the . fuel handling personnel (EI 1300.03) release of radioactivity indicating that an to Containment or Spent irradiated fuel assembly Fuel Pool area has been damaged and radf9 active gases are escaping AND 3 2. Fire Detection System / Radiation Monitoring System (FDS/RMS) alarms with high radiation monitor reading printed out on data logger OR
- 3. Local Radiation Monitoring Alarm Station alarms both audibly (born) and visually (green light goes OFF and red light comes ON) and is reported to the Control Room Fuel Handling Accident 1. Indications of fuel hand- Site Emergency * {
which results in SFAS ling accident which results (EI 1300.04) j actuation in the release of radio- < activity to Containment or Spent Fuel Pool area AND
- 2. SFAS incident level one actuation on radiation in Containment or isola-tion of ventilation in fuel handling area based on radiation 3 NOTE: For the above asterisked (*) classification (s), the plant can be in any Mode for the listed EAL's to be applicable.
~
I 21 EI 1300.01.5 TABLE 1 ABNORMAL CONTAIN?D T ATMOSPHERE Emergency Condition Indication (s) Classification Increasing Containment Any Two of the Following: Alert radiation, pressure, and 1. Containment high range (EI 1300.03) 5 temperature monitor (s) (RE 4596A or B indicate greater than 50 R/hr)
- 2. Containment pressure (PI 2000, PI2001, PI2002, PI 2003) indicates >17 psia
- 3. Containment average air temperature (TI1356, TI 1357, TI1358) indicates
>170'F High Containment radia- Any Two of the Following: Site Emergency tion, pressure and 1. Containment high range (EI 1300.04) temperature radiation monitor (s) 5 (RE 4596A or B indicate greater than 50 R/hr)
- 2. Containment pressure (PI 2000, PI2001, PI2002,.PI 2003) indicates >20 psia
- 3. Containment average air temperature (TI1356, TI 1357, TI1358) indicates
>200*F
- 4. Safety Features Actuation System (SEAS) functions
\ have activated Very High Containment Any Two of the Following: General Emergency radiation and pressure 1. Containment high range (EI 1300.05) radiation monitor (s) 5 (RE 4596A or B indicate greater than 10,000 R/hr)
- 2. Containment pressure (PI 2000, PI2001, PI2002, PI 2003) indicates >40 psia
- 3. Safety Features Actuation System (SFAS) functions have activated and Con-tainment Spray is operating
f 22 EI 1300.01.3 l l TABLE 1 ABNORMAL EFFLUENT RELEASE Emergency Condition Indication (s) Classification 3l Effluent Release > limits Confirmed analysis results Unusual Event
- allowed by E.T.S. 2.4.1 or for a gaseous or liquid (EI 1300.02)
E.T.S. 2.4.3 release indicates > the limits given in the Environ-mental Technical Specifica-tions Effluent release >10 Confirmed analysis results Alert times instantaneous for a gaseous or liquid (EI 1300.03) limits allowed by E.T.S. release indicates >10 2.4.1 or E.T.S. 2.4.3 times the instantaneous limits given in the Environ-mental Technical Specifica-tions 3 NOTE: For the above asterisked (*) classification (s), the plant can be in any Mode for the listed EAL's to be applicable. a 1
\_ ,
-, , - , e r
- r
- r. .
I 23 EI 1300.01.3 f TABLE 1 HIGH RADIATION LEVELS IN PLAhT Emergency Condition Indication (s) Classification General area radiation 1. Fire Detection System / Alert
- levels or high airborne Radiation Monitoring (EI 1300.03) radioactivity >1000 times System (FDS/RMS) Console normal from an unidentified Alarm with high radiation 3 source, lasting more than 30 monitor reading displayed minutes on CRT and printed out on data logger OR
- 2. Local Radiation Monitoring Alarm Station alarms both audibly (Horn) and visually (green light goes off and red light comes on) and is reported to the Control Room
. AND
- 3. An area radiation survey or airborne radioactivity sample indicates activity levels >1000 times normal 3 NOTE: For the above asterisked (*) classification (s) the plant can be in any Mode for the listed EAL's to be applicable.
I o i
. . . . . .. - -___.m. -- -__ - - --
24 EI 1300.01.3 TABLE 1 ABNORMAL RADIATION LEVELS AT SITE BOUNDARY Emergency Condition Indication (s) Classification l-Projected or actual 1. Station Vent Monitor - Alert
- radiation readings that (RE2024C or 2025C) read- (EI 1300.03) l indicate a potential dose ing >0.1 pCi/cc Xe-133*
i of 100 mR Whole Body'or for 2 hours or readings NOTE: (These are 500 mR Child Thyroid at which will give an equiv- the appli-3 the Site Boundary using valent dose in <2 hours cable con-adverse me.teorology. 2. Station Vent Monitor centrations, (RE2024B or 2025B) read- however they ing >7.2 x 10-s pCi/cc I-131 can not be for 2 hours or readings obtained which will give an equivalent from the dose in <2 hours presently
- NOTE: This concentra- 3. Radiation Monitoring Team installed tion is based on reports radiation levels at instrumenta-a stability class Site Boundary <50 mR/hr for tion. They of F and wind speed an incident projected to last are to be of 2 mph; if actual 2 hours or reports of read- used when the meteorology is used, ings whien will give an Kamen High this concentration equivalent dose in <2 hours range non-may be higher 4. Radiation Monitoring Team itors are reports I-131 concentrations installed.
>1.1 x 10-7 pCi/cc at Site Boundary j Projected or actual radia- 1. Grab sample, or Station Site Emergency
- tion readings that indi- Vent Monitor (RE2024C or (EI 1300.04) cate a potential dose of 2025C) reading >1.0 pCi/cc 1 rem Whole Body or 5 rem Xe-133* for 2 hours or NOTE: (These are s Child Thyroid at the Site readings which will give an the appli- 1 3 Boundary using adverse equivalent dose in <2 hours cable con-meteorology. 2. Station Vent Monitor centrations, !
(RE2024B or 2025B) > 7.2 however they l x 10-5 pCi/cc I-131 for can not be 2 hours or readings which obtained will give an equivalent from the dose in <2 hours presently
- NOTE: This concentra- 3. Radiation Monitoring Team installed tion is based on reports radiation levels instrumenta-a stability class >500 mR/hr at the site tion. They of F and wind speed boundary for an incident are to be of 2 mph; if actual projected to last 2 hours used when meteorology is used, or which will give an equiv- the Kamen this concentration alent dose in <2 hours High range
25 EI 1300.01.3 TABLE 1 ABNORMAL RADIATION LEVELS AT SITE BOUNDARY Emergency Condition Indica
- ion (s) Classification
- . may be higher 4. Radiation Monitoring Team monitors reports I-131 concentrations are in-
>1.1 x 10-8 pCi/cc at the stalled.
Site Boundary 3; NOTE: For the above asterisked (*) classification (s), the plant can be in any Mode for the listed EAL's to be applicable. f I e k 4 4
* , + 1
26 EI 1300.01.3 TABLE 1 ABNORMAL RADIATION LEVELS AT SITE BOUNDARY Emergency Condition Indication (s) Classification i Projected or actual site A radiological puff release Site Emergency *
! boundary radiation readings (short instantaneous release (EI 1300.04) 3' corresponding to a whole from a non-continuous source) body dose of 50 mr/hr for occurs with:
1/2 hour or 500 mr/hr for 1. Station vent monitor ; 2 minutes using adverse RE 2024C or 2025C readings l meteorology or five times and analysis indicating l these levels for a thyroid 9.6 x 10-2 pCi/cc* for 1/2 ; dose. hour or .96 pCi/cc* for 2 4 min.
- NOTE: These are the ap- OR ,
plicable concen- 2. Station vent monitor RE l trations, however 2024B or 2025B readings l they cannot be ob- and analysis irdicate I tained from the pre- 7.2 x 10-s pCi/cc* for sently installed in- for 1/2 hour or 7.2 x stalled instrumenta- 7.2 x 10-5 pCi/cc* for tion. They are to 2 min. used when the Kamen High range monitors are installed in the near future. Projected or actual site A radiological release General Emergency
- boundary radiation read- occurs with: (EI-1300.5) ing corresponding to a 1. Projected doses at the whole body dose of 1 R/hr site boundary equate to or a thyroid dose of 5 1 R/hr whole body or 5 R/hr asing actual R/hr thyroid (or higher) meteorology. using actual meteoroligi-cal data.
OR ,
- 2. A Radiation Monitoring Team at the site boundary reports radiation levels at 1 R/hr or 2.27 x 10-8 pCi/cc I-131 (or higher).
NOTE: For the above asterisked (*) classification (s), the plant can be in , any Mode for the listed EAL's to be applicable.
27 EI 1300.01.3 TABLE 1-
, , . , CONTAMINATED PERSONNEL Emergency Condition Indication (s) Classification Transportation of con- 1. ,Any event which requires Unusual Event
- taminated injured in- transportation of a con- (EI 1300.02) dividual(s) offsite taminated injured indi-vidual to an offsite medical facility 3l NOTE: For the above asterisked (*) classification (s), the plant can be in j any Mode for the listed EAL's to be applicable.
l t k 1
l l l 28 El 1300.01.3 TABLE 1 MAJOR STEAM LEAK Emergency Condition Indication (s) Classification Major Steam Leak with Increasing Containment pres- Unusual Event NO Primary to Secondary sure (if leak is inside Con- (EI 1300.02) leakage tainment) or unusually loud noise outside Containment And One of the Following:
- 1. Steam and Feedwater Rupture Control System (SFRCS) initiates
- 2. Main Steam Pressure (s) and/or Steam Generator Pressure (s) drop to <300 PSIG Major Steam Leak with 1. Indication of a Major Alert
>10 GPM Primary to Steam Leak (EI 1300.03)
Secondary Leak Rate AND
- 2. Main Steam Line Radiation Monitor (s) (RE 600 and/or RI 609) in the " Analyze Mode" to detect N-16 indicate increased activity, AND
- 3. RCS Water Inventory Balance indicates >10 GPM Primary to Secondary leakage 3 4. Main Steam line radiation i monitors in the " Gross Mode"
! indicating more than I 15000 cpm net; background l equals 1000 cpm Major Steam Leak with 1. Indication of a Major Site Emergency
! >50 GPM Primary to Steam Leak (EI 1300.04)
! Secondary leak rate and AND fuel damage indicated 2. Main Steam Line radiation monitor (s) (RE 600 and/or RE 609) in the " Analyze Mode" to detect N-16 indicate increased activity AND
.29 EI 1300.01.3 TABLE 1 MAJOR STEAM LEAK Emergency Condition Indication (s) Classification
- 3. RCS k'ater Inventory Balance indicates >50 GPM Primary to Secondary Leak rate AND'
- 4. Confirmed Primary Coolant sample results indicate Dose Equivalent I-131 above acceptable limits-of T.S. Figure'3.4-1 4
AND 3 5. Main steam line radiation monitors in the " Gross Mode" indicating more than 150,000 cpm net;- background equals 1,000 cpm. .I 4 i. a 4 e m x .se e , -. ,- - y , -- -+ +- -s,- ,- p - , - ,
30 EI 1300.01.3 TABLE 1 MAJOR ELECTRICAL FAILURES Emergency Cendition Indication (s) Classification 3l Loss of offsite power 1. Both Emergency Diesel Unusual Event or of casite AC power Generators and the Main (EI 1300.02) capability Generator out of service simultaneously OR
- 2. Loss of all three 345 KV transmission lines 3l Loss of offsite power 1. All AC bures deenergized Site Emergency and all onsite AC power more than 15 minutes (EI 1300.04) for more than 15 minutes 3l Loss of all onsite 1. All DC buses deen- Alert DC power ergized as determined (EI 1300.03) by breaker positions, and line voltage or amperage meters Loss of all onsite DC 1. All DC buses deenergized Site Emergency power for more than 15 for more than 15 minutes (EI 1300.04) minutes l
i l i i I l l e
- , . , , ,,, w--, . - , _ - - - , , , . , - , - - ,
31 EI 1300.01.3 TABLE 1 FIRE Emergency Candition Indication (s) Classification Uncontrolled fire NOT 1. Any fire at the Station Unusual Event
- involsing a safety that requires offsite (EI 1300.02) system, but requiring support offsite support Uncontrolled fire 1. Any fire at the Station- Alert potentially affecting that requires offsite (EI 1300.03) safety systems and support requiring offsite AND support 2. Has the potential to damage or degrade a safety system 3 Fire resulting in the 1. Observation of a major Site Emergency loss of redundant fire that defeats the (EI 1300.04) safety system trains capability of redundant or functions safety system trains which includes both trains or functions 3 NOTE: For the above asterisked (*) classification (s), the plant can be in any Mode for the listed EAL's to be applicable.
e m --
32 EI 1300.01.3 TABLE 1 SECURITY THREAT Emergency Condition Indication (s) Classification Security Threat, Attempted 1. Report by a senior Unusual Event
- Entry, or Attempted member of the Security (EI 1300.02)
Sabotage Force of an Attempted Entry, Attempted Sabotage, or a Security Threat Ongoing Security 1. Report by a senior Alert
- Compromise member of the Security (EI 1300.03)
Force that a Security Emergency is in progress Imminent loss of physical 1. Physical attack on the Site Emergency
- control of the plant plant involving Seminent (EI 1300.04) occupancy of the Control 3l Room or local shutdown stations Loss of physical control 1. Physical attack on the General Emergency
- of the facility plant which has resulted (EI 1300.05) in occupation of the 3l Control Room or local shutdown stations by unauthorized personnel 3 NOTE: For the above asterisked (*) classification (s), the plant can be in any Mode for the listed EAL's to be applicable.
1
i 1 l 33 EI 1300.01.3 TABLE 1 HAZARDS TO STATION OPERATIONS Emergency Condition Indication (s) Classification Aircraft crash onsite or 1. Control Room informed by - Unusual Event
- unusual aircraft activity Station personnel who have (EI 1300.02) over facility made a visual siting Aircraft crash affect- 1. Control Room informed Alert ing plant structures by Station personnel who (EI 1300.03) have made a visual siting Aircraft crash damaging 1. Control Room informed by Site Emergency vital plant systems Station 1(rsonnel who have (EI 1300.04) made a visual siting AND
- 2. Instrumentation readings on vital systems indicate equipment problems Train derailment onsite 1. Control Room informed by Unusual Event
- Station personnel who have (EI 1300.02) made a visual siting AND 3 2. Station Structures have been damaged OR
- 3. Danger or potential danger to Station personnel exists Onsite explosion Control Room informed by Unusual Event
- Station personnel who have (EI 1300.02) made a visual siting Onsite explosion affect- 1. Control Room informed by Alert ing plant operations Station personnel who have (EI 1300.03) made a visual siting AND
- 2. Instrumentation readings on plant systems indicate equipment problems 3 NOTE: For the above asterisked (*) classification (s), the plant can be in any Mode for the listed EAL's to be applicable.
. _ . . _ _ _ _ _ . . _ . . ~_. . .._ . . ..
e 34 EI 1300.01.3
- TME 1 1
4 HAZARDS TO STATION OPERATIONS (Con't) Emergency. j Condition Indication (s) Classification Explosion causing severe 1. Explosion causing either Site Emergency damage to hot shutdown of the'following combina- (EI 1300.04) equipment tions of systems to become inoperable: A. Makeup System and HPI System OR l B. Main Feedwater System
; and Auxiliary Feed j water System 3l Toxic or flammable gas -1. Control Room informed by Unusual Event
- release from its con- Station personnel who (EI 1300.02) tainer to atmosphere at have discovered it life' threatening levels near or onsite Uncontrolled toxic or 1. Control Room informed by Alert
, flammable gas release Station personnel who have (EI 1300.03) at life threatening levels made a visual siting
! within plant facilities OR i- 2. Chlorination System Trouble Alarm initiates and Station personnel verify a signifi-cant release Uncontrolled toxic or 1. Control Room informed by Site Emergency l flammable gas release at Station personnel who have (EI 1300.04) i life threatening levels made a visual siting within plant vital areas AND
- 2. Chlorination System-Trouble i
Alarm initiates and Station personnel verify a signifi-cant release OR
- 3. The Control Room Ventila-tion System automatically ~
shuts down 3 NOTE; For the above asterisked (*) classification (s), the plant can be in
- any Mode for the' listed EAL's to be applicable.
i av . +n* r , - , ,
'.+.,-,. - , - . - , - , ,- - -
,.,w m --i r - ~, , g
l I l l 1
-35 EI 1300.01.0 TABLE 1 4
HAZARDS TO STATION OPERATIONS'(Con't) Emergency Condition Indication (s) Classification Turbine damage causing Control Room informed by Alert casing penetration Station personnel who have (EI 1300.03) made a visual inspection of turbine casing Missile impact on plant Control Room informed by Alert structures Station personnel of any (EI 1300.03) missile Missile impact causing 1. Control Room informed by Site Emergency severe damage to Hot Station personnel of any (EI 1300.04) Shutdown equipment missile impact on Hot Shut-down equipment AND
- 2. Instrumentation readings on Hot Shutdown equipment indicate equipment problems Y
i (
36 EI 1300.01.3 TAB ~C 1 NATURAL EVENTS (WITHIN OTTAWA COUNTY) Emergency Condition Indication (s) Classification Any earthquake 1. Confirmed Station Seismic Unusual Event
- Instrumentation Alarm (EI 1300.02) 3 Earthquake > Operating 1. Procedure for Earthquake Alert Basis Earthquake (OBE) Evaluation (SP 1105.17) (EI 1300.03) levels indicates earthquake >.08 g Earthquake > Safe 1. Procedure for Earthquake Site Emergency Shutdown Earthquake Evaluation (SP 1105.17) (EI 1300.04)
(SSE) levels indicates earthquake 5 I
>.15 g
.Any Tornado onsite 1. Control Room informed by Unusual Event
- Station personnel who have (EI 1300.02) made a visual siting of a.
Tornado crossing the site boundary Tornado striking 1. Control Room informed by. Alert facility Station personnel who have (EI 1300.03) made a visual siting Hurricane 1. Control Room informed Unusual Event
- by Load Dispatcher of .(EI 1300.02)
Hurricane Watch for Ottawa County 3l Hurricane force winds up 1. Control Room informed by- Alert to Design Basis Levels Load Dispatcher of (EI 1300.03) Hurricane striking Ottawa County AND
- 2. Wind speed indication from the station meteorological tower is of sustained winds approaching 90 mph 3 NOTE: For the above asterisked (*) classification (s), the plant can be in .
any Mode for the listed EAL's to be applicable. N _ _ _ - _ ___- _ __ _ --____-_- _ __ - _ -
37 EI 1300.01.4 TABLE 1 NATIIRAL EVENTS (WITHIN OTTAWA COUNTY) (Con't) Emergency Condition Indication (s) Classification 3l Hurricane force winds 1. Control Room informed by Site Emergency
> Design Basis Levels Load Dispatcher of (EI 1300.04)
Hurricane striking Ottawa County AE
- 2. Wind speed indication from the station meteorological tower of sustained winds above 90 mph 50 year flood or low 1. Control 2oom informed by Unusual Event
- 3 water,~ surge or Load Dispatcher (EI 1300.02) seiche OR
- 2. Control Room informed by Station personnel who have made visual siting AND
- 3. High Forebay level alarm or lake level indication oscillating with readings-high (>580 feet I.G.L.D.)
or low (<565 Feet I.G.L.D.) 3 Flood, low water, surge 1. -Control Room informed by Alert or seiche at Design Load Dispatcher (EI 1300.03) Levels OR
- 2. Control Room informed by Station personnel who have made visual siting AE
- 3. High Forebay level alarm or lake level oscillating with readings at Design Levels high (584 feet I.G.L.D.) or low 562.1 feet I.G.L.D.)
3 NOTE: For the above asterisked (*) classification (s), the plant can be in any Mode for the listed EAL's to be applicable. 't I
- - . ~ -- , , - ...
38 EI 1300.01.3 TABLE 1 NATURAL EVENTS (WITHIN OTTAWA COUNTY) (Con't) . Emergency Condition Indication (s) Classification
-3 Flood, low water, surge 1. Control Room informed Site Emergency or seiche > Design Levels by Load Dispatcher (EI 1300.04)
OR
- 2. Control Room informed by Station personnel who have made a visual siting AND
- 3. High Forebay level alarm or lake ~ level indication oscillating with readings
> Desiga Levels high (>584 feet I.G.L.D.) or low
(<562.1 feet I.G.L.D.) 4 e l d W E
TRisuTioN originee, Respone604e Seet6en Head Amtson f _ Pile Copy. Mesent File CcPtES TO BE MoOIPIED PoM IMME01 ATE IMPLEMENTATION DAVIS BESSE NUCLEAR POWER STATION . UNIT 1 2 ShifC Supervisor - 2
-'*C.C*
l TEMPORARY MODIFICATION REQUEST Eo se2e Control Room - 2 SECTION 1 PROCEDURE TITLE AND NUMBER Unusual Event EI 1300.02 REASoNPoRCHANoE For added clarification of an EDO responsibility. To ensure the prompt notification of Key Emergency Fesponse Personnel and Agencies, if required. cMANGE Add a note to section 5.2.3 as follows: 5.2.3 NOTE: If the E.D.O. reports to the E.C.C., he should contact the Emergency Planning Supervisor (E.P.S.) by telephone, or request Control Room personnel to contact the E.P.S. via the Emergency Call System individual page. 15 PRoCEcuRE REVIsloN REQUIRED PREPAREDSY DATE
^~ "=" =^"
c 1 ,_ z _._ N c,6 A
.-o
.. qpjj g ..TE yjgj H DATE sueM/TTED U4
)
aY (SecWti#f - /*bb/,f;' REcoMMEsoEo ev (sRe eneirment DATE / /
// 1 Ia,_A d ,% - ) 2 / 2. 7 /RL QA APEnoVED SY (Menseer of Queitty Assurance) DATE
)
- PPRoVED SY (Station SuperEt=
m = , DAT') 1./ s 7 / A (T
EI 1300.02.0 Davis-Besse Nuclear Power litation Unit No. 1 Energency Plan Implementing Procedure EI 1300.02 Unusual Event
- l Record of Approval and Changes Prepared by G. J. Reed 5/30/80 Date Submitted by C. E. ' Jells 6/13/80 Section Head D te Recou: mended by S
[ /e' Chair $an hOM Date QA Approved M Quality Assurance Manager Date Approved.by N O / &/N StationSuperintendec$ Date Revision SR3 QA Sta. Supt. No. Recommendation Date Approved Date Ap roved Data
/ f Wff N }l/Y f8/
p p e g apqr p r ' v n ' a ,i m 3 p _ = g o0lssir2. //jr @
- 4 & '/*W-
e t
1 EI 1300.02.2
- 1. PURPOSE To outline the course of action and protective measures required to mitigate the consequences of a Station emergency at the Unusual Event level to safeguard Station persennel and the general public.
- 2. SCOPE Describes the actions and responsibilities of Davis-Besse per-sonnel and offsite support groups in the event the Shift Super- ,
visor declares an Unusual Event in accordance with the Emergency Plan Activation procedure, EI 1300.01.
- 3. REFERENCES 3.1 Davis-Besse Nuclear Power Station Emergency Plan 3.2 Station Response to Emergencies, EI 1300.00 3.3 Emergency Plan Activation, EI 1300.01 3.4 First Aid Response, AD 1827.02 3.5 Protective Action Guidelines , AD 1827.12 4 DEFINITICNS 4.1 Unusual Events - Event (s) are La progress or which occurred that indicate a potential degradation of the level of safety of DBNPS.
- 3. EMERGENCY MEASURES 5.1- Shift Supervisor The Shift Supervisor, having assumed the role.of interim Emergency Duty Officer and having classified the emer-gency as an Unusual Event, shall assure the following actions are taken as required (See Attachment 1):
5.1.1 Make the appropriate notifications or sound the appropriate alarm as necessary: 4
- a. Fire ,
- b. Containment Evacuation
- c. Initiate Emergency Procedures 2 NOTE: The station alarm need not be sounded if downgrading from a higher classification.
- . . - _. _ - ._-,_ ., y - . . _ _ ~, ., ,
O s 3 EI 1300.02.2 NOTE: The announcement should include; 1) the Emergency Action Level classification,
- 2) the level of response required, and 3) a brief description af plant con-ditions. .
- 3. The Shift Supervisor or his designee shall then activate the pagers of-the key ,
emergency response personnel as listed La Administrative Memorandum No. 37. 4 When paged (beeped), those individuals must telephone the Edison Operator who shall connect them with the Telephone Pager thus allowing them to hear the recorded message. . 5. These individuals shall then " call in" or notify additional personnel as required to provide adequate response to the event, by using Administrative Memorandum No. 37. NOTE: The NRC resident inspector can be telephoned or paged in accordance with AD 1827.17 if necessary. 4 5.1.4 Notification of the following agencies must 2 occur: NOTE: When notifying an outside agency, record the name of the individual contacted and request a return telephone call from the agency to verify notification. 2 a. Sheriff's Department, Ottawa County, as soon as possible after the declaration is made ] (normal time is approximately 15 minutes)
- b. NRC Region III, Office of Inspection and Enforcement;-NRC, NRR, Emergency Incident Response Center, Bethesda, Maryland (This is accomplished by the NRC Emergency Notifi-2 cation System - Red Phone) within one hour.
~
5.1.5 Continue in the capacity of interim Emergency Duty Officer until relieved by the assigned Emergency Duty Officer. 1 4 e f
,n ,,-w r-v e -,r , n y y
- 5 EI 1300.02.1 5.2.6 Recommend protective actions to the Ottawa County Sheriff if required by assessment results per AD 1827.12, Protective Action Guidelines.
5.3 Shift Operations Personnel 5.3.1 Control Room operators shall maintain safe operations of the Station and minimize the potential hazards to Station personnel and the general public as directed by the Shift Supervisor, 5.3.2 In the event that the Shift Supervisor is incapacitated, his duties and responsibilities indicated in Step 5.1 shall be assumed by the Assistant Shift Supervisor in the Control Room until relieved by a qualified Shift Supervisor. 5.3.3 Equipment and auxiliaries operators shall main-tain safe operations of the Station as directed by the Shift Supervisor. 5.3.4 The Shift Technical Advisor shall provide tech-nical and analytical support in the diagnosis of off-normal events. He shall also advise and assist the Shift Supervisor on matters per-taining to the safe and proper operation of the plant with regards to nuclear safety. 5.4 Shift Chemistry and Radiation Tester (C&RT) 5.4.1 The shift C&RT shall report immediately to the Health Physics Monitoring Room to await instruc-tien from the Shift Supervisor or Chemist and Health Physicist. 3.4.2 The shift C&RT shall provide radiological monitoring for the Fire Brigade in the event of a fire in RACA. 3.4.3 The shift C&RT shall monitor all injured per-1 sonnel before they leave the site. Jul off-shift C&RT shall accompany or meet the contaminated personnel at the offsite medical facilities. - 5.5 Fire Brigade 5.5.1 The Fire Brigade Captain shall respond to any announced fire, evaluate the situation, direct a the Fire Brigade, and keep the Shift Supervisor infor=ed of the status of the fire. S e
7 EI 1300.02.2 5.10.1 The Carroll Township Ambulance Service shall provide transportation service as required for offsite medical treatment. 5.10.2 The H.B. Magruder Memorial Hospital shall pro-vide offsite medical treatment for personnel as required. 5.10.3 The Carroll Township Fire Department shall provide primary resp 6nse to fire alarms onsite , as required.
- a. The Village of Oak Harbor Fire Department shall provide alternate response to fire alarms onsite as required through mutual aid with Carroll Township.
The Ottawa County Sheriff's Department is noti-5.10.4 fled in order that local authorities may be prepared to answer inquiries generated by the public. The Sheriff's Department is also the main contact for medical and fire support agencies who respond to Davis-Besse (See Sections 3.10.1, 5.10.2 and 5.10.3 above) .
- 6. TERMINATION 6.1 The Emergency Duty Officer and Station Operations Manager
, have joint responsibility for determining and declaring .
when the emergency situat ion is stable. 6.2 The Emergency Duty Officer shall assure notification of all offsite organizations and TICo personnel.that the emergency has terminated. 2 6.3 A written summary will follow notification of termination within 24 hours. 9 l \ l l l I e e
1 i 8 EI 1300.02.3 ED0/ SHIFT SUPERVISOR CHECKLIST FOR L*NUSUAL EVEVT A'ITACHMEhT 1 NOTE: If changing from a prior emergency classification checklist, com-plate steps NOT already accomplished by the previous checklist. Then attach all the previous checklists used to this one. Place N/A in steps that are not applicable. ACTION COMPLETED ACTION REQUIRED DATE TIME INITIAIS
- 1. Initiate corrective action as required
- 2. Make the appropriate announce-ment or sound the appropriate alarm NOTE: This step may be omitted when downgrading from a higher classification.
- 3. Announce locatica, type of emergency on Gai-tronics twice and make the appropriato announce-ment as to personnel assembly as required
- 4. Confira Emergency Classification.
(See EI 1300.01)
- 5. Conduct necessary notification:
- a. Secondary Alarm Station (S.A.S.)
NOTE: In the event of a Fire, or Medical Emergency the S.A.S. operator will make calls for emergency support and/or notification of the following agencies or personnel. 3
- 1. Fire Department (s)
- 2. Emergency Medical ]
Service (Ambulance)
- 3. Life. Flight Air Ambulance
- 4. H.3. Magruder Hospital
- 5. St.. Charles Hospital i
- 6. Edison Operator 1
.3 .
s'
- .- . . . _ . . _ . . . - . _ . _ - . ~_ . _ .
._._. . _ m.
t l 9 EI 1300.02.3 ED0/ SHIFT SUPERVISOR CHECKLIST FOR UNUSUAL EVENT ATTACHMENT 1 (Con't) 4
)
- ACTION COMPLETED
, ACTION REQUIRED DATE TIME INITIALS i i b. Nuclear Security Super-l visor (Ext. 556 or 557)
; c. Edison Centrex Operator I
(Ext. 88-000 or
) 259-5000)
} d. Station Management j (See Step 5.1.3(b) of this procedure) { . i 1. Station Superin-tendent NOTE: The Station Superintendant or his designee i is responsible for notifying the Ottawa l County Sheriff upon declaration of an j Emergency Action Level.
- 2. The Key Emergency Response Personnel:
E
- Emergency Duty Officer, Assistant Station Superin-l tende; e Operations, Chemist and Health Physicist, 1 Nuclear Services Director, Emergency Planning Super-
} visor, Nuclear Security Manager, News Media Relations
; Supervisor, Technical Engineer, Maintenance Engineer,
( and Operations Engineer,
- e. *NRC (use the Emergency 1 Notification Systes
!- - Red Phone) 4
-
- NOTE: NRC notification must be made within one hour and should be made by station sanagement. Health 3
physics information should be transmitted using the NRC Health Physics Network by the Chemist and Health Physicist or his designee. (Dial 22 for l NRC Headquarters - 23 for NRC Region 3 Office.) l l 6. Conduct Periodic Updates for: l.
~
I f r e- m e - , - - ,-r- r~ ,-n ,-.,,~.-re -
-m, , --< --- , st-.wa e -4 m w vv
.__ .. - . . _ , _ . . _ _ ___. . _..s . -. -
10 EI 1300.02.3 ED0/SHIIT SUPERVISOR CHECKLIST FOR UNUSUAL EVENT ATTACHMENT 1 (Con't) ACTION COMPLETED ACTION REQUIRED DATE TIME INITIALS
- a. TED Personnel
- b. NRC
- c. Ottawa County Sheriff i 7. As conditicas change, check EI 1300.01 to deter:nine 1 if reclassification is appropriate
- 8. When the conditien is resolved notify:
- a. TED Personnel
- b. STC
- c. Ottawa County Sheriff 3
l Reviewed by Filed by l Station Superintendent Emergency Planning ! Supervisor END
EI 1300.03.0 Davis-Besse Nuclear Power Station Unic No. 1 Emergency Plan Implementing Procedure EI 1300.03 Alert . Record of Approval and Changes Prepared by G. J. Reed 5/30/P5 Date Submitted by C. E. Wells 6/13/80 Section Head Data Recommended by Ig8 h h /.3 [t SR3 Chair #an 'Date QA Approved I/ Quality Assurance Manager Date Approved.by D -"~-i ' Oh StationSuperintengt Data Revision , SR3 QA Sta. Supc. No. Recommendation Date Approved Date Approved D,aJe .
/ M p+~ 'M/C/ NK f*qs2, */*/
p pw _ , gj,,jn p _ pme s /> wu . 3 p to}sS{tt,0f Tb " l *^ k t I
,-.,, _ - , .-- ,.,.,,.w - . . %y_ 7- aw.< -% - ,y ,_ a r -
, , c
1 EI 1300.03.2
- 1. PURPOSE To outline the course of action and protective measures required j to mitigate the censequences of Station emergency at the Alert j level to safeguard Station personnel and the general public.
- 2. SCOPE l Describes the actions and responsibilities of Davis-Besse per-sonnel and offsite support groups in the event the Shift Supervisor j declares an Alert as identified in the Emergency Plan Activation procedure, EI 1300.01.
- 3. REFERENCES 3.1 Davis-Besse Ne: lear Power Station Emergency Plan 3.2 Station Response to Emergencies, EI 1300.00 3.3 Emergency Plan Activation, EI 1300.01 3.4 Protective Action Guidelines, AD 1827.12 4 DEFINITIONS 4.1 Alert - Events are in progress or have occurred which involve an actual or substantial degradation of the level of safety of D3NPS.
- 5. EMERGENCY MEASURES 5.1 Shift Supervisor The Shift Supervisor, having assumed the role of interim Emergency Duty Officer and having classified the emer-gency as an Alert, shall assure the following actions are ;
taken as required (See Attachment 1): 5.1.1 Make the appropriate notifications or sound the ) appropriate alarm as necessary:
- a. Fire
- b. Containment Evacuation
- c. Initiate Emergency Procedures 2 NOTE: The station alarm need not be sounded if downgrading from a higher classification.
) l . l L. -- - _ - - - ---
2 EI 1300.03.2 5.1.2 Announce the location, type and classification of the emergency on the Station public address system twice and make the appropriate announce-cent as to the need for personnel assembly, non-assembly, evacuation, or non-evacuation as the conditions dictate. 5.1.3 Notify the following individuals: 2 a. Nuclear Security Supervisor ,
- b. Station Superintendent ,
\
- 1. During normal working hours, the Station i Superintendent should be reached over the !
Station gai-tronics or telephone or by utilizing his " beeper" pager. During off i normal working hours, manually telephone his office and home using the numbers listed in Administrative Memorandum No.
- 37. If there is no answer, then attempt a page. Upon being notified, the Station Superintendent shall then confer with the Shift Supervisor and ascertain the degree of response that may be necessitated by a plant event. i NOTE: If the Station Superintendent does NOT respond within five minutes, re-initiate the page.
2 If he fails to respond to a second page, the Assistant Station Superintendent, Opera-tions, should be contacted. If neither can be contacted, the Shift Supervisor should exercise his own judgement in dealing with the situation.
- 2. The Station Superintendent can then authorize the Shift Supervisor to tape an announcement on the Telephone Pager located in the Shift Supervisor's office.
(The Station Superintendent may elect to perform this evolution himself over the telephone. If so, the Station Superin-tendent should call the Edison Operator and request to be connected to the Telephone Pager.)
~
1
l l j 3 EI 1300.03.2 NOTE: The announcement should include; 1) the Emergency Action Level classification,
- 2) the level of response required, and 3) a brief description of plant con-dicions.
- 3. The Shift Supervisor or his design 6e shall then activate the pagers of the key emergency response personnel as listed in Administrative Memorandum No. 37.
4 When paged (beeped), those individuals must telephone the Edison Operator who shall connect them with the Telephone Pager thus allowing them to hear the recorded message.
- 5. Those individuals shall then " call in" or notify additional personnel as required to provide adequate response to the event 4
by using Administrative Memorandum No. 37. NOTE: The NRC resident inspector can be telephoned or paged in accordance with AD 1827.17 if necessary. 5.1.4 Notification of the following agencies must 2 occur: NOTE: When notifying an outside agency, record the name of the individual contacted and request a return telephone call from the agency to verify notification 2 a. Sheriff's Department, Ottawa County, as soon
, as possible af ter the declaration is made .
(normal notification time is approximately
. 15 minutes)
- b. NRC Region III, Office of Inspection and Enforcement; NRC, NRR, Emergency Incident Response Center, Bethesda, Maryland (This is accomplished by the NRC Emergency Notifi-
~
2 cation System - Red Phone) within one hour. 5.1.5 Continue in the capacity of interim Emergency Duty Officer until relieved by the assigned Emergency Duty Officer. _ - , ~ -- , . . , -
4 EI 1300.03.0 5.1.6 Assessment actions which shall include:
- a. Increased surveillance of in plant instru-mentation.
- b. The dispatching of shift personnel to the identified problem area for confirmation and visual assessment of the problem.
- c. The dispatching of onsite RMT's to monitor ,
for possible releases and to provide con-firmation of correct accident classification.
- d. Surveillance (if a radiological accident is occurring)' of the in-plant instrumentation necessary to obtain meteorological and radio-logical data required for calculating or estimating projected doses. This dose assess-ment activity shall continue until termina-tien of the emergency in order that the updating of initial assessments may be pro-vided to all concerned offsite agencies and to the EDO.
i 5.1.7 Corrective actions by plant operators shall be according to established procedures that place the plant in a safe condition. 5.2 Emergency Duty Officer (EDO) The Emergency Duty Officer, upon being informed that an Alert has been declared, shall: 5.2.1 Report to the Emergency. Control Center and assume the position of Emergency Duty Officer in the onsite emergency organization, relieving the Shift Supervisor of this duty. i 5.2.2 Evaluate the information, data, and methods utilized by the Shift Supervisor in making his determination in order to ensure that the proper emergency classification has been made.
- 5.2.3 Determine to what extent the offsite and onsite emergency organizations shall be activated.
, a For an Alert, the emergency teams shall be activated along with all or portions of the onsite emergency organization. l 1
]
5 EI 1300.03.1
} 5.2.4 If the onsite organization is required and the need exists, activate the ECC according to the Emergency Control Center Activation Procedure, EI 1300.08.
5.2.5 Continue assessment actions initiated by the Shift Supervisor.
; 5.2.6 Recommend protective actions to the Ottawa County Sheriff as required by assessment results per AD 1827.12, Protective Action Guidelines.
5.3 Shift Operations Personnel 5.3.1 Control Room operators shall maintain safe
! operations of the Station and minimize the
- potential hazards to Station personnel and the general public as directed by the Shift Supervisor.
; 5.3.2 In the event that the Shift Supervisor is
- incapacitated, his duties and responsibilities j indicated in Step 5.1 shall be assumed by the Assistant Shift Supervisor in the Control Roce
- until relieved by a qualified Shift Supervisor.
5.3.3 Equipment and auxiliaries operators shall main-tain safe operations of the plant as directed by the Shift Supervisor. 5.3.4 The Shift Technical Advisor shall provide tech-nical and analytical support in the diagnosis of off-normal events. He shall also advise and
. assist the Shift Supervisor on matters per- - ! taining to the safe and proper operation of the plant with regards to nuclear safety.
5.4 Shift Chemistry and Radiation Tester (C&RT) 5.4.1 The shift C&RT shall report immediately to the Health Physics Monitoring Room to await instruc-tions from the Shift Supervisor or Chemist and Health Physicist. 4 5.4.2 The shift C&RT shall provide radiological monitoring for the Fire Brigade in the event of a fire in RACA. I 5.4.3 The shift C&RT- shall monitor all injured per-I sonnel before they leave the_ site. An off-shift l C&RT shall accompany or meet- the contaminated personnel at the offsite medical facilities. I E
,I
A 6 EI 1300.03.3
. h, 5.5 Fire Brigade 5.5.1 The Fire Brigade Captain shall respond to any announced fire, evaluate the situation, direct the Fire Brigade, and keep the Shift Supervisor
, informed of the status of the fire. : I 5.5.2 Personnel assigned to the Fire-Brigade shall 4 respond to any announced fire with appropriate fire fighting and protective equipment and extinguish the fire as directed by the Fire Brigade Captain. l 3.5.3 The first_ Fire Brigade Captain arriving on the scene should remain in charge of the fire until termination of the emergency or relieved by the Fire Chief or Assistant Fire Chief. 5.6 First Aid Team I 5.6.1 The First Aid Team Leader shall respond to any announced personnel injuries, evaluate the situation, direct the First Aid Team and keep the Shift Supervisor informed of the status of the injured individual (s). 5.6.2 Personnel assigned to the First Aid Team shall respond to any announced personnel injury with appropriate first aid supplies and provide the necessary first aid treatment. ] 5.7 Nuclear Security Force 5.7.1 The Nuclear Security Supervisor, upon notifica-tion by the- Shift Supervisor that an Alert exists, shall implement the Industrial Security Plan Procedure, AD 1808.00.
- 5.7.2 Nuclear Security Officers shall maintain security
( of the Station as directed by the Nuclear Security-l Supervisor. 5.8 Radiation Monitoring Team (RMT) 5.8.1 All qualified non-chemistry and health physics RMT members will report to the turbine deck assembly area adjacent to the OSC. 3 5.8.2 The OSC Manager will designate RMT members as to their assignment as offsite or onsite. I - e
' p$ ,
) _ . , . _ '. - . , , . , , . -_ ~
. - - - - - - . . - . . . l 7 EI 1300.03.3
- a. A list of qualified RMT's is found in Administrative Memo 42.
- b. Only one = ember of each team should be from the C&HP section.
3 5.8.3 If requested by the EDO, offsite RMT's will be dispatched to the Radiological Testing Laboratory (RTL) for further instructions. 5.8.4 RMT's responding from offsite will report to the RTL for further assignment. 5.9 Casite Personnel 3 5.9.1 Personnel, who do NOT have specifically assigned duties shall proceed to areas as prescribed in AD 1827.11 Assembly, Accountability, and Subsequent Evacuation. 3.10 Offsite Personnel 5.10.1 Station personnel whose emergency response is at the station and who are normally authorized non-escorted access, will be admitted upon verbal communications with security. 5.10.2 Support group personnel requested to respond to the site will report to the Security Station at the north end of the Davis-Besse Administration Building for subsequent assignment. 3
- a. Personnel directed to the station, but who are normally granted escorted access, will be admitted unescorted upon written authorization.from the Station Cperations Manager.
- b. Personnel directed to the station, but who are normally granted escorted access, will be admitted with an escort upon verbal authorization from the Shift Supervisor or EDO.
5.11 Offsite Agencies and Organizations 3.11.1 The Carroll Township Ambulance Service shall provide transportation service as required for offsite medical treatment. 5.11.2 The H. B. Magruder Memorial Hospital shall provide offsite medical treatment for personnel as required.
8 EI 1300.03.2 5.11.3 The Carroll Township Fire Department shall provide primary response to fire alarms onsite as required.
- a. The Village of Oak Harbor Fire Department shall provide alternate response to fire alarms ensite as required through mutual aid with Carroll Township.
3.11.4 The Ottawa County Sheriff's Department is
- experienced in providing area control, com-munications assistance, and direct handling of the local population, including evacuation, should it become necessary. The Sheriff's Department provides 24 hour radio communication coverage with the Shift Supervisor at DBNPS and is the lead offsite governmental agency contacted in the event of an emergency at the site.
- 6. TERMINATION 6.1 The Emergency Duty Officer and Station Operations Manager have joint responsibility for decennining and declar-ing when the emergency situation is stable.
6.2 The Emergency Duty Officer shall assure notification of all offsite organizations and TECo personnel that the emergency has terminated. 2 6.3 A written su= mary will follow notification of termination-within 8 hours.
9 EI 1300.03.3 ED0/ SHIFT SUPERVISOR CHECKLIST FOR ALERT ATTACHMENT 1 NOTE: If changing from a prior emergency classification checklist, com- , plete steps NOT already accomplished by the previous checklist. l Then attach all the previous checklists used to this one. Place l N/A in steps that are not applicable. ACTION COMPLETED ACTION REQUIRED DATE TIME INITIALS
- 1. Initiate corrective action as required
- 2. Make the appropriate announce-ment or sound.the appropriate alarm NOTE: This step may be omitted when downgrading from a higher classification.
- 3. Announce location, type of emergency on Gai-trenics twice and make the appropriate announce-ment as to personnel assembly as required
- 4. Confirm Emergency Classification (See EI 1300.01)
- 5. Conduct necessary notification: l
- a. Secondary Alarm Station (S.A.S.)(Ext. 280 or 301)
NOTE: In the event of a Fire or Medical Emergency the S.A.S. operator will make calls for emergency support and/or notification of the following agencies or personnel. 3
- 1. Fire Department (s)
- 2. Emergency Medical Service (Ambulance)
- 3. Life Flight Air Ambulance 4 H.B. Magruder Hospital
- 5. St. Charles Hospital
- 6. Edison Operator
i l 10 EI 1300.03.3 ED0/ SHIFT SUPERVISOR CHECKLIST FCR ALERT (Con't) ATTACHMEhT 1 ACTION COMPLETED ACTION REQUIRED DATE TIME INITIALS
- b. Nuclear Security Super-visor (Ext. 356 or 557)
- c. Edison Centrex Operator (Ext. 88-000 or 259-5000) 3
- d. Station Management (See Step S.I.3(b) of this procedure)
- 1. Station Superin-tendent NOTE: The Station Superintendent or his designee is responsible for notifying the Ottawa County Sheriff upon declaration of an Emergency _ Action Level.
- 2. The Key Emergency Response Personnel: ,_
Emergency Duty Officer, Assistant Station Superin-tendent Operations, Chemist and Health Physicist, Nuclear Services Director, Emergency Planning Super-visor, Nuclear Security Manager, News Media Relations Supervisor, Technical Engineer, Maintenance Engineer, and Operations Engineer. 3 e. *NRC (use the Emergency Notification System
- Red Phone)
- NOTE: NRC notification must be made within one hour and should be made by station management. Health physics information should be transmitted using the NRC Health Physics Network by the Chemist and Health Physicist or his designee. (Dial 22 for NRC Headquarters - 23 for NRC Region 3 Office.)
1 1
\
11 EI 1300.03.3 ED0/ SHIFT SUPERVISOR CHECKLIST FOR ALERT (Con't) ATTACHMENT 1 ACTION COMPLETED ACTION REQUIRED DATE TIME INITIALS
- 6. Perform applicable steps of the ECC checklist (Attachment 3 of EI 1300.08, Emergency Control Center Activation)
- 7. Center Activation
- a. Emergency Control Center (EI 1300.08)
- b. Operations Support Center (EI 1300.06)
- c. Technical Support Center (EI 1300.07)
- 8. Conduct Periodic Updates for:
- a. TED Personnel
- b. NRC
- c. Ottawa County Sheriff
- 9. As _ conditions change, check EI 1300.01 to determine if reclassification is appro-priate
- 10. When the condition is resolved notify:
- a. TED Personnel
- b. NRC
- c. Ottawa County Sheriff Reviewed by Filed by Station Superintendent Emergency Planning Supervisor-E
EI 1300.04.0 j 1 l Davis-Besse Nuclear Power Station Unic No. 1 j Emergency Plan Implementing Procedure EI 1300.04 Site E=ergency . Record of Approval and Changes Prepared by G. J. Reed 5/30/80 Date , Submitted by C. E. Wells 6/13/80 Section Head Date Reco:r:= ended by , IIAA SR3 Chair,di h[ h
'Date QA Approved // [
Qual'itj Assurance Manager' Date Approved.by T)/ S'/hC Station Superintendent (/ Date Revision SR3 QA Sta. Supt. No. Reco::imenda tion Date Approved Date Approved Df te l W / f ///Y N / jfh TO W/M l ^ p A v g sjuja pit w w "- y 'I - 3 p: , iejalw /IY I
- M ' ' ' ' '~
e
l l. l 1 EI 1300.04.2 1
- 1. PCRPOSE To outline the course of action and protective measures required to mitigste the consequences of a Station emergency at the Site Emergency level to safeguard Station personnel and-the general
- public.
- 2. SCOPE 1
Describes the actions and responsibilities of Davis-Besse per-sonnel and offsite support groups in the event the Shift Super-visor declares a Site Emergency On accordance with the Emergency Plan Activation procedure, EI 1300.01.
- 3. REFERENCES 3.1 Davis-Besse Nuclear Power Station Emergency Plan 3.2 Station Response to Emergencies, EI 1300.00 3.3 Emergency Plan Activation, EI 1300.01
^ 3.4 Protective Action Guidelines, AD 1827.12
- 4. DEFINITIONS 4.1 Site Emergency - Events are in progress or have occurred which involve actual or likely major failures of DBNPS functions needed for the protection of the public. There -
also exists a significant actual or potential release of radiocctive material. S. EMERGENCY MEASURES S.1 Shift Supervisor The Shift Supervisor, having assumed the role of interim Emergency Duty Officer and having classified the emer-gency as a Site Emergency, shall assure the following actions are taken as required (See Attachment 1): 5.1.1 Sound the appropriate alarm:
- a. Fire b.' Containment Evacuation
- c. Initiate Emergency Procedures 2 NOTE: The station alarm need not be sounded when downgrading from a higher classification.
1 2 EI 1300.04.2 l 3.1.2 Announce the location, type and classification of the emergency on the Station public address system twice and make the appropriate announce-ment as to the need for personnel assembly, non-assembly, evacuation, or non-evacuation as the conditions dictate. 5.1.3 Notify the following individuals immediately: 2 a. Nuclear Security Supervisor ,
- b. Station Superintendent
- 1. During normal working hours the Station Superintendent should be reached over the Station gai-tronics or by utilizing his
" beeper" pager. During off normal work-ing hours, manually telephone his office and home using the numbers listed in Admin-istrative . Memorandum No. 37. If there is no answer, then attempt a page. Upon being notified, the Station Superin-tendent shall then confer with the Shift Supervisor and ascertain the degree of-response that may be necessitated by the plant event.
NOTE: If the Station Superintendent does NOT respond within five minutes, re-initiate the page. 2 If a second page fails, contact the Assistant Station Superin-tendent, Operations. If neither can be contacted, the Shift Supervisor should exercise his own judgment in dealing with the situation.
- 2. The Station Superintendent can then authorize the Shift Supervisor to tape an announcement on the Telephone Pager located in the Shift Supervisor's office.
(The Station Superintendent may elect to perform this evolution himself over the telephone. If so, the Station Super-intendent should call the Edison Operator and request to be connected to the Telephone Pager.) 9 o e t - e
3 EI 1300.04.2 NOTE: The announcement should include; 1) the Emergency Action Level classification,
- 2) the level of response required, and 3) a brief description of plant con -
ditions.
- 3. The Shift Supervisor or his designee shall then activate the pagers of the key emergency response individuals as listed in Administrative Memorandum No. 37.
4 When paged (beeped), those individuals must teleohone the Edison Operator who shall connect them with.the Telephone Pager thus allowing them to hear the recorded message. NOTE: The NRC resident inspector can be telephoned or paged in accordance with AD 1827.17 if necessary.
- 5. Those individuals shall then " call in" or notify additional personnel as required to provide adequate response to the event by using Administrative Memorandum No.
37. 5.1.4 Notification of the follcwing agencies must j 2 occur: NOTE: When notifying an outside agency, record the name of the individual contacted and request a return telephone call from the agency to verify notification. I 2 a. Sheriff's Department, Ottawa County, as soon as possible after the declaration is made (normal time is approximately 15 minutes) l
- b. NRC Region III, Office of Inspection and Enforcement; NRC, NRR, Emergency Incident Response Center, Bethesda, Maryland (This is accomplished by the NRC Emergency Notifica-tion System - Red Phone) within one hour.
2l 5.1.5 Centinue in the capacity of interim Emergency Duty Officer until relieved by the assigned Emergency Duty Officer. k t- - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
4 EI 1300.04.0 5.1.6 Perform assessment actions which shall include:
- a. An increased amount of plant instrumentation shall be monitored, in particular, indica-tions of core status (e.g., incore thermo-couple readings, etc.) shall be monitored.
- b. Monitoring efforts shall be greatly increased. Onsite and offsite monitoring teams shall be dispatched. In addition to ,
beta gamma field measurements, the change-out-of thermoluminescent dosimeters (TLD's) at frequent intervals may be performed; air sampling and collection of other environ-mental media for assessment of material transport and deposition shall be performed.
- c. Dose assessment activities shall be conducted more frequently, with an increased emphasis on dose projection for use as a factor in determining the necessity for protective actions. Radiological and meteorological instrumentation readings shall be used to
' project the dose rate at predetermined dis-tances from the Station, and to determine the integrated dose received. In reporting the dose projections to the EDO or to offsite agencies, the dose rate, dose, and the basis for the time used for the dose esti=ste shall always be provided. Any confirmation of dose rates by offsite RMT's shall be reflected in reporting and/or revising dose estimate information provided to applicable offsite agencies.
5.1.7 Corrective actions by plant operators shall be according to established procedures that place the plant in a safe condition. 5.2 Emergency Duty Officer (EDO) The Emergency Duty Officer, upon being Laformed that a Site Emergency has been declared, shall; 5.2.1 Report to the Emergency Control Center and assume the position of Emergency Duty Officer in the onsite emergency organization, relieving the Shift Supervisor of this duty. O
5 EI 1300.04.0 5.2.2 Evaluate the information, data, and methods utilised by the Shift Supervisor in making his determination in order to ensure that the proper ; emergency classification has been made, i 5.2.3 Determine to what extent the offsite and onsite
- emergency organizations shall be activated.
- a. For a Site Emergency, the emergency teams and the entire onsite emergency organization shall be activated. A major portion, if NOT all, of the offsite emergency organization may be activated.
J 5.2.4 Activate the ECC according to the Emergency Control Center Activation Procedure, EI 1300.08. 5.2.5 Continue assessment actions initiated by the Shift Supervisor. 5.2.6 Recommend protective actions to the Ottawa County Sheriff as required by assessment results
- per AD 1827.12, Protective Action Guidelines.
5.2.7 Ensure that continucus online phone ecmmunica-tions are maintained with the State and County Emergency Operations Centers. l 5.3 Shift Cperations Personnel l 5.3.1 Control room operators shall maintain safe , j operations of the Station and minimize the 1 potential hazards to Station personnel and the general public as directed by the Shift Super-visor. ! 5.3.2 IntheeventthatthelShiftSupervisoris incapacitated, his duties and responsibilities. indicated in Step 5.1 shall be assumed by the Assistant Shift Supervisor in the Control Room until relieved by a qualified Shift Supervisor. 5.3.3 Equipment and auxiliaries operators shall main-tain safe operations of the plant as directed by the Shift Supervisor. p 5.3.4 The Shift Technical Advisor shall provide tech-nical and analytical support in the diagnosis of off-normal avents. He shall also advise and assist the Shift Supervisor on matters per-taining to the safe and proper operation of the plant with regards to nuclear safety. 4 f i e - s a n - -
F 6 EI 1300.04.2 5.4 Shift Chemistry and Radiation Tester (C&RT) 3.4.1 The shift C&RT shall report immediately to the Health Physics . Monitoring Room to await instruc-tions from the Shift Supervisor or Chemist and Health Physicist. r 5.4.2 The shift C&RT shall provide radiological monitoring for the Fire Brigade in the event of a fire in RACA. , , t 5.4.3 The shift C&RT shall monitor all injured per-sonnel before they leave the site. An off-shift C&RT shall accompany or meet the contaminated personnel at the offsite medical facilities. 5.5 Fire 3rigade
, 5.5.1 The Fire Brigade Captain shall respond to any announced fire, evaluate the situation, direct the Fire Brigade, and keep _the Shift Supervisor Laformed of the status of the fire.
5.5.2 Personnel assigned to the Fire Brigade shall respond to any announced fire with appropriate fire fighting and protective equipment and extinguish the fire as directed by the Fire 3rigade Captain. 5.5.3 The first Fire Brigade Captain. arriving on the scene should remain in charge of.the fire until termination of the emergency or relieved by the l Fire Chief or Assistant Fire Chief. 1 5.6 First Aid Team 5.6.1 The First Aid Team Leader shall respond to any announced personnel injuries, evaluate the situation, direct the First Aid Team and keep the Shift Supervisor informed of ths status of the injured individual (s). 5.6.2 Personnel assigned to the First Aid Team shall
- respond to any announced personnel injury with appropriate first aid supplies and provide the necessary first aid treatment.
,2 5.7 Nuclear Security Force 5.7.1 The Nuclear Security Supervisor, upon notifica-tion by the Shift Supervisor that a Site Emergency t
- 9
- I ' =n""*^ **P"em+- * * ' * +r-- =--e*= -e 'v- * ** - + --* -t ~ w 7 -'
7 EI 1300.04.3 exists, shall implement the Industrial Security Plan Procedure, AD 1808.00. 5.7.2 Nuclear Security Officers shall caintain security of the Station as directed by the Nuclear Security Supervisor. 5.8 Radiation Monitoring Team (RMT) 5.8.1 All qualified non-chemistry and health physics RMT members will report to the turbine deck assembly area adjacent to the OSC. 5.8.2 The OSC Manager will designate RMT members as to their assignment as offsite or onsite.
- a. A list of qualified RMT's is found in Administrative Memo 41.
3
- b. Only one member of each team should be from the C&HP section.
5.8.3 If requested by the EEO, offsite RMT's will be dispatched to the Radiological Testing Laboratory (RTL) for furtner instructions. 5.8.4 RMT's responding from offsite will report to the RTL for further assignment. 5.9 Plant Staff Members of the plant staff that have been informed of a Site Emergency shall proceed to their designated loca-tions and perform their assigned functions. 5.9.1 The Plant Operations Manager shall proceed to the Control Roem. He shall direct plant operations and plant damage control' efforts. He shall also keep the Station Opera-tiens Manager advised of plant operations. 5.9.2 The Operations Engineer shall' proceed to the Control Room. His functions ars to super-vise control room activities, to perform on-the-spot operational analysis as required to assist the Shift Supervisor, and keep the Plant Operations Manager Lafor=ed of turrent plant conditions. 5.10 Cnsite Personnel
, , -. ,-,w-- - - ' ' ' '
4 8 EI 1300.04.3 3 5.10.1 Personnel, who do NOT have specifically assigned 2 duties shall proceed to assembly areas as prescribed in AD 1827.11 Assembly, Accountability, and Subsequent
- Evacuation.
5.11 Offsite Personnel 3.11.1 Station personnel whose emergency response is at the station and who are normally authorized non-escorted access, will be admitted upon verbal communications with security. 5.11.2 Support group personnel requested to respond to the site will report to the Security Station located at the north end of the Davis-Besse Administration Building for subsequent assignment. 3 1 a. Personnel directed to the station, but who are normally granted escorted access, will be admitted unescorted upon written authorization from the Station Operations Manager.
- b. Personnel directed to the station, but who are normally granted escorted access, will be admitted with an escort upon verbal authorization frem the Shift Supervisor or EDO.
5.12 Offsite Agencies and Organizations 5.12.1 The Carroll Township Ambulance Service shall provide transportation service as required for offsite medical treatment. 5.12.2 The H. B. Magruder Memorial Hospital shall provide offsite medical treatment for personnel as required. 5.12.3 The Carroll Township Fire Department shall provide primary response to fire alarms onsite as required. 4
- a. The Village of Oak Harbor Fire Department shall provide alternate response to fire alarms onsite as required through mutual aid with Carroll Township.
The Ottawa County Sheriff's Department is 5.12.4 experienced in providing area control, com-munications assistance, and direct handling of the local population, including evacuation, O
9 EI 1300.04.2 should it become necessary. The Sheriff's Department provides 24 hour radio communication coverage with the Shif t Supervisor at DENPS and is the lead offsite governmental agency contacted in the event of an emergency at the site.
- 6. TERMINATION 6.1 The Emergency Duty Officer and Station Operations Manager have joint responsibility for determining and declaring when the emergency situation is stable.
6.2 The Emergency Duty Officer shall assure notification of all offsite organizations and TECo personnel that the emergency has terminated. 2 6.3 A written, summary will follow notification of termination within 8 hours. l l 1 I G
1 10 EI 1300.04.3 EE0/ SHIFT SUPERVISOR CHECKLIST FOR SITE EMERGENCY ATTACHMENT 1 NOTE: If changing from a prior emergency classification checklist, com-plete steps .CT S already accomplished by the previous checklist. Then attach all the previous checklists used to this one. Place N/A in steps that are not applicable. ACTION COMPLETED ACTION REQUIRED DATE TIME INITIALS
- 1. Sound the appropriate alarm
- 2. Announce location, type of emergency on Gai-tronics twice NOTE: These steps may be omitted when downgrading from a higher classification.
- 3. Initiate corrective action as required 4 Confirm Emergency Classification (See EI 1300.01)
- 5. Conduct necessary notification:
- a. Secondary Alarm Station (S.A.S.)(Ext. 280 or 301)
NOTE: In the event of a Fire or Medical Emergency the S.A.S. operator teill make calls for emergency support and/or notification of the folicwing agencies or personnel. 3
- 1. Fire Department (s)
- 2. Emergency Medical Service (Ambulance)
- 3. Life Flight Air Ambulance 4 H.B. Magruder Hospital
- 5. St. Charles Hospital
- 6. Edison Operator
- b. Nuclear Security Super-visor (Ext. 556 or 557) e
~
11 EI 1300.04.3 ED0/ SHIFT SUPERVISOR CHECKLIST FOR SITE EMERGENCY KITACEMENT 1 (Con't) ACTION COMPLETED ACTION REQUIRED DATE TIME INITIALS
- c. Edison Centrex Operator (Ext. 88-000 or 259-5000)
- d. Station Management (See Step 5.1.3(b) of this procedure)
- 1. Station Superin-tendent NOTE: The Station Superintendent or his diesignes is responsible for notifying the Ottawa
. County Sheriff upon declaration of an Emergency Action Level.
- 2. The Key Emergency Response Personnel:
Emergency Duty Officer, Assistant Station Superin-tendent Operations, Chemist and Health Physicist, Nuclear Services Director, Emergency Planning Super-visor, Nuclear Security Manager, News Media Relations Supervisor, Technical Engineer, Maintenance Engineer, and Operatiens Engineer. 3 e. *NRC (use the Emergency Notification System
- Red Phone)
)
- NOTE: NRC notification must be made within one hour '
and should be made by station management. During an incident or abnormal occurrence, health physics information should be transmitted using the NRC Health Physics Network by the Chemist and Health Physicist or his designee. (Dial 22 for NRC Headquarters - 23 for NRC Region 3 Office.)
- 6. Perform applicable steps of the ECC checklist (Attachment 3 of EI 1300.08, Emergency Control Center Activation)
~
12 EI 1300.04.2 ED0/ SHIFT SUPERVISOR CHECKLIST FOR SITE EMERGENCY 4
- l. '
s ,:
-, . , NITACHMENT 1 (Con't)
" ' ' '~
ACTION COMPLETED ACTION' REQUIRED - ,', .-DATE' TIME INITIALS v t , ,
,'7. .CenterActivationCinfirmatihn ,
i
- a. .!mergency Control Center
^ ""f (EI 1300/03)
': /', ,
- b. - ~ Ope.rarions Support, ,
e ',, . Centac (EI 1300,06) * * .;; y , -, a . i
- 2 c' . Techn bal Support Center
/ , ,
(El 1300.07) ,
., ' f '/ .s
'j f,' .d.., Emergency Supp6rt Center (EI 1300.09) - ' - _
', / t ; s-
- 8. Conduct Periodic Updates for:
. ,' ,d <rs
/ '
e > r
/
, e TED Personnel '
if a. ,
'[ "
j 7_j i ,,
~ '
- , ' b. .::RC <
/
r
< ./
e ,
, .u ,- /, Ottawa Ctunty Sheriff
,/ j' -
9y / As cot.ditL~ui chrage, check j /, EI 1300'.0L o. determine 7, . ,
/ 'lii reclasrHi.ari:n is. app'A 4
- i priate
~
>/ -j r'
./ . . - ,
- 1 i
- 10. I When,the', condition /is, resolved '
'not,ifyf 1- ,, - -
s - rl l , >
- a. FED Personnel -
i l
- b. r>
e'* NRC.' /. t c.,. < Ottawa County Sheriff ( y 7
.. < fi
//
g'f e '
-, t
- ?
- l. , _
![.
,e Reviewed by File'd b,y -
Statipn Superintendent Zmergency Planning s .r > _ Supervisor
< I s '_ '/ ' ",
_ .E._ND 44 * ) 4
/
(l 3' o
.\
, '_ .[l 4
t
'/ ..
, 4 -
.,i.
4- -e
EI 1300.05.0 I l Davis-Besse Nuclear Power Station Unic No. 1 I i Emergency Plan Implementing Procedure EI 1300.05 General Emergency
- Record of Approval and Changas
{ Prepared by G. J. Reed 5/30/80 Date \ Submitted by \ l C. E. ' Jells 6/13/SO l Section Head Data f Recc= mended by Ma+m b /) , SR3 Chair d 'Da te ! k' QA Approved //[8 Qualitf Assurance Xanager D. ce Approved.by N [!/Date8/$ Station Superintendent d , Revision SR3 QA Sta. Supt. No. Recommendation Date Approved Date Date { Approved l l PhP V4/4 He '"'"-~74w Ysi l 3 pw g o/uja p.g g a y th e/r u 3 p+ =g ulaln- J/ rf' u b/W 9 e
l
\
1 1 EI 1300.05.0
- 1. PURPOSE To outline the course of action and protective measures required to mitigate the consequences of a station emergency at the General Emergency level to safeguard Station personnel and the general public.
- 2. SLOPE
~ Describes the actions and responsibilities of Davis-Besse per-sonnel and offsite support groups in the event of the Shift Super-visor declares a General Emergency in accordance with the Emergency Plan Activation procedure, EI 1300.01.
- 3. REFERENCES 3.1 Davis-Besse Nuclear Power Station Emergency Plan i 3.2 Station Response to Emergencies, EI 1300.00
, 3.3 Emergency Plan Activation, EI 1300.01 3.4 Emergency Offsite Dose Estimates, AD 1827.10 3.5 Protective Action Guidelines, AD 1827.12
- 4. DEFINITICNS i
I 4.1 General Emergency - Events are in progress or have occurred which involve actual or Laminent substantial core degrada-
; tion or melting with the potential for loss of contain-ment integrity, and/or involve the potential release of radioactive particulates or gases offsite of _ a magnitude to exceed regulatory limits.
- 5. EMERGENCY MEASURES 4
5.1 Shift Supervisor The Shift Supervisor, having assumed the role of interim Emergency Duty Officer and having classified the emer-i gency as a General Emergency, shall assure the following actions are taken as required (See Attachment 1): 5.1.1 Make the appropriate notifications or sound the appropriate alarm as necessary:
- a. Fire
- b. Containment Evacuation
- c. Initiate Emergency Procedures
+ <-
1 i l l 2 EI 1300.05.2 2 NOTE: The station alarm need not be sounded if downgrading from a high classification. 5.1.2 Announce the location, type and classification of the emergency on the Station public address system twice and make the appropriate announce-ment as to the need for personnel assembly, non-assembly, evacuation, or non-evacuation as the conditions dictate. . 3.1.3 Notify the following individuals: 2 l a. Nuclear Security Supervisor
- b. Station Superintendent
- 1. During normal working hours, the Station
. Superintendent should be reached over the Station gai-tronics or by utilizing his
" beeper" pager. During off normal work-ing houra, manually telephone his office and home using the numbers listed in Administrative Memorandum No. 37. If there is no answer, then attempt.a page.
, Upcn being notified, the Station Super-intendent shall then' confer with the Shift Supervisor and ascertain the degree gf response that may be necessitated by the plant event. i NOTE: If the Station Superintendent does NOT respond within five minute, re-initiate the_page. 2 If he does not respond to a second page, the Assistant Station Supervisor, Operations, should be contacted. If neither respond,- the Shift Supervisor should use his own judgment to deal with the situation.
- 2. The Station Superintendent can then authorize the Shift Supervisor to tape an announcement on the Telephone Pager located in the Shift' Supervisor's office.
(The Station Superintendent may elect'to perform this evolution himself over the telephone. If so, the Station Superin-Y e
/
3 EI 1300.05.2 tendent should call the Edison Operator and request to be connected to the Telephone Pager.) NOTE: The announcement should include; 1) the Emergency Action Level classification,
- 2) the level of response required, and 3) a brief description of plant con-ditions.
- 3. The Shift Supervisor or his designee shall then activate the pagers of the key emergency response personnel as listed in 4
Administrative Memorandum No. 37. 4 When paged (beeped), those individuals must telephone the Edison Operator who shall connect them with the Telephone Pager thus allowing them to hear the recorded message.
- 5. These individuals shall then " call in" or notify additional personnel as required to provide adequate response to the event by using Administratife Memorandum No.
37. NOTE: The NRC resident insepctor can be telephoned or paged in accordance with AD 1827.17 if necessary. 5.1.4 Notification of the following agencies must 2 occur: NOTE: When notifying an outside agency, record the name of the individual contacted and request a return telephone call from the agency to verify notification. 2 a. Sheriff's Department, Ottawa County, as soon as possible after a declaration is made (normal thee is approximately 15 minutes) 1
- b. NRC Region III, Office of Inspection and Enforcement; NRC, NRR, Emergency Incident Response Center, Bethesda, Maryland (This is accomplished by the NRC Emergency Notifica-tion System - Red Phone) within one hour.
E n
4 EI 1300.05.0 5.1.5 Continue in the capacity of interim Emergency Duty Officer until relieved by the assigned Emergency Duty Officer. 5.1.o Assessment actions which shall include:
- a. Increased surveillance of in-plant instru-mentation.
- b. Dispatching of shift personnel to the identi- ,
fled problem area for confirmation and visual ! assessment of the problem. l l c. Dispatching of onsite RMT's to monitor for possible releases.
- d. If a radiological accident is occurring, surveillance of the in-plant instrumentation necessary to obtain meteorological and radio-logical data required for calculating or estimating projected doses. This dose assess-ment activity shall continue until termina-tion of the emergency in order that the updating of initial assessments may be pro-vided to all concerned offsite agencies and to the EDO.
- e. Greater emphasis on offsite monitoring efforts and dose projection efforts extending to distances much further from the plant.
Additionally, since the projected doses are likely to be much closer to the EPA PAG's, greater emphasis shall be placed on the assessment of release duration. Dese assessment shall be in accordance with
, the Emergency Offsite Dose Estimates Pro-cedure, AD 1827.10.
- f. Should any potential danger to the general public be determined, a precautionary evacua-tien out to two (2) miles may be recommended.
5.1.7 Corrective acticas by plant operators shall be according to established procedures that place the plant in a safe condition. 5 .2. Emergency Duty Officer (EDO) The Emergency Duty Officer, upon being informed that an General Emergency has been declared, shall: e - t
. _______ __m___.________________._____ _ _ _ _ - . _ .
5 EI 1300.05.1 15.2.1 Report to the Emergency Control Center and assume the position of Emergency Duty Officer in the onsite emergency organization, relieving the Shift Supervisor of this duty. 5.2.2 Evaluate the information, data, and methods utilized by the Shift Supervisor in making his determination in order to ensure that the proper emergency classification has been made. 5.2.3 Activate the ECC according to the Emergency Control Center Activation procedure, EI 1300.08. 5.2.4 Continue assessment actions initiated by the Shift Supervisor. 1 5.2.5 Confer with the Emergency Operations Manager concerning distribution of a thyroid blocking agent to those TECo emergency workers involved in the Station response as specified in AD 1827.12, Protective Action Guidelines. 5.2.6 Recommend protettive actions to the Ottawa County Sheriff as raquired by assessment results per AD 1827.12, Protective Action Guidelines. 5.3- Shift Operations Personnel 5.3.1 Control Room operators shall maintain safe operations of the Station and minimize the potential hazards to Station personnel and,the general public as directed by the Shift Super-visor. 5.3.2 In the event that the Shift Supervisor is incapacitated, his duties and responsibilities indicated in Step 5.1 shall be , assumed by the Assistant Shift Supervisor La the Control Room until relieved by a qualified Shift Supervisor. 5.3.3 Equipment and auxiliaries operators shall main-tain safe operations of the plant as directed by the Shift Supervisor. 5.3.4 The Shift Technical Advisor shall provide tech-nical and analytical support in the diagnosis of off-normal events. He shall also advise and assist the Shift Supervisor on matters per-taining to the safe and proper operation of the plant with regards to nuclear safety. 5.4 Shift Chemistry and Radiation Tester (C&RT) i l . r -- , , -
6 EI 1300.05.2 5.4.1 The shift C&RT shall report immediately to the Health Physics Monitoring Room to await ins t ruc-tions from the Shift Supervisor or Chemist and Health Physicist. 1 5.4.2 The shift C&RT shall provide radiological monitoring for the Fire Brigade in the event of
~
a fire in RACA. 5.4.3 The shift CSRT shall monitor all injured per- , sonnel before they leave the site. An off-shift C&RT shall accompany or meet the contaminated personnel at the offsite medical facilities. 5.5 Fire Brigade 5.5.1 The Fire Brigade Captain shall respond to any announced fire, evaluate the situation, direct the Fire 3rigade, and keep the Shift Supervisor informed of the status of the fire. 5.5.2 Personnel assigned to the Fire Brigade shall respond to any announced fire with appropriate fire fighttng and protective equipment and . extinguish the fire as directed by the Fire Brigade Captain. 5.5.3 The first Fire 3rigade Captain arriving on the scene should remain in charge of the fire until termination of the emergency or relieved by the Fire Chief or Assistant Fire Chief. 5.6 First Aid Team 5.6.1 The First Aid Team Leader shall respond _ to any announced personnel injuries, evaluate the situation, -direct the First Aid Team and keep the Shift Supervisor informed of the status of , the injured individual (s). 5.6.2 Personnel assigned to the First Aid Team shall respond to any announced personnel injury with appropriate first aid supplies and provide the necessary first aid treatment. 2 5.7 Nuclear Security Force 5.7.1 The Nuclear Security Supervisor, upon notifica- I tion by the Shift Supervisor that a General Emergency exists, shall implement the Industrial i Security Plan Procedure, AD 1808.00. l b l I
L l i l 7 EI 1300.05.3 ( 5.7.2 Nuclear Security Officers shall maintain security l 3 of the Station as directed by the Nuclear Security Supe rvisor. , 5.8 Radiation Monitoring Team (RMT) 5.8.1 All qualified non-chemistry and health physics RMT members will report to the turbine deck assembly area adjacent to the OSC. 5.8.2 The OSC Manager will designate RMT members as to their assignment as offsite or onsite.
- a. A list of qualified RMT's is found in Administra-tive Memo 42.
3
- b. Only one member of each team should be from the C&HP section.
5.8.3 If requested by the EDO, offsita RMT's will be dispatched to the Radiological Testing Laboratory (RTL) for further instructions. 5.8.4 RMT's responding from offsite will report to the RTL for further assignment.
- 5.9 Plant Staff Members of the plant staff that have been Laformed of a Site Emergency shall proceed to their designated loca-tiens and perform their assigned functions.
5.9.1 The Plant Operations Manager shall proceed to the Control Room. He shall direct plant opera-tions and plant damage control efforts. He shall also keep the Station Operations Manager advised of plant operations and plant damage control efforts. 5.9.2 The Operations Engineer shall proceed to the Control Room. His functions are to supervise control room activities, to perform on-the-spot operational analysis as required to assist the Shift Supervisor, and keep the Plant Operations Manager informed of current plant conditions. 5.10 Onsite Personnel 3 5.10.1 Personnel, who do NOT have specifically assigned duties shall proceed to areas as prescribed in AD 1827.11 Assembly, Accountability, and Subsequent Evacuation. w - K v v-
8 EI 1300.05.3 5.11 Offsite Personnel 5.11.1 Station personnel whose emergency response is at the. station and who are normally authorized non-escorted access, will be admitted upon verbal communications with security. 5.11.2 Support group personnel requested to respond to the site will report to the Security Station located at the north end of the Davis-Besse Administration building for subsequent assignment. 3
- a. Personnel directed to the station, but who are normally granted escorted access, will be admitted unescorted upon written authorization from the !
Station Operations Manager.
- b. Personnel directed to the station, but who are normally granted escorted access, will be admitted with an escort upon verbal authorization from the Shift Supervisor or EDO.
5.12 Offsite Agencies and Organizations 5.12.1 The Carroll Township Ambulance Service shall provide transportation service as required for offsite medical treatment. 5.12.2 The H. 3. Magruder Memorial Hospital shall provide offsite medical treatment for personnel as required. 5.12.3 The Carroll Township Fire Department shall provide primary response to fire alarms onsite as required,
- a. The Village of Oak Harbor Fire Department shall provide alternate response to fire alarms onsite as required through mutual aid with Carroll Township.
5.12.4 The Ottawa County Sheriff's Department is experienced in providing area control, com-munications assistance, and direct handling of the local population, including evacuation, should it become necessary. The Sheriff's Department provides 24 hour radio communication coverage with the Shift Supervisor at DBNPS and is the lead offsite governmental agency contacted in the event of an emergency-at the site. I
= . - -. - - . .. - - . . - . ..
9 EI 1000.05.2
- 6. TERMINATION 6.1 The Emergency Duty Officer and Station Operations Manager have joint responsibility for determining and declar-ing when the emergency situation is stable.
6.2 The Emergency Duty Officer shall assure notification of all offsite organizations and TECo personnel that the emergency has terminated. 2 6.3 A written summary will follow notification of termination j within 8 hours. f
- -- y -.-- - - + , - ,- , , - vs+..w- .c.- , e -
- e. y-
i 10 EI 1300.05.3 ED0/ SHIFT SUPERVISOR-CHECKLIST FOR GENERAL EMERGENCY ATTACHMENT 1 NOTE: If changing from a prior emergency classification checklist, com-plate steps NOT already accomplished by the previous checklist. Then attach all the previous checklists used to this one. Place 4 N/A La steps that are not applicable. ACTION COMPLETED. ACTION REQUIRED DATE TIME INITIALS
- 1. Initiate corrective action as required
- 2. Make the appropriate announce-ment or sound the appropriate alara
- 3. Announce location, type of emergency on Gai-tronics twice and make the appropriate announce-ment as to personnel assembly as required. Announce no eating, drinking, or smoking until further notice.
- 4. Confirm Emergency Classification (See EI 1300.01)
- 5. Conduct necessary notification:
- a. Secondary Alarm Station (S.A.S.)(Ext. 280 or 301)
NOTE: In the event of a Fire or Medical Emergency the S.A.S. operator will make calls for emergency support and/or notification of the following agencies or personnel. 3
- 1. Fire Department (s)
- 2. Emergency Medical Service (Ambulance) l
- 3. Life Flight Air Ambulance
- 4. H.B. Magruder Hospital
- 5. St. Charles Hospital
- 6. Edison Operator i
e y , #_ ee.. .y- ---v
i 11 EI 1300.05.3 ED0/ SHIFT SUPERVISOR CHECKLIST FOR GENERAL EMERGENCY AITACHMENT 1 (Con't) ACTION COMPLETED ACTION REQUIRED DATE TIME INITIALS
- b. Nuclear Security Super-visor (Ext. 556 or 557)
- c. Edison Centrex Operator (Ext. 88-000 or 259-5000)
- d. Station Management (See Step 5.1.3(b) of this procedure)
- 1. Station Superin-tendent NOTE: The. Station Superintendent or his designee is responsible for notifying the Ottawa County Sheriff upon declaration of an Emergency Action Level.
- 2. The Key Emergency Response Personnel:
Emergency Duty Officer, Assistant Station Superin-tendent Operations, Chemist and Health Physicist, Nuclear Services Director, Emergency Planning Super-visor, Nuclear Security Manager, News Media Relations Supervisor, Technical Engineer, Maintenance Engineer, and Operations Engineer.
- e. *NRC (use the Emergency Notification System
- Red Phone) l
- NOTE: The NRC notification must be made within one hour and should be made by station management.
Health physics information should be transmitted using the NRC Health Physics Network by the l Chemist and Health Physicist or his designes. (Dial 22 for NRC Headquarters - 23 for NRC Region- , 3 Office.)
-w
12 EI 1300.05.0 ED0/ SHIFT SUPERVISOR CHECKLIST FOR GENERAL EMERGENCY ATTACHMENT 1 (Con't) ACTION COMPLETED
. ACTION REQUIRED DATE TIME INITIALS
- 6. Perform applicable steps of l
the ECC checklist (Attachment 3 l of EI 1300.08, Emergency Control l Center Activation)
- 7. Center Activation Confirmation
- a. Emergency Control Center (EI 1300.08)
- b. Operations Support Center (EI 1300.06)
- c. Technical Support Center l (EI 1300.07)
I
- d. Emergency Support Center (EI 1300.09)
- 8. Conduct Periodic Updates for:
- a. TED Personnel
- b. NRC
- c. Ottawa County Sheriff
- 9. As conditions change, check EI 1300.01 to determine if reclassification is appro-priate i
- 10. When the condition is resolved notify:
- a. TED Personnel
- b. NRC l
- c. Ottawa County Sheriff Reviewed by Filed by Station Superintendent Emergency Planning Supervisor M
m . 1
, - - - - - - - - ~
\
EI 1300.06.0 Davis-3 esse Nuclear Power Station Unic No. 1 Emergency Plan Implementing Procedure EI 1300.06 Operations Support Center Activation ' Record of Approval and Changes Prepared by G. J. Reed S/30/80 Date Submitted by C. E. Wells 6/13/80 Section Head Date Recommended by MWM - [j /3 f5
~ SRB Chairman' Date .
QA Approved //![ Qual'ity' Assurance Manager Date Approved,by D /8/@ Station Superintende Date Revision SR3 No. Recommendation QA Sta. Supt. Date Approved Date Approved Date
/
YP Y'//f/ jf/f Y
}// 4 #'" #!
A 3. w. aA anus i ut T o M j fC ' D M 'iI3 /h g I* A W lf 4
- , , - - - ---,n, - - - , , . - .,
a 1 EI 1300.06.3
- 1. PURPOSE i
4 To outline the personnel required for activation of the Operations l Support Center (OSC) and their responsibilities and actions during an emergency at Davis-Besse Nuclear Power Station.
- 2. SCOPE Describes the actions of personnel assigned to the OSC when the Shift Supervisor or Emergency Duty Officer has required its activation.
- 3. REFERENCES 3.1 Davis-Besse Nuclear Power Station Emergency Plan 3.2 Station Response to Emergencies EI 1300.00 3.3 Unusual Event EI 1300.02 3.4 Alert EI 1300.03 3.5 Site Emergency EI 1300.04 3.6 General Emergency EI 1300.05 3.7 Administrative Controls EI 1300.12 3.8 Davis-Besse Nuclear Power Station Emergency Plan 2 Telephone Directory
- 4. DEFINITION
'I 4.1 Operations Support Center (OSC) - An area in the Station 4 in close proximity to the Control Room to which Station 3 support personnel report and await instructions from the Shift Supervisor, Emergency Duty Officer or Station Operations Manager.
- 5. ACTIONS 3 5.1 The OSC is the lunchroom and the assembly area directly adjacent to the lunchroom on the 623' elevation of the Turbine Building.
i 5.2 The first Station management individual to arrive at the OSC shall inform the Control Room that the OSC is manned. 5.3 Maintenance Engineer , l 5.3.1 The Maintenance Engineer is the OSC Manager. l I i I l
~. .
2 EI 1300.06.1 1 5.3.2 The alternate for the Maintenance Engineer is either the Lead Maintenance Support Engineer or the Lead Instrumentation and Control Engineer as designated by the Maintenance Engineer. 5.3.3 The Maintenance Engineer is responsible for the i activation of the OSC. . 5.3.4 The Maintenance Engineer shall proceed to the OSC and, if NOT previously performed, notify the Control Room that the OSC is manned. 5.3.5 As personnel arrive at the OSC, the following three groups should assemble immediately:
- a. First Aid Team Members
- b. Fire Brigade Members
- c. Radiation Monitoring Team Members
. Each group should have at least 2 dedicated members and even though some plant personnel are qualified for more than one group, they shculd NOT all leave the OSC to respond to one casualty , and leave the other groups "short-handed" or , unmanned.
~
l 5.3.6 As available, the Maintenance Engineer shall provide, i i per request by the Shift Supervisor or EDO, the following:
- a. Radiation Monitoring Teams I
- b. First Aid Support
- c. Fire Fighting Support
- d. Chemistry Support
- e. Health Physics Support
- f. Emergency Maintenance Support
! 5.3.7 The Maintenance Engineer also coordinates and directs maintenance and equipment modification activities in support of Station operation, and keeps the Plant Operations Manager informed of current plant conditions.
)
l
i
. l 3 EI 1300.06.3 5.4 If Station personnel assembly has been directed by the Shift Supervisor, other Station assembly areas shall report personnel accounting results to the OSC.
3 5.4.1 The OSC shall coordinate with the Nuclear Security Force to ensure complete personnel accountability; and if persons are found missing, to initiate a search per AD 1827.16, Search and Rescue. 3l 5.4.2 Only assigned personnel should assemble at the OSC. 5.5 Onsite Personnel 3 5.5.1 All onsite personnel NOT assigned specific actions or responsibilities for emergency res-pense should assemble in areas designated in AD 1827.11 Assembly, Accountability, and Subsequent j Evacuation. 5.6 Offsite Personnel 5.6.1 Station personnel whose emergency response is at the staticn and who are normally authorized non-escorted access, will be admitted upon verbal communicarices with security. d i 5.6.2 Support group personnel requestad to respond to the site will report to the Security Station located at the north end of the Davis-Besse Administration Building for subsequent assignment. 3
- a. Personnel directed to the station, but who are normally granted escorted access, will be admitted unescorted upon written authorization from the Station Operations Manager.
- b. Personnel directed to the station, but who are normally granted escorted access, will be admitted with an escort upon verbal authoriza-tion from the Shift Supervisor or EDO.
5.7 A record of activities of the OSC shall be maintained to the best ability of personnel present. Record disposition shall be in accordance with EI 1300.12, Administrative Controls. 5.8 Attachment 1 is a list of typical equipment that may be available in the Health Physics Monitoring Room proximity. _, , y.,. , - - - - + ' "
?"'W
4 4 EI 1300.06.2 3 2 5.9 Additional equipment is available from the Emergency Radiation Monitoring Equipment locker as indicated in Attachment 2. This equipment is inventoried and main-tained specifically for emergency use. T k i i a
}.
J. 1 1
5 EI 1300.06.2 i HEALTH PHYSICS MONITORING ROOM PROXIMITY l EQUIPMENT LIST ATTACHMENT 1 t l lb ical Number Instrument Model Available 2 Survey Meter R02 or 2A 3-es. I Survey Meter E400 2 ea. Survey Meter PAC 4G3 1 ca. Survey Meter PNR4 or Rascal 1 ea. Survey Meter E520 2 ea. Hand-and Foot Monitor 1 ea. Survey Meter RM 14 5 ea. OTHER EQUIP.E'" Air Sampler 2 ea. Dosimeter, 0-500 mR 50 ea. TLD 50 ea. Cartridge Respirator 40 ea-Airline Respirator -40 ea. Protective Clothing (Anti-C's) >100 ea. i l f
t 2 , 6 EI 1300.06.2 EMERGENCY RADIATION MONITORING EQUIPMENT i- LOCKER CHECKLIST ATTACHME.VI 2 LOCATION: 623' - Elevation, east side of Turbine Deck by entrance to the center stairway 1 Designated for the Control Roem/ Operations Support Center Low volume air sampler SAM-2 (Operation described in AD 1850.05)
, *PIC-6
*E-400 4 2 Particulate and silver zeolite filters Designated for the Interim Technical Support Center 4
Low volume air sampler SAM-2 (Operation described in AD 1850.05)
*E-520 Particulate and silver zeolite filters
*These instruments can be substituted with equivalent types. -
5 s a i 1
)
{ Attachment 2
-- . m g
--p wo mmo -m 7 EI 1300.06.0 OPERATIONS SUPPORT CENTER l GENERAL ASSEMBLY LOCATIONS ATTACHMLNT 3
.3 . _ .
~N ^
%M[- x ._
==
r u
, .w,
. n[.' ="f
- - - e N ,,
\ _
Y -~ d ]f'T j i 7 & ~,x sv 's-h 3 _, y g e-h , t- o
; A,g2k w a -
@ %_IN i
5 2
!i: i::
cr. o
\
h 11 l' g - y % .s , ca Wm q
~
F) 1% e _ _ _ ad s aa!! l s g ./e PD.
.kEip' =
l' sssi num2
= " ~ :n i
N3
=
r ( of Rl;UTION l [ Original, Responsible Section Head Action [O _ PneCooy,MeowrPue COPIES TO BE MODIPIED POR IMMEDIATE IMPLEMENTATION DAVIS.BESSE NUCLEAR POWER STATION . UNIT 1 TSC (1) TEMPORARY MODIFICATION REQUEST ECC (2) ED 6926 gg3gion guOerintendent (1) SECTION 1 PROCEDURE TITLE AND NUMBER EI 1300.07 TECHNICAL SUPPORT CENTER ACTIVATION RE ASON POR CH ANGE TO IDENTIFY CORRECT EMERGENCY RESPONSE PERSONNEL TITLES. The foll: wing scCtions Of r.his procedures shcuid read: Page 2, Section(s) 5.a.5.a. Facility Engineering General Supervisor
- d. Instrumentation and Control Systems Tigi.wer e Nuclear S;rstems and Analysis Engineer Page 3, Section(s) 5.5.1 The Prica.y Guatte Assessment Manager is the Nuclear
.Syste:ts and Analysis Engineer 5.5.2 The Alternate Onsite Assessment Manager is the Instrumentation and Control Systems Engineer IS PROCEDURE REVISION REQUIRED Yes y No if no, this rnodification is valid until PREPAREO SY DATE Ron Durdel ert 3/30/83 APPROVEO SY DATE APPROVEO SY
*1 bd- DATE 3 3 I -2 R
- 0. d.%dn 3 SS _
DATE
!uJttl /bAc4 SUBMITTED 8ktSection Head) s .31 - J'3 RECOMMENDED SY (SRB Chairman)
.l DATE SDJ
/
QA APPROVED SY (Maneser of Quality NNurance) DATE g/s-/P3 APPROVED SY (Stetton Sucerintendent) DATE
, whm .
SECTION 2 COMMENTS SECTICN 3 SAFETY REVIEW , Yes C No NSR cnange in tne f acility as describes in tne PS AR. Yes C No NSR cnange in the procedures as described in tr.e FSAR. Yes C No NSR test or emperiment not described in tne PS AR. Yes ] No Change in the Technical Specifications. NOTE: If any of the amove Section lit are "Yes", a Section IV Safety Evaluation snail ce performed, un#ess tnis is part of a FCR. (FCR No, if soosicacle). Yes C No. Decrease in the effectiveness of the industrial Security Flan. If this is "Yes", the chenge cannot te made without NPC concurrence. _ SECTICN 4
- e. ...
SA FETY EVaLU ATION ver ] La 5-. concil6t a od occt.Frece or We consehences cf .sr* eccicent 9r me.tvectics of eculornent Wo*2rtsat to cofAy No % c wuudy o*J urtam in tet S:vety Ane!v s.s Rooort may be increased. Yes O N 3 @A A possinhity for an accident or malfuection cf a alfferent type thes any evaluated prestously in tne Safety Analysis Recort stay no created. a Yes C No The rrergin of sa'ety at de*Ined in tfie beses for any Tecnrical Speci'ication is reduced. NcTE- if aay of S.ctra a w c. "Yes", an 'unreviewed Sifete Lestion"is Irvceved and the er enge ca inot es maos witnout NRC
- if ecoticaciep concurew:e 'PCR N t. _
SECTION 5 FOR DELETICNS OR ACCITIONS OF PROCECURES, A TEMPCR ARY A4CCIFICATION MUST BE SU8MITTEC FOR A31805.02 AND/ OR AD 1838.00,1F APPUCA8LE. Yes C No C AD 1805.02 Temporary Mooification suomitted Yes No C AD 1838.00 Temporary Modification suomitted SECTION 6 i POR ADDITIONS, DELETICNS,NSR MODIFICATIONS, AND MOOlFICATIONS REQUIRING S AFETY EVALU ATIONS, AND NSR/NON. j NSR CHANGES. SR8 Comments: SR8 Recommendation: Date SECTICN 7 l STATION SUPE RINTENDENT APPROVAL DATE - DIST RI BUTION Master File Station Superintendent COAS Office Supervisor section Heeds
1 EI 1300.07.0 Davis-Besse Nuclear Power Station Unit No. 1 Emergency Plan Implementing Procedure EI 1300.07 Technical Support Center Activation
- Facord of Approval and Changes Prepared by G. J. Reed 5/30/80 __
Date Submitted by C. E. We ll s 6/13/80 Section Hesd Date Reco= mended by M&MAA _ b /, ft SR3 Chair 6sc b'a ce { QA Approved //!M ,,_ Quality Assurance Menager Date Approved by IP)Oh w- [!' @ Station Superintenden{} Dace ! l l
)
Revision SR3 QA Sta. Sept. No. Lecc=mendation Date Approved Date Approved Date
/ f ?#N/ llA YO # j,lGet k/
- 2. p, = g GIzt/n yp ge =g 7/='*b --
3 pa - r1ltslr1. gir Yb ' 'I'IV3 ' p w = _ y sl2z-lg2 f K M W Y' __________________m__ _ . . _ . _ _ _ _ _ _ _ _
l l l r 1 EI 1300.07.2
- 1. PURPOSE To outline the personnel required for activation of the Technical Support Center (TSC) and their responsibilities and actions during an emergency at Davis-Besse Nuclear Power Station.
- 2. SCOPE Describe the actions of personnel assigned to the TSC when the the need for its activation has been determined.
- 3. REFERENCES 3.1 Davis-Besse Nuclear Power Station Emergency Plan 3.2' Davis-Besse Nuclear Power Station Emergency Plan Telephone Directory 3.3 Station Response to Emergencies EI 1300.00 3.4 Unusual Event EI 1300.02 3.5 Alert EI 1300.03 3.6 Site Emergency EI 1300.04 3.7 General Emergency EI 1300.05 3.8 Administrative controls EI 1300.12 l 4. DEFINITION 4.1 Technical Support Center (TSC) - An area onsite in close prcximity to the Coctrol Rocm which has the capability to display and transmit plant status information to the individuals who are knowledgeable of and responsible for engineering and management
; support of reactor operations in the event of an emergency situation.
- 5. ACTIONS 2 5.1 The Technical Support Center is located at the Davis-Besse site, along Chio State Route #2, in the Davis-Besse Administra-tion Building. The primary function of the TSC is to house and 2
support an organization that provides management and technical assistance to the Station operations personnel during emergency conditions and to prevent or mitigate the consequences of abnormal plaat conditions. The TSC provides direct voice and data communication with the Control Room and serves as a primary 1 1 I a
A 2 EI 1300.07.2 s 2 communications contact with the offsite emergency organization of Toledo Edison. Visual observation of the Control Room will be available through closed-circuit television (CCTV). The TSC also contains the DAES to enable the TSC staff to acquire plant data and information necessary for technical evaluations needed to handle emergency conditions and recovery operations. Two communication lines to the NRC are available for direct communication to the NRC Health Physics Network and Emergency Notification System. The TSC contains work space for up to 25 people, including a main work area for 15 people and 3 conference areas, one of which will accommodate 8 people. 2 5.2 The TSC shall be activated at the Alert Emergency Classifi-cation level. 5.3 The first Station management individual to arrive at the TSC shall notify the Control Room that the TSC is manned. 5.4 Station Operations Manager 5.4.1 The primary Station Operations Manager is the Station Superintendent. 5.4.2 The alternate Station Operatiocs Manager is the Assistan: 2j Station Superintendent, Operations. 5.4.3 The Stction Operations Manager is responsible for assuring the activatice. of the TSC. 5.4.4 The Station Operations Manager should proceed to the TSC and, if NOT previously performed, notify the Control Recm that the TSC is manned. 5.4.5 The Station Operations Manager should assure the following individuals arrive at the TEC:
- a. Nuclear Engineering Manager
- b. Technical data communicator
- c. Technical Engineer
- d. Plant Instrumentation and Control Systems Engineer
- e. Plant Nuclear Systems Engineer 5.4.6 The Station Operations Manager may establish the s
I L
3 EI 1300.07.3 following telephone communications loops as needed per the DBNPS Emergency Plan Telephone Directory:
- a. Technical Data Loop t
- b. Technical Management Loop
- c. Policy Management Loop
- d. Public Relations Loop NOTE: If personnel are required as communicators, requests should be directed to the Operations Support Center.
5.4.7 The Station Operations Manager should assign an indi-vidual(s) to distribute applicable emergency equipment 3 listed in Attachment 1, (ie. log book, telephone books, and calculators). 5.4.8 Upon arrival, the Onsite Assessment Manager will assume control of the TSC from the Station Operations Manager. 5.5 Onsite. Assessment Manager 5.5.1 The primary Onsite Assesscent Manager is the Nuclear f Engineering Manger. 5.5.2 The alternate Onsite Assessment Manager is the Plant Nuclear Systems Engiceer. 5.5.3 The Oc2ite Assessmsnt Manager, upon being informed that a. Alert level emergeocy exist, shall procted to the Technical Support Center (TSC). 5.5.4 The Onsite Assessment Manager's responsibilities
'and duties include, but are NOT limited to:
j
- a. Directing the engineering assessment activities of the TSC.
- b. Coordinating the engineering assessment activities of engineering support personnel from the NSSS-vendor and the Architect Engineer.
- c. Ensuring that adequate mechanical, electrical, instrumentation and control, and technical engineers are available to perform engineering assessment, as required.
is r
+
4 ( EI 1300.07.4 3
- d. Ensuring that adequate support personnel are available to assist in records disposition,
,, updating status board, and providing communica-tions to the Control Room and Nuclear Regulatory Commission, as necessary.
- e. Reporting to 'ie'SEstion t Operations Manager and appraising hic of engineering assessment activities, equipment operation problems and any alterationa ir'the normal lineup or operation of plant sys'tems/
5.6 Technical Engineer 1 - 5.6.1 The primary, technical engineering individual is the Technical Engineer. 5.6.2 The alternate technical engineering individual is the . Nuclear Performance Engineer. 5.6.3 The Technical Ergineer shall assist in coordinat-ing and performing plant assessment activities. 5.6.4 The Technical Engineer shall, as necascary, assure that radiological controla are in placa such as:
- c. TSC monitored for airborne activity by opera- ,
tion of a portable air activity monitor.
- b. A high/ law survey instrument is utilized by personnel leaving the 13C for entry into the plant.
- c. Stepoff pads and contamination survey instru-sents are provided at the entrance to the TSC.
from the plant when required. 5.6.5 The Technical Engineer shall assure that personnel assembled in the TSC are briefed on conditions and monitoring methods in place while the TSC is activated. 5.7 Radcon Operations Manager 5.7.1 The Radcon Operations Manager is.the Chemist and Health Physicist. 4 5.7.2 The alternate Radcon Operations Manager is the Chemistry and Radiochemistry Supervisor or the Health Physics Supervisor. T
-)
5 EI 1300.07.2 5.7.3 The Radeon Operations Manager directs and coordinates the. radioactive waste and. radiological controls aspects of Emergency Operations and keeps the Plant Operations Manager informed of radwaste and radcon activities pursuant to the emergency. 4 I 5.7.4 The Radeon Operations Manager is responsible for coordinating the activities of the Health Physics Monitoring Room portion of the Operations Support Center, however he may do this from his office located in the Technical Support Center. He is also responsible for relaying health physics information over the NRC Health Physics Network phone which is located there. t . 5.7.5 The Radeon Operations Manager shall supervise the
- ensite radiation surveys and survey results analysis, i
5.8 Plant Staff j 2 5.8.1 Plant Staff, such as the operations engineering staff, l clerical support, etc., who are NOT assigned to other
. ' emergency functions, shall (if in protected area)
I report to the Operations Support Center and be directed ) to the-TSC as needed. 5.8.2 The Technical Engineering staff who are not assigned [ other emergency functions, shall report directly to the TSC. 2 5.8.3 The Plant Staff shall assist in accident assessment, as required.
)
5.9' Technical Support Center Activity i 5.9.1 Communications with the Control Room, Emergency Support Center, Operations Support' Center, Emerg- ) ency Control Center, and the NRC will be established as specified by the Onsite Assessment Manager or the Station Operations Manager. 1 ] 2 a. The Data Acquisition and Display System (DADS) I terminals in the TSC will provide sufficient station information and data communication for personnel to evaluate'and diagnose station conditions and activities so as to conduct i emergency operations in an orderly manner. l b. _The DADS provide data communication between
~
the ECC, TSC, Control Room and Emergency Support Center. l 1I P w ,) * , - - - v - m m- w
6 EI 1300.07.4
- c. The DADS can monitor plant transients during and following most events expected to occur during the life of the station.
5.9.2 The condition of the reactor and essential safety-related systems shall be assessed and steps taken to assure protection of Station personnel and the public. 5.9.3 Analysis of plant conditions shall be performed to determine reactor core status. Containment Radiation Plots in Attachment 2 provide the relationship between containment radiation levels and the time after plant shutdown for various amounts of fuel inventory released 4 into containment. This information can be used to declare the applicable emergency classification'. 5.9.4 Directives issued to the Control Room shall be assessed for potential adverse consequences before issuance - this includes all offsite directives from government j or company management organizations,
- a. Directives to the Control Room should be done verbally as long as there is mutual agreement to all parties that the correct action is being taken.
\
- b. If a dissgreement occurs between the Control /
Room and the TSC, a written directive from the TSC should be forwarded to the Control Room signed by the Onsite Assessment Manager or Station Operations Manager. 5.9.5 Contact shall be made and support requested as required from the following organizations:
- a. Babcock and Wilcox
- b. Bechtel
- c. Nuclear Safety Analysis Center (NOTEPAD) 5.9.6 A record of activities of the TSC shall be maintained to the best ability of personnel present. Record disposition shall be in accordance with EI 1300.12, Administrative Controls.
5.9.7 The decision to deactivate the TSC shall be made by joint concurrence of the Onsite Assessment Manager, Station Operations Manager, Shif t Supervisor and other key plant personnel-once accident recovery has reached a point where continuous technical assessment and advisory functions are no longer necessary to mitigate the consequences of plant conditions.
i 7 EI 1300.07.3 5.10 Procedure for Activation of the Alternate TSC 5.10.1 The Onsite Assessment Manager will direct the activation of an alternate TSC if the normal TSC becomes uninhabitable for any reason. 5.10.2 No more than three (3) persons assigned to technical support will be dispatched to the Control Room. The 3 balance of the technical support staff (including vendor, TED and NRC persennel) will be located at a suitable position as close to the Control Room as possible. Communications will be established by telephone, messenger, telecopier, etc. between technical-support personnel and the Control Room. Also, communica-tions will be established at least by telephone or messenger between the relocated TSC and the ECC. = _ _ _ . _ _ _ _ - _ _ - -
8 EI 1300.07.3 Technical Support Center Equipment List _ Attachment 1 Location Item Quantity Log Book 1 ea. E-Plan, Supporting & Implementing Proc. I ea. State of Ohio Emergency Plan 1 ea. FSAR 1 ea. TSC Library USAR 1 ea. Admin. Manual (Vol 1, 2, 3) I ea. Tech. Specs. I ea. Rad. Prot. Manual 1 ea. Drawing Change Notice (DCN) Log I ca. TI-59 Calculator 2 ea. Emergency Plan Telephone Directories 5 ea. Telephone Headsets 4 es. TI-55 Calculator 7 ea. Station Procedures (as Designated by the Tecn. Engineer) List of Drawings In TSC Library Electrical Mechanical ISIM ISID E-1 thru E-652 M-001 thru M-196 203A 233D 241B 12501-ISID-003 . E-80 203B 233E 241C 006B E-81 M-580A - C 203F 233F 241D 007 E-82 M-581A - G 203H 233G 241E 010B E-101 M-589 203J 234A 241F 015 E-102 M-592 206F 234B 241G 017 E-103 206G 234C 241H 019 E-104 M-101FW 207A 234D 241L 026A M-102FW 207B 235A 246A 027A M-103FW 207C 235B PS/PSU 027B M-104FW 210E 236A 028B M-105FW 210H 236B 029A M-106FW 220B 236C 029B M-107FW 229 236D 030 M-108FW 230A 236D 031 230A 236E 033 231A 236H 034 231B 240A 035 231D 240B 036 233A 240C 040A 233B 240D 040B 233C 241A 041 046 ISID - In Service Inspection Diagram ISIM - In Service Inspection Isometric
9 EI 1300.07.4 e\ s.DD0*I tx gg -
~
~ . .
;
- E.w1RCENCY ACTION LEVELS IIASED
, ON CONTAlhMLNT RADIATION LZVEL3 Sz 10' =
s-' --
. . ..... . .. . . . . .. _. _..._y... . . . .
.---- .----I 1"I -= CENERAL ENERGENCY ""
..(101 fuel.sett)---
5xto3 . . .. . . . . . . . . . . . . ... . . . . - .
\ .
..L
\ '
' ~ ~ ' '
3 ;
- Otz10 4
~
x
- s. .. ..
j 3,tg 2 - - - . -
. . _ . _. .. = - . . . - .E \ , SITE ARIA EMERGENCY 4 \ ^ '
(gap release . 50". of fue.) g . -
\. .
2 . . . I I ' I tx tg 2 __ . W n N . . . x
- x ..
g x - g5:10i
. . A1117 .
. ' ._- (loss of coolant - 5*. gap releas .
, .;.,, ,,, ...,. ... ;..--... 7 T , , .
t, t t:
.? . .
. .; .. ,. .. ..:.. L. : 17:,;:::. .: . ; .,t ~::. ; .;.?
tz10 3 . - , . . . . . . . . 4 .- 3 10't - - - -- .-
. . NOTIFICATION OF tNC51:AL EVENT
. . - ,, ,--e (toes of coolanE @ 0.1% failed fuel) "' [
. . . . . . . . . 1 . 'e.fp..;
- 4 b-
- 2:.p: { ..m.% ; L 3u2Ln- --- -Z Jg ..:h :L- : . . ; ; - : ' . : _.
[. ;
.... . i,.. .I TDE (hr) ... 1 : .
... .....t' .
1x10 - . I t i 3 i j ijl9 1 i I l l
- o 2 4 6 8 to 15 20 25 30 i
P
- Based on a report by J. Stewart Bland, P.O. Box 4154, Annapolis, MD 21403 dated January, 1983. .
I M Attachment 2
EI 1300.08.0 Davis-Besse Nuclear Power Station Unic No. 1 Emergency Plan Implementing Procedure EI 1300.08 Emergency Control Center Activation , Record of Approval and Changes Prepared by G. J. Reed 5/30/80 Date Submitted by C. E. Wells 6/13/S0 Section Head Data Recommended by _#W b[ b
, SR3 Chair =a f 'Date .
QA Approved [A Quality Assurance Manager Date Approved.by W /M Station S6perintendent ( Date Revision SR3 No. Recommendation QA Sta. Supt. Date Approved Date A proved Date
/
l$$f YYl/0 NA T5 A M y 9/P/ # rostgjw si/n
) f w=q 0/snjsu g qw = , 1/1./t -
pc -l 3 to)s9)n .py- nelse j " / W' I; f - g i,/,s/n NA w M ' "' t 1
I
- l , 1 EI 1300.08.3
- 1. PURPOSE To outline the personnel required for activation of the Emergency Control Center (ECC) and their responsibilities and actions during an emergency at Davis-Besse Nuclear Power Station.
- 2. SCOPE Describe the actions of p'ersonnel assigned to the ECC when the need for its activation has been determined.
- 3. REFERENCES 3.1 Davis-Besse Nuclear Power Station Emergency Plan 3.2 Davis-Besse Nuclear Power Station Emergency Plan Telephone Directory 3.3 Station Response to Emergencies EI 1300.00 3.4 Unusual Event EI 1300.02 3.5 Alert EI 1300.03 l 3.6 Site Emergency EI 1300.04 3.7 General Emergency EI 1300.05 3.8 Administrative Controls EI 1300.12 3.9 Protective Action Guidelines AD 1827.12 3.10 Emergency Offsite Dose Estimates AD 1827.10
- 4. DEFINITION 4.1 Emergency control Center (ECC) - A specifically designated location which is equipped to facilitate the control and coordination of emergency activities and assessments.
- 5. ACTIONS 5.1 The ECC is located at the DBNPS site along Ohio State Route 2 in the Administration Building.
- a. Command and control of site-related emergency efforts affecting local response within the Emergency Planning Zone originate from this center.
3
- b. The ECC contains communication links necessary for coordination with offsite organizations.
2 EI 1300.08.5
- c. The ECC contains a terminal of the DADS (Data Acquisi-tien and Display System) for acquiring necessary data for dose calculations.
5 d. The ECC will serve as an interface with the TED Emergency Response Organization and Local, State, and Federal agencies. 5.2 The first Station management individual to arrive at the ECC shall notify the Control Room that the ECC is manned. 5.3 Emergency Duty Officer Activities 5.3.1 The Emergency Duty Officer (EDO) is responsible for determining the need for and assuring the activation of the ECC. 5.3.2 The EDO shall proceed to the ECC and, if NOT previously performed, notify the Control Room that the ECC is manned and perform the steps sa indicated in Attachment 3. 5.3.3 The EDO shall ensure the following individuals arrive at the ECC as needed: 4
- a. Control Room Communicator
- b. State and County Communicator
- c. Teleprinter Operator
- d. Corporate Management Communicator
- e. Public Relations Communicator
- f. Nuclear Regulatory Commission Communicator
- g. Radiation Monitoring Team Communicator
- h. Radiation Monitoring Teams
- 1. Emergency Operations Manager J. Emergency Planning Supervisor
- k. Community Assistance Communicator 5.3.4 -The EDO may request to the Station Operations Manager that part or all of the telephone.com-munications loops be established.
e
3 EI 1300.08.5 5.3.5 The EDO shall assign an individual (s) to set-up necessary emergency equipment (located in the ECC and Radiological Testing Lab) as listed in Attachment 1. 5.3.6 ' The EDO shall assign an individual (s) to perform dose calculations and dose assessment, and to operate the CRT terminal for the Data Aquisition and Display System.. 5.3.7 The EDO shall ensure that Attachment 2 is com-pleted correctly and supplied to the State and County Disaster Services Agencies.
- a. This shall be accomplished as soon as pos-sible after the start of the emergency.
- b. Updates to Attachment 2 shall be supplied as requested by the State and County Disaster Services Agencies.
5.3.8 The EDO shall assume responsibility for distribu-tion of potassium iodide to station personnel as per AD 1827.12 and to RMT's as per AD 1850.05. 5.3.9 The EDO shall, when necessary, recommend protective actions for the plume exposure pathway to the State and County Disaster Services Agencies-per AD 1827.12, Protective Action Guidelines. 5.3.10 The EDO shall assign Radiation Monitoring Teams and inform Federal, State and local officials l of the affected areas by sector and zone desig- l nators as shown on Attachment 4. ' 5.4 Emergency Operations Manager 5.4.1 The primary Emergency Operations Manager is the Nuclear Services Director. 5.4.2 The alternate Emergency Operations Manager is 5 the Assistant Superintendent - Outage Mgat. 5.4.3 The Emergency Operations Manager, upon being informed that an emergency exists, shall proceed to the ECC. 5.4.4 The Emergency Operations Manager's responsibil-ities and duties include, but are NOT limited to: 9
4 EI 1300.08.3
- a. Report to the Operations Director and appraise him of emergency operations and community relations matters.
- b. Provide direction and guidance for the EDO.
3 c. Notify the state and local officials that protective action for the injestion pathway may be necessary.
- d. Coordinate short term community _ assistance activities and response to the needs of local government officials.
3 5.5 Emergency Planning Supervisor 5.5.1 The Emergency Planning Supervisor, upon being informed that an emergency exists, shall proceed to the ECC. 5.5.2 The Emergency Planning Supervisor's responsibilities and duties include, but are NOT limited to:
- a. Report to the Emergency Operations Manager and appraise him of emergency response
)
activities.
- b. Consult with and provide assistance to the EDO.
- c. Provide guidance needed to coordinate the various emergency response activities.
- d. Ensure contact is made as required to the following agencies (phone numbers are found in Administrative Memorandum No. 37):
*1. Institute of Nuclear Power Operations-(INPO) 3 2. REMS Corporation
*3. American Nuclear Insurers (ANI)
- 4. Federal Bureau of Investigation
- 5. State of Michigan
- 6. Department of Energy (IRAP)
- 7. Consumer's Pcwer Company
- 8. Detroit Edison Company.
- 9. Cleveland Electric Illuminating Co.
- 10. Cincinnati Gas and Electric Co.
i *Must be notified at the Alert level or above. l l' 5.6 Radiation Monitoring Teams I i 1
l l l t i 5 EI 1300.08.5 5.6.1 The first RMT to arrive at the ECC shall perform the functions listed below:
- a. Using appropriate survey instruments, survey 5 the immediate areas surrounding the ECC and TSC.
- b. Standby with a Radiation Monitoring Team Kit and Protective Clothing Kit. Protective clothing to be used as directed.
- c. Check out equipment for operability.
- d. Perform surveys offsite as directed by the EDO.
5.6.2 Other RMT's that arrive at the ECC:
- a. During normal working hours:
- 1. Standby with a Radiaton Monitoring Team Kit and Protective Clothing Kit to be used as directed.
- 2. Check out equipment for operability.
- 3. Perform surveys offsite as directed by the EDO.
- b. During off-normal working hours:
- 1. If not needed as an offsite RMT (as deter-mined by EDO), assignment as onsite RMT's to the Radeon Operations Manager (at the Technical Support Center) or the Shift Supervisor (if the TSC is not as yet manned) will be made by the EDO af ter it is assured that additional aid is needed onsite.
5.7 Staff Personnel 5.7.1 Staff personnel such as the Nuclear Reliability Manager, and other personnel qualified as EDO who are NGT assigned to other emergency operations
- functions shall report to the ECC to assist the EDO, act as communicators, or perform other duties as directed by the EDO.
5.7.2 The staff will assist in communications as l well as in assessment of the data supplied to the ECC. l O
-- e
6 EI 1300.08.5 5.7.3 The EDO may designate members of the staff to perfore dose calculations and assessments.
- a. If a release of radioactive particulates or gases from the plant occurs, dose calcula-tions should be performed in accordance with AD 1827.10, Emergency Offsite Dose Estimates.
- b. Total population exposure should be calculated in accordance with the following:
- 1. Population exposure calculation:
Dose Rate'x PET x PPA = man rem Where: Dose Rate = rate of exposure per unit time in rem PET = Projected Exposure Time or after the release actual exposure time PPA = Population in Plume Area 5 NOTE: Population values can be derived from Figures 6, 7 and 8 in Appendix D of the DBNPS Emergency Plan.
- 2. Schedule for Calculation or Estimates:
8 hours after release - 1st day 24 hours after release - 1st day every 12 hours thereaf ter for 3 days daily beginning the 4th day after the incident. 5.7.4 A record of activities of the ECC shall be main-tained to the best ability of personnel present. Record disposition shall be in accordance with EI 1300.12, Administrative Controls. 5.8 Responding Personnel 5.8.1 Station. personnel whose emergency response is at the station and who are normally authorized non-escorted access, will be admitted upon verbal communications with security.
7 EI 1300.08.4 4 5.8.2 Support group personnel requested to respond to the site will report to the Security Station located at the north end of the Davis-Besse Administration Building for subsequent assignment.
- a. Personnel directed to the station, but who are normally granted escorted access, will be admitted unescorted upon written authorization from the Station Operations Manger.
- b. Personnel directed to the station, but who are normally granted escorted access, will be admitted with an escort upon verbal authorization from the Shift Supervisor or EDO.
m_..
1 8 EI 1300.08.3 DAVIS-BESSE ADMINISTRATION BUILDING RADIOLOGICAL TESTING LABORATORY EQUIPMENT LIST CABINET "1" Survey Equipment: RM-14 HP 260 Probe and Power Cord I ea. PRM-4A with HP 210 Probe 2 ea. PIC-6A Ion Chamber 1 ea. PRM-7 Micro R-Meter 2 ea. Dosimeter Charger 1 ea. Dosimeter 0-100R S ea. Dosimeter 0-5R 5 ea. Dosimeter 0-500mR 25 es. TLD 25 ea. Check Source, CS-137 (~8pCi) I ea. Air Sampler, DC 4 ea. Batteries: - 12-Volt 35-102 Booster 1 ea.
"D" Cell, 1 1/2 Volt 12 ea.
9-Volt 12 ea. NEDA 220, 15 Volts for SK-1 Speakers 12 ea.
"AA" Penlites 12 ea.
Protective Clothing Kits, Each Contain: 12 ea. 1 Pair Cloth Coveralls - 1 Fair Rubber Shoecovers - 1 Cloth Hood - 1 Cloth Cap - 1 Pair Cottor Liner - 1 Pair Rubber Gloves - 1 Pair Plastic Booties - Full Face Respirator - Masking Tape - Other Protective Clothing: Plastic Shoe Covers 30 ea. Disposable Rubber Gloves 2 Boxes Cotton Glove Liners 30 ea. Paper Coveralls 30 pairs Miscellaneous: Smears 2 Boxes Smear Folders 2 Boxes Plastic Bags, Swirl Pack - Tweezers - Plastic Bags, Assorted - Extension Cord 1 Radiation Signs and Inserts - s Rope - Attachment 1 Page 1 of 4
. ~, . - - _ _ . _ .
i ! l 1 9 EI 1300.08.3
, DAVIS-BESSE ADMINISTRATION BUILDING RADIOLOGICAL TESTING LABORATORY EQUIPMENT LIST CABINET "2" Ottawa County Maps 2 ea.
First Aid Kit 1 ea. Da*.a Sheet 1/1 for AD 1850.05 25 ea. Data Sheet til for AD 1827.10 25 ea. Data Sheet #2 for AD 1827.10 25 ea. Stenographer Pads - Bottle of KI Tablets (Approx. 1000) 1 ea. Ledger 1 ea. Pencils and Pens - Felt Tip Pen 1 ea. Particulate Filter, 2 1/4" 30 ea. Silver Zeolite Cartridges 30 ea. Duct Tape - Raincoats 12 ea. Radio 2 ea. Radio Charger 2 ea.
*RMT Kit, Off-Site 2 ea.
*RMT Kit, On-Site 2 ea.
Seals - SAM-2 Analyzers 2 ea. Onsite Radiation Monitoring Team Kit PIC-6A Survey Meter 1 ea. E-520 Survey Meter 1 ea. Flashlight 2 ea. Dosimeter 0-500 mrem 2 ea. Dosimeter 0-1 3em 2 ea. TLD. 2 ea.
! Smear Swipe NUCON 25 ea.
Tweezers 1 ea. Planchet 10 ea. Pencil 2 ea. Note Paper 1 pad Bag-Plastic 5 ea. Screwdriver 1 ea. RMT Procedure, AD 1850.05 I set
*Can be stored outside cabinet.
Attachment 1 Page 2 of 4 i l l
4 10 EI 1300.08.3 DAVIS-BESSE ADMINISTRATION BUILDING RADIOLOGICAL TESTING LABORATORY EQUIPMENT LIST Offsite Radiation Monitoring Team Kit PRM-7 Micro R-Meter 1 ea. E 520 Survey Meter 1 ea. Flashlight 2 ea. Dosimeter 0-500 mrem 2 ea. TLD 2 ea. 3 Smear Swipe NUCON 25 ea. Tweezer 2 ea. Coins (Dime) 20 ea. . Planchet 10 es. Pencil 2 ea. Note Paper 1 pad Bag - Plastic 5 ea. Screwdriver 1 ca. RMT Procedure, AD 1850.05 1 set County Map - Ottawa 1 ea. i Attachment 1 Page 3 of 4
11 EI 1300.08.5 DAVIS-BESSE ADMINISTRATION BUILDING EMERGENCY CONTROL CENTER EQUIPMENT LIST LOCATION ITEM QUANTITY CABINET 1 TI 59 Calculator 1 ea. TI 57 Calculator 1 ea. Extra Paper for Printer - Log Book 1 ea. Procedure Checklists (EI 1300.02, 03 10 ea. 04, 05, 08) . 5 BOOKCASE Emergency Plan, Implementing and 2 sets Supporting Procedures Davis-Besse Technical Specifications 1 ea. State of Ohio, Michigan and Ottawa 1 ea. County Emergency Plans
*Can be stored
- Emergency Plan Telephone Directories 5 ea.
within the ECC,
- Telephone Headsets 5 ea.
but outside *Gaitronics Headsets 1 ea. specific stor- *10 Mile EPZ Map Board 1 ea, age areas *NRC 10 Mile EPZ Map 1 ea.
*NRC 50 Mile EPZ Map 1 ea.
)
1 Attachment 1 Page 4 of 4 1
J l
. a l
i 12 EI 1300.08.5 DAVIS-BESSE NL' CLEAR POWER STATION Emergency Nuclear Incident Essential Information Date Time: ' Sheet No.: Part I: - A. : Classification of incident B. : Time release started or is expected to start C. to the : Wind direction D. m/sec.: Wind speed E. Ci/see: Noble gas release rate F. Ci/sec.: Radiciodine release rate G. : Stability Class H. : Expected duration of release r l I. mr/hr @ miles.: field monitoring reading pei/cc @ miles: I-131 field survey Location er/hr @ miles: field monitoring reading pei/cc @ miles: I-131 field survey 5 Location , mr/hr @ miles: field monitoring reading pei/cc @ miles: I-131 field survey Location Attachment 2 Page 1 of 2
13 EI 1300.08.5 DAVIS-BESSE NUCI. EAR POWER STATION Emergency Nuclear Incident Essential Information (con't) Part II: A. Sector (s)/ Zone (s) are involved B. mr/hr @ miles: whole body dose (pro-jected value) mr/hr @ miles: thyroid dose (projected value) NOTE: Before acting upon the above information, reverify the information and ensure that all assumptions being made are known by the utility, State and local officials. C.
- Facility recommendations (stay inside or evacuate / distance)
D. : Weather conditions (precipitation) Part III: A.
- Plant condition B.
- Cause of incident -
NOTE: When disseminating information during an actual event, if a space is skipped, insert "W/F" or "N/A" to indicate that there has NOT been a mis-take and that the information will be forwarded as soon as possible. W/F = will follow N/A = not applicable Attachment 2 Page 2 of 2
14 EI 1300.08.2 ECC CHECKLIST ACTION COMPLETED ACTION REQUIRED DATE TIME INITIALS
- 1. Emergency Duty Officer
- 2. Perform applicable steps of the ED0/Shif t Supervisor checklist in either EI 1300.03 (Alert),
EI 1300.04 (Site), or EI 1300.05 (General) depending on the action level of the event.
- 3. Assignment of individuals:
- a. Log keeper
- b. RMT Offsite Teams _
2 c. Dose Assessment Indi-vidual(s)
- d. Control Room Communicator
- e. NRC Communicator
- f. State and County Communicator
- g. RMT Communicator
- h. Teleprinter Operator
- 4. Ensure offsite RMT's are sent out in downwind direction for survey per AD 1850.05
- 5. Ensure offsite dose estimates are being made per AD 1827.10
- 6. Assign a C&RT individual for air-borne iodine counting and analysis per AD 1850.05, ,
Attachment 3 Page 1 of 2
15 EI 1300.08.3 ECC CHECKLIST (con't) ACTION COMPLETED
- ACTION REQUIRED DATE TIME INITIALS
, 7. Evaluate what protective actions should be taken based on AD 1827.12 for the plume exposure pathway and make recommendations to the State and County as necessary. Affected areas should be desig-nated as shown in Attachment 4,
- 8. Complete'the Essential Information form (Attachment 2) and release to the State and County Emergency Operation Centers as needed.
i 9. Verify that the Shift Supervisor has requested the post accident sampling procedure AD '1850.04 be put in service per the Station Chemist and Health Physicist
- 10. Ensure total population exposure calculations are made per step 5.7.3(b) of this procedure
- 11. Coordinate the activities of the i following individuals as necessary:
- a. Community Assistance Com-municator
- b. Corporate Management Com-municator
- c. Public Relations Com-municator
'I i I Reviewed by Filed by l' 3 Station Superintendent Emergency Planning Super-visor Attachment 3 Page 2 of 2 l
I' ,
-_ , _ . ~ , , ,, . . . . . ,
16 EI 1300.08.2 Sector and Zone Designators for Emergency Planning Zones Sector Nomsnelature Zone Nomenclatuce Sector in Degrees True 22 1/2' Miles from North from Facility Sector Facility Zoce 348.75* to 11.25' A 0-1 1 11.25' to 33.75' B 1-2 2
- 33. 75* to 56. 25' C 2-3 3 56.25* to 78.75' D 3-4 4 78.75' to 101.25' E 4-5 5 101.25' to 123.75' F 5-6 6 123. 75' to 146.25' G 6-7 7 146.25' to 168.75' H 7-8 8 168. 75' to 191.25' J 8-9 9 191.25' to 213.75' K 9-10 10 213.75* to 236.25' L 10-15 15 236.25' to 258.75* M 15-20 20 258.75' to 281.25' N 20-25 25 281.25* to 303.75* P 25 -30 30 303.75' to 326.25' Q 30-35 35 326.25' to 348.75* R 35-40 40 40-45 45 45-50 50 i AREA SEGMENT - An area is identified by a Sector and zone designator.
EXAMPLE - Area F4 is that area which lies between 101.25' to 123.75* true north from the facility and between 3 and 4 miles out from the facility. a l l l Attachment 4 Page 1 of 3 l l
, ,v . ~ _ --
J j 17 EI 1300.08.2
- u n a
! j j 10 Mile Emergency Planning Zone g %. \ l O - \
o 9 3
\ \
= W s S g
., C -
*q l
~
- l 3 b '
5(% L. g i g g " f r NC % . I. d 2 !! r1
~
,=\
~
_~
/ r si - -
\ l e \
m M / L 'z IA5 f -
.\
'q
/ i I' N'S
=~
( ' ). I\ , l j 4 s ,st
- , n t!* y pe '
- s /\' !1 1 -
h i s. t g ' ! ;-- l5
,l > t 4= l s f < ,
E ' M lr s, , s .I O r
~ ii .
Z ]!l I 8! i l o i q l p -- - -
; l l . .O 1 )
I
~
Attachment 4 m Page 2 of 3 ;
l
~
-- 18 EI 1300.08.2 1
- 50. Mile Emergency Planning Zone N
us. n . .. A d "'
-. . R ", , c., , .M:: f'. ,n; N B^
22s.25* ~ c mr
! n ,r3*
( .i ,,,,,
~.J /
Q ,. Y c
. vg--- -
303.75* % - 54.25* 9 s p -
' i ,
- o. .* -
D C a. .no -, 281.25' N@ 78.75
~ . k /
f f . ,e i - ~; , - 2 N .t, ,
),p m
' i ,,,, ,
d
"" "~
E
.gjgy _.
-w r.
258.75* .. \ 4 % ...
%, T* "o L. ~
. / .i-k -
f c ., ,, a- .. . /
* ' * "
- 123.758 236.25' .. .
-3 [
,~-. 1""*
L g- - --
._ G 213.75* ti 46.25*
=~ --
K H 191.258 168.75* J Attachment 4
- ~
END Page 3 of 3 .
EI 1300.09.0 l Davis-Besse Nuclear Power Station Unic No. 1 E:sergency Plan Implementing Procedure EI 1300.09 Emergency Support Center Activation . Record of Approval and Changes Prepared by G. J. Reed 5/30/80
. Date Submitted by C. E. Wells 6/13/80 Section Head Date Reco::: mended by I#MA
" SR3 Chair:: din Ob Dac5 QA Appreved '
//[!M Quality' Assurance Manager Date Approved by /8[h
. Station Superintendent Data Revision SRB QA Sta. Supt.
No. Recomc:endation Date Approved Date Approved Date
/ I F II PA- /VA p /yte-- '7/ez./tri i
l
1 EI 1300.09.0 I 1. PURPOSE To outline the activation of the Emergency Support Center (ESC).
- 2. SCOPE
, To describe how the steps are taken for response to an emergency from the ESC.
- 3. REFERENCES 3.1 Davis-Besse Nuclear Power Station Emergency Plan 3.2 Davis-Besse Nuclear Power Station Emergency Telephone Directory 3.3 Station Response to Emergencies EI 1300.00 3.4 Unusual Event EI 1300.02 3.5 Alert EI 1300.03 3.6 Site Emergency EI 1300.04 3.7 General Emergency EI 1300.05 3.8 TEco Corporate Radiological Emergency Response Procedures 3.9 Public Relations Policy and Procedures Manual
- 4. DEFINITION 4.1 Emergency Support Center (ESC) - The TED Edison Plaza Building, Toledo, Ohio is designated as the ESC. Key technical and non-technical groups of the offsite emer-gency organization can be housed here.
- 5. ACTIONS 5.1 The Station Superintendent shall notify the Operations Director that an emergency exists.
5.2 Upon being informed of the emergency, the Operations Director shall notify the Emergency Director and the Vice President - Public Relations. 5.3 The Operations Director shall mare recommerdations to the Emergency Director for activation of the necessary portions of the Offsite Emergency Organization. l l _ , _ , , , , = '& '
f .. . . .. .. - - - . - - - . .. . . . . . . . { 2 EI 1300.09.1 S.4 Those portions of the Offsite Emergency Organization
- activated will function as per the TECo Corporate Radio-logical Emergency Response Procedures.
- a. To facilitate Corporate emergency response, personnel have been designated a Notification Level number.
- 1. Level I Directors - those personnel necessary for immediate response at the declaration of an Alert, Site, or General Emergency.
- 2. Level II Directors - those personnel necessary at the declaration of a Site or General Emergency.
- 3. Level III Directors - those personnel necessary at the declaration of a General Emergency to assist in a full Corporate response.
I b. Nuclear Support is provided by the Operations Director, who has direct control of the accident management through Station personnel, and the Engineering Support Director (Nuclear Engineering & Construction Director), who is responsible for engineering and recovery planning.
- c. The overall dissemination of information concerning the accident, emergency activities, re-entry, recovery, and on going Corporate activities will be provided by the Public Relations Mission headed by the Public Relations Director.
- d. The Administrative and Logistics Director will be responsible for providing support in the areas of security, personnel, transportation, procurement, and provisions.
- e. Legal Support is provided by the Legal Director.
- f. Indirect Support is provided by the Finance Director and the Assistant to the Chairman in the form of financial advice and community assistance advice.
5.5 Key Areas of the ESC are:
- a. 7th Fl'oor - The Nuclear Engineering & Construction 1 j
Division (NE&C) is located on the 7th floor of-the i Edison Plaza. This area includes all engineering departments, as well as the Nuclear Licensing Depart-ment. This group will provide engineering support to the Technical Support Center (TSC) and Facility 1 i
3 EP 1300.09.1 , Engineering Group. A terminal of the Data Acquisi-tion & Display Systen (DADS) is available in this area to acquire and transmit current data as necessary between facilities.
- b. 8th Floor - The eight floor contains the Public Relations area which will function as a center for Public Relations and community assistance efforts.
I
- c. 16th Floor - The Planning Center, located on the 16th floor, will~ serve as the Corporate Management Emergency Response Headquarters. It is equipped with all necessary communications, both radio and telephone, and other necessary emergency planning items.
5.6 The Operations Director may direct that one or more of the following telephone communications loops be established as needed per the DBNPS Emergency Plan Telephone Directory:
- a. Technical Data Loop
- b. Technical Management Loop
- c. Policy Management Loop
- d. Public Relations Loop 1 5.7 The V.P. Administrative Services - Nuclear or his designee shall coordinate the response activities of the ESC.
- 6. EMERGENCY SUPPORT 5.1 When activated, the ESC will provide Station support for emergency operations. This support includes, but is NOT -
limited to:
- a. Operational Data (systems operations, set points, procedure writing, etc.)
- b. Technical Data (equipment specifications, etc.)
- c. Engineering (in-house, consultants, vendors, etc.)
- d. Quality Assurance
- e. Public Relations
- f. Personnel (operational, clerical, mutual aid per-
.sonnel, etc.)
- g. Security l
l l
l 4 EP 1300.09.1
- h. Transportation 1
- i. Provisions (food, billeting, etc.)
j . Procurement (parts, equipment, etc.)
- k. Administrative services 6.2 Requests for offsite support should be transmitted to the res-ponsible TED Department or Mission for action per the TECo Corpor-ate Radiological Emergency Response Procedures.
1 6.3 Refer to the Corporate Radiological Emergency Response Plan for a more detailed description of corporate response and responsibili-ties. G END
- i i
s
-- -,y-- , -,
1 EI 1300.10.0 l l Davis-Besse Nuclear Power Station Unic No. 1 Emergency Plan Implementing Procedure EI 1300.10 Reentry - Record of Approval and Changes Prepared by G. J. Reed 5/30/80 Date Submitted by C. E. L' ells 6/13/80 Section Head Date Recommended by /Ae
SRB Chairmai hO Date QA Approved Quality ' Assurance Manager Date Approved by = --- , / IP/8<>
Station Superintendent g Date Revision SR3 QA Sta. Supt. No. Recommendation Date Approved Data Approved Date i p ag sl:ntsz- na DMM '/7lP'-
1 EI 1300.10.1
- 1. PURPOSE To outline a course of action and the protective measures required !
for reentry into Station areas. l
- 2. SCOPE
, Describe the actions and responsibilities of Davis-Besse personnel i and offsite support groups after the Emergency Duty Officer and the Station Operations Manager have jointly determined and declared the Site or General Emergency situation stable and the Station is ready for reentry phase operations.
- 3. REFERENCEF i
1 3.1 Davis-Besse Nuclear Power Station Emergency Plan
- 4. DEFINITION Not applicable
- 5. REENTRY ACTIVITIES 5.1 Initial Coordination
, 1l 5.1.1 The TEco Engineering Support Director shall t develop, coordinate and expedite plans and schedules for the reentry. 5.1.2 The Company Nuclear Review Board (CNRB) shall 1 oversee the activities of the Engineering Support Director, and the Operations Director, to assure
! that all nuclear safety aspects of the operations are satisfied.
5.1.3 The Station Operations Manager, under the direction of the Operations Director, shall be responsible at the site for authorizing the start of. reentry activities. 5.1.4 Offsite reentry activities will be coordinated with the State and County Disaster Services
- Agencies.
5.2 Reentry Requirements The following are actions which shall be considered prior to authorizing reentry. 1 5.2.1 Assess the need for re-entry and whether the l- benefits to be gained offset the potential l' hazards to the re-entry personnel. I
2 EI 1300.10.1 ! 5.2.2 Review available radiation surveillance data. Qetermine areas potentially affected by radia-tion and/or contamination. l l 5.2.3 Review radiation exposures of personnel required to participate in the recovery operations. 5.2.4 Determine the need for additional personnel and the source of these additional personnel. 5.2.5 Review the adequacy of radiation survey instrumenta-tion and equipment for quantity, type, ranges, and calibration. 5.2.6 Pre-plan survey team activities to include:
- a. Areas to be surveyed
- b. Anticipated radiation and contamination levels
- c. Radiation survey equipment required
- d. Shielding requirements and availability
- e. Protective clothing and equipment required
- f. Access control procedures (issuance of new REP's)
- h. Decontamination requirements, and
- i. Communications required.
5.2.7 Periodic determination of the estimated total population exposure. 5.3 Reentry Actions 1 The Engineering Support Director and Operations Director shall determine the priority requirements and assure per-formance of the following activities through coordina-tion with the Station Operations Manager. 5.3.1 Determination of the initial required recovery operations (i.e., road blocks, application of locks and safety tags, etc.). l 1 5.3.2 Visual observation of hazards or potential hazards associated with the recovery operations. M e
3 EI 1300.10.1 5.3.3 Comprehensive radiation surveillance of plant facilities and define radiological problem areas. 5.3.4 Isolate and post areas in the plant with appro-priate warning signs and rope barriers, as Radiation Areas, High Radiation Areas, and Contaminated Areas, as appropriate. 5.3.5 Establish re-entry teams from personnel available in the Operations Support Center (OSC), Technical Support Center (TSC), or other assembly areas. Re-entry teams shall:
- a. ' Consist of at least a team leader and a communicator.
- b. Be briefed on the plan of action.
- c. Be authorized emergency exposure limits as necessary and be advised to frequently check direct-reading dosimeters and withdraw to a safe area if assigned exposure limits are approached.
I d. Be qualified for first aid, plant operations, health physics, and/or maintenance evaluation and corrective action as necessary for the specific re-entry evolution. se e. Be equipped with, or have available, appro-priate emergency equipment and protection devices. Such equipment shall be tested for 1 operability prior to re-entry. 5.3.6 Direct re-entry personnel to withdraw to a safe area if severe unanticipated or unplanned con-ditions are encountered, pending further evalua-tion of the re-entry effort. 5.3.7 Ensure that re-entry teams maintain continuous communication and a continuous status of progress is maintained. 5.3.8 Coordinate the retura of the re-entry teams.
- a. Ensure necessary monitoring, decontaminations, and/or first aid is performed as per appropria-te procedures.
- b. Debrief team members.
4 EI 1300.10.1
- c. Report results and status of re-entry teams.
5.3.9 Determine the need for additional re-entries and for initiation of recovery operations per EI 1300.11 Recove ry. I
- 6. FINAI. CONDITIONS 6.1 Re-entry operations have been completed and all re-entry team members have been accounted for.
6.2 Debriefing of re-entry personnel has been completed and documented.
. O END ,
l
c.I 1300,11.0 Davis-Besse Nuclear Power Station Unic No. 1 Emergency Plan Implementing Procedure EI 1300.11 Recovery . Record of Approval and Changes Prepared by G. J. Reed 5/30/80 Date Submitted by C. E. k* ells 6/13/80 Section Head Date Reco::: mended by SR3 Chair::u6 Et' b /3 Date QA Approved / !M ~ Quality Assurance Manager Date Approved by --^
, ' b Station Superintendent d Date Revision SR3 QA Sta. Supt.
No. Reco=mendation Date Approved Date Approved Data fj , . . ,5 g ae --
"If27[ra.A/A #!" N'E-6 1
1 EI 1300.11.1
- 1. PURPOSE To outline the course of actton for placing the plant in an antici-1 pated recovery condition following a plant event which required activation of the Station Emergency Plan.
- 2. SCOPE Describes the actions and responsibilities of Davis-Besse and offsite support groups in activities after the Station Operations Manager and Emergency Duty Officer have jointly declared that the emergency situation is stable and the Station is ready to enter recovery phase activities.
2.1 The actual magnitude of event recovery will dictate the extent of personnel involvement La the recovery operation. 2.1.1 For events of a minor nature, the normal on-shift organization should be adequate to perform necessary recovery actions (i.e. for Unusual , Event classifications). 2.1.2 For events involving significant damage to plant systems required to maintain operation of the plant, the on-site emergency organization should be adequate to coordinate the necessary recovery actions (i.e. for Alert classifications.) 1 2.1.3 For events involving damage to plant systems required to maintain safe shutdown of the reactor the off-site emergency organization should be adequate to manage the necessary recover actions (i.e. for Site or General Emergency classifica-tions). 2.2 The Station Operations Manager, under the direction of the Operations Director, shall be responsible at the site for authorizing the start of reentry, recovery, and restoration activities; and the return to normal operations.
- 3. REFERENCES 3.1 Davis-Besse Nuclear Power Station Emergency Plan
- 4. DEFINITION 4.1 Recovery Actions - Those actions taken after an emergency to restore the Station as nearly as possible to pre-emergency conditions.
I I 1 I 1 l
2 EI 1300,11.1
- 5. RECOVERY PROCESS 3.1 Itfrial Conditions 3.1.1 Plant conditions are abnormal, but appear stabilized following an event requiring activation of the Emergency Plan,
- a. The plant is in a shutdown condition with adequate core cooling.
1
- b. In-plant radiation levels are stable and decreasing with time,
- c. The release of radioactive material to the environment is controlled and there is no significant potential for additional uncontrolled releases,
- d. Fire, flooding, or similar emergencies are under control.
5.2 Recovery Requirements 3.2.1 Reentry activities have been completed as required by the Reentry Procedure, EI 1300.10. 5.2.2 Plant and TECo personnel have been assigned activities under the direction of the Emergency Duty Officer through approval of the Recovery Director and Operations Director. 5.2.3 Special team members are NOT designated prior to the initiation of this procedure but should be selected from available personnel based on experience and training. 5.3 Recovery Considerations 3.3.1 Particular attention shall be directed towards isolating components and systems as required to control or minimize the hazards. 5.3.2 A systematic investigation shall be conducted to determine the equipment that has been damaged and the extent of the damage. 5.3.3 A detailed investigation of the accident causes 1 I
3 EI 1300.11.1 and consequences both to the plant and the environment shall be conducted. 5.3.4 Determinations shall be made as to the repair work required to perform necessary modifications to plant equipment and/or operating procedures. 5.3.5 Repair work and approved modifications shall be carried out as required by existing or prepared procedures. 3.4 Radiological Considerations 5.4.1 Normal limits of occupational exposure shall be applied during recovery since no emergency is considered to exist. 3.4.2 Compliance with the limits shall be the res-pensibility of the Recovery Director through the Chemist and Health Physicist. 5.4.3 Recovery operations that may result in the release of radioactive materials shall be evaluated by the Recovery Director and his staff as far in advance as possible. 5.5 Procedure 5.5.1 The Shift Supervisor shall direct any necessary recovery actions that are minor in nature (i.e., through normal maintenance work requests).
- a. Repair work and approved procedure modifications shall be carried cut as required by existing procedures.
1
- b. Reports on the cause and reparation of the event shall be made as required by existing station or regulatory procedures (i.e.,
licensee event report or deviation report, etc.) 3.5.2 If the event involves significant damage to plant systems, the responsibility for recovery actions should be shifted to the TSC.
- a. The Station Superintendent, Outage Management becemes the Recovery Manager and recovery actions involving significant plant repair, including:
m
f
'I l l
)
l 4 EI 1300.11.1 l- [ 1. Re-entry into affected areas of the plant ! as per EI 1300.10. l l
- 2. Modifying plant equipment and/or operating l procedures.
- 3. Initiating appropriate system tests to verify the plant's capability to return to service.
- b. All emergency procedures shall be closed out or have an individual assigned to them for completion and closure.
- c. All activated emergency response or support organizations shall be notified in recovery situation and subsequently of its termination.
5.5.3 If the event involves damage to plant systems impairing the ability to maintain safe shutdown for protection of the public, recovery responsibility should be shifted to the EOF. 1
- a. The Recovery Manager under the authority of the Engineering Support Director, shall develop, coordinate, and expedite plans and schedules for recovery operation.
- b. A long-term recovery organization shall be established to coordinate all recovery operations.
- c. A detailed investigation of the accident cause and consequences both of the plant and the environment will be conducted.
- d. Any discharges will be controlled as per plant or regulatory limits.
1 e. Special procedures for decontamination and repair, installation and operation of backup systems, inspections and tests necessary to assure plant integrity and the adequate repairs, waste handling and processing, and ALARA considerations will be developed and implemented. NOTE: As necessary, a technical review group will be identified in the development of the recovery organization, as well as the individual (s) having T s) :
)
. l j
1 l l l 5 EI 1300.11.1 final signature authority on all procedures.
- f. Process and administer any additional support services for personnel, legal counseling, and special funding requirements,
- g. Any procedural waivers granted during the emergency phase shall be either terminated or documented through appropriate procedural modifications.
- h. To the extent possible, applicable limiting conditions for operation and surveillance requirements of the plant Technical Specifications shall be complied with.
NOTE: For those conditions and surveillances in which compliance is iepractical, t.he NRC shall be informed and consulted with regarding aafety implications of continued operation in that mode.
- 1. Applicable off-site agencies shall be notified of recovery organization and activity changes and subsequently of its termination.
J. Any necessary restoration activities shall be implemented to prepare for resumption of full power operating, including:
- 1. Disposal of all waste generated during the emergency and recovery phases.
- 2. Elimination of potential effects of the emergency on future plant operations.
- 3. Training of plant operations, Shift Technical Advisors, and other applicable individuals on changes that occurred to the plant during the emergency outage.
- 4. Replenishment of any emergency equipment or consumable materials.
- k. If recovery and restoration efforts cannot restore the plant to an operable status, a O
6 a erw - y +
n
! 6 EI 1300.11.1 s,
, decommissioning organization shall be established to shutdown the plant to a safe long-term condition. l 5.6 Final Conditions 5.6.1 A recovery organization has restored the plant to its pre-emergency status, to a modified pre-emer-gency status capable of power operations, or to a decommissioning status. i f ' I k 1 j 4
1 F.l!UTION Original. Responsible Section Head Action p ( _ Pile Copy, Master Pile CCP e TC BE MODIPIED POR IMME QlATE i 1PLEMENTATION DAVIS.BESSE NUCLEAR POWER STATION . UNIT 1 c' ' 3 gds $c ( Q Qe3 TEMPORARY MODIFICATION REQUEST E ' ED 6926 SECTION 1 PROCEDURE TITLE AND NUMBER fwa e t ,% b .3 h tt e t . A c , . 6. 1 is o o.12 REASON PCMMANGd fMM VW W Ca e.:ac L- ca.:kt,chs
') n&D pc (Y\t&;ec.9. E<g 9.m.cb loccJcto is F 9f' to Eia.sb 4so 3). h e A o t. Loc th e., o e /m'. M o C cg. p mt.W CHANGE i 1. 5. I E mee. t.o M6oical E ~. p m e.ch Ca .o.ete ac ioc : 6 oa un' lc 4 LaPt.uc,wst9.h;a 6 ecm G x.ict C.w cua.s s , e u ) ,o se s , m.'
t=g4c g o.ec) eO Lowy e6 P.det.ci sk.A e a es i 1.5. 2 Cn.b. e c b 1 6 2 3 ' I cJ e( T ~ t.i .c c_. I h ld ;.od I. O e.c i ht.c hs 9 a t icle.W Q cc em A%L mc.0-h il.s . s hbs ch a i Pra.ses ee i 9.tc te ss W, FA c; t% eA a - w w c b . w < ,o t- n 2-. cc.c 4c.uis ,a a.t_. c\ t,06 Gn o GW \cl:. cc 4 k U C n, y,q q.v6;.c c t- s. AdmM O M o E' gg g 'g cQ,c h (.; c O C'O L'" ('V #3.
,a er7xuo IS PROCEDURE REVISICN REQUIRED -
(twt) s s a ans PREPAREDSY M bu ^"% /y, _ APPROVEQ SY DATE APPSCVED SY 9 19 OATE 7/ w k 2. L COAY A]
- SU8MITTED SY 5ection Headi 4 OATE
' M u u / b u' a L - to4/Cv RECOMMENCEO SY (SRS Chairment DATE
&l
/ O -- f (J [(T-=
j QA APPROVED 8'Y (Manager of Quality Assurance) DATE OATE 1 0 APPROVEO BY (Station Superintencent)rv w_gism Iclell'w
& 9 b
f,gjy B C/W /
- 4 2
ll. 0,0 -- A faicat TMa r mas 7 Room d'o s , l i v il. Cas 7s,v7~s ers t IDaaro'Fsto e,v A7racis m swr +!. l ll 5 b fins 7~ aid k;T Cta f fais And /ptv7/fino ad A TTACAmt#7 Af, ilA 7 has7 Aw squ,pnsx7 is ),e naroniso m a pis, sara,w a
=
}V A CCc AD ANcd w e' 7/9 19D / fj C,0 -L.
1 l 1 1 i i j i i , I 4 9 0 4
, m,. , - . _ - - .....-%_. . . _ _ . , , , , . , , - . , - . , , ,_.,r,. , '4.....,,,,.m.
, ,.n. ...__,,._m, ,d..,._- -
f'hf U . 9 _ l '. EI 1300.12.2
/o S3, L f v'E L TMsou E. G esi_0i N 6- ,
0 lO W C CN3 e M T CC' EMERGENCY MEDICAL EQUIPMENT m..o..m. ... ma (423 ' O . u has_; 21';_) i 3 Demand valve resuscitator and aspirator unit (.mb Adult Hope II resuscitator (obsdskQ) m SL4w O'2 double sphere unit - Full length backboard Short Backboard - liare traction leg splint Stretcher Shovel Axe CPR board liot stick Bolt cuttars r Crowbar Thermal gloves ' Sterile water (pint bag) n ,. , ,, e ,, *.,,,.u* I Fir:5ci[:::[ Sky Geni Decent Device (100' nylon line) la goF vgoa Soc aca.i.oG- iWes ( U l Rescut iocibs cM lec.Kiw3ai.cs.s (.z.) ( CVAl tecKi.ccy n_i ' s U 41I beh14a.ccs, f SAFETj GC Lt , c.u C D- Oc Sf,ttkltt.t bud.h 8ai I La ! Futs+ ADuck Ca.se_ LO . 1- T M C\ . R - G 1 amu.ko I4 gp( bh [ _ c,[e b b-M - A SLtedlL o b N 't. ( L i 10 c tOCC(9 Y~c_ idf3
. - _ . ~
o- :*
"Z' 7 ,3 _ .3,.00 0.,_
l~ LW G , , ~~ ~ _ p ori IX m;p
,z v-9'9 L
r 7.c ,- ~ Y. / -7 ';' .e . I _ s l- nub. cue,t.J ung ' r g a I ' E.g CLt 0 '- (AQ Cc i b l - U O x 1o " Tema %..cc - b 3(o 6 @* b tA W - I .. jp T7 sn R mdNT 1 , g
- FAG.d Iof2
( w cac0)
. l l
10 f hl
+ EI 1.100.12.2 cpg .d f J. ! (mcgwes) meorced2 Ep pd Gas ~^ ~
523' 74(CcOT) (chit,O S CT ^ .: . .J L - - - - - m.G. , ,
....~._=u s
r Cem ~%* k* t'pver Trs$ t 2-Thermometers, oral & rectal 1-roll 4" gauze bandage 24-Sml. alcohol prep pads 1-roll 3" gauze bandage [ 5-sterile cotton tip applicators 1-roll 2" gauze bandage [ 6-lcmon glycerin swabs 2-rolls 1" gauze bandage 5-oval eye pads 1-roll 6" elastic bandage 1-eye irrigation solution 1-roll 4" elastic bandage 1-rescue blanket 56x86" 1-roll 2" elastic bandage 1-surgical sissors-Lg 2-1/2" roll adhesive tape 1 pr sissors-clamp 4-4" bandage compress 1-pr various tweezers 3-3" gauze compress 1-sm child lifesaver tube 2-2" gauze compress 1-adult lifesaver tube 3-8x10 gauze pads 6-diagnostic flashlights 2-5x9 gauze pads
, 1-box (10) a=monia inbalents 2-eye dressing packets 1-box (10) soap swabs 25 plastic finger tip bandages r 100-bandsids 10-oval coverlets, bandaids Upper Compartme'nt Bottom Compartment t '
l-Poison antidote kit 1-burn & trauma dressing 18x24"-arm
. 9-5x9" abdominal pads 1-burn & trauma dressing 24x31"-leg 10-4x4 dressing sponges 1-disposal blanket 1-flashlight 1-set of body binders L I-Saunders snakebite kit 1-cervical collar-lg 1-jaw spreader 1-trauma dressing 30x10"-Dyna Med 1-2" adhesive tape roll 1-sterile burn sheet 66x99-Dyna Med 1-1" adhesive tape roll 1-4 1/2x6" self adhesive gauze 1-ring cutter 1-full leg air splint 1-blood pressure cuff 1-1/2 leg air spline 1-stethoscope 1-foot / ankle air splint 6 3-sal ice paks 1-full air air splint 2-1g ice paks 1-1/2 arm air splint 1-hand / wrist air spl at , Fd Aio MW'Al t CMM*1 i
(E: 01 c i 'C ' : ,_.. D il M r;; C2t ir. : t ';- 1 i i
, A rTewiwr .;t.,
f a c e 2 c / 2.
\
^ Ei 13 CO I2. 2. n, [IfW g htecE S5 s M G--[A; D U'AQg OA6hMb Q ; f[ lit.ScN4d t, mtatgt.scsyshtoien2.c. fn.CC G *A Emergency Medical Equipment located in the Personnel Processing Facility. Life Flight Ecuitment 4 pylons 6 flares 2 smoke flares Resuscitator Robertshaw Demand Valve Reuscitator, inhalator & aspirator unit m.,.st
.8F_19 _ NOM Kit Top Co=partment 10-4x4" Dressings 1-Ring:. cutter 1- 1/2" tape 1- 2" tape 1- Thermometer 6- Penlights 10- Ammonia Inhalants 2- Triangular Bandages -
2- 2x5 yd bandage 2- 3x5 yd bandage 2- 4x5 yd bandage 3ottom Compartment 1- Blood Pressure Cuff 1- 10"x30" Dressing 1--2"' Elastic Bandage 1- 3" Elastic 3andage 3- 3" Unsterile Bandages 3- 4" Unsterile 3andages 100- 1" 3andaids 6- c.irways 10- cleansing wipes 2- Aydx3" Bandage 2- Ice Packs 1- forceps 1- shears 1- 7 1/4" scissors 1- Stethoscope . 1- Blanket 1- Rebreather Mask A r7nca mn er ? 54 l Of ] C i i
pbD l
@ c t t 3 co . n 2-geg g : Ao mis O *E'c 0 ME bN Cmt.tgt.ccq m t@ d % f.wc CIM i SE T -
Lckby { ' 9_ _-- _. u-#g l l 2- 50x90 blanke:s (60% wool, 40% acrylic) ' 2- D Cytinder 02 bottles 1- Pediatric Resusitator-Hope 11 1- Dyna-Med Hare Traction Splint ' 1- Long 3ack Board with 2 Straps l- Shor: Back Board with 2 straps, head & chin strap & wrist restr. 2- 48" Solint boards
~
2- 36" Splin boards 2- 14" Splin boards 1- Roeha=pton 3 urns Dressing Kit includes: 2 arm 18x24 2 leg 24x31 1 body 24x54 1 12"x12" 1 12"x 6" l- bottle of York Isopropyl Alcohol Rubbing Compound 1- ba**1e of 2r? all pr p:0&le-ion Hut-s ;f Criffich Cin -ant-relaav%ia irig 1- bottle of Llavr.-Inffered Ae;i-i..-10Cr 1--h.___
- lo ,,.-vf Yaz. N ir-in-100
=, e. .- . . - - - .
5n hn' e- fly bc.-Aadds n, < ,. . ,a g__ .
,sp BTTA c A mswT 3 Pu-e i es 2.
l
.(p/ H Q #f/W
,a WWCt 3 : /4Srvu e-d. tab i ch (.O 6 rWCtt CNc3 OM hiN t.a b kS C p,to @ c & ( c.d L E ,
(,Cen'0 Blue Trauma Kit 3ottom Compartment 1-3 urn & Trauma Dressing 18x24"-arm 1-3nrn & Trauma Dressing 24x31"-leg 1-Disposable 31anket 1-Cervical Collar-Lg 1-Cervical Collar-Sm 1-Sterile Burn Sheet 60x99"/ disposable 1-Box of 6 air sulints Full leg, 1/2' leg, foot / ankle, full arm, 1/2 arm, hand / wrist 1-Box of 6 oral airways-various sizes 1-Jaw sureader ^ 1-Silver Swaddler (infant blanket) 1-Stethoscope 1-Aneroid Sphygmomanometer Upper Compartment 3- 5x9" abdominal pads 10- Topper Sponges 4"x4" (2ea) 2- 10"x2.5' Trauma Dressing 1- Fracture Strap Kit 1- Tracheal Suction Catheter 1- Wrist Restraints 1- Saunders snakebite kit 2- Kerlix Rolls (sterile) 2- 3" guaze wraps (not sterile) . 2- 2 1/2" guaze wraps (not sterile) 2- Umbilical Cord Clamps 1- Tube of Johnson's First Aid Cream 1- Rinz Cutter 1- 5 172" Ielly Forceps 1- 7 1/4 " sissors 1- Econo-shears 1- 3" Dyna Flex 3andage - 1- 6" Dyna Flex 3andage 1- 1/2" roll adhesive tape 1- 1" roll adhesive tape 1- 2" roll adhesive tape Upper Trays 1- Stubby Thermometer 2- Seizure 31te Stick 12- Alcohol Prep Pads 4- Oval eye pads 1- Eye Irrigation Solution 6 '.Kwick Kold Paks (ice) 6- Penlights 2- Triangle Bandages l'- Box (10) Ammonia Inhalents 2- 3" Elastomull 2- 4" Elastomull l A 7 7 A c. 8 ni n s' T .S - l PRGL ~ Q Cf 2. Y ,
7".hfbC Ik
-b4 EI 1300.12.0 MEDICAL TREATMENT ROOM EQUIPMENT LIST i ; Equipment Type Quantity Location
[ 1 Box (12) Cabinet 1
- 1. Surgical Sutures (4-0) Cuticular 662G
- 2. Surgical Sutures (000) Cuticular H 882G 1 Box (12) Cabinet 1
- 3. Reflex Hammer 1 ea. Cabinet 1
- 4. Straight Safety Razor 1 ea. Cabinet 1
- 5. Hair Clippers I set cabinet 1
- 6. 2" Adhesive Tape 3 rolls Cabinet 1
[ Cabinet 1 L 7. 1/2" Adhesive Tape 6 rolls
- 8. 1" Adhesive Tape 5 rolls Cabinet 1
- 9. Scissors 1 pair Cabinet 1
[ 1 ea. Cabinet 1 ( 10. 11. Finger Ring Cutter 4" Elastic Wrap 7 rolls Cabinet 1
- 12. 2" Elastic Wrap 7 rolls Cabinet 1
- 13. Disposable Syringes 96 ea. Cabinet 1 14 AMBU Resusitator 1 ea. Cabinet 1
- 15. Arm Splint 1 ea. Cabinet 1
- 16. Otoscope 1 ea. Cabinet 2
- 17. Sphygmodanometer 1 ea. Cabinet 2
- 18. lituminator for Disposable Laryngoscope 1 ea. Cabinet 2
- 19. Small size curved Disposable Laryngo-
; scope 10 ea. Cabinet 2
- 20. Large size curved Disposable Laryngo-
. scope 10 ea. Cabinet 2
- 21. Flashlight 1 ea. Cabinet 2 22, 19 Gage Scalp and Small Vein Set 2 sets Cabinet 2 23, 21 Gage Scalp and Small Vein Set 2 sets Cabinet 2 -
Cabinet 2 24 Intravenous Injection Set 2 sets
. 25. Martin Laryngectomy Tube, Size 8 1 ea. Cabinet 2
- 26. Martin Laryngectomy Tube, Size 10 1 ea. Cabinet 2
- 27. 2 BU, Trachex Tube 1 ea. Cabinet 2
- 28. 2 AU, Trachex Tube 1 ea. Cabinet 2
- 29. Sterile Cotton Tipped Applicator 24 ea. Cabinet 2
- 30. Sterile Tongue Depressor 33 ea. Cabinet 2
- 31. Rubbing Alcohol I bottle Cabinet 2
- 32. Eye Wash Irrigator 2 bottles Cabinet 2
. 33. Tincture Benzoin 2 bottles Cabinet 2 34 Extra Large Bandaids 1 box Cabinet 2
- 35. Plastic Kidney Tray 2 ea. Cabinet 2
- 36. Combine Dressing I box Cabinet 2
- 37. Finger SplinL Tape 1 roll Cabinet 2
- 38. Triangular Bandage 1 ea. Cabinet 2 l
l
- 39. Bandaids 1 box Cabinet 2 0 40. Velcro Tourniquet 1 ea. Cabinet 2
- 41. Oval Eye Pads I box Cabinet 2
- 42. 2" x 2" Gauze Pads I box Cabinet 2
- 43. 4" x 4" Gauze Pads 1 box Cabinet 2 l .i 44 Minor Laceration Pads with Instruments 4 sets Table 2/ Drawer 2 L
l f ATTACH mdwT 9 lh4C-i i e f L i
j f(b$ L C 11F EI 1300.12.2 MEDICAL TREATMENT ROOM
,-_yQQIfu{NTLIST
* ~~ ;
Equipment Type 23FdNd? ' Quantity Location , 2l 45. Sterile Tracheotomy Care Set {
- 46. I set Table 2/ Drawer 3 Basic Suction Kit 2-kits
- 47. Napkins Table 2/ Drawer 3
- 48. Duckhous Towel Clamp Table 2/ Drawer 4
- 49. Surgical Razor Holder 4 ea. Table 2/ Drawer 1
- 50. Razors 1 ea .- Table 2/ Drawer'1
- 51. Large Tweezers 12 es. Table 2/ Drawer 1
- 52. Small Tweezers 1 ea. Table 2/ Drawer 1
, 53. Pick 1 ea. Table 2/ Drawer 1
- 54. Tissue Forceps 1 ea. Table 2/ Drawer 1
- 55. Large Towel Clamp 2 ea. Table 2/ Drawer 1
- 56. Surgical Shears 1 ea. Table 2/ Drawer 1
- 57. Kelly Murphy 4 pairs Table 2/ Drawer 1 . '
- 58. Rectal Thennometer I ea. Table 2/ Drawer 1
- 59. Oral Thermometer 1 ea. Table 2/ Drawer 1
- 60. Thermometer Holder 5 ea. Table 2/ Drawer 1
- 61. Towels ~ 2 ea. Table 2/ Drawer 1
- 62. Examination Clothes 2 ea. Table 2/ Drawer 6 2 63. HEMS Medical XIL 2 sets Table 2/ Drawer 6
- 64. Surgical Gloves 3 kits Table 2/ Drawer 7 i 12 pairs Table 1/ Drawer 2 f
1 f L r 4 e 6 1 5 6
?
ATTA cand"T 4 fAC-L2efL
e
- f. b[ Ls?
/(a
-tfr EI 1300.12.2 FIRST AID KIT CONTENTS A"
Elastoplast Knuckle Converlets I Form-Cut Fingertip Bandages 1" Adhesive Bandaids 3" x 3" Sterile Gauze Pads . 1/2" Adhesive Tape 1" Adhesive Tape Merthiolate Swabs Triangular Bandages Eye Dressing Kits ; 2" Compress Bandages
~
4" Compress 5andages 2" Gauze Dandage , 4" Gauze Bandage . Antiseptic Soap. Swabs - Sting Kill First Aid Cream Poison Ivy Solution 1 Tweezers
~
Eye Cup 2 Eye Wash Solution Tourniquet, Forceps + Scissors EA&& /Cf/ AFV
EI 1300.12.O' Davis-Besse Nuclear Power Station Unic No. 1 Emergency Plan Implementing Procedure EI 1300.12 Administrative Controls
- Record of Approval and Changes Prepared by '
G. J. Reed 5/30/80 Date Submitted by C. E. Wells 6/13/80 Section Head Date Reco=c: ended by mmh M SR3 Chairma# Dath QA Approved M Quafity'A'ssurance Manager Date Approved by / 8/b Station Superintendent Date Revision SRB QA Sta. Supt. No. Recommendation Date Approved Date Approved Date
/ f#N/ NM 7 p p_. =g ajulez yR P *= 2 "k 1
e l
;--,- y-- - g .- - tm
1 EI 1300.12.2
- 1. PURPOSE To implement the administrative requirements of the DBNPS Emer-gency Plan.
- 2. SCOPE To outline the administrative requirements for maintaining the readiness of the Emergency Plan and Emergency Plan Implementing Procedures (EI 1300 series).
- 3. DEFINITION Not Applicable
- 4. REFERENCES 4.1 The Davis-Besse Nuclear Power Station Emergency Plan 4.2 Station Operations AD 1839.00 2l 4.3 TED Corporate Radiological Emergency Response Procedures 4.4 Emergency Control Center Activation, EI 1300.08 4.5 Emergency Supply Checklists, PT 5199.14 2 4.6 Fire Protection / Safety for Buildings Outside the Protected Area, AD 1810.02 4.7 Technical Support Center Activation, EI 1300.07 4.8 Operations Support Center Activation, EI 1300.06 4.9 Station Pecords Management, AD 1848.00 4.10 Control of Conditions Adverse to Quality, AD 1807.00 4.11 Reports Management, AD 1804.00 4.12 Records Retention Requirements, AD 1848.17 4.13 Public Relations Policy and Procedures Manual 4.14 Emergency Call System, AD 1827.17 4.15 Personnel Training Program, AD 1828.00
l 2 EI 1300.12.2
- 5. EMERGENCY DUTY OFFICER AND OTHER KEY EMERGENCY' RESPONSE PERSONNEL I (Administrative Non-Emergency Duties) 5.1 The Emergency Duty Officer shall be a member of the Nuclear Mission. A current list of personnel designated as Emergency Duty Officers will be maintained in the Control Room and the Station Superintendent's office.
5.1.1 Assignment periods are weekly commencing at 0800 Monday and ending at 0800 the following Monday. 5.1.2 If the assigned EDO will NOT be available (cannot be reached by pager), it is his responsibility to ensure that acother EDO assumes his duties. 5.1.3 While on duty, the EDO will either carry a " beeper" . pager and remain within a 15 mile radius of either ACME or Lindsey, or leave a locating number with the Shift Supervisor's Office. The EDO should be capable of responding to any problem in 60 minutes or less. 5.2 The Key Emergency Response Personnel are those Toledo Edison Company individuals that are contacted on the first wave of notifications (following the Station Superintendent) after an emergency condition has been declared at the Davis-Besse Station.
- a. The following personnel have been designated Key Emergency Response Personnel:
2 1. Assistant Station Superintendent, Operations
- 2. Chemist and Health Physicist
- 3. Emergency Duty Officer 2 4. Emergency Planning Supervisor
- 5. Nuclear Services Director
- 6. News Media Relations Supervisor
- 7. Nuclear Security Manager
- 8. Technical Engineer
- 9. Maintenance Engineer
- 10. Operations Engineer
- b. Other than the EDO who shall perform his duties in accordance with Step 5.1 above, the Key Emergency Response Personnel should follow the below listed directives:
3 EI 1300.12.2
- 1. If an assigned person will NOT be available (cannot be reached by pager), it is his respon-2 sibility to ensure that another qualified individual assumes his duties.
- 2. These personnel are also responsible for additional notifications per AD 1827.17, Emer-gency Call System in order to provide for adequate response of appropriate personnel.
- 6. PERSONNEL RELIEFS DURING EXTENDED EMERGENCIES 6.1 Should it become necessary during the course of an emer-gency to have personnel relieved of their emergency functions, the relieving personnel should come from off shift personnel NOT already involved with emergency actions.
6.2 Reliefs should take place during a period when conditions . will allow a smooth transition between relieved and relieving personnel. 6.3 Relief scheduling will be accomplished as directed by the Station Operations Manager. 6.4 Reliefs shall be conducted in a controlled manner as con-ditions permit,
- a. The essential information form, or the appropriate EI checklist should be reviewed prior to turnover.
2 b. When facility Managers change, they must verbally announce it so that all personnel in the facility are aware of the change,
- c. All status boards must be up-to-date prior to releas-ing personnel.
- d. All turnovers are logged in the appropriate facility log books.
- 7. ENTRY CONTROL DURING AN EMERGENCY 7.1 Support group personnel reporting to the Station during 2 an emergency assemble at the Radiological Testing Laboratory (RTL) located on the first floor at the north end of the Administration Euilding.
l
f
.ef ,
e 4 EI 1300.12.2 7.2 Personnel assigned to enter the' Station site will pass through a guarded gate. 7.3 Authorized entry to the Station during an emergency will be determined by:
- a. Any Station employee normally authorized nonescorted access will be admitted upon verbal communications from the employee. to security personnel that the employee was directed to eater the Station, or
- b. Writt'en direction from the Station Operations Manager (or designee enereof) co security personnel to admit a person NOT normally granted nonescorted access with an escort, or
- c. Verbal communications from the Shift Supervisor, or the EDO to admit a person NOT normally granted non-esco'rted access for emergency response purposes.
Such visitors must be escorted by security or Station personnel at all times while on the site.
- 8. RECORDS OF DRILLS 2 8.1 The Emergency Planning Supervisor is responsible for collect-ing and reviewing all records concerning Emergency Plan drills and exercises.
8.2 Records shall include: ,
- a. Drill and exercise scenario's
- b. Personnel participating and observing by name, title, iccation, and function during the drill or exercise
- c. Comments and recommendations resulting from the p ,
critique of the drill or exercise
- d. Documentation of deficiencies and the proposed corrective actions
- e. Documentation of the completion of corrective actions. <
- 9. REIEASE OF PUBI.IC INFORMATI0'i 9.1 It is considered important that factual Laformation be l supplied promptly to the public in the event of a Station 1
i I t - ea -
i 5 EI 1300.12.2 emergency. Release of infonmation will be coordinated by the Toledo Edison Vice President - Public Relations 2 according to the TED Public Relations Policy and Pro-cedures Manual. 9.2 The Public Relations Department will dispatch at least one representative to remain at the site, in the ECC or onsite Public Relations Center, for'the duration of any Station emergency. 2 9.3 The Energy Education Center (EEC) is located on the non-restricted side of the Administration Building first floor. This area provides a radiologically and structurally pro-tected location for press gatherings, and briefings. Equip-ment is available to support timely communications and information dissemination on plant conditions and emer-gency operations. ! 10. GUIDANCE TO DOCUMENT HOLDERS Ob'ISIDE TED 10.1 Comments and recommendations concerning the DBNPS Emer-gency Plan and Implementing Procedures should be made in 2 writing to the Emerger.cy Planning Supervisor. 10.1.1 Comments should be mailed to: Toledo Edison Company Emergency Planning Supervisor 300 tiadison Avenue Toledo, OH 43652 2 10.1.2 The Emergency Planning Supervisor will then incorporate appropriate comments in accordance with existing administrative procedures. 4 10.2 The Emergency Planning Supervisor shall update and reissue all necessary Letters of Agreement and Mutual Aid Agreements on an annual basis. 2 10.3 The Emergency Planning Supervisor is responsible for the distribution and maintenance of the DBNPS Emergency Plan Telephone Directory.
- 11. EMERGENCY EQUIPMENT 11.1 Emergency Control Center 11.1.1 The emergency equipment located within the ECC is identified in Attachment 1 to EI 1300.08, Emergency Control Center Activation.
I l
6 EI 1300.12.2 11.1.2 The emergency equipment is inventoried and l maintained in accordance with PT 5199.14, Emer-gency Supply Checklists. 2 11.1.3 Fire protection and detection equipment located within the ECC is maintained and tested in accordance with AD 1810.02, Fire Protection / Safety for Build-ings Outside the Protected Area. { 11.2 Technical Support Center j 11.2.1 Emergency equipment for use in the TSC is identified in Attachment I to EI 1300.07, Technical Support Center Activation. 11.2.2 The emergency equipment is inventoried and maintained in accordance with PT 5199.14, Emer-gency Supply Checklists. 11.3 Operations Support Center l 11.3.1 Emergency equipment for use in the OSC is ! identified in Attachment I to EI 1300.06, l Operations Support Center Activation. 11.3.2 The emergency equipment is inventoried and maintained in accordance with PT 5199.14, Emergency Supply Checklist. 11.4 Radiological Testing Laboratory
- 11.4.1 The emergency equipment located within the RTL is identified in Attachment 1 to EI 1300.08, Emergency Control Center Activation.
2 11.4.2 The emergency equipment is inventoried and main-i tained in accordance with PT 5199.14, Emergency Supply Checklists. 11.4.3 Fire protection and detection equipment located within the RTL is maintained and tested in
- accordance with AD 1810.02 Fire Protection /
Safety for Buildings Outside the Protected Area. 11.5 First Aid Equipment l 2 11.5.1 The orange trauma kit contents are identified in l Attachment 1. 4 2
EI 1300.12.2 7 11.5.2 The first aid kit contents are identified in j Attachment 2. 11.5.3 First aid equipment locetad within the Medical Treatment Room is identified in Attachment 3. 11.5.4 First aid case contents located in the Emergency Medical Equipment Cabinets, 623' level, Turbine Building, are identified in Attachment 4. i 2 11.5.5 Emergency medical equipment cabinets contents,
- 623' level, Turbine Building are identified in l Attachment 5. .
2 11.5.6 First aid equipment is inventoried and main-tained in accordance with PT 5199.14, Emergency Supply Checklists. 1 11.6 Fire Equipment 2 11.6.1 Fire equipment is idencified, maintained, and tested in accordance with AD 1810.02, Fire Pro-tection/ Safety for Buildings Outside the Pro-tected Area.
- 12. EMERGENCY RECORDS 4
12.1 Each Emergency Response Center (TSC, ECC, OSC, ESC) shall maintain a chronological log of the activities of the center. This log shall be maintained under the direction of the individual responsible for directing the centers activities. Entries should include notations of plant status, directions given or received, recommendations made to outside organizaticas, etc. 12.2 Each communicator shall maintain a record of all com-munications received or transmitted. These entries may
- be summaries of conversations, however, data reports and directives should be as specific as possible.
i 12.3 Records of emergencies shall be maintained and disposed of in accordance with Station Records Management, AD 1848.00 and Record Retention Requirements, AD 1848.17.
- 13. TRAINING 4
13.1 Training on the Davis-Besse Emergency Plan and Emergency Plan Implementing Procedures should be a coordinated effort between the Emer3ency Planning Group and the i Nuclear Training Department. t J
, ,, , ,3y--.
_m.-- , w- 2,_, _ , .- . - , , ..y . -e_ _
_ -_ . . . . . . . . = .-_. . ____ .-_ _ __. _ . _._ _ - . _ .. i 8 EI 1300.12.2 i 13.2 Actual training requirements are outlined in Section 8
; of the Davis-Besse Emergency Plan.
13.3 Special case training situations (e.g., news media ' personnel, the general public, etc.) will be handled 2 by various departments within TED as coordinated by the Emergency Planning Group. 4 I 4 i . i f I
.)"
9 O
~ w r- . - - e 4- .'- . 9 --w- i--f . _ p 'y %- py- -
y ,, 7-we+ w-- yg- ,w w, ,
1 I 9 EI 1300.12.2 : ORANGE TRALMA KIT CONTENTS ATTACHMENT 1 Upper Trays 2-Thermometers, oral & rectal 1-roll 4" gauze bandage 24-Sal. alcohol prep pads - 1-roll 3" gauze bandage 5-sterile cotton tip applicators 1-roll 2" gauze bandage 6-lemon glycerin swabs 2-rolls 1" gauze bandage 5-oval eye pads 1-roll 6" elastic bandage l 1-eye irrigation solution 1-roll 4" elastic bandage 1-rescue blanket 56x86" 1-roll 2" elastic bandage 1-surgical sissors-Lg 2-1/2" roll adhesive tape 1-pr sissors-clamp 4-4" bandage compress 1-pr various tweezers 3-3" gauze compress 1-se child lifesaver tube 2-2" gauze compress 1-adult lifesaver tube 3-8x10 gauze pads 6-diagnostic flashlights 2-5x9 gauze pads 1-box (10) ammonia inhalents 2-eye dressing packets 1-box (10) soap swabs 25-plastic finger tip bandages 100-bandaids 10-oval coverlets, bandaids Upper Compartment Bottom Compartment 1-Poison antidote kit 1-burn & trauma dressing 18x24"-arm 9-5x9" abdominal pads 1-burn & trauma dressing 24x31"-leg 10-4x4 dressing sponges 1-disposal blanket 1-flashlight 1-set of body binders 1-Saunders snakebite kit 1-cervical collar-lg 1-jaw spreader 1-trauma dressing 30x10"-Dyna Med 1-2" adhesive tape roll 1-sterile burn sheet 66x99-Dyna Med 1-1" adhesive tape roll 1-4 1/2x6" self adhesive gauze 1-ring cutter 1-full leg air splint 1-blood pressure cuff 1-1/2 leg air splint 1-stethoscope 1-foot / ankle air splint 3-sml ice paks 1-full air air splint 2-1g. ice paks 1-1/2 arm air splint 1-hand / wrist air splint 1 I l l I L
i
)
10 EI 1300.12.2 , FIRST AID KIT CONTENTS ATTACHME.VI 2 4 Elastoplast Knuckle Converlets > Form-Cut Fingertip Bandages 1" Adhesive Bandaids 3" x 3" Sterile Gauze Pads 1/2" Adhesive Tape 1" Adhesive Tape Merthiolate Swabs Triangular Bandages Eye Dressing Kits 2" Compress Bandages 4" Compress Bandages 2" Gauze Bandage 4" Gauze Bandage Antiseptic Soap Swabs - Sting Kill First Aid Cream Poison Ivy Solution Tweezers Eye Cup 2 Eye Wash Solution
- - Tourniquet, Forceps + Scissors 1
i
11 EI 1300.12.0 MEDICAL TREATENT ROOM EQUIPMENT LIST ATTACHME.NT 3 Equipment Type Quantity Location
- 1. Surgical Sutures (4-0) Cuticular 662G 1 Box (12) Cabinet 1
- 2. Surgical Sutures (000) Cuticular H 882G 1 Box (12) Cabinet 1
- 3. Reflex Hammer 1 ea. Cabinet 1
- 4. Straight Safety Razor 1 ea. Cabinet 1
- 5. Hair Clippers 1 set Cabinet 1
- 6. 2" Adhesive Tape 3 rolls Cabinet 1
- 7. 1/2" Adhesive Tape 6 rolls Cabinet 1
- 8. 1" Adhesive Tape 5 rolls Cabinet 1
- 9. Scissors 1 pair Cabinet 1
- 10. Finger Ring Cutter 1 ea. Cabinet 1
- 11. 4" Elastic Wrap 7 rolls Cabinet 1 i
- 12. 2" Elastic Wrap 7 rolls Cabinet 1
- 13. Disposable Syringes 96 ea. Cabinet 1
- 14. AMBU Resusitator 1 ea. Cabinet 1
- 15. Arm Splint I ca. Cabinet 1
- 16. Otoscope 1 ea. Cabinet 2
- 17. Sphygmonanometer 1 ea. Cabinet 2
- 18. Illuminator for Disposable Laryngoscope 1 es. Cabinet 2
- 19. Small size curved Disposable Laryngo-scope 10 ea. Cabinet 2
- 20. Large size curved Disposable Laryngo-scope 10 ea. Cabinet 2
- 21. Flashlight 1 ea. Cabinet 2 1
- 22. 19 Gage Scalp and Small Vein Set 2 sets Cabinet 2
- 23. 21 Gage Scalp and Small Vein Set 2 sets Cabinet 2
- 24. Intravenous Injection Set 2 sets Cabinet 2 25 . Martin Laryngectomy Tube, Size 8 1 ea. Cabinet 2
- 26. Martin Laryngectomy Tube, Size 10 1 ea. Cabinet 2
- 27. 2 BU, Trachex Tube 1 ea. Cabinet 2
- 28. 2 AU, Trachex Tube 1 ea. Cabinet 2
- 29. Sterile Cotton Tipped Applicator 24 ea. Cabinet 2
- 30. Sterile Tongue Depressor 33 ea. Cabinet 2
- 31. Rubbing Alcohol 1 bottle Cabinet 2
- 32. Eye Wash Irrigator 2 bottles Cabinet 2
- 33. Tincture Benzoin 2 bottles Cabinet 2
- 34. Extra Large Bandaids 1 box Cabinet 2
- 35. Plastic Kidney Tray 2 ea. Cabinet 2
- 36. Combine Dressing 1 box Cabinet 2-
- 37. Finger Splint Tape 1 roll Cabinet 2
- 38. Triangular Bandage 1 ea. Cabinet 2
- 39. Bandaids 1 box Cabinet 2
- 40. Velcro Tourniquet 1 ea. Cabinet 2
- 41. Oval Eye Pads 1 box Cabinet 2
- 42. 2" x 2" Gauze Pads 1 box Cabinet 2
- 43. 4" x 4" Gauze Pads 1 box Cabinet 2
- 44. Minor Laceration Pads with Instruments - 4 sets Table 2/ Drawer 2 I
L _ ___ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _
l l 12 EI 1300.12.2 MEDICAL TREATMENT ROOM EQUIPMENT LIST ATTACHMENT 3 (Con't) Equipment Type Quantity Location , 2l 45. Sterile Tracheotomy Care Set I set Table 2/ Drawer 3
- 46. Basic Suction Kit 2 kits Table 2/ Drawer 3
- 47. Napkins Table 2/ Drawer 4
- 48. Buckhous Towel Clamp 4 ea. Table 2/ Drawer 1
- 49. Surgical Razor Holder 1 ea. Table 2/ Drawer 1
- 50. Razors 12 ea. Table 2/ Drawer 1
- 51. Large Tweezers 1 ea. Table 2/ Drawer 1
- 52. Small Tweezers 1 ea. Table 2/ Drawer 1
- 53. Pick I ea. Table 2/ Drawer 1
- 54. Tissue Forceps 2 ea. Table.2/ Drawer 1
- 55. Large Towel clamp i ea. Table 2/ Drawer 1
- 56. Surgical Shears 4 pairs Table 2/ Drawer 1
- 57. Kelly Murphy 1 ea. Table 2/ Drawer 1
- 58. Rectal Thermometer 1 ea. Table 2/ Drawer 1
- 59. Oral Thermcmeter 5 ea. Table 2/ Drawer 1
- 60. Thermometer Holder 2 ea. Table 2/ Drawer 1
- 61. Towels 2 ea. Table 2/ Drawer 6
, 62. Examination Clothes 2 sets Table 2/ Drawer 6 q 63. REMS Medical Kit 3 kits Table 2/ Drawer 7
- 64. Surgical Gloves 12 pairs Table 1/ Drawer 2 l
S
4 13 EI 1300.12.2 FIRST AIR CASE CONTENTS (Emergency Medical Equipment Cabinet, 623' Turbine Bldg.) ATTACHMENT 4 1-Towel 2-Blankets 4 paper sheets - not sterile 1-cloth sheet - not sterile 10-wood splints 5-body binders 6-air splints - full leg full arm 1/2 leg 1/2 arm hand / wrist foot / ankle 1-eed. cervical collar 1-lg. cervical collar 1-30x10" Trauma Dressing 3-36x99" burn sheets 1-flashlight wrist & chin straps / backboard pillow for backboard 4
14 EI 1300.12.2 ' l EMERGENCY MEDICAL EQUIPMENT CABINET CONTLNTS (623' Level Turbine Bldg.) ATTACHMLNT 5 Demand valve resuscitator and aspirator unit (Robert Shaw) Adult Hope II resuscitator j 10'2 double sphere unit Full length backboard Short Backboard Hare traction leg splint Stretcher Shovel Axe CPR board Hot stick Bolt cutters Crowbar Thermal gloves Sterile water (pint bag) Orange trauma kit First aid case Sky Geni Decent Device (100' nylon line) i I e 1 0
.s/
i
DAVIS-BESSE NUCLEAR POWER STATION THE TOLEDO EDISON COMPANY EMERGENCY PLAN SUPPORTING PROCEDURES THIS MANUAL IS THE SOLE PROPERTY OF THE TOLEDO EDISON COMPANY. IT MAY BE RECALLED AT THE OPTION OF TOLEDO EDISON. THIS MANUAL MAY NOT BE REPRODUCED. CONTROL COPY NO.: 50A 7 ISSUED TO: NRC - NUCLEAR REACTOR REGULATION DATE: MAY 1, 1983 ISSLT.D BY: STATION SUPERINTENDENT / EMERGENCY PLANNING
l t i
.t -
? - l THE TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION EMERGENCY PLAN SUPPORTING PROCEDURES I REVISION INDEX PAGE REVISION PROCEDURES REVISION TEMPORARY MODIFICATIONS i 7 HP 1602.01 12 HP 1604.01 4 HP 1604.02 0
! AD 1827.01 3 j AD 1827.02 9 AD 1827.03 2
.. AD 1827.04 2 l AD 1827.05 2 .
.: AD 1827.06 2 AD 1827.07 3
~1 AD 1827.08 2
_j AD 1827.09 2 AD 1827.10 12 T-649L T-711% T-7118 AD 1827.11 4 AD 1827.12 9 AD 1827.13 6 AD 1827.15 - 5
. AD 1827.16 2 j AD 1827.17 4
'1 AD 1850.04 5 l _j AD 1850.05 6 AD 1850.05 0
, l, ,
4 ADMINISTRATIVE MEMORANDUMS REVISION No. 37 ECS Pager and Telephone Numbers 30 No. 38 First Aid Team 12 No. 39 Fire Brigade 13 No. 41 Emergency Duty Officer (EDO) 27 No. 42 . Radiation Monitoring Teams (RMT) 19 Revision 176 April, 1983 e
EMERCE'TCY PLAN SUPPORTING PROCEDURES 4 1. External Personnel Radiation Exposure Monitoring (HP 1602.01)
- 2. Personnel Decontamination (HP 1604.01)
- 3. Area and Equipment Decontamination (HP 1604.02) 4 Annual Radiation Emergency Medical Exercise (AD 1827.01)
- 5. Medical Treatment of Injuries (AD 1827.02)
. 6. Oil spill (AD 1827.03)
- 7. Overexposure / Internal Contamination (AD 1827.04)
- 8. Explosion (AD 1827.05) '
- 9. Tornado (AD 1827.06)
- 10. Earthquaks (AD 1827.07) r
;, 11. ylooding (AD 1827.08)
- 12. Radioactive Transportation Accident (AD 1827.09)
- 13. Emergency Offsite Dosa Estimates (AD 1827.10) l 14 Assembly Accountability and Subsequent Evacuation (AD 1827.11)
- 15. Protective Action Guidelines (AD 1827.12)
- 16. Containment Evacuation (AD 1827.13)
- 17. Area and Equipment Decontamination (AD 1827.1'4 )
. 18. Emergency Isolation (AD 1827.15)
- 19. Search and Rescue (AD 1827.16)
- 20. Emergency Call System (AD 1827.17)
- 21. Post Accident Radiological Sangling and Counting (AD 1850.04)
- 22. Radiation Monitoring Team Surveys (AD 1850.05)
. 23. Radiation, Contamination and Airborne Radioactivity Monitoring During Emergencies at the Davis-Besse Administration Building (DBAB) (AD 1850.06) l l ' ' ~ Revision 7 i December, 1982
, , - , , e-r- n, -'v r
HP 1602.01 - Davis-Besse Nuclear Power Statica thit No.1 , Health Physics Procedure HP 1602.01 External Personnel Radiation Exposure Monitoring Wll1 !D Q g r7 pp p tr llU J.I.611 Ubl b i !!L.nlLL Pecord of Approval and Changes Prepared By Pon Scott & John Tapley 11/28/73 Date Submitted By D. W. Briden 5/17/74 Section Head Date Pa - - - Aad By Jack Evans 5/17/74 SRB N 4 = n Date QA Approved N/A Quality Assurance Director Date Approved By Jack Evans 5/17 /74 Station Super 2.ntendent Date Bevtsien SRB QA Sta. Supt. No. PA - -4.ation Date Approved Date Approval Date 12 fv.t ) . Gh 2./S /g3 N/A g mw_ _ r - Sff,/ p _d
o l 1 HP 1602.01.11
- 1. PURPOSE 1.1 This procedure describes the monitoring and recording of external personnel radiation exposure and the monitoring for personnel contamination.
- 2. REFERENCES 2.1 Health Physics Procedures - Guides and Limits for Radiation Exposure, HP 1601.01.
2.2 Title 10 CFR Part 20 (Standards for Protection Against Radiation). 2.3 FSAR, Section 12.3 (Health Physics). (TS) 2.4 Technical Specifications Section 6.10.2 (Station Operat ing Records). 2.5 American National Standards INSI N13.6 - 1966 (R1972), Practice for Occupational Radiation Exposure Records System. 2.6 AD 1808.08 Access Control 2.7 HP 1601.03 Radiation Exposure Permits 11 2.8 NRC Regulatory Guide 8-14, Personnel Neutron Dosimeters
- 3. EQUIPMENT REQUIRED 3.1 Thermoluminescent dosimeters (TLD's) 3.2 Self-reading pocket dosimeters 3.3 Dosimeter chargers 3.4 Neutron sensitive dosimeters 3.5 Health physics personnel contamination monitoring equip-ment 3.5.1 Portal monitors 3.5.2 Hand and foot counters 3.5.3 Hand-held friskers
- 4. DATA SHEETS REQUIRED 4.1 NRC Form 4 (Attachment 1)
2 HP 1602.01.10 4.2 NRC Form 5 (Attachment 2) 4.3 Radiation Exposure Record, ED 6458 (Attachment 3) 4.4 Dosimeter Record, ED 6547 (Attachment 4) 4.5 Visitors TLD Log (Attachment 5) 4.6 Temporary TLD Exposure Record (Attachment 6) 4.7 Extremity Badge Log (Attachment 7) 4.8 Toledo Edison Temporary TLD Issue (Attachment 8) 4.9 Current Radiation Exposure Record (Attachment 9) 4.10 Dosimeter Record for Neutron Calculation (Attachment 10)
- 5. PRECAUTIONS AND SAFETY 5.1 TLD's and self-reading dosimeters must be protected against loss or damage. Report any loss or damage to the Chemistry and Health Physics Section immediately. Badges and dosimeters must not be removed from the site.
5.2 Care should be exercised not to jar, or drop pocket dosimeters as false readings may be obtained. Dropping a dosimeter discharges .! the electroscope which may give an off scale reading indicative of a high exposure dose. Return a pocket dosimeter to the Health Physics Monitor Room immediately when an offscale reading is observed. An estimate of the dose received will be made and the dosimeter rezeroed.
- 6. PROCEDURE I
6.1 Thermoluminescent Dosimeter Badges (for beta and gamma dosimetry) NOTE: l For neutron dosimetry, see Section 6.1.5. 6.1.1 Personnel assigned to the station and any person likely to receive a dose in any calendar quarter in excess of 25 percent of the quarterly dose limit for whole body, extremities, or skin of whole body shall be given a " permanent" or a " temporary" TLD Badge. 10 1. Any individual likely to receive an exposure to his extremities in excess of 5 times his whole body exposure, his extremities shall be monitored if a significant dose is expected.
4 3 HP 1602.01.12
- 2. Special attention must be given to nonuniform radiation fields so that the region of body (head, chest, or gonadal area) is monitored, whichever receives the highest exposure.
- 3. Personnel with " permanent" TLD badges will pick up their badges at the gate office upon entering the station and return them to the gate office when leaving the station. Badges are supplied by the Chemistry and Health Physics Section.
12 4. Personnel with " temporary" TLD badges normally pick up their badges at the PPF and return them to the PPF exit whenever leaving the Station. Temporary TLD's are issued by Chemistry and Health Physics personnel at the beginning of each month or whenever needed. NOTE: Visitors will turr, their " temporary" TLD's in at the exit to RAC/. NOTE: A self-reading dosimeter or an alternate means of estimating personnel exposure approved by the Chemist & Health Physicist or his designee may be substituted for a TLD.
- 5. For personnel issued permanent TLD's, the following must be done by Chemistry & Health Physics personnel.
(1) An NRC' Form 4 (A'ttachment 1) must be com-pleted as instructed on the form. (2) Past radiation exposure records must be obtained before the quarterly whole body exposure is permitted to exceed 1.25 Rem. (3) A radiation exposure record must be kept (NRC Form 5, Attachment 2). This record shall be updated quarterly from monthly TLD readouts. This record must be pre-served indefinitely and the data reported annually within the first calendar quarter to the NRC as required in 10 CFR 20.401 and 20.407.
.m e
a e- ~< v -
~
1 l 4 HP 1602.01.9 (4) Upon termination of employment or work, or in the event of overexposure, the NRC i and the individual must be furnished a report of personnel exposure as required in 10 CFR 20.405, 20.408, and 20.409. Upon request, the individual must be furnished a report of his exposure. 6.1.2 Other persons required to enter RACA shall be issued a
" visitor" or " temporary" TLD badge. For these persons,
, the following applies:
- 1. Continuing visitors, contractors, and other utility personnel not assigned to DBNPS who will -
l be entering known radiation areas shall be issued , a " temporary" TLD badge by the Chemistry and Health Physics Section. " Temporary" TLD badges are to be read monthly.
- 2. " Temporary" TLD's shall be issued the first time an individual enters RACA for the current calendar month. Attachment Nos. 6 and 8, " Temporary TLD 9
Issue Log"and " Toledo Edison Temporary TLD Issue Report", shall be filled out for each Temporary TLD as it is issued. The Temporary TLD will be removed from use at the end of each month. These
^
individuals . requiring a Temporary TLD shall have l Chemistry and Health Physics-re-issue them a new Temporary TLD each month. 9 3. Attachment No. 8 shall contain all required-Attachment 9 information and is to be updated from monthly TLD readouts with each individual's monthly exposure recorded. This record mu't s be preserved indefinitely and the data reported annually within the first calendar quarter to the NRC as required in 10 CFR 20.401 and 20.407. ! 4. Upon termination of employment or work, or in i the event of overexposure, the NRC and the f individual must be furnished a report of per-sonnel exposure as required in 10 CFR 20.405, 20.408, and 20.409. Upon request, the individual must be furnished a report of his exposure.
- 5. Visitors who are at DBNPS for_ only a few days l
and who will be entering RACA, shall be issued a
" visitor's" TLD. The visitor's TLD will be issued at the entrance to RACA the first time the visitor enters RACA and returned to the RACA entrance when exiting.
- ~-
l l
. 5 HP 1602.01.11 NOTE:
Persons wearing a " VISITOR" TLD badge and have completed RCT may enter RACA unescorted. Those 11 persons who do not have current RCT training must - be escorted by an individual who has current training. This does not remove necessity for escorts for security reasons.
- 6. When " visitor" TLD is issued, the visitor shall supply the information requested in Attachment 5, Visitor's TLD Log. The " visitor" TLD badge may be reused by another visitor unless a radiation exposure is known or suspected. If an exposure is suspected, the " visitor's" badge is to be retained for readout (ie., a net exposure on self-reading dosimeter in excess of 20 MREM).
- 7. The visitor's TLD's shall be read out monthly and the dose recorded according to TLD badge number only.
. CAUTION:
Individuals who have " visitor" TLD badges should receive essentially no dose; the Chemistry and Health Phyaics Section should be notified when visitors will be allowed to enter radiation areas to determine whether a " permanent" or
" temporary" TLD badge should be issued. Under no circumstances should " visitor" badged individuals be permitted to receive a dose in any calendar quarter in excess of 25% of the quarterly dose Ibnit for the whole body. .
- 8. Individuals using Visitor TLD's being being escorted are not required to sign in on an REP.
The escort is responsible to verbally inform his visitor (s) of the conditions and health physics requirements in the area. The dosimeter readings and times are entered on the Visitor Badge Record Sheet (Attachment 5). 6.1.3 Personnel shall wear the TLD badge on the front of the body between the knee and head so that an accurate measurement of whole body dose can be made. NOTE:
.11 The whole body includes the area of the body from the top of the head to the kne-- The TLD should be worn i
i
l 6 HP 1602.01.11 l in that region of the whole body which is likely to receive the highest dose. A. When worn in an area of contamination or high contamination, the TLD badge should be worn in the pocket of the coveralls so that it is protected from contamination. NOTE: If the work area has higher radiation levels which require checking the dosimeter frequently, place dosimetry in a plastic bag. B. TLD badges must be secured so that there is no chance for loss. 6.1.4 Extremity TLD's shall be used when specified as a requirement on a Radiation Exposure Permit (REP). They 11 . should be worn on the hand or foot which is likely to receive the highest radiation dose. They should be worn so that the TLD is not shielded by the hand or foot. NOTE: If extremity monitoring is to be provided then the Extremity Monitoring Log Sheet (Attachment 7) must be filled out and placed in the Temporary Badge Issue book for that month. 6.1.5 Neutron Dosimetry 11
- 1. Neutron whole body doses should be limited to 300 ,
mress per quarter.
- 2. There are three methods which can be used to assign personnel exposures from neutrons:
(1) Multiply the self-reading dosimeter reading times five (5); or (2) Multiply the time exposed to neutrons times the neutron dose rate determined from the measurement of a Neutron Rem-Counter; or l (3) Use the integrated neutron dose determined l_ with the RASCAL Neutron Rem-Counter. l l l
7 HP 1602.01.12
- 3. When working in areas where there is a potential for neutron exposures, each individual is to sign in on Attachment 10 (Dosimeter Record for Neutron Calculation). Send the completed Attach-ment 10 to the Health Physics Supervisor to ensure that the individual's neutron exposure is added to his exposure record.
6.2 Self-Reading Dosimeters 6.2.1 The self-reading dosimeter is used as a dayby-day indication of personnel gamma exposure so that expo-sure guide values given in EP 1601.01 will not be inadvertently exceeded. In the event that a TLD badge is lost or damaged, the dosimeter readings are used to replace the lost TLD badge official records. 6.2.2 All personnel entering RACA shall wear a self-reading dosimeter. Personnel are to wear the dosimeter in . , close proximity to the TLD badge. 6.2.3 Persons requiring access to the Radiation Access Control Area (RACA) shall be issued a self-reading 12 pocket dosimeter for which they shall be responsible. 6.2.4 Before entering the RACA, personnel may "zero" their own' dosimeter by inserting it in the dosimeter charger and adjusted the control until the hairline is on zero. NOTE: After the dosi' meter is removed from the charger, the zero position should be checked because the hairline may shift its po'sition when the dosimeter is' removed from the charger. If this happens, the dosimeter should be replaced in the charger and adjusted below zero to compensate for the shift. 6.2.5 At the end of each work day when the RACA was entered,
" permanent and temporary" TLD badge wearers shall read their dosimeter and record the radiation dose received on their Radiation Exposure Record, ED 6458 (Attachment 3).
- 1. The Radiation Exposure Record is signed the first time an entry is made for each month.
- 2. An individual's daily dose is recorded in the
" Daily" column next to the number correspond-ing to the day of the month.
i l i i
<1 8 HP 1602.01.12
- 3. The " Daily" dose is added to the accumulated whole-body exposure and recorded in the " Quarter" column.
- 4. Radiation Exposure Record cards are administered -
by the C&HP Section. When the mouthly TLD results are received, the cards will be corrected. (1) When the dose for the " running total calendar quarter" from TLD results exceeds 300 mrem, the current Radiation Exposure Record card shall be corrected to agree with the TLD record. (2) Corrected entries are made on the card by Chemistry and Health Physics personnel who will initial and date any corrections. 12
- 5. The C&HP Section will provide assistance in zeroing dosimeters, readings, and recording exposures.
6.2.6 Four models of the self-reading dosimeter are used. Selected according to REP requirements.
- 1. 0-200 or 0-500 mR range - for normal use
- 2. 0-1R range - dosimeter used for entering high radiation areas
- 3. 0-5R range - dosimeter used when the quarterly dose is approached for a single exposure
- 4. 0-100R range - dosimeter for lifesaving ,
NOTE: The 0-IR and higher dosimeters are used only on a planned basis. I 6.2.7 Personnel zero their own dosimeters before entering the RACA when the reading is greater than 20% (40 mR for 0-200 mR, and 100 mR for 0-500) of full scale. On the Dosimeter Record ED 6547 (Attachment 4), enter the information required. The issuance and use of the Dosimeter Record is covered in HP 1601.03, Radietion Exposure Permits. 6.2.8 Personnel will periodically check the reading (expo-sure) on their dosimeters during the course of a day. When working in a high radiation area, personnel shall 1 l l I 1
-. .- . _ - - - - _- . . . - ~ . - - . - _ _ - . . .-
4 9 HP 1602.01.10 check their dosimeter readings (exposures) before 4 entering, during occupancy, and upon leaving the area. 10 6.2.9 If at any time during the course of a day, a 0200 or 0-500 mR range dosimeter exceeds 80% of the full scale reading (160 mR for 0-200 mR range, or 400 mR for 0-500 mR range), the wearer shall return to the Health Physics Monitor Room to have C&HP personnel record the i dose, check his quarterly accumulated dose, and rezero the dosimeter before re-entering the RACA. 6.2.10 If at any time a personnel dosimeter is found to be , ,
; off scale, a read-out of the individual's TLD Badge is 4- required before an individual is allowed to . return to RACA, unless the Chemist & RP or his designee determines j that the off scale reading is not due to over exposure.
6.2.11 Personnel who are working in contaminated areas shall not read dosimeters by holding with contaminated
. gloves. Gloves shall be removed carefully or clean j gloves placed on over contaminated gloves before
. handling personnel dosimeter. A second individual who
- is known to have " clean" non-contaminated gloves may-read other persons' dosimeters in order to determine exposures.
6.2.12 Every effort 'should be made to prevent contamination 1 of personal dosimeters. When it is known or suspected that they have become contaminated, they shall be delivered to C&HP Section for surveying and de-con-tamination if necessary. 6.2.13 Whenever personal dosimeters are lost or damaged, the
- , individual shall immediately leave the RACA and notify ,
C&HP Section. A reasonable estimate of the dose . received by the lost or damaged dosimeters will be l made for. record purpose. l 6.3 Friskers l 10 6.3.1 The.NRC and INPO guideline for personnel contamination 2 is 5000 dpe/100 cm . A frisker is the only type of personnel monitor capable of detecting contamination at 5000 dpa (or 500 eps as read from the rate meter). Anyone leaving a Contamination or High Contamination Area must frisk as described in.this section before leaving RACA. L l o l I
. ._ _ _ . , _ _ , - _ . ~ . , . . _ .. _ __ ._, - _ - . - _ _
< . i,
. 10 HP 1602.01.12 6.3.2 Count-rate meters (friskers) will be installed in locations in the station where monitoring for per-
- sonnel contamination is deemed necessary. The moni-tors will be set up and the alarm point set by the Chemistry and Health Physics Section. The alarm setting and range selection switch must not be changed by personnel using the monitor. Personnel other than Chemistry & HP should use only the volume control and the reset button.
6.3.3 Approach to probe (detector) of the unit with the hands, but don't pick it up until the hands are moved slowly near the probe (as close to the probe as possible without touching it). If the alarm sounds, de-contaminate the hands before touching the probe, i 6.3.4 Once hands are shown to be free from contamination, pick up the probe. 6.3.5 Survey the rest of the body by passing the probe slowly over the body. Make an thorough survey of the bottoms of shoes, elbows, knees, face, and rear. A. If no increase in the clicking rate is heard, no significant contamination is present. B. If clicking rate increases, survey that area even more carefully. If the alarm does not sound, no significant contamination is present. C. If the alarm sounds, contamination is present and must be removed. Put on the clean gloves
. or shoe covers provided if the hands or feet 12 are contaminated. Reset the alarm. Go to the H.P. Monitor Area until clean. Seek assistance from Chemistry & HP if necessary. Restrict ,
i movements until the source of contamination is determined and cleaned up. , NOTE: l Persons must not leave the RACA with contamination on their bodies, clothing, or equipment. 6.4 Hand and Foot Monitor I 6.4.1 A beta gamma hand and foot monitor, located at the Radiation Access Control Area at Door 415, will provide a means of detecting the presence and general location of contamination on hands and shoes. After removing protective clothing and washing hands, the l i _ _ _ _ _ , _ _ __ _ _ _ _ ,_ _. _. ,_ _
.. - ~. - - - .- . - -
4 11 HP 1602.01.12 hand and foot monitor shall be used before leaving the Radiation Access Control Area at Door 415. 6.4.2 To ase the hand and foot monitor, stand on the front apron and place hands in the slots provided. ^ 6.4.3 Wait for the time period indicated on the monitor. If there is no alarm response, the hands and shoe bottoms may be considered free of contamination. 6.4.4 If there is an alarm response, observe the various meters to determine which hand or foot has the high count rate. Proceed as in Part C of Section 6.3.5. Reset the alarm. 6.4.5 A hand-held frisker is located on the side of the unit to detect contamination on clothing and localized areas of the body. Use it as described in step 6.3. 6.5 Portal Monitor 12 6.5.1 A portal monitor (walk-thru) provides complete head to foot monitoring for beta-gamma contamination detec-tion. All personnel must pass through the portal monitor as they exit the RACA through Door 415 or Door 310 and as.they pass through the gate, office when leaving the station. 6.5.2 Enter the portal monitor and stand for the pre-deter-mined count time. If at the end of the counting time, there has been no alarm response, no contamination is present. 6.5.3 If the alarm sounds, contamination is present. Observe the various meters.to determine the general location 4 of the contamination. Proceed as in Part C in Section
- 6.3.5. Reset the alarm.
- 'e
i 12 HP 1602.01.3 ATTAC E NT 1
===**
' esse a
- o.
u 5. muttaan accutatomy coneussace
- e2 Z,"
OCCUPATIONAL EXTERNAL RADIATION EXPOSURE HISTORY 5es laswwsteens en the Out eoenterocatusu 1.NA404 IPAINT
- LAST. Pim57. ANO M100 LEI 2. SOCI AL 54CURITY NO.
1 OATE OP SI ATM IMONTM. QAY. Y EAAI
+ & AGE IN PULL Yi A AS eNI cccusa tions a s amm e . *e e veous ..s ron ,
- s,PetveusEurtovut475savcLvr44 e, carts C8 thatGvut mf f Ptneosce taposume a wieott 3o0v e escono om CatCutatto AAosafsose ta8Cthet.tsst naast aJeo spmou.foi tatees esessanT onti accatss 08 ansetovt A 14L #Eh8AAK3
- 11. ACCUMULATED QCCUPAflONAL 0C$(
-TOTAL .
l l 0 11 CALCeJLATIONE. PE RMissiaLE 0054 tut
- OLE SCCY: 11 CE RTip eCATICM: 1 CE 471'Y TheAT TME EXPC5UmE Mr$704Y L137ED IN COLUMrs5 3. 4. ANO T IS CORRECT AND COMPLETE (Al PEAasts$leLE ACCU 40ULATED . AEM TO TME stif CP MY KNOWLEQGE ANO SEUEF.
l 0054
- SIN-ISI i
(43 TOTAL EXP05VAE TO DATE , AEM EnaPLovEE1s GNATURE 7 ACM ITEM Ill 04TE l IC) UNUSEO PART OP AEM 84. NME GF WNSEE PERur$$38LE ACCUMULATED DOLE (A-48 _ , Page 1 of 2
1 i 1 l 1 13 HP 1602.01.7 ATTACHMENT 1 INSTRUCTIONS FOR PREPARATION OF NRC FORM 4 . Tks term or a clear .no ie,o.e escore et.t.n.ng as ene of ine .ne e.ai as escutatee unoer Section meerm.s.an ,vou. eve on ta.s toem aause no oreoarse av esca 2tL102 Cow .s to ne g en e r.n. 1a.nme of en. Nuciear me ato,v Comemes.on eno. our ant to
$senen 24101. erosu.es to e.oo.e an *ew.ouas to a remat.on "Does to trie noie toev" e.4 tw osemos to .n clues any oo.e to sne none neev. ganaes. .str.e ese e e.com et tre amounts so. cit.ee .n Parserson 20101tas of the esguiar one in Part 20. ~1 andares for Protection aga.ast beene to,m ng organs. neas ano truna, er ' ens os eye.
Rae.atsen." 10 C7ft The reau.tvenent 'or corno.roon of ems
- form is contanee .n Sect.an 2tL102 at inat regusae.on The meermat en coata. nee a ines term s used for niin ateg tne seem g. After eacn entry a fees 8 .necate .n item 9 vne indi..ous for emetae r eose .s ontainee 'com *ec:rss or ca.cu-e tems enem oneaccuenwaa.ee norm .s corpo.e'ett o6cuoet a sau ateond Formn.ow NACof 4 snait De latee e accorsance tn Section 21102.
item.10. Se.' e eianetory. cesnoiet.: tot eacn co ove to he e.oe.o to a ree t,on eow in e ceis of tre hn.ts so.ciego en Paragraon 20.101ias of Part 20 L.stees es.o ev stem are . Tout huisseese Oesvoanond Do.s m1.We Jeovl of sne Con.nesten e.gruscens s requ'.anons ano adettenas
- ngormacon erectiv o.rt.nent to com.
- emag ines form. tesen I1 3 The term 'or the one.e Doev .s atta*ee tv un-enateen of a64 44ues e etem 8.
Careneseen stem t. Seef e.manatory. seem 2. Set 4.oianatory e. cent spat. .f we..ma6 pas eo . ne as issunty numeer ene . ore "none in.s to item 12. Upon commenon of ine evoort. tne emoievee must corney enas tne eformacon .a Caiusens 5. 4. aas 7 mesetes. f =s. i Sest ensianatory. .s accur.e and caramete to rae oest of ms neow. Item 4 taser tpe age .a fuit weart TNs m cWied t" an.n toega. The ease is tne cate of ma e.gnuure. unse a cascuseeng tree ernostee Goes. as s'eo.m to tne nurneer of years of age of tpe .wp. pud , on hs Last turtneav. Castest.ene , tsom Il The i.8eeme accuanulated occusas.onse som for Ommessenes Esos. ire eacn mer eues ane tpe =erme.mo.e co.e under Paragrann 221011t6 are notanee av caraves out imm 5. L,se tne aame and seerves of eacn ore ous em- me tone ng steos Tee sv. eer N snauee ne osover and tne accress of emosovraent. Start witn taen *com stem A Svetract 18 from 's ano avts une me.t recent.rpoiover ane orn eace. o.y the cetf.sr.ce av 5 rem. iPor asamo.e .oan Sn.tn. age 32. N = 22. Pa0 5(22131 = 10 rem.' anctuse eney inose oenoes os emmovenent once ener tota eseosure to ease from trem 18 Suc> tract 4ts e,om sal aae ea*e* tne effereate uncer Se e.gnisone n.r neev e.oim g accuoacons tct. Tne ave e les recc ents tne unuseo part se e.eesure to raeapon. 8cr oenoes of wif*a.osov-n nt. . mart ine were wdea.oie ee." ine o.cm.esose accuenu. arse cow. TNe . e for item 4 Gi.e une ans.e os e.cn emosovment heree in item 5. serm.m ees ca.e es to se carries forware to Form lam 7. List osnoes eunng on.cn occuoacond encomete NRC.S. " Current Occuset.onas Esternal Masacon ise manen acurr.o. sao re mno.e soevi.~ r. iam s. Las ce ese recense for each aerme of noo from o.e regeres of ore eus occusamanal e com.re leone 14. $sef _ ,
- ee .
.e PRIVACY ACT STATEMENT
.e.. e. 3 e ia.e a w iva . . L usm = ew ne n =.we..e- a.s p
.,-nac4.rn n.e.. . e. . aacar.
e.se
.. s u s.c . sera is.t .. c a m. e, t3 fin, e e.s.ee0p a.e as3aasu.e
- s. st es.es.n. ist m . isn isu .e aee ,,a , m(. ianus.c. art met mm.rttt.
t aun. oar.Tvstat ar2 . :mit
=n.i. .r - m. .. iwa ..,t :o.
,. e .e e t e=e.oeat evuosais. Ti.. . e. =ac . . - * =.
.e..-. e e.e a,. . e . . .. T .am
. . ,v,
.e v - o . , ,e . .. - ..=
a,. e . -
.e. t
. e e . e.e si.. ; wer . v a .-
t noute.s uses Ti.
- e. e e s n.no er s e.., n e e s .e e, m.res.,.e rt The .'.na a suma =.8 w *.>4 e
.,- e i.
..c s, .e,..e .e.e .e .n a e
r..,.a. t. te i. .eam-s A uset. . ntwt -.4 e. Ot4CL0su e is mas.caTony .n, on vcLumfaav aMO .foegCT a ON '.motviov.al
,. . .e o.ac4
.e .+--a08 MCT .aov10the p.s on - . . a r - . . ,o era t e a to C,o eioat<. n. a.a e w e to r.
.,wasn=e s m
- e s. .ne =.w .s .a .e.e 401 71.e s.ri. =
e r .,a .,a.
.ac = n. ..n. - c - .,s.,,e s sysTsu amaciatsi ano ao0 ass o n . em e . - e e-IAt s.u.a , a ; . Cama.m.n.w % 04 : osse l
l t Page 2 of 2 i 1 1
14 HP 1602.01.7 1 ATTACIDENT 2 g-==* ^^^ F2 8" ***" e see se u & ensuas esev6 atony E CURRENT OCCUPATIONAL EXTERflAL RADIATION EXPOSURE Seeleuenans.eemSass teENT186CAftCN
- 1. MAAeE LPRtfiT = Last, ficut and me.aam I SOCIAL SECUAITY AC.
- 4. N WE CF LaCINSE3 10 ATE QF BIRTw (**onar osv. veurs
& WMCLE SCCY CCSE
- 7. METMoD QF uCNiTCRING sas. hem 4*oor-S. OCSE RECORCEQ FC A t5omefv venone soev: FE:Pesmet Chemeer - PC. Casasieseru - Casi STATUS (rems
.se of emee tusev: or w eae foreams x 0A GAasMA BETA feet and anahl NEUTAON' CCSE.FOR THE PERICO (romb 11 RUNNING TOTAL FOR 4.PEAICC 07ExFC$uRE CALENDAA QUAATER Wrens - Tot uome g.xogGAmuA, til SETA ! 11. N EUTRCN 11 TCTAL k
u t?iut s ACCWMVt.A
- 10 OCS E is esses ass. sues seem ==e m answena reva ,==e a torn aaa.arsest os e j
. s revu.e--rse es ~
1.*ssoeu. w=wse.a.soas.ae.es.===usess
.m e Page 1 of 2
I i i l
- l I
15 IIP 1602.01.7 ATTAClfMENT 2 .
- c. ear and segions frens 9 Seet ensematory. The*mwes se to av e sa e tem The spressemea and utanomo immemai.oa et ta,re-s form or a.s
.rea on m form .e rua to aae As musurewats are to os weerareten .a tee oest recore ceaema.ag asi ceea 20 401 et '$caneares for Protecnoa 11. tnea maown ano a accorenace w ra Paraeessa 22 4 set osares sweassat to Sect a noe. ore ca.cwaar. ora se maae re cetermee now. a ce: w os 10 C7 m m.ca cacwatsoas is te ne ma.aemaen e con.wwtion ..ea agmane roeation enteraan Aaeatena.oow,es.20 e asaarecureeae recaen of o.cevoat oaas Seca for eaca .aoa.com eor waom wwwane .sew maa.earma
=wse tw ee arasaee reav.ireeearm NAC 5 s to se tnis recor awater . e. In anv case waee r-e aow ear a csea. ,sens can 10 , or tae mwe uaner Seenoa 20.*02. asete visat a seoarme . e wese ter recoreag neeram e=oonure to ili tne wnee noov 423 sam et = nee noev; t3 asnos ano torurms: or ses *ees aae
'O.to heu of altaa. tae waa avraerica carate ."e.s taan 1C'. ' .aav ne sarecs .a
!ssas 12. a v 1eum n ecow Ace tae *ms.es w cer seems 9 10 saa 1I for eicn o.c.oo .
or noowre aae rue a me eats- ea ca.cwiac.ae m senses Lisesoasocaworow.cea ov a.eem are .aucun.oas aae aoemonae etermanen Iotal'* aav entr "r# l 8a30*'***<* 8'dr**N# a a erWily oertinent to cora@eet*$ trws torat, leus 11 Tae aaan.ag nota'is is ceam ta+ea P aragr aon 2 3.as 46.*e oa v'ae.me.s.s e'HI-t s im ee-1# O #888" Ca.easar cuar'ers Noc e . m a. aaoo,ee.e
- s. o ou.sertero~.atew 8.e.ee.rie.me or eso. o . e --oes e.a -*ese sw-sseem s.er ease iIt.W.Uds. h.scu,es.ofv oe an.at.orv.e e wer. aone e,,v ,nes se ~m serve . oot , .. .e m.w io. ii aao u a
=;F g; = =;g. ve.me a eee. O.w m,.o.e . e If t N.O.TE:,e e oi o.n..e
. . e.c.e.aiee ee- tme C9e,ewsn v na nto io. hees Pe.aevedum's
. -s com o~n= E=-re d to .aewee saw 14 enrowea sa awenot se c=-o etes = owe.w .a taat : ate ene ter se ear eaca ca. eats awarter liess 5. "esseCowtototae t== waoe wase peev. toov inas tie goaacs. ceemeoco actwo o formene 13 ter etem 2 in ue-organs. neae aae resas or sees os eve.c. t.:ases tee
- emes of me even are ocotscree w m eve in osnow eres wocao e
121setc.a.m
.ed not encue wame I t.4 ees ocav coe evaerwev esws ar a waee spe,e croug conveo.. aow w
owe inc%ce me e, ment me a ta ascose seso.rc.er
,,, g g ,,,,g,,., ,,e, .s.oa,t,o,f
,,p, se.=.cn, ness,,,,,,,,,,,,,,n,,,,,,,,,.,,,,,,,,,,,,.y,,,,,,,,,,,ti,,,,,,,,,,
of g,,,,,,,, , ,,F,wa,w a,,,M to f Joo,a.n a cm e =a tee er ses e ve evn eye
*'octe of a taisacar cuartw. aae ven.n in oom 88. ra w n ne ore.mt oYe'rN of a.co one ci se e FErUcra me so. ocawe.oIr ed . a NeosN asseroer asang a picmaes of 1.000 rage
-o or **neue iem.
a.eo. e ll;;;; ,tio ,,, ag,t,r,, 4,', ,y, a, g;n,wleao.,,,,,,,
, , , , , , , , , , . a. .e o trosa ,,,,e,,o,ra ,,,
er Form AE" 5 or aSAC 5 or ire- i1 of 8erm AeC 4 Does recoroes ano forearms, or as tutcose am aanto tne iam of me.waoe coav. saaes or NAC 4). Yee tot occusat.one reeseca cow oes= area meowga a ega.e eau meat s ano.wi actorcer acNee as .ag a tae now recewee av ce ao a.awm raws: ne eareces .a tn.s .cem. t sectue ag a.*v ocasanoam oow mewee trem seurces :e P owcaness of 7 mg cra or ess. ?ae cow to ee uwe e.es tne maee coav asnos ano tarearms or feet we aan - -- of raec.ac.o= act e.esaws onerv so. ces os aveacution tre Cems.oa act sneuse ne recorces on secarate *orms wrwess tne cow to pens sats of tre noo, aos osea ce:wees as oou eo me um tae wn evoeweC mos l rm a EC 4to.oa or i AC tw4 ses navse.on-9 caeaoar :.e t.w waeee poor en a term raamtanes for recoromg wame soev s.ceasse av.eeng atter 23rao, eauvoe -=a. eat was me **ewsom av not .wors emoceare. raoreto.re it em. a se astrae leem 8. TNs iten ases to cornosetes om, wae.n me weei es uses of 3 be rems c.rm,oesca emns.cateeca e eve.m ewe ci a come e car cwarter nv e oosures one a' to recore waoe co.ows=vecer ne prov.esioen acensee es o* earagraan teens 15. Eater tmeiJtotas smeacar from trem it c.artwev cows cuartw e*e eaterescae. team I*,m n.emi2t 13.c* 92tLiott tne I wni.no ca meews we so 3 rems oer evaeter to tee ano e
- umme noev. Sater.a mes tem tre wauses oart of cor- in watn.e cri case tae soieceseacag re eaee e' tae was recease cmeaam 4aren cus-w
- 33. leti2e.
masse e. ac.cumwated
.e nem 4 se tae erweeag cose tanees dem aiCfrem 5 or oreseus reeeres isen 16.
et aae etes- 14 are ium I5 ea ene** met sura. Iten 17. Cota.a tae sema o.e aceva wa.:et.Cosa iPaCl ;a rem N .$ or item 13 et F ter ce emCLE ACDv v se .a rs ene aw o
.copas sums's e.soomre w ca mes recora, curia,orm caseovmeat a &Ca or N AC 4.* Se sae=*
wise tre e.ceanse veers et age ce tee .au .e = on a.s ast orme ..ae tr . leem 7. saecate me meces wwe for moruterme ce ine,.ouars eract Is from N ans n w.t eev r= a."wenee av 5 rem aic9 a te g.. Jena Smast. age 22; **
- 22. # A3 * $432 1Si -
m r ee ca rie es arsEvoecueen. actre..mone 70 rem. eneseu e.to earn et earnaSon to raa,e w wsea.*s essomed se It**e 18. C e term.eae tee..awee1 satt et ** # AO tv mar
- ace.e9 Isma 8. Does rece=eo ove e.,secane os see tasa a smeaa svarwt item 18 fron stem a i. Tae vause art at tae *40 nees aos se neoerats eateree on tae *erva crow ses mar A::. % eteo C w e mas percon et ce.L.fetwame saareemas rer ma ag as me saa et ce ser me aceaue.masa*a.as a current recore of tra essee recewee esverse av trhe sneet av twai,eeTheaev serau.m wa.ca saouse ae et usomre asee not soecie asv ee wetsaw seem tre eaterea on ce -
se ano tne eav - men reweat of tast.esoouvre was mt ae it oe'v ewarterty en an.cn . was term ames. 8er esamer esses are entereo.tne :eace of esocsu e for ce heut emeneer ep.arter of I962 m.gnt ce asen es cuan.ag era teensev.4anuary 1.1562. meanet Aricav ' tar:a 4 1912 2 er ane 1952. wewee se enescates en s s etem as smo. I 196.nswee . 30
, noenes,It mom wees.iv ag, asawarvsones4.are ? entered a film teCge aeev January 8,1962 wowie caree ne one.
es4en. sol. B. tG6aae sacneo us '2 4mi. 3. 1862. PetyACY ACTSTAf(MENT n Assammas sei US f .} d G **ctee mee see av weren 3 ed tae prose, Ast et 13 74 arve s Lee 33 $73), eae ease..at massment es formenee to momeums o e en f are meC 5. The meermoeien se mem maet m a vissa es esterse songaews es gaC 27 me esser.see asese interen" Je > vwe
- smoser, C-er40 fear
- hpaa h 4 .0c sca I.19 753.
< see $3. 63.15. 88,133.104.16 8 th). aae 1818e6 as tse Asems Enere, Act of 1954. m ameasse 442 U.512073. 20g3. 2095. 2111.2133.
t . M. +
, sif Tae ausnearv for is'icnet to uses ocurate au m eer e te CF4 Pars M Etb Q.%
nenne ==ocee r= 6aa.e ut r me e t e.*Capet, etam T= mecen.e. esees e, =e aaC .n e.ei.n.e.e t= as e r e ieaseg essaseser, reame.a.nes to meestsr aae r*,viere = news eaebeene ernstern of asseeners. Tne essa same e maagawa esmeanism et seen tw. t rens one teag sure esemer* eenmae eseg evees et lic=ames saa amea, mesanes earn.a eace twee Dars se veer emessuri es remasen .s a.m anse se veu meen I een seosast. Tae meemenee mov ee need to scenes esta se einer ieserne one sese essares meeaves a meanerme saerer e.e.aimg remes.e4 eseesure 1 ROUTiet U$ts , == . e nees,e e-ee e, a.a.reree s to .m . e a m. .e me.me ., .ma.e..e .a mi . e ra.sa. . tem
$mlose le se amaneenas FeeseM. $ tam. W tesal ogsaev m t= owat tae megaaseem ac. sages a.e.4 essa er eewme masem W tas ese J ene gews ed as a.e ,=e. . .s. er.-e.
it .s sen,mer,
- 4. Igiff7Befe OtsCLCSU8f +3 Isam0ATOst 08 v0LU97'45 A40 EFFECT Cu emoWroyal of 4c7 pgovtormC en#0nvartog that ses fusassa ta= **emposse meermahes. metwemt sec as Ww am avseer: housewer fas basese muss esmeene f are 4 AC 5 en esceisme Cre.as a 2oter saimaese I
=ce e w,in I
me.a,= mea.ena, e e t i= acea e = e*ercomem ut.ea ! eam m .s,e. o umr teetCse .C..ea 2e.n2. so-.m.q . a.ra. == .e men. =s aee.m. - . ..e.s.aea,-.,. i news. I a.m e . - eas .aem a e _
.e pre am C- . U s m as,,,.m Crm e .
- i. sysT:= uanactam no aconess o . sei e .e .eems.oane,m.
no o C 2em l l l Page 2 of 2 l
l 16 HP 1602.01.0 l ATTAC10ENT 3 1 i RAOfATION EXPCSURE RECCRO TOTAL EsT. wacLE scov axacsume e.a case SD 4 ASS DAY
*** I " ^ * * " * * * "
mama. 9lrLasaccamo. Tessi From Preas l acciaL, sac. No. MONTM Y ta A 9, l II l Sura nysson TLO, O 24 Me. C tu. Me. O 3re. Mo. ,, j l TOTA 4. EST. WHCLE SOCY EXPCSURE (in MREMI can, i o w er as w an a 19 l
- s- o- l .= l ,
l n l . 2 l n l
* . I = 1 l
4 l 24 i i 5 l n
. l =
2 i = l s I = i s = l 30 to l n j zi l 12 l NW H,Wm % e 600,1200 and 13 2500 MMEM for tar svarter nas teen ressnac. 14 l r I (MPLQVCS $4GreaTURE 15 l i io ,, i Front l l i
==
17 HP 1602.01.0 ATTACIDfENT 4 DAVIS BESSE NUCLEAR POWER STATION l DostMETER RECORD raos esO. UNIT NO. REPeC. so sea?.i Oi O2 Os __ DESCMIPTION I TIME OCSIMETER REAbsvCS 4 Out DO ' 8 NAA4E 3A E DAfg NUMSER g m REMARK.S e
V 8 HP 1602.01.3 ATTACEENT 5 a f c, t - I :s i \, . 25 " 55-i g l
! od I l ==
l i l a O !
~ .
Y l i a i d 00
=
~ .10,5 2 5 g 4
%e l 9
555 ! l
*339 e 3 i
i 2
$.3 .
85 o . a l l D
=
32 M*
~1 .
N . 1 i
, ., l b b a !
( 1 i 6 ah 1 g '
- f C i g '
8 i l
- j
' " 8 g l !
f ' * * ! ' h ! e' Ac E 3 0
$ggf S I i. \ 1 .s. , . -
I 2
.Q i !
~ *3 SE E >0
>0 IIg
~e <3 QW Q N wl E
E I EOP.OE J e o. e >
- 4>n 4 s
o o a e n a = s v i u t e T s o R O u C S E s t , u O A N n O . o. n i sO m u _ R D E E Ds N G LuI T USS d f A Y R TE I E RGB UDM CAU ES S H e s Y f4 g Au P Ma g O C i g
. Y T
t n uR cE ES SM Lu Ah I C O S N . OI T A T S R EO WH... , OO . PC E . g RR A EE LG CD UA ND EY S S R EA BRt D SOr ipr Yt VM. u AE 0"si . _ D T .e l e s I
0 0O9.OweNO _ O
> >O n~
R E D L U O H S n _a T v S r _E e s A 8 n W o _t u - _ TT _- HO GO fuF
, tT _
_ tO O EO - LF o T0 H4 t _ n GA I 4 _t H8 - m 6 u _ 4 TD FN EA LH _ _ _ b e D A E m M H _ . e e <. Y A T IE RB UM CU _ EN
' S _
Y . _ N . A f f Pu _ MA _ On C - h M _ V T N RI O Un I CE _ T Ee A Su Lu T S An I R C E O S W O P MG AO EL LE CG g g UD NA a m). EB g S Y S EI T BM SE: o IR5 VE Au VTro AXo DE Dss i
r . s 21 HP 1602.01.9 9 ATTACHMENT 8 TOLEDO EDISON TEMPORARY TLD ISSUE RECORD NAME (Last, First, Middle) S.S. No. Birth Date Home Mailing Address Company Date of GOT-2 Completion Current Quarterly Exposure MREM (actual or estimated) Lif,etime Exposure MREM (actual or estimated) Security Badge Number I hereby certify the above information is correct and accurate to 'the best of my' knowledge. Signature Date Temporary TLD Issued # Issued By l luu si u ... - _ _ . _ _ _ _ - _ _ _ . _ _ _ _ _ . -
l 22 HP 1602.01.9 CURRENT RADIATION EXPOSURE RECORD 9 ATTACHMENT 9
- 1. NAM ( # MINT - Last twst, eng m.egles L SCCIAL $10:,;m4TV NC.
i a cATE 08 aanTM imenui. es,. ,.are
- 4. NAME OF UCENSEE Aedress. cic7 scace ap
't. 7055 ALCC Act3 FCA tsond,- Ame*e ecow; 6, *MCLE 300Y OOgg 7. METMCQ C# McNa TQAsNG is.6. Fum ssege =
ase se maese besv: er nanes and foresm STATUS pems F 8: Passet Chemeer - PC. Canawiens - Cases se e=e samme x en cauuA1 sata M
~ kihola 3ody -
NEUTACNS CSICU12tioS a.rtmsdo CF EArcsunt 87* - T*8 m cess een TNg penico trems 11 RUNNING TOTAL FOR No. CALINOA A CUA ItTIR
- g. x on CAuuA l 10.atTA l 11.NEUTRCM f 11 TOTAL (remi
( 1/1/ to 1/31/ f i i i *I 4/1/ to 2/29/ i ! 6 1 1 4 3/1/ to 3/31/ ' s i i 6 1
; 4/1/ to 4/30/ i l 8 .I 5/1/ to 5/3rf f i i
. 6/1/ to 6/30/ 6 i e 8 1 7/1/ to 7/31/ I t i I i I 3 /1/' to 8/31/ I ' 4 i 1- I 9/1/ to 9/30/ I I I I I f ,
10/1/ to 10/31/ I i i l I i 11/ 1 / to 11/30/ i I 6 1 12/1/ co 12 A ir 1 8 l 8 t i 6 I l i I I I i 1 4 I I l
-~
Emmarks Otacord Extremity Monitori=r Here) . l l I v*e nwe accwaut.. t o Ocss
= sw reva a res .rs.s, a re,* u-rie n. .. ur. se a . ms
; sees sans .- wa.se..
.ssu. rie a -
o 8 _ .a . _ _ . . . .. -- -- - - L_.
. l 23 l HP 1602.01.9 l 9 ATTACHMENT 10 ;
DAVIS.SESSE NUCLEAR POWER STATION . . . _ . . - .-. . DOSIMETER R ECORD FOR N EUTRON CALCULATION ' **""""'V**' *""" lNeuracs wtrega t..C. 1 . .C2 . _ . . C3 1 so sana I iius cosiusran as aomos mai =w e aos.=n= maue saoct oATI our OUT 4 ggy g ! y NO in im i 1 i I. t i I i i i I e i e . i i
. I i i I l
l
- 1 1 l
I I I ' l I i I i ' l I \
- I I
i anuaus i cAu userto av i aswtwto av l t=Tsatoemasconos I 1% oars camapontua= I lcame sunavisc= l oars hoars l l END
HP 1604.01 Davis-Besse Nuclear Power Station Unic No. 1 Health Physics Precedure HP 1604.01 Personnel Decentamination
!!?!.nlr?n
- q ;% .3 , : , , .. .
%.,,'y $ 7 w.
~. .
Record of Approval and Changes ~ ' -i Prepared by Eruce L. Geddes - 2/6/76 - Date Submitted by 1S.LJ. O m 2 /I o / 7 6 Sec n Head Date Recer.nended by f//4ftM (( SIG Chairman tate QA Approved NA $08 Manager of ity Assurance Date Approved by // d N M
/" Station Superintendent Date Revision SRB QA S ta. Syyt .
No. Rec - ation Date Approved Date ppsdved Date
.j - eD $ b7 HR 's f//Y/77 z ym .ypp. pg w _ _q n,-r 3 ffy W git- nylm njajn-sj,jn ,mo
- o shdo p , Jr l
l 4 I
-- $5 l
. \
l
)
l 1 HP 1604.01.4
- 1. PURPOSE 1.1 This procedure delineates guidelines to be followed by all personnel in the methods of personnel decontamina-tion.
- 2. REFERENCES 2.1 Davis-Besse Radiation Protection Manual, Section 3.5.4.2 2.2 US Department of Health, Education and Welfare Radio-logical Health Handbook 2.3 Health Physics Procedure - External Personnel Radiation Exposure Monitoring, HP 1602.01. ,
- 3. EQUIPMENT NEEDED 3.1 Health Physics personnel contamination monitoring equip ment:
3.1.1 Rm-14 with HP 260 or HP 210 probe. 3.2 Protective clothing to prevent spread of contamination, such as plastic gloves, apron, bib, etc. 4 3.3 Personnel Decontamination Equipment (some of which could be): 3.3.1 Gauze pads 3.3.2 Cotton swabs 3.3.3 Nail clippers 3.3.4 Hair cutting equipment, such as clippers, scissors, etc. 3.3.5 Safety razor and blades 3.3.6 Soft brush 3.3.7 Mild hand soap 3.3.8 Special decontamination soap, such as Turco's "Decon Hand Soap"
- 4. DATA SHEETS REQUIRED
, 6 4.1 Attachment II Personnel Contamination Worksheet i l
a G E 2 HP 1604.01.4
- 5. PRECAUTIONS AND SAFETY l
- 4 5.1 Contact Chemistry and Health Physics Section personnel in event of any contamination of the hands or body or any contamination of the ears, eyes, nose or throat.
5.2 Where contamination spread to open wounds is possible, contact the Chemistry and Health Physics Foreman or his designee before decontamination is started. 5.3 Only water will be used to decontaminate the mouth or i nose. I i 5.4 When washing, caution must be exercised to prevent break - ing the skin, as this creates a potential for internal contamination. 5.5 Never use water which is warmer than body temperature for washing, as this opens the body pores which may absorb contamination, creating a more difficult problem and t potential internal contamination. f 5.6 Decontamination shall be performed using the necessary precautions and protective clothing to prevent the spread of contamination. 5.7 Decontamination of skin with iodine absorption cannot be achieved. If levels of skin contamination cannot be reduced after several attempts have been made, a whole 4 body count should be used to determine the presence of
~
iodine contamination. If contamination levels'are greater-than ~ 10,000 dpe, medical help may be necessary. Iodine levels in the skin less than 10,000 dpm could be released and so noted on Attachment I. ! 5.8 All personnel contamination / decontamination will be l documented on Attachment II~. Forward the completed i Attachment II to the Health Physics Supervisor.
- 6. ONSITE DECONTAMINATION PROCEDURE l 6.1 Contamination of Hands or Body 6.1.1 If contamination is detected on the body of
~
radiation worker, contact the Health Physics Department for assistance. 4 NOTE: A person is considered contaminated when
- . there is greater than 100 cpm.over background as indicated on a RM-14 Frisker or other similar instrument.
- e O
3 HP 1604.01.4 6.1.2 Thotoughly wash the affected areas with mild soap for 2-3 minutes. When washing hands pay particular attention to finger nails and areas between fingers. 4l 6.1.3 Use lukewarm water, using caution to prevent contamination from entering any body openings or skin breaks, wash, starting with the head and proceeding downwards. 6.1.4 Rinse thoroughly with large amounts of clean water, dry and monitor with a survey instrument such as a RM-14 using HP 260 or HP 210 probe. 4 If contamination levels exist greater than 100 cpm above background, repeat the washing and rinsing process two (2) more times using fresh water for each wash. 6.1.5 When surveying for contamination, be sure to check in areas where contamination may be hidden. Areas not previously contaminated must be surveyed as contamination may have been spread to those areas. 6.1.6 Decontamination is considered complete when the 4 area is 100 cpm above background or less when monitored with an RM-14 with a HP 260 or HP 210 probe. 4 6.2 The following steps are to be performed under the supervision of Chemistry and Health Physics Foreman: 6.2.1 Cleanse the area with special decontamination soap, such as Turco's "Decon Hand Soap" (a soft brush may be used); dry' the area ~ and survey. 6.2.2 Repeat Step 6.2.1 until contamination levels are 4 less than 100 cpm above background or until there is no decrease in the level of contamina-tion. 6.2.3 If the contamination is located in and around the finger nails, clip or trim the finger nails as much as possible. 6.2.4 If none of the proceeding steps are sufficient to remove the. contamination, any further decon-tamination will be administered by the Chemist and Health Physicist or a medical coordinator. 1 i l
, - - .- , -c
4 HP 1604.01.4 i 6.3 Hair Contamination 6.3.1 Contamination of the hair shall require the im-mediate notification of the Chemistry and Health Physics Foreman or his designee. 6.3.2 If the contamination is present only in a small area, the hair may be cut off. 6.3.3 If washing is required, the hair should be washed with the individual.in a position that will prevent the spread of contamination to other parts of the body. 6.3.4 Dry the hair and survey for contamination. 6.3.5 Continue Steps 6.3.3 and 6.3.4 until con-4 tamination levels are less than 100 cpm above the background or until there is no decrease in the level of contamination. 6.3.6 If none of the proceeding steps are sufficient to remove the contamination from the hair any further decontamination will be administered by the Chemist and Health Physicist or a medical
- coordinator.
6.4 Contamination of the Ear 6.4.1' Contamination of the ear shall require the immediate notification of the Chemistry and Health Physics Foreman or his designee. 6.4.2 Contamination in the outer ear may be decon-taminated with soap and tepid water on a cotton tipped swab, using care not to get any water in the inner ear. The swabs should only be damp and the individual shall tilt his head so-that the ear is down. i 6.4.3 Do not flush the ear with water or anything i else. 6.4.4 Contamination in the inner ear or other methods of decontamination of the outer ear will only be administered under the s'pervision u of the Chemist and Health Physicist or a medical coordinator. ,
5 HP 1604.01.2 6.5 Contamination of the Eyes or Mouth , 6.5.1 Contamination of the eyes or mouth shall require the immediate notification of the Chemistry and Health Physics Foreman or his designee. 6.5.2 The eyes and mouth may be flushed with tepid water but no other action may be taken. - 6.5.3 When flushing the mouth, bend the individual over the sink to prevent swallowing of the water. 6.5.4 Any further decontamination steps will only be administered under the supervision of the Chemist and Health Physicist or a medical coordinator. 2 6.5.5 After decontamination, have the individual whole body counted to evaluate internal exposure. 6.6 Contamination of the Nose 6.6.1 Contamination of the nose shall require the immediate notification of the Chemistry and Health Physics Foreman or his designee. 6.6.2 Have the contaminated individual blow his nose into a facial tissue or paper towel. 6.6.3 Check the paper for contamination. 6.6.4 Check the nose for remaining contamination. If contamination remains, a damp cotton swab may be used for decontamination. 6.6.5 It is generally better if the contaminated individual performs the following steps himself:
- 1. Insert the damp swab into the nostril as far
. as possible. Exercise caution so that the l swab does not touch the sides cf the nostril during insertion.
- 2. Press the swab lightly against the sides of the nostril and withdraw in a circular motion
- so all sides of the nostril are wiped. Check i swab for contamination.
t 6.6.6 Continue Steps 6.6.5.1 and 6.6.5.2 until con-tamination levels are less than 100 counts above
6 HP 1604.01.3 background and are no longer decreasing or the nostril becomes tender. 6.6.7 If none of the above steps are sufficient to remove the contamination, any further decon-tamination will be administered by the Chemist and Health Physicist or a medical coordinator. 6.6.8 After decontamination is complete, the indi-vidual showers and then will be whole body counted to check the internal exposure received.
- 7. OFFSITE DECONTAMINATION PROCEDURE 7.1 Offsite Decontamination Facilities 7.1.1 Decontamination of a few plant employees during an emergency could be accomplished at the DBAB Radiological Testing Lab.
7.1.2 The major Decontamination Center for an evacua-tion of Davis-Besse personnel is the TED Lindsey Service Center. This is located at State Route
#590 and State Route #20.
7.2 Offsite Decontamination 7.2.1 The Chemistry and Health Physics Section is responsible for monitoring and decontamination of personnel evacuated from the DBNPS. 3 7.2.2 The Chemist and Health Physicist or his designee will assign C&HP Testers to the Offsite Decontamin-ation Center to perform monitoring and decontamin-ation as required. NOTE: The number of C&HP Testers assigned to the center will be determined by the number of DBNPS personnel evacuating to the center. 7.2.3 Personnel decontamination should first be attempted by using sealed towelettes or a spray foam and clean rags. NOTE: This first method will generate very little liquid radwaste for easier clean up. 7.2.4 Further decontamination should be accomplished in accordance with Section 6 of this procedure.
4 7 HP 1604.01.3 7.2.5 Attachment I lists the equipment available from the Station Health Physics Monitoring Room for 3 use at the Offsite Decontamination Center. Additional C&HP Tester Equipment, if required, is available upon approval by the Chemist and Health Physicist or his-designee. NOTE: Equipment should be picked up by and accompany the assigned C&HP Tester (s) to the Decontamination Center. G 4 i r [ I l i
~
, 8 HP 1604.01.3 0FFSITE DECONTAMINATION EQUIPMENT (Not all instruments will be requ! red) E-520 Survey Meter 1 ea PRM-4A with HP 210 Probe 1 ea , RM-14 with HP 260 Probe 1 ea j E-400 with HP 270 Probe 1 ea Additional supplies that may be required and should be considered are as follows:
- 1. A special decontamination soap such as "Turco's Decon Hand Soap"
- 2. Soft brush
, 3. Mild hand soap
- 4. Cotton swabs l
i
- 5. Gauze pads
- 6. Hair shampoo
- 7. Towels
- 8. Razors and shaving cream
- 9. Towelettes
- 10. . Spray foam deconer ,
i l ( l l s l Attachment 1 Page 1 of I
9 HP 1604.01.4 DAVIS-BESSE NUCLEAR POWER STATION PERSONNEL CONTAMINATION WORKSHEET NAME DATE TLD. TIME LOCATION OF INCIDENT DESCRIPTION OF INDICENT: t LOCATION OF HOW INITIAL 1st 2nd 3rd CONTAMINATION DETERMINED LEVEL DECON DECON DECON BI0 ASSAY AND/0R WHOLE BODY COUNT INFORMATION RL M l C/M..P. Technician Date l ( Health Physics Supervisor f Attachment 2 ER- Page 1 of 1 i
3
. j HP 1604.02 I
Davis-Besse Nuclear Power Station Unit No. 1 Health Physics Procedure HP 1604.02 Area and Equipment Decontamination
. l 'l l Record of Approval and Changes Prepared by Michael P. Horne, Sr. 10/23/82 Date s
Submitted by & LJ - Ww I 0 / 2 9 / B 2., Section Head Date Recommended by Mrh // /.2 / h_ SRB Chairman / Da'te QA Approved / Quality Assurarre Director Date Approved by D @ '^-- - , /// f / A Station Sup p tendent Date Revision SRB QA S ta . S upt . No. Recommendation Date Approved Date Approved Date P t i
1
~
l 1 HP 1604.02.0
- 1. PURPOSE The purpose of this procedure is to establish the guidelines necessary to perform decontamination (decon) activities in a safe and economic manner.
This procedure discusses the methods and controls for decontaminating areas and equipment, providing for the protection of cersonnel and the environ-ment against unwarranted exposure to radiation. The contamination levels, relative and incidental costs of tools and equip-ment, and external exposure during decon, will be considered when selecting the process to perform decon activities.
- 2. REFERENCES 2.1 AD 1844.05, cleanliness Control 2.2 HP 1601.04, Radiation, Contamination, and Airborne Radioactivity Areas 2.3 HP 1601.05, ALARA 2.4 10 CFR 20, " Standards for Protection Against Radiation" 2.5 Davis-Sesse Radiation Protection Manual 2.6 AEC Regulatory Guide 1.39, Housekeeping Requirements for Water-Cooled Nuclear Power Plants 2.7 U. S. Department of Health, Education, and Welfare Radiological Health Handbook 2.8 F.S.A.R., Section 17.2 2.9 Ultrasonic Cleaning Information. (Equipment File 3306-6/M20, Turco Products) 2.10 Chem & H.P. Library, Decontamination of Nuclear Reactors and Eouio-ment - Author, J. A. Ayres 2.11 HP 1601.03, Radiation Exposure Permits
- 3. EQUIPMENT NEEDED 3.1 Health Physics Contamination Monitoring Equipment 3.1.1 Nuclear Measurements Corporation - ASC-70 or ASC-75 3.1.2 Eberline - BC-4, RM-14, SAC-4, PRM-4a or PRM-5 3.1.3 Nucon Smears 4_
3.1.4 Various Survey Maps l l { i l
2 HP 1604.02.0 3.2 Protective Clothing as required to prevent personal contamination or spreading of contamination 3.3 Decon material 3.3.1 Ultra-Sonic Cleaners 3.3.2 Electro Deconing Unit 3.3.3 Commercial deconing solutions: i.e., floor wax stripper, Turco, Unichem Decon Solution 3.3.4 High pressure Freon spray booths 3.3.5 High pressure water sprays 3.3.6 Rags, paper towels, squeegees 3.3.7 Spray bottles, mops, buckets, ringers, etc. 3.3.8 Wire scrub brushes, putty knives 3.3.9 Wet and dry vacuums 3.3.10 Strippable paint and coatings, tape 3.3.11 Other equipment as needed or approved by C&HP Management
- 4. DATA SHEETS REQUIRED 4.1 Various survey maps and results of contamination surveys
- 5. PRECAUTIONS AND SAFFTY 5.1 Decontamination should always be performed using all necessary precautions and protective clothing to prevent the spread of con-tamination or personal contamination.
5.2 Decontamination work should normally start at the lowest levels and work toward the higher contamination points. 5.3 Respiratory protection shall be required whenever there is a chance of an internal uptake of contamination, in the presence of Radioiodine at levels greater than 25% MFC, or when surface r contamination approaches 100,000 d/m/100 cm2. l l 5.4 Decon equipment which is not a high cost item shall be disposed of when radiation levels become a source of exposure for workers, (about 1 R/hr). 5.5 only C&HP approved cleaning agents may be used. Special precautions must be exercised to prevent their introduction into the RCS or its support systems. 1 i t
. 3 HP 1604.02.0 5.6 When performing decon activities with a dry vacuum cleaner, a HEPA filter must be installed and working. This piece of equipment is not available for use in any area outside RACA.
5.7 HEPA Filters are disposed of when the differential pressure becomes ex-cessive or when radiation levels exceed 1.0 R/hr at inch from filter housing. 5.S Contaminated areas will be identified by C&HP personnel. They will also post the areas as per HP 1601.04 Radiation, Contamination, and Airborne Radioactivity Areas. 5.9 The C&HP Foreman will advise the decon group on the preferred method of decon based on contamination levels and environmental conditions. 5.10 General and Special REP's will be used in accordance with the procedures for HP 1601.03 Radiation Exposure Permits.
- 6. PROCEDURE 6.1 Methods of decontamination The following steps are guidelines for decontaminating areas, equip-ment, and tools.
6.1.1 Decon with Dry Vacuum Cleaner 6.1.1.1 Loose contaminated dust will be vacuumed with a vacuum cleaner equipped with -a HEPA filter. 6.1.1.2 Collected dust will be disposed of as solid radio-active waste as per SP 1104/28 Solid Radioactive Waste Disposal.
. 6.1.2 Decon with Wet Vacuum Cleaner ,
6.1.2.1 The HEPA filter will be removed from the vacuum < cleaner before it is used for the wet vacuum mode. 6.1.2.2 If the area is nec wet, it'will be wettad down with available clean water. - I l 6.1.2.3 The contaminated area will be vacuumed with the wet vacuum cleaner, and the contents will be disposed [ of as liquid radioactive waste as 'per SP 1104.45 l Station Drainage. 6.1.3 Decon with Demin Water l 6.1.3.1 A water hose may be used for rinsing equipment l- utilizins demineralized water tap. 6.1.3.2 The vertical surfaces are to be rinsed at an angle j l working from top to bottom to avoid recontamination.
- ~
\
l
. l 4 HP 1604.02.0 NOTE: Care should be exercised when using a water hose to prevent airborne- contamination.
6.1.3.3 A floor area will be mopped from outer contaminated area to an area floor drain. The floor drains inside RACA drain to the Miscellaneous Waste Drain Tank and are processed as radioactive waste per SP 1104.30 4 Miscellaneous Liquid Radioactive Waste. 6.1.3.4 The excess rinse water will then be removed with a mop, squeegee, wet vacuum cleaner, or absorbent material such as rags, blot paper, etc., and the floor will then be air dried. 6.1.4 Decon with Chemicals 6.1.4.1 The area will be mopped down with demineralized water and a cleaning agent. 6.1.4.2 The chemicals will be applied in solution form to the contaminated area. 6.1.4.3 Th'e contaminated area will be' cleaned with the use of a mop, hand brush, or powered scrubber. 6.1.4.4 The contaminated liquid will be disposed of to the Miscellaneous Waste Drain Tank via area floor drain as per SP 1104.45 Station Drainage. 6.1.4.5 The contaminated area will be remopped with demin water. 6.1.5 Decon with Ultrasonic Cleaning 6.1.5.1 Small parts, equipment,.and tools may be cleaned by using the ultrasonic cleaner and following the procedure in the Ultrasonic Cleaning Equipment Instruction Manual. Contaminated wastes generated from ultrasonic cleaning will b2 disposed of to the Detergent Waste Drain Tank and processed as radioactive waste as per SP 1104.30 Miscellaneous Liquid Radioactive Waste. 6.1.6 Decon with High Pressure Freon 6.1.6.1 High pressure Freon can be used on parts and tools in an enclosed container.
- 6.1.6.2 Continued spraying will reduce contamination.
Further reduction will require other methods. 1 i ! NOTE: Filters in these units will have to be l changed out periodically following manu-l factor's instructions for handling radio-l active filters, l l l,___ - - - _ -
. _, - - nt - 9
5 HP 1604.02.0 6.1.7 Decon by High Pressure Jet Sprays NOTE: Will not normally be used because of the likelihood of creating a serious airborne problem. 6.1.7.1 A high pressure jet sprayer may be used to wash, chemical clean, and/or rinse a contaminated area utilizing demineralized water tap. 6.1.7.2 The vertical surfaces are to be sprayed at an angle working from top to bottom to avoid recontamination. 6.1.7.3 A floor area will be sprayed from the outer con-tamination area to an area floor drain. The floor drains inside RACA drain to the Miscellaneous Waste Drain Tank and are processed as radioactiv,e vaste per SP 1104.30 Miscellaneous Liquid Radio-active Waste. 6.1.7.4 The excess rinse water will then be removed with a mop, squeegee, wet vacuum cleaner, or absorbent material such as rags , blot paper, etc. , and the floor will bhen be air dried. 6.1.8 Decon by Electro-Polishing 6.1.8.1 Not used at Davis-Besse at this time and will be covered by a Health Physics Instruction when available. 6.2 Solvents and Chemicals for Decon Use 6.2.1 Below is a list of solvents and chemicals available for use in deconning: (See Attachment 1)
i
~
6 HP 1604.02.0 Attachment 1 Page 1 of 2 SOLVENTS AND CHEMICALS AVAILABLE FOR USE IN DECONNING Approx Suggested ' pH Temp for Suggested Designation Form Use Use OC(CF) Applications as Used Viking Floor N/A Stripper & Demin N/A All temps Various strengths Wax Stripper H2O <2120F Uni-Chem N/A Chemical Solvent N/A All temps Vcrious strengths plus Demin H2O <212 F Chemical Composition or Description Turco Decon Powder Mildly alkaline 7.5 Ambient to Removal of contami-4182-A (high detergent boiling nation from cotton-foam) clothing, rubber articles, painted , surfaces such as walls and vehicles. Turco Decon Powder Mildly alkaline 7.5 Ambient to Same as above. 4324 (low detergent boiling foam) Turco Decon Powder Inhibited acidic 1.2 65-90 Removal of activated 4306-C material (150-190) corrosion products, fission products and and fissile material from aluminum, stainless 4306-D (150-212) steel,_ carbon steel, and Zirealoy surfaces. Turco Decon Liquid Highly alkaline 13.5 115-120 conditioning-of tena-4501-A (240-250) cious contamination on high-temperature alloys and stainless [ steel. ( Turco Decon Powder Highly alkaline; 14 95-100 Conditioning of con-4502 contains potassium (200-210) taminated films.on permanganate. ' carbon steel and Inhibited to protect stainless steel sur-Stellites and faces of equipment, Graphitar pressurized water i loops, fuel reprocess-ing equipment and reactor components.
--___-_-__.___L__ .-+
e 7 HP 1604.02.0 Attachment 1 Page 2 of 2 Approx Suggested Chemical Composition pH Temp for Suggested Designation Form or Description as Used Use OC(OF) Applications Turco Decon Powder Alkaline rust 13.5 85-90 Removal of radioactive 4507 remover with low (185-195) contaminated rust, chloride content carbon scale, paint, and oil. Turco Decon Damp Disodium salt of 3.3 70-95 Decontamination of 4509 Powder EDTA, citric acid, (160-200) components removed synthetic nonionic from pressurized water reactors. Turco Decon Liquid Inhibited phosphoric 1.3 60-65 Decontamination of 4512-A acid type reagent (140-150) carbon steel loops, very low in fluorides reactor components, and chlorides hand tools, and equip-ment. Also for removal of rust from ferrous surfaces. Turco Decon Powder Inhibited acidic 1.2 60-65 Decontamination of. 4513-A material predomi- (140-150) carbon steel loops, nantly sodium reactor components, bisulfate hand tools, and ' equipment. Turco Decon Powder Inhibited acidic 1.3 85-95 Decontamination of 4518 material predomi- (185-200) loops, components, nantly oxalic acid tools, and systems made of stainless steel and high temperature alloys. Turco Decon Powder Inhibited synthetic 2.2 90-95 Suggested for use on SAC ammonium citrate, (190-200) stainless steel, surfactants, soil carbon steel, Inconel, redeposition and Stellites. retardants to promote greater efficiency END
~
AD 1827.01 Davis-Ea.sse Nuclear Pcwar Station Unit No. 1 - AEMINISTRATIVE PROCEDURES AD 1827.01 Annual Radiation E=ergency Medical Exercise 3
..-m
, .y . -
N u , Q.; ,,, Racord of !.:prov.sl and Changes Prepared by Bill Green April 23, 1975 D.ca Su*omittee by k1 b'Qg 5 / M }7{, cic,n Head ears Reccenended by // ,,
/
[ SR3 Chairac.n D ta QA Approved NA__dLOG ,_ _ _ _ , , . , , __
!! scar,ar n' ality Ascur.:nre D:ste Appre,ved by V
[ M Station Suparantendent
~
04.5~~ [ Revisicn SE3 QA st . Supt. No. Rece: mea.dctio t sate Apprevad D.t t o Apneoved An 1 / # r 967/so NA row - to "I etS te. 9 /" f* l & AMy 7/yx syt l ,1 p ,. , ajujr. pg sbw 3 stw~ 1 l l l
'N l 1
l
. 1
~
AD 1827.01.3 1
- 1. PURPOSE The purpose of this procedure is to provide guidelines for the coordination of activities in the preparation, execution and critique of annual radiation emergency exercises.
- 2. APPLICABILITY This procedure will be used by personnel having responsibility for conduct of emergency exercises with the off-site organizations providing emergency medical support to the nuclear power station.
- 3. REFERENCES 3.1 Davis-Besse Nuclear Power Station Emergency Plan, Section 8.1.2, " Drills and Exercises" 3.2 Davis-Besse Nuclear Power Station Emergency Plan 3.3 AD 1827.02, " Medical Treatment of Injuries" 3.4 HP 1604.01, " Personnel Decontamination" 3.5 HP 1602.02, " Internal Personnel Monitoring"
! 3.6 Emergency Implementing Procedures, EI 1300 series
! 3.7 Magruder Memorial Hospital Procedure " Decontamination and Treatment of the Radioactively Contaminated Patient", j Sections I, II, and III
- 4. PRECAUTIONS AND LIMITATIONS '
i All communications relating to an emergency medical exercise shall be unequivocally identified as a drill. Verbal communications shall be initiated and closed by the statement, "This is a drill".
- 5. PREREQUISITES 5.1 Agreement shall be obtained from the following 4 individuals or organizations as to the time and sequence of an exercise.
5.1.1 Station Superintendent , 5.1.2 Emergency Planning Supervisor 5.1.3 REMS Corporation 3 . 5.2 A scenario shall be prepared and distributed by REMS .
2 AD 1827.01.3 3 Corporation to the individuals and organizations identified in paragraphs 5.1.2 and 5.1.3 above. It shall describe a credible sequence of events from the time of accident occur-rence until the accident victims have been transferred from the Radiation Emergency Area of the hospital to the uncontrolled area of the hospital and the Radiation Emergency Area has been restored to its original uncon-taminated condition.
- 6. PROCEDURE 6.1 General Coordination and general supervision of the annual radia-3 tion emergency medical exercise shall be provided by REM Corporation and the Toledo Edison Emergency Planning Group.
6.2 Preparation 6.2.1 Annually REMS Corporation shall consult with the Emergency Planning and Preparedness Supervisor and select a date that is mutually convenient for the annual radiation emergency medical exercise. 3 6.2.2 REMS Corporation shall initiate coordination of subsequent exercises NOT later than one week preced-ing the anniversary calendar quarter of the previous year's exercise. 6.2.3 NOT less than two months prior to an exercise, 3 REMS Corporation shall submit an exercise scenario to the Emergency Planning and Preparedness Super-visor for approval. 6.2.4 Disclosure of the scenario beyond the parties supervising the exercise shall be restricted. 3 6.2.5 Station personnel, and REMS Corporation shall pre-sent a training program to members of the Station Staff within:approximately two weeks prior to the annual exercise.
- l. 6.2.6 The Station training program referred to in paragraph 6.2.5shall include instruction relating to the references identified in para-
. graphs 3.1 through 3.6 above. l' 3 6.2.7 The Lead Medical Coordinator and REMS Corporation , shall present.a training program to members of the Magruder Memorial Hospital and the Carroll l l l L
. .. _ . _ _ _ - . _ . - - _ . _. - _ _ ~ _ __ . . _. __
t i i i i 3 AD 1827.01.3 Township Emergency Medical Service staff within approximately two weeks prior to the annual exercise. 6.2.8 The training referred to in paragraph 6.2.7 shall include instruction relating to the pro-cedures identified in paragraphs 3.3 through 3.7 above. 6.2.9 In accordance with agreements among the Station Superintendent, Emergency Planning Supervisor, Lead Medical Coordinator, the Magruder Memorial 3 Hospital Administrator, and REMS Corporation, umpires for the exercise shall be appointed. 6.3 Execution 6.3.1 The tima of initiation of the exercise shall be decided by the Emergency Planning and Pre-
- paredness Supervisor with concurrence of the Station Superintendent.
6.3.2 The participants shall exercise every aspect of i the emergency plan and procedures as pertains to the problem unless specifically directed to exclude certain aspects. 6.3.3 Participants will inject as much realism into the exercise as is compatible with safe opera-tions. NOTE: Extreme care shall be exercised to assure that individuals receiving exercise
- communications and-those who may overhear ,
such communications, are NOT misled into l belief that an emergency exists. The phase "This is a drill" shall be used at the start and finish of communications. 6.3.4 Simulation of time and/or the availability of supplies, instruments or equipment shall NOT be employed during the exercise. 6.3.5 Umpires shall be assigned in sufficient number and at locations to observe the responses of the participants. I r 6.4 Post-Exercise Critiques 6.4.1 Post-exercise critiques shall be held at the Station and at Magruder Memorial Hospital by ~ 3 REMS Corporation. i 1
, ,- -~ , . + . ~ , . - _,,#- y 1
4 AD 1827.01.1 6.4.2 The principal objectives of these critiques shall be evaluation of plans and procedures and evaluation of training, based on observations made during ,the exercise. 6.4.3 Critique attendees shall be specified by senior officials of the respective institutions. 6.4.4 Minutes of the critiques shall be maintained. 6.4.5 Verbal comments by off-site personnel shall be confirmed by written reports to the Station 1 Superintendent, Emergency Planning Supervisor, or the Administrator, Magruder Memorial Hospital, as applicable. , 1 b e 9 D f i 4 END l i i l
. AD 1827.02 DavisLBesse Nuclear Power Station Unit No. 1 Administrative Procedure AD 1827.02 Medical Treatment of Injuries J a i Record of Approval and Changes Prepared by Bob Peters April 14, 1975 Date Submitted by Terry D. Murray 6/9/75 I Section Head Date Recommended by Jack Evans 7/8/75 SRB Chairman Date QA Approved NA/TM Manager of Quality Assurance Date Approved by Jack Evans 7/8/75 Station Superintendent Date Revision SRB APM QA Sta. Supt.
No. Recommendation Date Approved Date Approved Date Approved Date 1 Jack Evans 1/13/76 NA NA/TDM Jack Evans 1/13/76 2 T. D. Murray 6/23/76 NA NA/TDM Jack Evans 6/29/16 3 T. D. Murray 4/5/77 NA NA Jack Evans 4/6/77 4 T. D. Murray 9/13/77 NA NA / Jack Evans 9/13/77 5 p, 3 /7 77 g , , , , ' .' 3 gg h p s/3g/g b 4WNy 'h?/7 .YA
/N ofsh) 7 J M y ~ w )u a y =nmom m+4" q ,, , .,jupt pe on =g 7 pg - w)sjau }lb llA 'm " 1 "' "~
1 AD 1827.02.9 l
- 1. PURPOSE 1.1 To list and describe the methods of treatment of injur.ies including radiation casualties.
- 2. REFERENCES 2.1 Davis-Besse Nuclear Power Station Emergency Plan 2.2 EI 1300.02, Unusual Event 2.3 Administrative Memorandum No. 5, Accident / Injuries -
Reports and Forms 2.4 Administrative Memorandum No. 38, First Aid Team 2.5 HP 1604.01, Personnel De~ contamination 9 2.6 Administrative Memorandum No. 37 ECS Pager and Telephone Numbers
- 3. SCOPE 3.1 Priority for medical treatment will depend on the severity of the injury and whether it has radiological aspects or NOT.
3.2 A minor injury is an injury that, in the estimation of a First Aid Team Leader, requires only First Aid Treatment. 3.3 A major injury is an injury that, in the estimation of a First Aid Team Leader, requires professional medical treatment. 3.4 The order of medical treatment will be: 3.4.1 Care of major injuries 3.4.2 Care of minor injuries 3.4.3 Decontamination of personnel . 3.4.4 Monitor for Internal Contamination 3.4.5 Definitive treatment and subsequent therapy as required. 3.5 The Davis-Besse Station has trained personnel and neces-sary equipment to respond to immediate First Aid require-ments of injured personnel; in addition, the Medical i Treatment Room on the 603' elevation of the Auxiliary i l
v \ 2 AD 1827.02.9 Building adjacent to the Control Room elevator hrs suf-ficient supplies and equipment to allow a physician to treat many injuries locally, if necessary. 9 3.6 First Aid Response Equipment in the form of First Aid Trauma Kit, First Aid Suitcase, splints, back boards, Resuscitator and stretcher are located in a cabinet inside the cafeteria on the Turbine Deck 623' level. 3.7 The First Aid Team consists of a First Aid Team Leader and First Aid Team members. First Aid Team Leaders hold a minimum of Red Cross Multi Media Certification while First Aid Team members have received First Aid Training. First Aid Team Leaders / Members are identified in Admin-istrative Memorandum No. 38, First Aid Team. 9 4. ACTIONS - WITHIN PROTECTED AREA 4.1 Actions of the injured person or any individual who discovers an injured person, i 4.1.1 Notify the Control Room of the nature, extent, and location of the injured person (s). 4.1.2 Render life saving first aid as necessary. 4.1.3 Keep the Control Room informed of the status of the injured individual (s). 4.1.4 When the first aid team arrives, standby to assist the first aid team by:
- 1. Assisting first aid team as requested.
- 2. Maintaining' communications with the Control Room.
4.2 Actions of Shift Supervisor / Assistant Shift Supervisor NOTE: Transportation of contaminated injured individ-ual(s) constitutes an Unusual Event and requires action per EI 1300.02, Unusual Event. 4.2.1 Summon First Aid Team to the location of the injured person (s) by sounding the Initiate Emergency Procedures Alarm and announcing loca-tion.and nature of emergency on the PA System. Unless the Shift Supervisor believes that addi-tional help is necessary, all other personnel should be instructed to stand clear and that assembly according to the Emergency Plan is NOT required.
3 AD 1827.02.9 4.2.2 Request assistance from the Chemistry and Health Physics person in charge to determine if decon-tamination is needed. 4.2.3 Call the Secondary Alarm Station Operator, who will make medical treatment arrangements as per Section 4.4. of this procedure (AD 1827.02). NOTE: If the event S. A.S. is unavailable to ' make medical treatment arrangements, the Central Alarm Station Operator should be l notified to make necessary arrangements. 9 4.2.4 Contact the Davis-Besse Station Medical Coordinator when the moving of an injured victim (s) may be life threatening or professional medical advise is requested by the First Aid Team Leader. (Reference Administrative Memo No. 37, Attachment XI for designated Medical Coordinators.) NOTE: If contact with the Medical Coordinator cannot be made, contact the Magruder Hospital, 24 hour Emergency Room Doctor and relate accident and injury information. 4.2.5 Ensure that Security and the First Aid Team are notified of the impending' ambulance arrival and give necessary instructions (i.e. access door, number of ambulances responding). 4.2.6 Send a can to the Gate Office (P.P.F.) to direct the amoulance.
. 4.2.7 Notify the Station Superintendent and the ,
Chemist and Health Physicist. 4.2.8 The Station Superintendent or his designated representative will arrange for notification of the injured person (s) family. NOTE: Some member of Station Supervision will l accompany the man to the doctor or hospital. If the injury occurs during off normal hours, weekends or holidays, then a member of Supervision will be called to meet the employee at the i- doctor's. office or hospital. l 4.3 Actions of the First Aid Team i
l l 4 AD 1827.02.9 4.3.1 Proceed immediately to the injured individual (s) with the First Aid Response Equipment. 4.3.2 Evaluate the extent of the injury and render First Aid as required. 4.3.3 Keep the Shift Supervisor assessed as to the status and degree of injury to person (s) involved. 4.3.4 The First Aid Team Leader shall use the follow-ing criteria in determining where and when to move the injured person (s).
- 1. If in his estimation, the injured person (s) should NOT be moved without Professional Medical Care, First Aid will be provided locally until Professional Medical treatment is available.
- 2. If th'e injured person (s) requires immediate professional medical treatment and may be moved, he will direct the transportation of the injured person (s) to the nearest 585' elevation exit for ambulance pickup.
- 3. If the injured person (s) does (do) NOT require immediate professional medical treatment, then:
- a. Contaminated injured person (s) may be taken to the Medical Treatment Room and/or Decon Room for decontamination and further First Aid and/or Professional Medical Treatment.
- b. Uncontaminated injured person (s) may be taken to the Medical Treatment Room for further First Aid and/or Professional Medical Treatment.
4.4 Actions of the Secondary Alarm Station Operator (S.A.S.) i 4.4.1 Contact the Carroll Twp. Emergency Medical l Service (Ambulance) through the Ottawa County l Sheriffs Office and relate the extent of known I inj uries . Refer to Administrative Memo 37, i Section XI. l l 9 NOTE: Mid-County EMS (Ambulance) or Lift Flight Air Ambulance should be considered when backup ambulance support is required. l
5 AD 1827.02.9 9 Refer to Administrative Memo 37, Section XI for Mid-County EMS, or Attachment 2 of this procedure for Life Flight Air Ambulance. 4.4.2 Contact the H.B. Magruder' Hospital, Nursing Supervisor to inform her of the extent of injuries and the impending ambulance arrival. Refer to Administrative Memo 37, Seciton XI. NOTE: St. Charles Hospital has been designated as backup hospital support with the capabilities for care in the event of radiological emergencies. Refer to Administrative Memo 37, Section XI. 4.4.3 Contact the Edison Operator giving the injured - individuals name and the nature of the injury. The Edison Operator will notify the individuals Supervisor, the Safety and Health Services Administrator and the Station Safety Coordinator. 4.5 Actions of the Chemistry and Radiation Tester (C&RT) 4.5.1 Proceed immediately to the scene of the accident. 4.5.2 Check area dose rate,
- a. If greater than 25 R/hr. , the First Aid Team should more the injured party from the area as soon as possible or set up shielding to reduce exposure,
- b. If less than 25 R/hr. , Do Not move the party until approved by the First Air Team Leader.
- c. If an airborne or surface contamination hazard exists, inform the First Aid Team Leader than the victim should be moved as soon as feasible.
NOTE: Dose rate of 25 R/hr is recom-mended by the Station Medical Consultant, REMS Corporation.
- 5. ACTIONS - OUTSIDE PROTECTED AREA 5.1 Actions of the injured person or any individual who discovers an injured person.
5.1.1 Notify the Secondary Alarm Station Operator of the nature, extent and location of the injured person (s).
6 AD 1827.02.9 9 5.1.2 Render lift saving first aid as necessary. 5.1.3 When the first aid team or ambulance arrives, stand by to assist the first aid team as required. 5.2 Actions of the Seccadary Alarm Station Operator , l 5.2.1 Contact the Carroll Twp. Emergency Medical Service (Ambulance) through the Ottawa County Sheriffs Office and relate the extent of known inj uries . Refer to Administrative Memo 37, Section XI. NOTE: Mid-County EMS (Ambulance) or Lift Flight Air Ambulance should be considered when back up ambulance support is required. Refer to Administrative Memo 37, Section XI for Mid-County EMS or Attachment 2 of this procedure for Lift Flight Air Ambulance. 5.2.2 Contact the Edison Operator giving the injured individuals name and the nature of the injury. The Edison Operator will notify the individuals Supervisor, the Safety and Health Services Administrator and the Station Safety Coordinator.
- 6. DISCUSSION 6.1 Minor injuries 6.1.1 Move injured person (s), for injuries NOT requir-ing immediate professional medical treatment, to the Medical Treatment Room, taking care to
, minimize aggravating the. person's condition.
The Medical Treatment Room is located on the 603' elevation of the Auxiliary Building adja-cent to Access Control. Immediate and temporary care may be given to a victim of an accident at this point. 6.2 Major injuries 9 6.2.1 In cases involving major injuries (except Section 6.2.2) transportation of injured personnel should be the Magruder Hospital (Port Clinton, Ohio) or ! M&gruders designated back-up facility, St. Charles ! Hospital (Oregon, Ohio). l l 6.2.2 In cases of severe burns, severe eye ' injuries, l uncontrolled bleeding or heart attacks, transporta-tion of injured person (s) should be to St. Vincents
l 7 AD 1827.02.9 Hospital. This can be done by the use of Life Flight-Emergency Air Ambulance Service (see Attachment 2). - 6.3 Radiological - 6.3.1 If the injury involves contamination, all 4 efforts will be made to decontaminate the injured to below 220 dpe/100 cm2 If decon-tamination delays necessary medical treatment, the victim will be covered in such a manner as to avoid any spread of contamination and appropriately shielded until medical aid can be obtained or hospitalization made. 6.3.2 Remove protective clothing and begin decontamin-ation according to KP 1604.01, Personnel Decon-tamination, if required and only if this will NOT - aggravate the injury. 6.3.3 For minor injuries personnel decontamination may be accomplished in the Personnel Decontamination Area located in the Auxiliary Building. This area contains showers, a large sink, wash basin, and necessary monitoring equipment. 6.3.4 In case of injury, both minor and major, medical attention should take precedence over contamina-
- tion controls. Emergency medical treatment of 1 . inhalation cases shou 1d take precedence over
- decontamination and/or wound treatment. In the event of any minor open wound in the RACA, the wound will be flushed with copious amounts of water and bleeding wil.1 be controlled as required. In cases of a puncture wound, forcing it to bleed will remove some contamination if present.
NOTE: Transportation of contaminated injured individual (s) constitutes an Unusual Event and requires actions per EI i 1300.02, Unusual Event. 6.3.5 When hospitalization is required and contamin-
- ation or its possibility exists, the ambulance driver, hospital and doctor shall be advised in advance. Precautionary measures to prevent spread of contamination shall be initiated, i.e., placing injured person on a cloth sheet ,
and shielding him if required, providing the i ambulance driver with TLD, dosimeter and pro-tective clothing as required. l i
8 AD 1827.02.9 6.3.6 For each injury involving radiological compli-cations, the C&RT individual shall complete a Body Map, Attachment 1. Should the injured individual require transport to an off-site medical facility, the Body Map shall accompany the individual to expedite recovery actions at the facility. 6.3.7 Should hospitalization be required, one Health Physics Technician shall accompany the individ-ual in the ambulance to the hospital. Should enough casualty victims exist which require more than one ambulance, only one Health Physics Technician is required. The Technician shall accompany the first injured individual trans-ported and wait at the hospital to provide radiological assistance as the other casualties arrive. 9 NOTE: During off normal working hours, Health Physics Technicians should be cognizant of shift manning requirements. Contact should be made with the Chemistry and health Physicist or his alternate, to obtain additional assistance. 6.3.8 Urinary bio-assay or whole body counts will be performed on all persons suspected of having received 10% of the maximum permissible body burden. .
- 7. REPORTS 7.1 Reports of accidents and injuries shall be completed and processed in accordance with Administrative Memorandum No. 5, Accident / Injuries - Report and Forms.
t . l l
l . . l 9 AD 1827.02.8 BODY MAP l , Indicate Contaminated Areas as to Location, Degree of Contaminatiion, and Decon Effort Indicate Location of Wounds l RIGHT (use additional sheets if necessary)LEFT . O. BACK se . i, o[ FRONT R F J ' 2.s ' l (l'W)/_.UAf,f g [L T f' '
\
\ fi 8 l, l
\ ,
q CHEST h/ MSW dg 4 e
\I I I s_ 1 s
J Type of Meter Used: (indicate model and number) Distance Skin-to-Probe: in. Attachment 1 Page 1 of 1
_ ._, __ ._ ._ __ _ . _ - . . _ . _ - _ _ _ _ - = _ . _ l 10 AD 1827.02.9 I PROCEDURES FOR THE USE OF LIFE FLIGHT - ' EMERGENCY AIR AMBULANCE SERVICE CONTENTS ATTACHMENT PAGE NO. Background Information . . . . . . . . . . . . . . . . . . . . . Page 1 Procedure to Follow . . . Actions to Initiate Service . . . . . Page 2 9 Instructions for Secondary Alarm Station Operator . . . . . . . Page 3
! Safety Rules . . . for establishing and marking landing site . . Page 3 - 5 (for Security Supervisors)
Life Flight, (an Emergency Room in a h.elicopter), rapidly transports a ~ St. Vincent emergency physician, specialized registered nurse, life support medications and supplies to any medical emergency scene within a 130 mile radius of Toledo. Life Flight transports the patient to the most appropriate hospital or hospital of choice, (Physician referrals are honored). l Medical treatment is begun at the scene, continued in flight, and the receiving hospital is alerted to the nature and severity of the injury or illness, and medical specialties needed. Life Flight was initiated in coordination with the Regional Medical Services of Northwest Ohio (REMSNO). It augments existing primary ground emergency transportation systems and provides service 24 hours a day, seven days a week. Since Life Flight is a self-contained emergency treatment center, it can carry a maximum of two adult patients at a time. ! Nost appropriately, utilization of this service at the Davis-Besse Nuclear , Power Station should be limited to severe injuries and illnesses or treat-ment cases best suited to the use of available specialty service of St. Vincent's, (i.e. , heart attacks or suspected heart attacks, eye injuries, burns, etc.). However, designation of particular care facility, will be determined through contact with the Shift Supervisor. 9 - To Call Life Fliaht: (419) 241-5433 is the emergency number; the call is received simultaneously by REMSNO and Life Flight Communications Center. 9 PLEASE NOTE: Contact must be made through the Secondary Alarm Station Operator (the phone number is shown here only for informational purposes and as an alternative measure, should contact with the Secondary Alarm Station Operator be unworkable). Attachment 2 Page 1 of 5
11 AD 1827.02.9 PROCEDURES TO FOLLOW . . . ACTIONS TO INITIATE SERVICE: 9
- The Shift Supervisor or his designee will contact the Secondary Alarm Station Operator and detail the following information which '
will be passed along to the Life Flight Dispatcher.
- 1. This is (your name & position) calling from Davis-9 Besse, I am requesting that you call: 241-5433, to establish " Life Flight" Emergency Air Ambulance Service.
Please provide the following information to the Life Flight Dispatcher: A. - Type and extent of injuries . .. B. - Call-back telephone number . . 259-5663, D-B Control Room (for contact through Shift Supervisor with First Aid Team Leader) C. - Probable landing site / landing instructions . . . s
, D. - Patient's name and expected destination . . .
9 E. - Hold on the line until the S.A.S. Operator tells d you to hang up
- 2. Notify the Control Room that ext. 5663 must be kept open for possible incoming emergency information call.
9 3. Request the Nuclear Security Supervisor to establish and mark landing area and to follow Safety Rules (attached to this procedure).
- 4. Inform First Aid Team Leader that arrangements have been made and help is on the way . . . (This is extremely important to NOT only keep him informed but to enable him to comfort and reassure the injured).
- 5. Ensure that a First Aid Team member or Operations person is designated to meet Life Flight and take medical per-sonnel to the injured.
- 6. Note arrival and departure times of Life Flight Service.
Attachment 2 Page 2 of 5
12 AD 1827.02.9 9 INSTRUCTIONS FOR THE SECONDARY ALARM STATION OPERATOR TO INITIATE LIFE FLIGHT AIR AMBULANCE SERVICE Upon receiving request from the field for this service, make certain.that you obtain the following information to pass along to the Life Flight Dispatcher:
- 1. Caller's name, phone number, and location Name Phone Location Time In
- 2. Type and extent of injuries or illness
- 3. Call-back telephone number (for D.B.: 259-5663, Control Room).
- 4. Address, cross streets, nearby landmarks, and nearest landing site
- 5. REPEAT INFORMATION BACK TO CALLER TO VERIFY ACCURACY.
- 6. INFORMATION COMPLETE 7 Yes! Tell caller to hang up.
Not Tell calle'r to hold on. 9 7. Call 241-5433, (the call is received simultaneously by REMSNO and the Life Flight Communications Center).
- 8. Repeat information written above. Time Out-
- 9. Follow normal, established procedures.
SAFETY RULES: (For Davis-Besse Security Force Supervisors) . . . For establishing and marking LIFE FLIGHT landing site and general precautions concerning aircraft. A vital part of the total information supplied to the Life Flight Dis : patcher is the - address, cross streets, nearby landmarks, and nearest landing site. Attachment 2 Page 3 of 5
13 AD 1827.02.9 Due to plant architecture, our cooling tower provides an obvious and convenient " landmark of address". However, we must remember that the landing site for Life Flight has some definite requirements:
"The site must be 60 feet square and free of rubbish and overhead obstructions."
i 9 The On-Duty Nuclear Security Supervisor will:
- 1. Select an appropriate landing area;
- 2. Direct Station Security Personnel to mark the land-ing site; and
- 3. Arrange a rapid transport of medical personnel to the injury scene.
to ensure -- the safety of the aircraft and its personnel; prompt treat-ment for the injured; and security control of landing activities. LANDING SITE LANDING SITE MARKINGS WIND DIRECTION 60 foot square, clear of trees, Mark landing site in each Station one smoke wires, emergency vehicles, corner with smoke bombs bomb (daylight or trash cans, signs, fallen (daylight) or flares flare (night) on branches, and snow. (100 (night). the upward side foot square needed when high of the landing winds are a factor). site to introduce X X wind direction. Surface should be as smooth as possible with no more than 60 ft* -------- 14 foot difference in eleva- -.----- tion from one end of the landing site to the other. X X Crowds must be kept back 100 feet from the helicopter at all times. GENERAL SAFETY PRECAUTIONS
- 1. Approaching Aircraft:.
Always approach the aircraft from the front. l I Never approach the aircraft until signaled to do so by the pilot. l Attachment 2 Page 4 of 5 N
.- .r.
I 14 AD 1827.02.9 Never approach aircraft when blades are in motion. At no time is anyone permitted near the tail of the aircraft. No smoking within 50 feet of the aircraft. No running within 50 feet of the aircraft. Do NOT assist crew members in opening or closing doors of the aircraft.
- 2. Loading or Unloading:
Flight crew is responsible for loading and unloading , equipment. Flight crew will direct loading and unloading of patient. When Aircraft Has Landed . . . There should only be three people aboard. The Life Flight Crew consists of - physician, nurse, and pilot. The Shift Supervisor or his designee shall have an escort, at the landing site, to direct medical personnel to the injured. If the pilot elects to remain at the aircraft, a Security Officer will stay with him, at all times. Prior To Departure . . . Security personnel shall make certain that the injured's badge and TLD are NOT on the injured and have been turned over 9 to the Nuclear Security Supervisor. Clear area of take off. Note time of departure and record. 1 Attachment 2 END Page 5 of 5 i
AD 1827.04 - Ddvis-Desse Nuclear Pcwer Station Unit No. 1 Administrative Procedure AD 1827.04 Overexposure / Internal Contamination Ih 1 21 i Record of Approval and Changes
' Prepared by C. Dovel/W. Green 1/13/76 Date
[) O. SIu9 tw Submitted by 2 /IS /7 G crion Head Data Recommended by / _ ,
~
/ 8 N SRB Chairman Date QA Approved # - M O 2 '
V Manage o ~ aliff-issurance Date Approved by [ [ (( Date
/~StationSuperintendent, i ~
Revision SRB QA S ta. Supt. No. Re om=endation Date roved Date Approved Date f /kf //Jl/O #$2 ~ ** *' 'TC 3lWlk W ' ' '~ 4 figna - g 7ls3)ez. t h Y k f Y l ** T " l I e
1 AD 1827.04.2
- 1. PURPOSE To describe the actions necessary to investigate, treat and report the overexposure of an individual at Davis-Besse Nuclear Power Station (DBNPS) due to radiation. Overexposure is defined as any internal or external radiation exposure where the whole body dose is in excess of permissable limits set forth in 10 CFR 20.
- 2. REFERENCES 2.1 10 CFR 20, " Standards for Protection Against Radiation" 2.2 Davis-Besse Station Radiation Protection Manual 2.3 AD 1842.00, " Chemistry and Health Physics" 2.4 FSAR Section 12 2.5 HP 1602.01, " External Personnel Radiation Monitoring" 2.6 HP 1605.06, "Whole Body Counting" 2.7 AD 1807.00, " Control of Conditions Adverse to Quality" 2.8 AD 1804.00, " Report Management J
2.9 TEco NQAM
- 3. RESPONSIBILITIES 3.1 General Each person who works at or visits the DBNPS site shall be responsible for complying with the requirements of AD 1842.00, " Chemistry and Health Physics" for personnel radiation exposure. Should any person suspect that he has been subjected to overexposure, he shall immediately notify a member of the Chemistry and Health Physics Section.
3.2 Chemist and Health Physicist 3.2.1 Conduct final overexposure investigation if indeed it is determined by Health Physics per-
- sonnel that an overexposure did occur.
i-3.2.2 Complete " Report of Overexposure Investigation", (Enclosure 1). 2 3.2.3 Submit applicable reports to the NRC as defined in 10 CFR 20.403, 20.405(a), and 20.405(b).
0 2 AD 1827.04.2 3.2.4 Initiate an Action Item Report if required in accordance with AD 1807.00, " Control of Con-diticas Adverse to Quality". 3.3 Chemistry and Health Physics Section Conduct the initial investigation of reports of over-exposure to verify the incident and determine the need for further action and investigation as directed by the Chemist-Health Physicist.
- 4. PROCEDURE 4.1 External Exposure 4.1.1 An over-external exposure is defined when it is known or suspected that an individual has been
- exposed in excess of the limits specified by 10 CFR 20.101, an immediate investigation will be conducted by Chemistry-Health Physics Section j personnel and such reports or notifications as i
required by 10 CFR 20 will be submitted. f
'2 If an exposure comes within the definition of 10 CFR 20.403(a), the Station Superintendent will contact the company's radiation medical emergency consultant for their recommendations.
4.1.2 Routine external radiation monitoring (which will be the indicator that an overexposure has occurred) is described in HP 1602.01, External Personnel Radiation Monitoring Program. 4.2 Internal Exposure 4.2.1 If an over-exposure resulting from internal I contamination is known or suspected in excess of the limits specified by 10 CFR 20.103, an investi-gation will be conducted in accordance with HP 1605.06. l
- 1. The services of the company's radiation medical emergency consultant say be utilized to determine the magnitude of any excessive exposure, its cause, and effective preventive measures.
2
- 2. If the amount of radioactive material in the body exceeds 10% MPOB, a dose assessment should be performed.
l l l l t
;, =
._ . = . _ _ _ . _.
3 AD 1827.04.2
- 3. If there is a reasonable probability that any s
individual incurred an internal deposition of 2 one or more radionuclides exceeding 520 MPC-hours the Station Superintendent will
- contact the company's radiation medical emergency consultant for their recommenda-
{ tions. 4.2.2 Routine internal monitoring of contamination, (which will detect if an over-exposure resulting from internal contamination has occurred) will be performed as described below. f Whole Body Counting
- 1. Yearly whole body counts will be taken on selected station personnel.
- 2. Selection of the individuals for whole body
, . counting shall include at least 25% of the ! personnel assigned to the station. 4 3 3. Criteria used for selecting individuals will j be quarterly whole body exposure records and work history in airborne radioactivity areas. Tritium Monitoring
- 1. Urinalyses for tritium will be performed for selected station personnel.
l
- 2. On a quarterly basis, a bioassay for tritium will be collected from individuals rho have
~
,. been working in areas where there could be a,
- potential for inhaling tritium.
1 NOTE: During periods when the Refuel-ing Canal is filled,. urine i samples for tritium should ba 1 collected from selected indi-viduals every two (2) weeks. 4.3 Records 4.3.1 If the limits specified in 10 CFR 20.403, .405, have been or are likely to be reached,' the Region III Director of the NRC shall be noti-fied. 3
~ _n . . - - .
- l
- 4. AD 1827.04.0 4.3.2 The Chemist & Health Physicist shall be respon-sible for initiating the Report of Over-Exposure form.
e }
5 AD 1827.04.0 REPORT OF OVEREXPOSURE (Over-exposure resulting from internal or external radiation exposure) Name Date Soc. Sec. No. Job Title Date & Time of Possible Overexposure Location Exposure Occurred REP No. Type of Work or Operation at Time of Exposure How did Exposure Occur 1 Why did Exposure Occur Was Employee Injured Yes No Describe Medical Treatment Required Damage to Equipment Type of Exposure Involved: Whole Body Other Skin Radionuclides Hands & Forearms Feet & Ankles Internal Survey of Exposure Location: By Title
- Gen. Bkgd. mR/hr Hot Spot (s) mR/hr-
.)
Enclosure 1 Sheet I of 3 l l m
6 AD 1827.04.0 Air Activity pCi/cc Hot Spot (s) mR/hr Contamination: Surface dpm/100 cm 2 Dosimeters Readings mR-Ser# mR-Ser# Evaluation of TLD: Beta mR Gamma mR Beta & Gamma mR Neutron Exposure Were Nasal Swipes Taken Results Was Sputum Analyzed Results Was Whole Body Counter Utilized (Attach. scan to this report) Bioassay Program Begun Final Disposition: Did overexposure occur Yes No (If yes, initiate NCR) Total Dose Assigned for Period to Whole Body (External) (Internal) Skin Extremities Other Future Radiation Exposure Limitations l l i Future Clinical Radiation Data Required From Title 10 CFR 20 " Standards for Protection Against Radiation"; 20.403 and 20.405 - is an NRC notification and. report to Regional Compliance Required Yes No l Enclosure 1 Sheet 2 of 3
7 AD 1827.04.2 2 Has 520 MPC-hours in a 13 week period been exceeded? Yes No If the answer to either of the above questions is yes, contact the company's radiation medical emergency consultant, and complete report NP-02 as required in accordance with AD 1804.00, " Reports Management". l l NRC Region III Telephone (Days, Nights, Sundays & Holidays) - 312-858-2660 l l , Who made telephone call Time Date To whom call was made Capacity Date and Time of Telegram Confirmation To whom telegram sent Capacity Date and Time 30 day written report mailed To whom report sent Capacity Vas report Mailed Registered Return Receipt? (Attach copy of report, telegram statement, and phone conversation to this investigation.) Signatures of Personnel Making Investigation: Name Title Date Name Title Date Name Title Date Chemistry & Health Physicist Signature Date Station Superintendent Signature Date Enclosure 1 END Sheet 3 of 3
AD 1827.05 Davis-Iosse Nuclear Power Station Unit No. 1 , Administrative Procedure AD 1827.05 Explosion . ll Record of Approval and Changes l Prepared by R. P. Wathen/W, H. Green Feb. 6. 1976 Date Submitted by b. ll. bk w .- 3/23/74 S y 11ead Date Recoc= ended by . 4 [N E c2
" SRB Chair =an Date QA Approved NA St3 B M Man . r t ality Assurance Date Approved by d[6f/
Station Superintendent Date Revision SRB QA Sta. Supt No. Reco=cendst;'on . Date Approved Date Appr Da QM 4/$ try , p.yrz Nf 2 par <,o;g n e.,t.- -- ) e,a3 l .
.sp e
I l 9 1 AD 1827.05.2 '
- 1. PURPOSE & SCOPE This procedure describes the emergency actions to be performed by station personnel in the event of an explosion at the' Davis-Besse Nuclear Power Station.
- 2. REFERENCES 2.1 AD 1804.00, " Reports Management" 2 2.2 Davis-Besse Nuclear Power Station Emergency Plan 2.3 EI 1300.02, Unusual Event 2.4 EI 1300.03, Alert s
- 3. SYMPTOMS 3.1 Any explosion witnessed by any individual or group or otherwise determined to have occurred.
3.2 High radiation alarms from the radiation monitoring system following release of radioactivity due to the f explosion or explosive effects. ' 3.3 Fire alarm' due to fire created by explosion or due to ' damage et smoke / heat sensors and/or fire protection piping (e.g. low pressure signal actuating fire alarm).
- 4. IMMEDIATE ACTIONS ,
4.1 An onsite explosion constitutes an Unusual Event and , requires actions be taken per Unusual Event, EI 1300.02. i 4.2 An onsite explosion affecting plant operations con-stitutes an Alert classification and requires actions be taken per Alert, EI 1300.03. 4.3 Immediately following the determination that an explosion occurred, the Shift Supervisor shall-direct a search of the effected area for injuren personnel and also, the Shif t Supervisor or other/ licensed operator shall conduct a' physical examination of all affected areas with par-ticular attention to the following systems- as appro-priate:
- 1. Engineered Safety Features, and Borated Water Stor-age Tank l
- 2. Radwaste including makeup and purificacion and Boric l Acid Storage Tanks with their associated piping
'l l
. s e . /
4 e
2 AD 1827.05.2
- 3. Component cooling and service water
- 4. Spent fuel pool and new fuel storage
- 5. Containment building and penetrations
- 6. Nuclear steam supply system
- 7. Gas decay tanks An explosion could cause tank leaks, pipe whip damage, equipment or component failure and structure damage.
The primary concerns are for injured personnel and to detect, if any of the aforementioned damage has occurred and has compromised containment integrity, ESF functions and ESF equipment, or if any damage has occurred that could lead to the release of radionuclides. Once this has been determined, the possibility of damage to the station shall be investigated. 2 4.4 The Station Superintendent shall notify the NRC in accordance with AD 1804.00, " Reports Management", if after the initial investigation sabotage is suspected or confirmed. i l: it i l [ I ? l l t I END
1 AD 1827.06 (Supersedes EP 1202.38) Davis-Besse Nucicar Power Station Unit No. 1 ADMINISTRATIVE PROCEDURE AD 1827.06 Tornado
- n "' " ~ ~~,)
E f.g I.h _i=. *' ; . . :
- la '
mi .. i Record of Approval and Changes Prepared by Bill Green 12/20/75 Date Submitted by
/hb G /f Yk/
SecpAi' H Date Recoecended by _[ ((4P // Yd
/ RB Chai . 'Date QA Approved / //~h~#7 nager f' ity Assurance Date Approved by /
[ '
///ef/94 Station Superintendent ' Date Revision SRB QA S ta . S upt .
No. Recommendation Date Ap Date Approved Date j f p df/7/ja d-11-** v lyL' -- - Tlk)S4 s ,w =g sisfrs b . /*}b el dri 9 : ^ q 9l'*/1* l l t
~
e
1 AD 1827.06.2
- 1. SYMPTOMS Load Dispatcher notifies Davis-Besse Station that a tornado watch or a tornado warning exists for the vicinity of the Davis-Besse Station.
1.1 Tornado, Watch 1.1.1 Meteorological conditions are favorable for the formation of a tornado. 1.2 Tornado Warning 1.2.1 A tornado has been sighted in the vicinity of the Davis-Besse Station.
- 2. REFERENCES 2.1 Davis-Besse Nuclear Power Station Emergency Plan 2.2 EI-1300 series, Emergency Implementing Procedures 2 3. AUTOMATIC ACTION None
- 4. IMMEDIATE OPERATOR ACTION 2l 4.1 Load Dispatcher 4.1.1 Keep the Davis-Besse Station informed until tornado conditions have abated.
4.2 Control Room Operators 4.2.1 Notify the Shift Supervisor if a tornado watch or tornado warning is received. 4.2.2 Monitor the control boards to determine any effects on instrumentation, controls or station operations. 4.3 Shift Supervisor NOTE: Check Emergency Plan Activation, EI 1300.01, to determine proper emergency classification and take actions accordingly. 4.3.1 Tornado Watch l
- 1. Assign station personnel to look and listen i
l 1
2 AD 1827.06.2 for a tornado and to report any sightings to the Control Room. 4.3.2 Tornado Warning
- 1. Order all fuel handling operations suspended
- 2. If fuel is being supported from a crane or a bridge, order that it is to be stowed in a secure place
- 3. If plant is in power operation, instruct station personnel to standby to prepare .
for emergency shutdown
- 4. Order all non-essential station operations halted
- 5. Order the diesel generators started and prepare for loading
- 6. Notify the Station Superintendent and/or the Operations Engineer.
2 5. SUPPLEMENTARY ACTIONS None 2 6. DISCUSSION 6.1 Meteorological conditions that could result in a tornado would be determined by the Weather Bureau. 6.2 Weather Bureau services are available to the TECo Load Dispatcher through a teletype. 6.3 TECo also maintains a radar weather surveillance system covering a 64 mile radius of Toledo. 6.4 The plant should be prepared in such a way to mitigate the consequences of tornado damage. The Shift Super-visor, in the absence of the Station Superintendent, shall take on the additional measures he feels necessary to protect the station and the public. END l
AD 1827.07 (Supsrssdas EP 1202.42) - Davis-Besse Nuclear Power Station Unit No. 1 ADMINISTRATIVE PROCEDURE AD 1827.07
^ '
Earthquake "-- ; - ;
, . . -. -* ' ) T
{U;N - ,,,[3 .
.p c . .. . . .-
Record of Approval cnd Changes Prepared by Bill Green 12/20/75 Date Submitted by [ u TN / 2-/=2 9/f$' on Heatf
~
S i Date i Recotmnended by
//[/8/
liRB Chairman
///h/'/d
/Date QA Approved ' * '
MM @M
., anager aality Assurance Date Approved by s / (([/
' Station Superintendent
///d/'/d
,, ' Date' Revision fRB QA Sta. Supt.
No. endation R Date Approved Date
$ '.'. */$$
+ -
la. Y7/n e.uo g ,/q n n A =2 - 2.f. nAPProvep lDatef}y f www 3 ps e-g Hb'In _ c . r. ,q s g p u . n ,. .s,m e
=
l
l l 1 AD 1827.07.3
- 1. SYMPTOMS 1.1 Station Seismic /Instrumentatien alarm in the control room on the Reactor and Station Auxiliaries panel. l l
1.2 Tremor indicating an earthquake.
- 2. REFERENCES 2.1 Davis-Besse Nuclear Power Station Emergency Plan 2.2 EI 1300 series, Emergency Implementing Procedures 2.3 10 CFR 100, Appendix A 2.4 TECo NQAM 2.5 DB Tech. Spec. 6.9 3 2.6 AD 1807.00 Control of Conditions Adverse to Quality
- 3. AUTOMATIC ACTIONS 3.1 The Strong Motion Recording System and Seismic Monitoring Equipment is actuated and records the seismic disturbances.
- 4. IMMEDIATE OPERATOR ACTION 4.1 Control Room Operators
~
4.1.1 Check the control boards to determine the effect, if any, on instrumentation, controls or station operations. 4.1.2 Notify the Shift Supervisor. 4.1.3 Pay particular attention to sump level alarms and tank levels. 4.1.4 If the unit has been shutdown by automatic protection systems, place the unit in a safe shutdown condition. 4.2 Shift Supervisor 4.2.1 Assign personnel to verify the authenticity of the 3 Station Seismic / Instrumentation Alarm. If the Seismic System is inoperable, contact the Technical Engineer for further guidance. 4.2.2 Order all fuel handling operations suspended.
2 AD 1827.07.3 4.2.3 If fuel is being supported from a crane or a bridge, order that it be stowed in a secure place. 4.2.4 Control rod position, reactor power, and other pertinent variables shall be evaluated to verify that no change has occurred in core reactivity. 4.2.5 Verify that there is no abnormal sump operation and tank levels are stable. 4.2.6 Check Emergency Plan Activation, EI 1300.01 to determine proper emergency classification and take actions accordingly. ,
- 5. SUPPLEMENTARY ACTION 5.1 Operating Personnel 5.1.1 Perform RCS leak test (ST 5042.01) 5.1.2 Exercise control rods (ST 5013.04) 5.1.3 Perfonn Diesel Generator test (ST, 5081.01) 3 5.1.4 Carry out Section 9 of SP 1105.17, Seismic Monitoring Systems. Section 9 provides an analysis of the .
graphic recording, determination if OBE earthquake ! has been exceeded, and the requirement to shutdown the Unit if OBE has been exceeded. 5.2 Shift Supervisor 5.2.1 If the unit has NOT been shutdown and no apparent damage has occurred, maintain the station in its present status. 5.2.2 Order a physical inspection of the station with particular attention to the following systems:
- 1. Engineered Safety Features and Borated Water Storage Tank
- 2. Radwaste including makeup and purification, and Boric Acid Storage Tanks with their associated P ii P ng
- 3. Component cooling
- 4. Spent fuel pool and new fuel storage 1
l
. a
3 AD 1827.07.2
- 5. Containment boundary
- 6. Nuclear Steam Supply System 5.2.3 Notify the Station Superintendent and/or the Operations Engineer.
2' 5.3 Station Superintendent 5.3.1 Notify Company Management 5.3.2 Notify the NRC in accordance with AD 1807.00, Control of Conditions Adverse to Quality 5.3.3 With the assistance of the plant operating staff and staff personnel, convene the SR3 to evaluate the subsequent reports, records, and recordings for any possible damages to the equipment and structures caused by the earthquake and determine if any of the Engineered Safety Features are damaged. 5.3.4 If the station has been shutdown, determine, in consultation with the Shift Supervisor and the Operations l_ Engineer, whether it should be returned to power. o S END - '
AD 1827 08 - 1 1 Davis-Bosse Nuclear Power Station Unit o. 1 Administrative Procedure AD 1827 08 Flooding Record of Approval and Changes Prepared by R. P. Wathen 1/o/76 Date Submitted by Ihh *% 3!3 7b Recommended by ~ [I
~ SRB Chairman Date
, "c.'
' e .
QA Approved - 4A7 8" Man ofA[uality Assurance Date Approved by V
// M
~ ~ Stiation Superintendent
. Date Revision SRB QA Sta. Supt.
No. Recommendation Date d Date Approved Date y gy 7,9,p,,, a.z . gw=9 at,an y pa spz)e:s c r 34/4L qu/u wnq vh.m l t i
1 AD 1827.08.2
- 1. PURPOSE This procedure describes the action levels and procedures to be followed by station personnel if flooding is imminent or has occurred at or near the Davis-Besse Nuclear Power Station. Spec-ific actions to be taken in the event of flooding at or near the station will depend on the conditions of the emergency. Since time will be available to make critical decisions, this procedure emphasizes the conditions that warrant action and NOT the actions themselves.
- 2. REFERENCES 2.1 DBNPS-FSAR Section 2, " Site Characteristics" 2.2 Davis-Besse Nuclear Power Station Emergency Plan 2, 2.3 AD 1827.11, " Assembly, Accountability & Subsequent Evacuation" 2.4 EI 1300 series, Emergency Plan Implementing Procedures
- 3. ACTION LEVELS 3.1 General 3.1.1 The occurrence of natural flooding is a situa-tion that can be anticipated; therefore, pre-cautions can be taken prior to the worst case to prevent station damage.
3.1.2 Below mean lake elevation 574' no appreciable flooding of the area surrounding the station will occur. This is the normal condition requir-ing no emergency preparation or action (See Enclosure 1) unless level drops below the 565' lake elevation (See EI 1300.01, Emergency Plan Activation). 3.2 Flood Watch , A " Flood Watch" shall be in effect at DBNPS during lake l water elevations for 574' to 576' as indicated by local ! flooding of the marshes and low areas around the station and water on or covering portions of the "A" access roads. (See cross-hatched areas of Enclosure 3). 3.3 Flood Warning l Lake water elevations between 576' and 578' as indicated
- by the flooding and closure of all "A" access roads (See Enclosure 3) require that a " Flood Warning" condition be l
l
s 2 AD 1827.08.1 announced. host of the area around the station will be under water and only Duff Washa and other "B" or "C" roads will be usable for access and evacuation. If determination that a " Flood Warning" condition exists, preparation should be made for the possibility of a flood emergency. Since there is no real danger to the station under this condition, operations are NOT affected but preparations for personnel transporation and rescheduling are important. 3.4 Flood Emergency 3.4.1 At lake water level of 578' and a'oove, all roads to the station are under water and impassable. Because of the limited access (rail, boat or helicopter) to the plant in case of other types of emergencies, this level for action is con-sidered to be a " Flood Emergency". The Station Superintendent shall evaluate station opera-tional safety at this level since personnel and access are limited. 3.4.2 Worst case flooding with lake water levels over l Elev. 580' may damage or cause deterioration to station equipment, particularly electrically operated apparatus. Items at ground level (Elev. 585')'are, for the most part, protected from excessive water by dikes, walls and doors (See Enclosure 2). 3.4.3 Water levels above the 585' elevation will enter buildings and flood lower levels except for the containment, which is sealed. Water inflow to electrical or electronic rooms may cause damage and probably require shutdown of the reactor. i I
- 4. PROCEDURE 4.1 General 4.1.1 The Shift Supervisor is responsible for monitor-ing station operations during a flood condition and to schedule shifts for emergency operation 1 depending upon available personnel. He shall maintain communications with the Gate House (and l EDO when on site) in order to assess the flood
) conditions which may adversely affect station j operation. I 4.1.2 The EDO is responsible for supervising emergency activities during flood emergencies and main-i i 1
I
- l 3 AD 1827.08.1 taining communications with the off-site support groups. He is responsible for monitoring off-site flood conditions by, for example, sending ,
out patrols to monitor access roads or com-municating directly with the County Sheriff's Office, and for communicating this information to the control room and Station Superintendent. 4.2 Flood Watch (Water Levels from Elevation 574' or 576') 1 4.2.1 The Shif t Supervisor shall notify the Station Superintendent that a " Flood Watch" condition has. occurred as soon as he receives notification that there is high water on the access roads to the ;s ta tion. Station evacuation is NOT neces-sary at this point. 1 4.2.2 The Shift Supervisor shall assign someone to begin evaluating the conditions around the
, station during the " Flood Watch".
4.3 Flood Warning (Water levels between Elevtion 576' and 578') 4.3.1 The Shift Supervisor will announce that a " Flood Warning" condition is in effect when lake water levels have reached 576' and Route 2'has been closed. 4.3.2 This second or intermediate stage of flooding requires a transition to a state of readiness by station personnel, particularly if higher water is expected. .
- 4.3.3 Nonessential personnel should be sent off-site i
before the "B" evacuation routes become impass-able (578') or if conditions indicate that higher water levels are expected. 4.3.4 During the " Flood Warning" period, assemblies 1 may be held in the Operations Support Center (assembly room) to inform station personnel of the existing conditions, the possible dangers if the water levels increase appreciably, and the proposed operations and shift scheduling if evacuation and/or isolation is imminent. 4.3.5 Prior to the station becoming isolated, the Ottawa County Sheriff's Department and Ohio Disaster , Services Agency shall be notified in order to l l l 1
i 4 AD 1827.08.1 provide emergency tradsportation to or from the site by DKW vehicle or boat. 4.3.6 Since the station will be isolated at water l levels over 578' except for. rail, boat or DKW, a [ minimal workforce shall be scheduled for essen-i tial operating and emergency activities. The
. Station Superintendent should determine at this level if station isolation would adversely affect other types of emergency conditions and safe operation.
4.3.7 Rail transportation for operating personnel shall be requested by the Station Superin-tendent if isolation is anticipated. 4.4 Flood Emergency (Water Levels over 578') 1 NOTE: Check Emergency Plan Activation, EI 1300.01, to determine the proper emergency classification and take actions.accordingly. 4.4.1 At these water levels (over 578') all access
; roads will be impassable (See Enclosure 3) except by rail, DKW vehicles, or boats and a
" Flood Emergency" should be announced by the l Shift Supervisor.
4.4.2 Station operation will be maintained by essen-tial operating and staff personnel until a , shutdown is determined to be necessary by the Station Superintendent and/or the Shift Super-visor. l 4.4.3 Full evacuation is NOT anticipatIed under any flood emergency conditions. Overnight accom- [ modations shall be provided for emergency per-l sonnel during isolation. Rail, boat or DKW transportation shall be utilized to change shifts as required. l 4.5 Transportation 4.5.1 Vehicular transportation into and from the site shall be utilized to the greatest extent pos-sible. Motor vehicles can be used unitl "B" l ) access routes are impassable (Water Elev. 578'). l l 4.5.2 Rail transportation into and from the station is the secondary transportation mode. Personnel may board rail mobiles or cars at the: inter-
5 AD 1827.08.0 section of the rail spur with State Route 590 about three miles south of Route 2, three miles north of State Route 163 at the intersection of Toussaint North Road (62), or in Oak Harbor. (See Enclosure 3) 4.5.3 DKW vehicles or boats are the third type of transportation that can be used for site access if all roads are closed. It is anticipated that most of these DKW vehicles and boats will be used for personnel evacuation in the surrounding areas and won't be available for regular service to the station site. l l l l l I
l l i 6 AD 1827.08.0 LAND SIDE LAKE SIDE 591' Top of Dike
/ \
590' 585' Sta. Floor Level ~
\\\ \N N Record High Water Level-583.7' 580' 579' ECC Floor Level ,
\ Level FLOOD EMERGENCY 578.1' Max. Expected Water
\ FLOOD WARNING 576.0'
\ FLOOD WATCH 574.0'
\
Average Mean Water Level 571.0' 570' \
\
Low Water Level (Ave.) 568.6' Min. Expected Water Devel. 562.0' 560' , 551' Bedrock Line DAVIS-BESSE NUCLEAR POWER STATION t ELEVATION PROFILE l Enclosure 1
7 AD 1827.08.0
* *' s 5l 0-Eeamy 8. --a A,c
- { . 2 ,- ~l 8 8 .-
.k. &e f=,,)t:f- g 6 5- 3 2 9 : m 5- *
- t
,i
*;qi.
- p. , ,-... -
- , , . , r- - - r- -- s, .j t } ';: i '
. i.. -
l .? !
... i .,
,1
/2 i p ;. [ .
'p.
' w ,. .
N .}'j'
'!,; 1,
&{f;;:q
-, l n ,. ,
,f--- \ ! '1 . l- -f - 1 'f'i>
c.',v
/ ,. 3
' ..i.! F;i i
i
+\ - < <
\ih'jks; ;I !--!j i L} I ! :l 7
)()
i .
~ai e3 %rr (l.k T y. i,,i.
ogsR %, p1 ;.1<
.r
!=;
ii f# ' r- 1, i .:4
,.t w v ,s.L ',111.N A y,' ...'ii,j -
. :J il
,.p ic e Is-,
,.l5
,o ,
i
. i i . >s. . .
~
< 1, i i,:i,,
. .. .i . i. . _a. I=.
i.
.j. 9. N. , i
;'t,
.e -it!.,.1,.i.
- a. s
, 3 , q,J-..
s .s .
..i i .
, =.
k~ j,. J j,_1 {u,gb .% ?4] * ,i - -
,1 /,,= E
,- Q .... .
% ';,, j 1 p,,, ! a p.,,, .... . e 5 E
'. ..%(,,
k-l. 3;*,53,: E' . I
,. J.
,dy Lil l j "
*y l *li ..
. m __ a=
Uj vL : f 1 wnt L #
>.,,. w . '. a.,3 g,
,9 g NhE
+h
*co s 2 ~n t *
% ~ 3 ~ ~ .t *
~~
~
si y s W -- ,- ' w{. -*.c-30 f \ k- A [ ' kp l T'
! O.di ;r'nh. l /$f'x!!!$g-j ..I 4 4.3. !4 9.
'Nij w Eo, v
tf *
- r i-JM .igi' g ' AM \ :.5'M(3,.r$'! g g;- ;c _.. % i M._.r i. -
,. gym - -
2 'l t g i { l l .} Enclosure , Enclosure 2
8 AD 1827.08.0
, f ..
s 3 I, s, I TEj,ji:}z :.. ;:,r:,;y'
.- { ' si.
6 2
- pyW *N-.E
E* '.,g : : ;;;.,. ',j! ;;py, 4 *
- S3 , . . . 3 : .s Qg - g g 32W * * ,' " % . , [.=S' .
= tai a 2eI. . .,. g
\e , g:. 03-3 I
- n.4 g g -
- "' \ 't' . i.
> - , e a eI'37,3 -#.;.*
? j' .s'
;)g' : :v.v \5 f~ E 4' g w* : :. a :
.:::, : *,%griy sq e
*. ' 5 =5 g
o4 i 3., 8 e-
- ix:
- f.N' .
-'l-
;t - b
'e&Js l Ei!:
- 3.o-L :p]
,< z= 5 m- C,ds .s s v.
yWg o y , os. , f , s,- }. g-f.*; .,7:s'::r-NI!$g 1 %- ; f6#d - g55 w 3 r $i
= = =3sig:J::J::!,;;
3 l:s' i.'is t- s: ,
$'J 2^ d . i
. , OsN' y ? s' a
.N:: gf (
- 4.?
i^: 3! N,,i
, ;.:.yl:
- v:,s..
,nw::
. . .;e' - re q 6 , , . ,
,g
) ' m. //, a .
.s ,,v.. > .~-
tg,
.: sa 'h ;;. ,,
w N p (,) d g.
.?' T...
. :. [1 3 j .'.jNf [ ,4 _ b,,y,f.E M.. g,ifjjh a e ,- - .; '.. ;l .. ~-- a < ,. - ' . ,
'~ n; 2
,/
S M
&O ',,
9 J 3 e gGy'.i[ e h.~. m s,IE3!
,1 es -
s:x .' /. -y es M'"k.; ?
' f'$ $ ylf-@w L
-y "D':
Jr a y, 9 3 ! E[:3 .J .
, g.- :? - -? 'p. .
%;G
~
~
- 'ff h? ,
u .
\
Y-I. s . W:j: r c ::e;3p:<i.m a. N xu . n
.% 4 y
~
. M(;
z n., 52 .:2 , , ...s .. o ds:27 .k[:hN .s;dN D.N 4 :' . < S' h .s)Z'.e o J / *h ,,
$h! ih d'< $ :' ; F ' \. . T '#~ d' ! !
%'vsc#g@h5 .K .'M +
;'g\. k + . . /
f p f/ e >
. c.a 4:4.p xs NN ' '
x ' .N - ( - NN, - ,- it:: Y p,s:.:s.*r c *,N,;'..asa - - i ..
- s:.:~ .:. ,',,' . .
/ l s
1
- .:s!:((!5f'\.{..'
s . : . . .: ,-- . hys ,r; x N'JsN. /,
/.' = 1
- g. '
i y 5
.:e;;: x: .
py:'
- h ,,'hn,' -
,' / hn_
i Q i_ e J:?.:t; My::: :th-r 2,g N. . * .)l.//',,. </ e,/
- s. .
^
'//'..
i
=
rwj e ss- . l : -t;;'p!:
, s
- n ' a sg.
s N:' . I 1 l v ,gigi? s ,
, , , t I a i
l - 1 END Enclosure 3
1 l AD 1827.09 Davis-Besse Nucicar Power Station Unit No. 1 Administrative Procedure AD 1827.09 Radioactive Transportation Accident
.j .9 r n,., ..
Record of Approval and Changes Prepared by C. B. Doyel, W. H. Green 2/4/76 Date Submitted by D. W. Briden 2/10/76 Section Head Date k Reco= ended by Jack Evans 2/24/76 SRB Chaiman Date QA Approved NA/DWB Manager of Quality Assurance Date Approved by Jack Evans 2/24/76 Station Superintendent Date Revision SRB Q1 Sta. Sept. No. Recommendation Date Approved Date Approved Date l l hf/7f N Oh YWE0 &% a pe vb1}82 ei-Htl y ww 4 +1~ lh i e l l
1 AD 1827.09.2
- 1. PURPOSE The purpose of this procedure is to establish the actions which may be taken by various members of the Davis-Besse Nuclear Power Station (DBNPS) to give assistance in the case of an accident involving a transportation vehicle carrying radioactive material either (1) within the station boundary or (2) in the general vicinity of the station when requested by the carrier or other outside source (i.e., police or sheriff).
Toledo Edison assumes no legal responsibility for planning or coordinating the overall response to any transportation accident outside the station boundary. Assistance may be provided by the
; Davis-Besse staff emergency organization when requested, as long
'as the capability to deal with a possible on-site emergency is not compromised. This procedure delineates the actions that could be 1 taken in the event that a transportation accident does occur. If the incident involves nuclear fuel, or a Type B shipment, the Director of QA shall be notified.
- 2. PROTECTIVE ACTION GUIDELINES The provisions of this procedure should be implemented if either of the following events occur:
(- 2.1 Verification from TECc operating personnel that an accident involving the transporting vehicle has occurred on-site (within the owner controlled area of the DBNPS). 2.2 Verification from an outside source that an accident involving a vehicle transporting radioactive material has occurred offsite (within approximately 25 miles of the DBNPS) and assistance is requested by the carrier or local emergency agency.
- 3. ON-SITE ACCIDENTS On-site accidents are to be dealt with using the provisions of EP 2l 1202.40, " Radioactive Spills", and AB 1203.13, "High Airborne Activity". These two procedures contain all the provisions necessary to successfully handle the accident and any accompanying radiological emerr-acy.
- 4. OFF-SITE ACCIDENTS All actions listed in this section are predicated upon notifica-tion of the station staff of an accident off-site by an outside organization.
l l 4.1 Actions of Persons at the Station Receiving the Call for Assistance
2 AD 1827.09.1 4.1.1 Obtain the following information:
- 1. Location and time of accident
- 2. Type of accident
- 3. Type of radioactive material involved
- 4. Extent of the radiological spill, if any (an estimate) 1
- 5. Emergency actions taken by outside organiza-tions
- 6. Name of individual or organization making call -
- 7. A return phone contact if available
- 8. ID of carrier, shipper, and/or destination if any are readily known.
4.1.2 During normal working hours, notify the Station Superintendent and the Chemist and Health Physicist and inform them of 4.1.1. 4.1.3 During off normal hours, weekends, and holidays, notify the Shift Supervisor of 4.1.1. 4.2 Action of Shift Supervisor (During off normal working hours, weekends, and holidays) Ensure that the information of 4.1.1 is forwarded to the Station Superintendent, the Chemist & Health Physicist and the EDO, and enter in the Unit Log. 4.3 Action of the Station Superintendent Determine from the information obtained in 4.1.1 whether or not Toledo Edison will provide assistance, and inform the Chemist.and Health Physicist and the EDO of his 1 decision. He shall also notify Toledo Edison Management to advise them of the situation. The Toledo' Edison Company Public Relations Department shall be responsible j for any news released from Toledo Edison Company con-l cerning the incident. 4.4 Action of Chemist and Health Physicist s If directed, the Chemist and Health Physicist-should dispatch a Radiation Monitoring Team (s) with radiological 1 monitoring and sampling equipment (off-site Kit from the
3 AD 1827.09.1 ECC). The C&HP should accompany the RMT(s) sent to the scene and provide assistance to the State authorities and others as required. He shall be responsible for recording relevant events and informing the EDO of l status. He should also provide the Station Superin-tendent with reports of events. 4.5 Action of EDO 4.5.1 If directed, proceed to (ECC) Emergency Control Center. 4.5.2 Establish communication with Chemist & Health Physicist. - 4.6 Action of the Radiation Monitoring Team (s) The Radiation Monitoring Team (s) should accomplish the following actions upon arriving at site of accident: 4.6.1 Commence making surveys as required. 4.6.2 Set,up a controlled area if not already established. ( 4.6.3 Take smear sample of the vehicle and cask as required. 4.6.4 Prepare to decontaminate the area as conditions permit. 4.6.5 Obtain persennel dosimetry results from all persons involved in the accident and clean up. 4.7 Davis-Besse Facilities Availability Toledo Edison Company may, as determined by the Station Superintendent, also make the facilities at Davis-Besse Nuclear Power Station available for use by the carrier. Decontamination of personnel and treatment of minor injuries may require the use of the facilities. Decon-l tamination shall be accomplished in accordance with HP 1604.01, " Personnel Decontamination Procedure". Where injuries are involved, the situation shall be governed by EP 1202.43, "Non-Radiological Injuries Procedure" or EP - l 1202.39, " Medical Treatment and Handling of Contaminated Individuals Procedure".
- 5. RECORDS In addition to the Unit Log entries, the Chemist and Health Physicist may keep an accurate record of all actions taken from
!~ l a m - - - w - , - - - - n ,- - - -
e 4 AD'1827.09.1 the onset of the incident until the area is decontaminated or the Toledo Edison Company assistance is no longer required, whichever is first. This record should be kept by the Chemist and Health Physicist. After the completion of the incident, the Chemist and Health Physicist should prepare an evaluation of the incident and along with the copies of all relevant records, submit the report to the Station Review Board (SRB) for review. After the SRB review and recommendations are documented, the records shall be filed in the 1 central file under the heading of Radioactive Transportation Accidents.
- 6. INCIDENT REVIEW Review of the incident is conducted by the Chemist and Health Physicist as he prepares his evaluation and by the SRB as they review the evaluation and the associated records. The review should consider the following items:
6.1 The readiness and ability of the station staff, especially the RMT, to cope with the incident. 6.2 The suitability of this procedure to provide sufficient guidelines to handle the emergency In light of these two items, the Chemist and Health. Physicist and / the SRB may make recommendations to changes in training and pro-cedures to deal with this type of emergency. 9 I END
F DISTRIBUTION
~
i riginal, Responsible Section Head Action +
, f ,
File Copy, Master File
' COPIES TO BE MODIFIED FoR IMMEDIATE IMPLEMENTATION DAVIS-BESSE NUCLEAR POWER STATION . UNIT 1 TEMPORARY MODIFICATION REQUEST ContrQ1 Room (2) ECC (2)
ED 6926 Shift Supervisor (2) TSC (2) I i i SECTION 1 PROCEDURE TITLE AND NUMBER AD 1827.10 0FFSITE DOSE ESTIMATES RE ASON FOR CH ANGE TO CORRECT REFERENCE NOTED IN THIS PROCEDURE. CHANGE SECTION 4. PART 4.1.1, NOTE (FIRST NOTE), SHOUI.D READ: NOTE: If data cannot be obtained from the site meteorological tower, backup data to perform Offsite Dose Calculations may be obtained by calling the agencies listed in Attachment 2, Section X, Part F, of Admin. Memo No. 37. IS PROCEDURE REVISION REQUIRED PREPARED 8Y oATE Ron Durdel m a 4/8/83 APPROVED BY
% & fM, w
~
OATE 1Nes APPROVE D 8Y Q. d. ,da as DATE y/W93 SUBMITTf D BY (Section Head) / i DATE '/ /
)
RECoMMENoEO BY (SR8 Chairmen) b U- kw 4[lI[83 ( ,pna.-x M DATE c1jisin
, '3A APPROVED SY a(Menever r p.qr APPROVED SY (Station Superintendent) of Quality Assurance). /%L DATE q)ujj; OATE .
h1? 9 w L'% *~ # 4 l g
o8 TRIBUTION oa w.s euen H e 4. tion y/ 1// / ._ ,ori,,.nc.... R. M r .. cop 3 To BE Mo IEo poR IMMiot ATE IMPLEMENTATION DAVIS 8 ESSE NUCLEAR POWER STATION . UNIT 1 , TEMPORARY MODIFICATION RECUEST l Eo se2s i SECTION 1 PRoCEoVRE TITLE ANo NUMSER AD 1827.10 Offsite Dose Calculations RE ASoN PoM CHANot Incorporate use of Prime Computer for performing dose calculations. i n f a CHANGE tb . Add the following note to secti6n 4 prior to section 4.1. _. - . _ _ _ _ _ . . . . . 8' Note: Dose calculations mayh performed using the Prime Computer. j Instructions for accessing the Prime can be found at the ECC terminal and the Control Room terminal, I i 2 1 5
?
Is PRoCEcuRE REvlSloN REQUIREo Y.s X No if no, thle enodific.tlen is v. eld until William L. Yarosz ^" 3/22/83 APPRoVEo SY , oATE 6 Wu h9%W N '$ .i$ APPRovEo sv , g oATE u susuirTEo av e. n 1 k /n RECoMutNoeb sY (sRe Ch.irm.nl / oATE v o 1
, & p )/ /
oATE b
&l S/83
't oA APPRovEo sh tu of L.r.ne: oATE
/
Y s I- t ^* g AremovEo av (st.tson sve. rind t) oATE gs m m n'. .;~ ~ , 4ll t j? ? l
OLS ISUTION Originea. Resoonsit>ie Section Head Action pg,g/ _ Pn. Coo .Me ,,.e COPIES TO 8E MODsPIED POR IMMEDIATE IMPLEMENTATION DAVIS.BESSE NUCLEAR POWER STATION . UNIT 1 g,4 7, ,
'qcg , A TEMPORARY MODIFICATION REQUEST ,
J ED 6926 M I MN// [ ,s/~1 SECTION 1 PROCEDURE TITI.E AND NUMOER f' f
/ ):f'2 7,, /0 / /&b ' ' ' ~
DM. b ' { ric h R E ASON POR'CH ANGE ,
}($ e * .0bW
[ {l [ Tyic ?he s a W o .>> u a " ! g. f f h e r e A g up.( puma , a f jih3. b! CHANGE
.g# / ea WM v
la. c;,d* i ,' >< u;aaega>> y c'. -r (n. . n - pn adaaGl g>J IS PROCEDURE REVISION REQUIRED PREPAR . DATE - lU
- k ) f APPROVED 8Y '
[ j DATE / / b .'/ ., APPROVED BY ,,,, / '/ e .#
- OATE ,.
. g s -5 /,
- _, C '
- l. lo D SUBMITTED SY (Section Hok) '
DATE _IL Li d d I 7/ M /RL RECOMMENDED Y (SR S Chair'nen) DATE /
*[%7 WM_ _ g l{f DM/
QA APPROVED 5 eneger welly AssurTel DATE
)* <?
/
lb APPROVED SY (Station Supertnton' dent) DATE {W 3 c .W= -- - v
+ 9 /2-3 /S~z
l 26 AD 1827.10.11 Instructions For Accessing DEC PDP 11/03 For Meterological Data .
- 1. Turn phone accessed data terminal on.
I
- 2. Ensure unit is in ready mode (Press the LOCAL / TALK button on Model 43 terminal). *
- 3. Check three options:
. *. ~
a) PARITY - off ' b) DUPLEX - l'ull ' c) . BAUD
- 300 c,r 30 CPS
/ *
- 4. Dial phone number 898-6240 (Oak Harbor)/ When the frequency tone is heard, press the DATA button on Model 43 terminal or inserc
- receiver into the acoustic coupler on other models. l
\
/
- 5. Correspondence \between Computer and Terminal Operator:
a.
\
Computer ,will type: WHO ARI YOU7
- b. Type in: t (an up arrow) m
- c. Computer will type !! = IIR, M = MIN, C = CA1.
- d. Type in:
\g H, M, or C (Type only one for v"
either hourly, minute or cal-Nx ibration check)
.'i,
'N, - Type "H" to . request data', .by
, , , , N hourly in(erv,als, for'.the-date
, , . , \specified.: '8 ,- ,1
,,,- n
-d
~~
. . , y. - ,
Typc'"M" L'o request data',.,,by?15 minute' intervals, for t.he
- dale specified.'- .: -
" l \ > . : e .. .
Type "C" to request calib' ration
~
, check (not normally s used) -
s
- c. Compulcr will typc: ACCESSED COhPUTER. '. -
TYPE JULIAN DATE REQ.' , N-l' . Type in: Three digit Julian'daLc (e.g. 001, 072, 365) .
% =
Compulcr wi'11 print g.. . TRANSMISSION COMPLETE. s' ouL data requested and ALL DONE7...Y or N then type: '
,N' V.
.x g
.' =
Attachment 2 Page 1 of 3 .
'. ~
27 AD 1827.10.11 .
,. .\.
- h. in: ' ~-
N (if'more data *' e ed, then
. Proceed th ,.. ste,ps c g again),
or .
, . -# ; .j a , . , ,
.,...,s.
. i. Type ins if no f6'r'ther data is needed)
- j. "O. .
. ,Coeputer will type: TERMINA7 G C012fUNICATION.,
GOOD DAY
- k. /
Mang up the p, hone and turn the terminal.,off, as uired.
.r..
...t,.
/
e : . r*..
,f :.' 8.*1 ,
/ -
,/ -
,/
. :a -
/
/
/
9 i,.
.s - % .
l.s c a'.-
- *t
* .'. ,Rg ; , ..
*e .
f*. J,s .
.-{< m ., ,4 t. -
' * ..4 -:t, -
.S -
** 2.- .
w t .. . ,t * .d.
.'e. ' ' ; l- ,.
- T* .
.;.g.. gs' . .
'.g!.'. f .
. e,~,.
..,i,.*
' *4 .
g.- .)* .. n .!' .~. .
- u. .
Attachment 2 Page 2 of 3 i i i- - -
.~.
.V. -
28 AD'1827.10.11- i. s .
.. V Sample Output of Meteorological Data #
s ile Accessing DEC PDP 11/03). ,
\ ,- ('*.- ~i.
Fhr?.T$chnical Specifie'ation 4*.3.3.4 N . 7 . . ;.- Elev*821' wind speed Ele,v 821' wind direction - Elev' 612' wind sp'eed .. . VV VY Elevf612' wind. direction l 4 Elev.'821'-612F tempe'rature differential KEV 2 <--1905---><-- s 755---><---10M---><100d><7',n><-TEMPER 4TURE->< PRE ><SSSDD ADS
/
ItR:nN US UD SD US b S8 US W3 Sit DT- DT An8 100DW 10DW CIP DDDFFPun 13 27.7 2. 24.4 3. 13.0 ' 7. 0.1 ' 30.6 15.4 1 0 115. 202. 114. 0.0 11.7 0.00 1 0. 2: 26.8 2. 23.4 2. 12.4 7. 0.3 3 t.0 17.0 E 1 0 Iff. 204. !?4. 0.0 13.4 0.00 1 0 E 3 25.3 2. 21.7 2. 1 4 7. 2.0 31.7 18.? 1 0 l 210. 213. 74. 15.5 0.00 1 0 is 27.6 3. 24.4 3. 13.7 4. 0.5 1[ 35.s 17.7 1 0 220. 227. 2i 3: 31.t 3. 27.7 3. 17.5 -0.1 f... 37.1 ii.5 20.7
. 00 >
1 0 0 ' 221. 228. 216. -0.0 17.5 0.00 1 0 J, 6: 32.2 3, 27.2 3. 18.5 5. 03 37.4 23.4 1 0
- 222. 230. 217. -0.I 22.5
- 0.00 1 0 7: 34.3 3. 31.5 3. 22.7 4. -0. 37.? -
24.3 0 Q 230, ' .1 238. 227. O.5 25.8 0.00 1 0 0: 31.6 3. 27.0 3. 20.7 4 -0.4 34.4 28.2 1 0 236, 245. 235. - - 0,. -- 28.0 0.00
- 1 0
?: 3. 27.0 3. 21.2 /4.
31.3 -0.5. . 35.3 28,.8 1: 0- W 24J.' 250. 2. 9. -0.3 . 2 8. 4*/. . . 4. 0 0:*i . .;1
- los 27.2 4. 27.4 4. 29 5 5. -1.1- '*. . . 3L 2 .,29.1 Tf . ,1, 9l[j.
.0 25 6'.*
- 265. 255. ' -
-0.8'. 28.7 ..o.0.40.f 03.y ,
11: 27.2 3. 25.4
' ' t. a
- 4. 1 t',2 5. -1.2 .
'35.0- ^ 27.1%: . 1 f.04 -
/ .254.
256, 264. - 0 . 8' - '2 .'7", ' ',0. 0 0. :1 - 09,
- 12 28.0 4. 26.7 4.[21.1 '4. -1.2 -
34.,2 . 27.'.1 5 .
. . !^1.1 246. 257. / ,244. -0.? ;>*. ,28,.4 . O,0.,'. - m
, f.ECEND !I 0.00 ,t ~((
' f
- j. .
...b .s.
h,.,*
. e,
/
- i
*.;,.-Q' l!R:MN , s -
i.',h . hour, minute (Eastern Standar:1, NOTE: .
.. Data for P.11/03 is-Time)-
- read from e' Met.. Tower "*
luuM 100M elov (917') thH and stored- r.threc 75M elev (828') days only.' Met Tower lut! IOM clev (612') is down, only eruvious' WS wind upcod (MPil) - WI) wind direction (degrecs) Information ca be SI) / accessed. DT ./ standard differential deviation temperature 'F - amis ambient dry bulb temperature *f ' IN devpoint temperature *F' E precip precipita tion - A:.tachment 2 E,N,[D P. age 3 of 3 k I
_In9tructions For Accom ing DEC PDP 11/34 , a For Meteorological Data
- 1. Turn phone accessed data terminal on.
- 2. Ensure unit is in ready mode (LOCAL button on)
- 3. Check the options:
- a. PARITY - off
- b. DUPLEX - full
- c. BAUD - 300 or 30 CPS g
- 4. Dial phone number: 2379. When the frequency tone is heard, press DATA button. Mang up phone receiver.
- 5. Computer / Operator correspondence:
- a. Computer will type: >
- b. Operator will type: HELLO 100,100 Return carriage
- c. Computer will type: PASSWORD:
- d. Operator will type: (Rafer to memo dated July 1, 1982 from Jennifer Scott-Wasilk for the appropriate password)
Return carriage NOTE: Password will not be printel
- e. Cenputer will type:
RSX-llM BL26 MULTI-USER SYSTEM GOOD AFTERNOON . 08-JUL-82 13:23 LOGGED ON TERMINAL TT10: Toledo Edison Company Davis-Besse Site Environmental Monitoring Comrocar System UNA'JTHORIZED ACCESS INTO THIS SYSTEM IS PA%14TED BY FEDERAL LAW NOTE: The ayucca timo on this computer remains at Eastern Standard Time the year around.
>eLOGIN.CMD
> SET / SLAV-TI:
>; DAVIS-BESSE WEATHER DATA
>RUN SURVEY l
l SELECT OPTION 1 - DISPLAY HOURLY AVERAGE WEATHER DATA 2 - DISPLAY 15 MINUTE AVERAGE DATA 3 - LIST WEATHER TOWER GENERAL INFORMATION 4 - LIST DEFINITIONS OF WEATHER DATA ABREVIATIONS OR CARRIAGE RETURN TO LOG OFF l
. _. _ _ _ _ ~ . _. _ __ . - . _ . ._
4 h ENTER OPTION (1, 2, 3, or 4):
- f. Operator will types (Enter option of your choice)
Return carriage NOTE: Computer is on EST
- g. For Option 1.
l Computer will type: Please anter the starting month, day, and hour you wish to look at or RETURN to return to option list (MM.DD.HH, or RETURN) Operator will type: (Entur month, day, and hour of your choice. Return carriage Exataple: 07.08.10) Computer will type: Please enter the ending month, day, at:d hour j you wish to look at (MM.DD.HH): Operator will type: (Enter month, day, and hour of your choice. Example: 07,08,15)
- h. For Option 2 Computer will type: is the current time (EST). Any hours you ask for which are greater than this hour will assume to be hours which occurred yesterday.
A total of 24 hours worth of 15-minute average data is available. Enter the starting and ending hours (0-23), or 24 to get all 24 hours, or RETURN to return to option list (SHR, EHR, or 24 or RETURN]:
- 1. Computer will print out requestod data and return to option list i j. If more data is requirod, repeat steps f - j,
- k. If you wish to sign off push RETURN and computer will print:
> SET /NOSLAVE=TI:
> BYE TASK "...AT." TERMINATED l
ABORTED VIA DIRECTIVE OR MCR AND WITH PENDING 10 REQUESTS HAVE A GOOD AFTERNOON ! 08-JUL-82 13: 25 1T10: LOGGED OF7
- 1. Push TERM READY to return printer to a statad 'uy cundition.
i l
, , , . - -. .. . . - . . ,. + . - -
. . . .. . , . _ . . ~ .
DAVIS-BESSE SITE WE'ATHER DATA HOURLY AVERAGES 7/ 9/82 100 METERS 75 METERS 10 METERS 100 75 AMS 10DW HOUR USPD WD/SD USPD WD/SD USPD UD/SD DI DT TEMP PNT RAIN I 8.0 339. 8.0 337. 4.1 324. 1.2 1.0 72.7 69.4 0.00 3.0 4.0 5.0 2 9.4 342. 9.2 343. 5.4 333. 0.1 0.4 72.2 68.0 0.00 5.0 6.0 10.0 3 9.2 346. 9.0 348. 5.6 340. -0.8 -0.4 71.7 67.5 0.00 3.0 5.0 9.0 4 10.0 340. 9.9 347. 6.3 338. -0.5 -0.1 70.9 22.4 0.00 3.0 4.0 17.0 5 11.1 349. 10.9 348. 6.3 339. -0.4 -0.0 69.7 43.1 0.00 6.0 7.0 10.0 6 8.9 5. 8.8 3. 6.6 355. -1.2 -0.9 70.4 65.3 0.00 4.0 3.0 8.0 7 8.8 7. 8.3 7. 7.6 3. -1.5 -1.2 76.8 65.6 0.00 7.0 7.0 12.0 8 99.9 999. 99.9 999. 99.9 y99. 99.9 99.9 999.0999.0 0.00 esse sees esse e l E
- e METEOROLOGICAL PARAMETER ABREVIATION DEFINITIONS {
l USPD -- Wand speed in nales per hour. WSPD's are given at the 100 neter 75 neter, and the 10 noter levels. UD -- Wind direction in degrees, north = 0. UD's are given at the 10 0 neter, 75 noter, and the 10 neter levels. SD -- Standard deviation (sagna theta) of the hort:ontal wind direct 2on SD's are given at the 100 neter, 75 neter, and the 10 neter levels 100 DT -- Tenperature differential an degrees fahrenheit between the 10 0 neter and the 10 noter levets. 1 75 DT -- Tenperature differential in degrees fat.renheit betueen the 7 l 5 neter and the 10 noter levels. AMB TEMP -- Tenperature in degrees fahrenheit at the 10 neter level. 10 Du PNT -- Dew point tenperature in degrees fahrenheit at the 10 nete e level. 100 DU PNT -- Dew point tenperature in dasrees fahrenheit at the 10 0 neter level. 100 DW PNT's are only available for 15 ninut e averaged data. RAIN -- Precipitation an inches (down to 1/100 of an inch) at the 1 neter level. Precipitation is never averaged, 2nstead, it i s totalled.
- a n d , " '
; 5e
l l l AD 1827.10 Davis-Besse Nuclear Power Station Unit ST.' 1 Administrative Procedure AD 1827.10 Emergency Off-Site Dose Estimates
.J' =
Record of Approval and Changes Prepared by C. Doyel W. Green 2/6/76 Date Submitted by D. W. Briden 3/3/76 Section Head Date Recomended by Jack Evans 5/18/76 SRB Chairman Date QA Approved J.D. Lenardson/JCB 6/3/76 Manager of Quality Assurance Date Approved by Jack Evans 6/4/76 _ Statica Superintendent Date Revision SRB QA . S ta . S upt . No. Recoc=endation Date Approved Date Approved Date 2 f W 4/24/79 #! # ' l - 3 My #do g g jy S [*DW~he 1 n WA'^ ~~ r ' ,' ,f,, d Y gg, ymp cs0 ~~ w m ' ",' ; ,' y' gg upg/r0 Q l -15~ 4 e TOAY h ,, g , y , QM 41 \ 0 l % I UO 8kE/ Y 7 n ,1 u e.a MAbrMk w m =v'n I cy , Q sop,,p,, eaD#/99 "Inhi rv n = n " & 1 l0 An y s,lvim r_.aspimu/w, w m aim,
;j,,p v u b+lQ 1h$1- '#DfgsssW
,, ypp p .n +4f p, c kC46b'ido- v% *Mk
O 1 AD 1827.10.11 l l
- 1. PURPOSE AND SCOPE 1.1 The purpose of this procedure is to estimate off-site whole body exposure rates from Xenon-133, and thyroid exposure rates to adults and children from I-131 for accidental, uncontrolled releases.
1.2 Radioactive particulate material is not addressed because protective actions are based on assuming the iodine exposure pathway is critical, and should provide suf-ficient protection from radioactive particulate material. (Based on information from Section 5.1.2 of EPA-520/1-75-001, Revised 6/79.)
- 2. REFERENCES 2.1 NRC Regulatory Guide 1.4, Assumptions Used for Evaluating the Potential Consequences of a Loss of Coolant Accident for Pressurized Water Reactors 2.2. Manual of Protective Action Guides and Protective Actions for Nuclear Incident EPA-520/1-75-001, September 1975 (Revised June 1979) 2.3 Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of 11 Nuclear Power Plants, NUREG-0654/EEMA-REP-1, Rev. 1 2.4 NRC Regulatory Guide 1.23, Onsite Meteorological Programs a
2.5 The Davis-Besse Nuclear Power Station Emergency Plan and EI 1300 Series, Implementing Procedures 2.6 AD 1827.12, Protective Action Guidelines I 2.7 AD l'839.00, Station Operations 2.8 TECo NQAM 2.9 FSAR, Section 17.2 2.10 Admin. Memo 37, ECS Pager and Telephone Numbers 11 2.11 NRC Regulatory Guide 1.145, Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants
- 3. RESPONSIBILITIES In the event of the accidental release of gaseous radioactivity,
2 AD 1827.10.12 the Shift Supervisor shall make an initial evaluation of the *situa-tion and classify the emergency in accordance with EP 1202.37, High Airborne Activity. 3.1 For local releases, any calculation of release rates and dose rates should be done under the direction of the Shift Supervisor by:
- 1. An Administrative Assistant, or
- 2. Other qualified, available personnel.*
*The STA may perform release and dose rate calcula-tions if the STA feels that performing such calcula-tions does not interfere with his primary respon-sibilities of maintaining a broad perspective 'of the event and consulting with the Shift Supervisor.
Requirements for notification of other persons to deal with these types of releases are found in the EI 1300 series, Emergency Plan Implementing Procedures, and EP l 1202.37, High Airborne Activity, and AD 1839.00, Station Operations. 3.2 For conditions that require Emergency Plan implementation,
; release rates and dose rates should be performed under the direction of the Emergency Duty Officer (EDO). The Shift Supervisor, acting as interim EDO, should designate:
- 1. An Administrative Assistant, or Other qualified, available personnel,*
~
2. to perform these calculations. If the Emergency Control Center has been activated, the designated EDO should direct response personnel within the ECC to perform the j dose calculations relieving the Shift Supervisor of this responsibility. i
*The STA may perform release and dose rate calculations if the STA feels that performing such calculations does not interfere with his primary responsibilities of maintaining a broad perspective of the event and consulting with the Shift Supervisor.
l l 4. PROCEDURE l 12 4.1 Release from Station Vent. l 4.1.1 Complete Data Sheets No. 1 and No. 2. Instructions for completing the required information are provided on the Data Sheets.
~
3 AD 1827.10.12 NOTE: If data cannot be obtained from the site meteoro-logical tower, backup data to perform Offsite Dose Calculations may be obtained by calling the agencies listed in Attachment 2, Section IX.6 of Admin. Memo No. 37. NOTE: A programmable calculator and its printer (located in the Shift Supervisor's Office and Emergency Control Center) may be used in place of Data Sheets No. I and 2. See Attachment 1 for instructions. 4.1.2 Use AD 1827.12 Protective Action Guidelines to determine the protective actions to be initiated. The EDO should make plume exposure recommendations per this procedure. 4.1.3 If an evacuation is initiated, it should include an area 22 1/2' to 45* each side of the plume center line (Based on Appendix I from NUREG-0654/ FEMA-REP-1). 4.1.4 If evaluations or RMT sample results indicate ingestion exposure that exceeds the plume exposure evacuation area, recommendations for further evacuation should be made by the Emergency Operations Manager in accordance with ingestion exposure Protective Action Guidelines given in AD 1827.12. 4.1.5 Should the NRC request direct contact with the individual performing offsite dose calculations, it is the respon-sibility of the Emergency Duty Officer to ensure that the requesting NRC official is contacted directly by an appropriate cognizant individual. Any available phone could be used for this purpose. 4.2 Releases from MSSV's, Auxiliary Fe'ed Pump Turbine Exhaust, and Atmospheric Vent Valves. 4.2.1 Calculate the release of Xe-133 from the SJAE as follows: Release Rate (Ci/sec) = (CONV FACT)(SJAE ACT)(SJAE FLOW) 12 Where: CONV FACT = 6.6 E-11 (RE 1003A) or 1.2 E-11 (RE 1003B) SJAE ACT = RE 1003A or B reading in cpm SJAE FLOW = FI 1002 in efa 4.2.2 In the event of a reactor trip, quantify the gaseous ) release of Xe-133 and I-131 via any and all other 4 release points using the following calculation: I l l l 1
4 AD 1827.10.12 Release Rate (Ci/sec) = 6.3 E-5 (LR)(RCS, Cone'n) Where: RCS Conc'n = latest I-131 or Xe-133 con-centration in the RCS in pCi/cc. LR = latest leak rate in gpm as determined from EP 1202.57, Appendix C, or Appendix D,
- Step 7.
NOTES: 1. I-131 and Xe-133 are expected to be the highest dose contributors, how-ever, any radionuclide may be used in the above calculation.
- 2. The above calculation conservatively assumes all the activity leaking to the secondary side is escaping. That assumption is accurate if the MSIV's go closed for the first minute follow-ing the trip. When the MSIV's open the calculation becomes more conserva-tive.
- 3. Emphasis should be placed on the latest leak rate determination as it could be reduced upon power reduction.
- 4. If steam continues to be released with the MSIV's open, and the affected S/G still not isolated, a sample of the S/G steam on the affected S/G should be collected and analyzed. The following comparative evaluation can be made for radioactive release rate:
Release Rate (Ci/sec) = 3.5 E-6 (STM FLOW)(SG STM CONC) Where: STM FLOW = Total Steam Flow, #/hr. (if an estimate of steam flow cannot be determined, use the maximum flow I of 1 E+6 #/hr.) l SG STM CONC = Concentration of a nuclide, pCi/cc l l 4.2.3 If the MSIV's remained closed following a reactor trip, ! and there is a S/G tube leak, Xe-133 in Ci/sec can be determined use RE 600 or RE 609 as follows:
- 1. The analyzer / gross switch must be positioned in the Gross Mode.
1 I
5 AD 1827.10.12 NOTE: These switches are normally in the Analyzer Mode 'to selectively monitor N-16. When the switches are changed to the Gross Mode, high alarms will result bec'ause the setpoints were selected based on N-16. -
- 2. Net cps readings are calculated by subtracting a 1000 cpm from the actual readings. (1000 cpm are the normal background readings in the Gross Mode.)
- 3. While in the Gross Mode, convert the cpm readings on RE 600 and RE 604 xato pCi/cc Xe-133 by multiply-ing eps times 1 E-5 (pCi/cc)/ cpm.
- 4. To obtain Ci/sec of Xe-133 being released, multiply pCi/cc times 3.5.
NOTE: Steps 1. through 4. above are based on 1 E+6 lb/hr saturated steam flow at 995 psi with a specific volume of 0.45 ft 3 /lb, and a Bechtel to TED letter (BT-10372) dated June 4, 1980. 4.2.4 To calculate the resulting whole body dose rate from Xe-133, start with Step (7.) of Data Sheet No. I and insert the Ci/sec Xe-133 as determined from Steps 4.2.1, 4.2.2 or 4.2.3. 4.2.5 To calculate the resulting thyroid dose rate from I-131, start with Step (5.) of Data Sheet No. 2 and insert the Ci/sec I-131 as determined from Step 4.2.2. l l l
-- =
1 6 AD 1827.10.11 DATA SHEET No. 1 Estimated Downwind Whole Body Exposure from Xenon-133 (1.) Record the date Date Time . and time (2.) Record Xe-133 activity RE 2024C reading CPM being released from the appropriate meters RE 2025C reading CPM for RE 2024C and RE 2025C NOTE: If these readings are off scale, the Xe-133 in the Sta-tion Vent is to be obtained using the Emergency Station Vent sampler described in AD 1850.04. 11 (3.) From Figure 1, record RE 2024C cone'n pCi/cc the corresponding concentration in RE 2025C cone'n pCi/cc pCi/cc (4.) Record the flow rate through the Unit Vent KCFM x 103 CMD = CFM from Computer Point F885 Flow rate and convert to CFM from F885 (5.) Convert Unit Vent flow CFM (4.72x10') = cc/sec rate to ec/sec
'(6.) Calculate the estimated release rate for b. x cc/sec =
Xe-133 by multiplying From (3.), cc From (5.) pct the highest value highest sec from (3.) times (S.) value (7.) Convert release rate . ! (Q) in (6.) to Ci/see b. x (1 x 10~6 pCi) = From (6.) sec Ci/sec i (8.) Record the wind direction (use 612' elev. if avail-l' l able) from the instru- 1 180' = 11 mentation as listed in Wind direction Downwind Table 1. Then add or direction subtract 180' to obtain the downwind direction (this value should not l exceed 360*) (9.) Record the wind speed (use 612' elev. if avail-11 able) from the instru-mentation as listed in mph x 0.447 m sec = m/see Table 1. Then convert Wind SPh the wind speed from mph Speed to m/sec Page 1 of 3
. I 1
l l 7 AD 1827.10.11 DATA SHEET No. 1 (Continued) (10.) Determine Stability Class by any of the following Stability Class (a) Read 6T from computer point T698 then from Table 2-A, record the Stability Class,
'or (b) Determine 6T by 821'
*F versus 612' *F then from Table 2-A,
, record the Stability Class, or if not avail-able, 11 (c) Read the Standard *See Attachment 2, Instruc-Deviation of Wind tions for Accessing DEC PDP Direction at the 35 11/03 on G.E. Time Sharing. meter level (612' - elev.) from the PDP 11/03 printout * (Column SD under 35M) then from Table 2-B, record the Stability Class, or, if not available, (d) Read the Standard Deviation of Wind 1 Direction at the 75 meter level (821' elev.) from the PDP 11/03 printout * (Column SD under 75M) then from Table 2-B, record the Stability Class. (11.) Using Table 3, enter Xp/Q (m 2) for distances of 1, 2, 5, 10, and 20 miles for the stability class in (10.), and enter in Column A. (NOTE: Real time X p/Q can be used if known) (12.) Divide Column A by the windspeed (m/sec) from (9.), and enter in Column B. (13.) Multiply Column B by the Xe-133 (Ci/sec) from (7.) and enter in Column C, which are the concentrations at 1, 2, 5, 10, and 20 miles downwind. (14.) Multiply Column C by 3.3 x 10' to calculate the estimated whole body dose rate from Xe-133 and enter in Column D. (Based on Regulatory Guide 1.109, table B-1) Page 2 of 3
8 AD 1827.10.7 . DATA SHEET No. 1 (Continued) Column A Column B Column C Column D Downwind Xy XJ Xe-133 Whole body Distance Q (wind speed) concentrations exposure from (miles) Q 2) (m (sec/m3 ) (pCi/ce) Xe-133 (mR/hr) 1 2 5 10 20 f I 1 l l l l Page 3 of 3
9 AD 1827.10.11 D4TA SHEET No. 2 Estimated Downwind Thyroid Dose to Adults and Children from I-131 (1.) Record the date and time Date Time (2.) Record the I-131 activity RE 2024B: from RE 2024B and RE 2025B (i) 1st count: time , cpm CAUTION: Noble gases can (a) (b) make the I-131 (ii) 2nd count: time , cpm appear falsely (c) (d) high. Have C&HP personnel verify the I-131 de-
- tected. If the incident con- = =
tinues, insert (iii) *E*"* = (("~*~ silver zeolite filters. (i) Record the time and cpm for RE 2024B and RE 2025B RE 2025B: (ii) Approximately 10 (1) 1st count: time , cpm minutes later, re- (a) (b) cord the time and (ii) 2nd count: time , cpm cpm for RE 2024B (c) (d) and RE 2025B (iii) Subtract cpm in (i) (iii) min CU" = ( ~ = from (ii) and di- (c-a) = vide by the dif-ference in minutes to obtain cpm / min for RE 2024B and RE 2025B - 11 (3.) From Figure 2, record RE 2024B cone'n pCi/cc the corresponding concentration in RE 2025B cone'n pCi/cc 4 pCi/cc (4.) Calculate the estimated release rate for Ebb x 4.44x10 7 cc/sec = I-131 by multiplying From (3.), ** the highest value highest YC*' sec from (3.) times 4.44x107 Value (5.) Convert release rate . C. 11 (Q) in (4.) to Ci/sec N[x(1x10s ), From (4.) Ci/sec (6.) Same as (8.) on Data Sheet No. 1 Downwind direction (7.) Same as (9.) on Data m/sec Sheet No. I wind speed l ! Page 1 of 2 i _-
10 AD 1827.10.7 DATA SHEET No. 2 (Continued) 7 (8.) Same as (10.) on Data Sheet No. 1 Stability Class (9.) Using Table 3 enter Xp/Q (m 2) for distances of 1, 2, 5,10, and 20 miles for the stability class in (8.), and enter in Column A. (NOTE: Real time X p/Q can be used if known) (10.) Divide Column A by the windspeed (m/sec) from (7.), and enter in Column B. (11.) Multiply Column B by the I-131 (Ci/sec) from (5.) and enter in Column C, which are the concentrations at 1, 2, 5, 10, and 20 miles downwind. (12.) Multiply Column C by 1.1 x 10" to determine the estimated adult thyroid dose rate from I-131 in mR/hr and enter in Column DJ * (13.) Multiply Column D by 2 to determine the estimated child thyroid , dose rate from I-131 mR/hr and enter in Column E.
- The constants used in (12.) and (13.) above have a maximum differ-ence of 120% from' time zero to 120 hours after reactor shutdown; this error is acceptable. The actual values are shown in Figure 3 for information.
Column A Column B Column C Column D Column E Downwind X_E Xp I-131 Adult Child Distance Q Q (wind concen- thyroid thyroid dose speed) trations dose rate rate from from I-131 I-131 (miles) (m 2) (sec/m3 ) (pCi/cc) (mR/hr) (mR/hr) , 1 i 2 1 5 10 20 Page 2 of 2
1
. 11 AD 1827.10.11 TABLE 1 l Data Acquisition and Display System at ECC (Date)
(Time) Tower MET TOWER Bailley (Time) 821 ft. - Wind Velocity - 612 ft. 9.9 gpg 9.9 9.9 gpg 99 821 ft. - Wind Direction - 612 ft. 99 9 DEG NN'I 00'0 DEG NN'I 821 ft. - 612 ft. - Temperature - 612 ft. . 9.9 op 9.9 99 op 9.9 STATION VENT FLOW 99.9 KCFM Panel in Control Room 0-100 0-360* -4 to +8 SI996 ZI997 TDI998D Wind Velocity Wind Direction Temp 612' Elev. 612' Elev. 821'-612' Computer Points in Control Room Computer Point. Wind Velocity, 612' Elev., in MPH A901 Wind Velocity, 821' Elev., in MPH A902 Wind Direction, 612' Elev., in degrees 'A900 Wind Direction, 821' Elev., in degrees A903 Temperature, 612' Elev., in 'F T699 Temperature, 821' Elev., in 'F T697 Temp. Diff., 821'-612', in *F T698 Station Vent Flow, in KCFM F885
V F' 12 AD 1827.10.11 11 TABLE 2-A Pasquill Stability Class vs. AT i Class AT = 821F minus 612'*F A Extremely unstable < -2.2*F B Moderately unstable -2.2*F to -2.0*F C Slightly unstable -2.0'F to -1.8*F ) D Neutral -1.8'F to -0.6'F E Slightly stable -0.6*F to 1.8'F F Moderately stable 1.8'F to .4.7*F G Extremely stable > 4.7'F (Derived from NRC Regulatory Guide 1.23) 11 TABLE 2-B Classification of Atmospheric Stability by Standard Deviation of Wind Direction Stability Pasquill SD
- Classification Categories (dearees)
Extremely unstable A SD > 22.5 Moderately unstable B 22.5 > SD > 17.5 Slightly unstable C 17.5 > SD > 12.5 Neutral D 12.5 > SD > 7.5 Slightly stable E 7.5 > SD > 3.8 Moderately stable F 3.8 > SD > 2.1 Extremely stable G 2.1 > SD
- Standard deviation of horizontal wind direction fluctuation over a period of 15 minutes to I hour.
l l
! 13 AD 1827.10.11 TABLE 3 Xp/Q (m 2) for Stability Classes as a Function of Downwind Distances of 1, 2, 5, 10, and 20 miles gg A B C D E F G l 6 6 5 5 4 4 4 1 1.2x10 S ax10 2.1x10 7.0x10 1.3x10 3.0x10 4.5x10 7 6 6 5 5 4 4 2 6.0x10 1.4x10 5.0x10 2.2x10 4.6x10 1.0x10 1.5x10 7 7 6 6 5 5 5 5 2.9x10 3.8x10 1.1x10 6.0x10 2.2x10 3.0x10 4.5x10 7 7 7 6 6 5 5 10 1.7x10 2.1x10 3.2x10 2.0x10 4.7x10 1.1x10 1.65x10 8 j 20 9.0x10
~
1.2x10
~
1.7x10" 6.8x10
~
2.0x10- 5.1x10 7.65x10 8 The values for classes A through F were derived from Figure 5-3, Page 5.22 of EPA-520/1-75-001, Revised 6/79. The values assumed an inversion lid at 1000 meters altitude and a ground level release. The values for class G were determined as per Reg. Guide 1.145 guidelines dated August 1979. -t 9
.. - _. - . - - ._ . . - - . =
P
) .
l l 14 AD 1827.10.11 11 FIGURE 1 l Conversion Chart for Noble Gas Releases (RE 2024C and RE 2025 C) i 10 . I i I 1 l : i. 10
~
/
! ,' l i e i e
-2 ,
10 . e s m > s , M r i ' 10
-3 -
d Xe-133 / l - u ,
% s '
t y _4 . 10 / .
)
/
10
-5 ,
A
/
f I -6 ' 10 , . l 1 f i f 10~ 2 h 3 4 5 6 7 i 10 10 10 10 10 10 10 cpm-(Copied from the Victoreen Calibrztion Manual). _
.. . _ _ . __ . . . ~ . . . _ _ . . . -- _ . - . .. - - _ . - . ._ . - _ _ .
l f I s 15 AD 1827.10.11 11 FIGURE 2 Conversion Chart for Iodine Releases (RE 2024 B and RE 2025 B) i
~
10 ~ l i
/
10
-5, .
. i
---'~ '
-6 .
} ,, s j 1 . s-l l / l 1 10
~
. l /
e l ! l /
~ ! 10 j/
- l. o e' i u /
. 2 - / S 10 '
~
/ -
A
. s , .
/
/
-10 (10~4)10 /
(10~ )10
~
/ . . _. -
l
' l
, ' \
. J l l (10-0) 10
~
/
0.01 0.1 1 10 10 10 lb~ 4 5 6 (10 ) (10 ) (10 ) cpm / min (Copied from Victoreen Calibration Manual) i
. - , . . . _ ~ . _ _ . , _ . _ . _ . _ . , _ . _ , _ _
i l 16 AD ,1827.10.6 ; l FIGURE 3 Radioiodine Dose Rate Factors for Infant Thyroid Dose' Rate vs. Time After Reactor Shutdown ____.. = . . . = . . .=. . ==. .. . .:.: . = . =. .= . =_ _ . .= . .:.- . . . = . . .=. . a= = . . .=. . . .: .-- '
- .: = . . . = . .=.. .a. :. : u= =. . :. =. .=
g . . . . .... . . . . . nj
-i :ii: :iti -!: - -
- :3n . . . . .
i... 2.6 19'5 ii.i: 5 = E !! !- i= .iii !E .- i = - 1 -!: fii - . iiH i-ii I (-jji i jpj :it: ; p:; upi Hi: .
..- ;iii ;p : . . ..
n =. n: nn
= . . .=
2.5 x . . :.:.:.
- 2. . :. . =..
=: : - -
. : = = =....
.Ei ss"@5 !s ?- 1
- s . :
i= ;-, Mi tid 3:
= i =. Si :
E s ! ii idi =d 5 ii r-5 2'. 4 E- h :.- SNSE 5 !E!:5 = IE % 5 35i@ Bi E E 5 55i != h 5: 355 dii 5 Ei 5: 3: 5 : 3i
. = .. o = :_
_=: = t ;:. :.::
. . .: n .: .:. u nn n: nu
=
. . . . :: . ....r =_=_ =
.=...
=.. =_..
= r..- J . . . . . . ... . . . . _..
.:= --A.
4' ';O*. ** :-*:- : -*:: se -
..r ---"="g:: =.
2.3
.~. ?- - -:.*:.J. . . . *:. :::,
--.4 . - - . - - - . -. . . _ .
- . - -... - . -. . _ - - . - -::J'"--I=*..J- - - -
E% 5ilE 0:4(N EiT ~~ i~i! = Bi '!!- i:2 i :i' 'iii 5 2: ! ilii 5E 55:j :* ~~ i: "Ji ii:- !! !!! iri 55i 2" "- 15E.T_\M+ ri 9 5 5
$7 w< ,$$,
2.2 Ei!
'E- I"i Hi
+- :5' 5. _-
55 9 : 5 Eli !! - iE
=:
5 5 5 iE Iiii i* # -~i 25 Ei! 5 _. ::ii. =. 1.:i.i. l..:.'N.lii-pii
- - . i.iii. d.ii iE. i. :=. :.
i "ti ::n..i'i .- iiH .i.i .! i= wS 2.1 1 .. fE 5E #i 11 ' "r '
~i E- : E - - - 2'~ = ~
= EiE: EE E !!:i :? ~2 !"- =
h 5 ii: -! ..' .1 u! 5 iMi 35 j-iii :E 55 55 i'N i. !5 =32 mili iid 5 E- i!: 5 =i @i : - :.45 w2 2.0 5 5Ai = -i H', h = ri E
- E -
E =
" ~~
5 EW *i 9 'i 8 !:i ii'" : {u idi iiH iir-15 5 5 5
- ii d '.I:[N Ei 5 5 :d i i! 5 liii fili idi = 5 i5i. 5 @ # Mi} ':i: 'fi: ii i 'lii: !=
w 1.9 5 I N ~
.k. g;.
v="'.=. =' .N o -
- . . u. .: . .a s _ .a. .= u .= =u =... a :n::._ :.c u ==
ze 4 p - __. = .,=
= :.-- = :-f:r;- :=-ar- .=n ~
.r. = :.:.
- :' ::: n=-==- 2 : =:Tr:
n ::: = ., _n 0M
-w 1.S ==-=
= 9 E rii' 5 35 " l 5 M! E lEr MEi! Mk !!? i:5 5 :i; T5 Mi 5 s # -
i- 'E 1 i? -
= 1::.; .:. = :; :: .n .= :.. 5 : .- - .: := Z r' . =,n. .=.
=.%5%: 2:.
.o m = = 2: =_2:= = = = = {:= . = = == = = = an
_u = j === =.=
=
=
a g 1.7 . _ _ == == =. . =l==- =:: -:
.: .=- .--= . = . .
==.:
= = ==
.=-:a
=
=. =. .=
n- : -"
= ==
v- =
=
. .=- _:- --- n
=r= -a : -
. . . . :... . . . :.:- .=. = == :. .. .: == :.q =:u = . == :.= = = = = u: ;- . = = = = .= u :
l ,
---.. == = = := == = =- : = =. ::= .- :- = = = = == =T. =u- = == := . n
=: =
9 E'5IEEE- = = = i~ 'I= = 'i 'Ei
=] Ei =
(x10 ) ;--~ 5IIE" 5 ii=0'
=5 2 ~
~! Sii '~
1 l 4 812 16 20 24 ,32 36 40 48 60 72 84 96 108 120 i 1 l HOURS AFTER REACTOR SHUTDOWN The constant 2.2 x 109 has a maximum difference of 120% from time zero to 120 hours after reactor shutdown for the infant thyroid dose rate. This is based on the worst case of radioiodine activities in the fuel core 90 days after irradiation, Regulatory Guide 1.109 and NUREG-0133.
- J
-l 1
17 AD 1827.10.11 0FFSITE DOSE CALCULATIONS USING TI PROGRAMMABLE CALCULATOR A miniprogram for the TI programmable calculator and its printer has been developed to simplify the offsite dose calculations. The program is . divided into six sections which are discussed below. Samples of runs of each section are attached; circled items are inputs. Each section performs a different type of calculation, and each can be performed independently with the exception that either the noble gas or iodine release rate calculation must be performed once before any other section is run. The program is not permanently stored and must be loaded into the cal-culator prior to use. 11 NOTE: The program does not include Table 3 Xp/Q values for stability , class G, thus for those instances where a stability class G exists, hand calculations should be performed, however, if time constraints require using the calculator, stability class F should be used. (The values obtained using F stability class will be approximately 50% low.) LOADING PROGRAM: The program is encoded on both sides of two magnetic cards kept with the calculator. Handle these cards only by the edges. The sides are marked 1-4. To load the program, perform the following steps in order: 11 1) Turn on the printer, and then the calculator (printer switch on right side), then press; 1, 2nd, OP, 17 on the calculator, the calculator should display 879.09.
- 2) Press "1" and "+/ "
- 3) Feed the end of the magnetic card labeled "1" into the program' slot on calculator side - the calculator will automatically feed the card through the calculator and out the other side pull the card out by the edges.
11 NOTE: If the calculator read the card properly, the (-1) will be shown in the display; if the (-1) is flashing, the card was read improperly. If this occurs, press clear and reenter the card.
- 4) Press "2" and "+/ "
- 5) Repeat the feeding process with side 2 of first card
- 6) Press "3" and "+/ "
- 7) Repeat the feeding process with side 3 of second card Attachment 1 Page 1 of 9
18 AD 1827.10.11
- 8) Press "4" and "+/ "
- 9) Repeat the feeding process with side 4 of second card
- 10) Proceed by pressing A for noble gas or B for iodine release rate
- calculations, either program will print a line of output on the printer which finalizes the program within the calculator.
11 11) Finally, run programs E (see page 5 of 9) and 2nd A'(see page 6 of
- 9) to test that each of the main programs will run with fixed data.
These test routines ensure that the program was loaded in the cor-rect sequence into the calculator memory. Compare your printout with the output listed below each of the programs (E and 2nd A'). If an error (an incorrect output line or a flashing display) was encountered during either of the test runs, the user can reload the program (following the above procedure) or if the error continues contact the calculator programmer (Technical Section) for assistance. 11 PROCEDURE: Once the program has been loaded as stated above, start any of the calculations by pressing the A, B, C, or D buttons (top row of calculator) corresponding to the functions described below: 11 NOTE: To enter data, simply input the values in standard or scientific format, then press "R/S". (If an error is made in the entry, press "CE" and reenter the value.) Also note that the calculator may be used in the normal manual mode without affecting the programming; when manual ! calculations are complete, to re-initiate a program simply press the button (s) corresponding to the desired calcula-tion. I A - NOBLE GAS RELEASE RATE
- This program calculates the noble gas release rates in curies /see from the-i stack. As input, it requires the countrate from the noble gas monitors l (RE2024C, 2025C) and the stack flow rate in KCFM.
11 FIRST PRESS A N CPM ENTER COUNTRATE IN CPM FROM RE2024C OR 2025C, THEN PRESS R/S l (5.5205 ENTER STACK FLOW RATE IN KCFM .FROM COMPUTER l S FLO KCFM POINT F885, THEN PRESS R/S 98. 6.38 8 00 C/SC 2r- OUTPUT IS IN CURIES /SEC Attachment 1 Page 2 of 9
19 AD 1827.10.11 B - IODINE RELEASE RATE This program calculates the iodine release rate in curies /sec from the stack. As input, it requires the countrate from the iodine monitors RE2024B, 2025B) at two different times and the time span between the readings. 11 FIRST PRESS B I CPM - ENTER TE INITIAL COUNTRATE FROM RE2024B OR h 2025B, TEN PRESS R/S T MIN - ENTER TE TIME SPAN BETWEEN READINGS, THEN PRESS R/S I CPM ENTER TE FINAL COUNTRATE FLOW RE2024B OR 2025B, G.56 06 THEN PRESS R/S 1.9243116-03 C/SC > OUTPUT IS IN CURIES /SEC C - PREDICTED OFFSITE DOSE RATES - NOBLE GAS This program calculates the whole body dose rates due to noble gases at various distances from the station. Required inputs are wind speed, stability class, and noble gas release rate. Note that stability class input is numerical with A=1, B=2, C=3, D=4, E=5, F=6. 11 FIRST PRESS C WND SP MPH - ENTER TE WIND SPEED IN MILES PER HOUR, THEN h PRESS R/S ST'BCL ENTER TE STABILITY CLASS (NUMERICAL VALUE), TEN PRESS R/S C/SEC ENTER THE NOBLE GAS RELEASE RATE IN CURIES /SEC,
. THEN PRESS R/S 5.364 M/SC 7 THIS OUTPUT IS WIND SPEED IN METERS /SEC y PREDICTED N0BLE GAS CONCENTRATION AT 1 MILE IN 1.5462342-04 UC/C pCi/cc WBDR= y WHOLE BODY DOSE RATE AT 1 MILE IN MILLIREM / HOUR 5.1025727 00 MR/H Attachment 1 Page 3 of 9 l
o . 20 AD 1827.10.11 5.4712901-05 UC/C
- WBDR= SAME AS ABOVE 2 MILES 1.8055257 00 MR/H 2.616704-05 UC/C WBDR= SAME AS ABOVE AT 5 MILES ,
8.635123-01 MR/H 5.5902312-06 UC/C WBDR= SAME AS ABOVE AT 10 MILES 1.8447763-01 MR/H 2.3788218-06 UC/C WBDR= SAME AS ABOVE AT 20 MILES 7.8501119-02 MR/H D - PREDICTED OFFSITE DOSE RATES - IODINE This program calculates the adult and child thyroid dose rates due to iodine at various distances from the plant. Required inputs are wind speed, stability class, and iodine release rate. Note that stability class input is numerical with A=1, B=2, C=3, D=4, E=5, F=6. 11 FIRST PRESS D WND SP MPH ENTER WIND SPEED IN MILES PER HOUR, THEN PRESS R/S STBCL ENTER STABILITY CLASS (NUMERICAL VALUE), TEV 5 PRESS R/S
~C/SEC ENTER IODINE RELEASE RATE IN CURIES /SEC, THEN PRESS R/S 5.364 M/SC > THIS OUTPUT IS WIND SPEED IN METERS /SEC 4.6532438-08 UC/C g i ATDR= IODINE CONCENTRATION AT 1 MILE IN pCi/cc 5.1185682 01 MR/H CTDR= ADULT THYROID DOSE RATE IN MR/HR AT 1 MILE 1.0237136 02 MR/H CHILD THYROID DOSE RATE IN MR/HR AT 1 MILE l
i I l Attachment 1 Page 4 of 9
21 AD 1827.10.11 1.6465324-08 UC/C
- ATDR=
1.8111857 01 MR/H SAME AS ABOVE AT 2 MILES CTDR' 3.6223714 01 MR/H 7.8747204-09 UC/C ATDR=
- 8.6621924 00 MR/H SAME AS ABOVE AT 5 MILES CTDR=
1.7324385 01 MR/H 1.6823266-09 UC/C ATDR= 1.8505593 00 MR/H SAME AS ABOVE AT 10 MILES CTDR= 3.7011186 00 MR/H,,) 7.1588367-10 UC/C ATDR= 7.8747204-01 MR/H SAME AS AB0VE AT 20 MILES CTDR= 1.5749441 00 MR/H E - TEST ROUTINE C - THE PREDICTED OETSITE DOSE RATES - NOBLE GAS This program calculates the whole body dose rates due to noble gases at various distances from the station. The calculator will generate the input from this test run of routine C, so no additional input is needed. Compare your output with the printout listed below. TEST C=N G TEST RnUTINE C 11 PRESS E WND SP MPH 2 THE WIND SPEED IN MILES PER HOUR 1. STBCL p THE STABILITY CLASS E=5 (NUMERIC VALUE)
- 5. --
C/SEC y THE NOBLE GAS RELEASE RATE IN CURIES /SEC 1. 0.447 M/SC + THIS OUTPUT IS WIND SPEED IN METERS /SEC 2.9082774-04 UC/C --*- PREDICTED NOBLE GAS CONCENTRATION AT 1 MILE IN WBDR= pCi/cc 9.5973154 00 MR/H
- WHOLE BODY DOSE RATE AT 1 MILE IN MILLIREM / HOUR Attachment 1 Page 5 of 9 - c, 1
e
l
~
22 AD 1827.10.11 1.0290828-04 UC/C WBDR= SAME AS AB0VE AT 2 MILES 3.3959732 00 MR/H 4.9217002-05 UC/C WBDR= SAME AS AB0VE AT 5 MILES 1.6241611 00 MR/H 1.0514541-05 UC/C WBDR= SAME AS ABOVE AT 10 MILES 3.4697987-01 MR/H 4.4742729-06 UC/C WBDR= SAME AS AB0VE AT 20 MILES 1.4765101-01 MR/H 2nd, A' - TEST ROUTINE D - THE PREDICTED OFFSITE DOSE RATES - IODINE This program calculates the adult and child thyroid dose rates due to iodine at various distancee from the plant. The calculator will generate the input for this test run of routine D, so no additional input is needed. Compare your output with the printout listed below, a TEST D = IDN TEST ROUTINE D 11 PRESS 2nd, A'
=
WND SP MPH
- 1. .i THE WIND SPEED IN MILES PER HOUR STBCL
- 6. > THE STABILITY CLASS F=6 (NUMERIC VALUE)
C/SEC
- 1. > T [E 10 DINE RELEASE RATE IN CURIES /SEC 0.447 M/SC + THIS OUTPUT IS WIND SPEED IN METERS /SEC 6.7114094-04 UC/C - =% IODINE CONCENTRATION AT 1 MILE IN pCi/cc ATDR=
7.3825503 05 MR/H + ADULT THYROID DOSE RATE IN MR/HR AT 1 MILE CTDR= 1.4765101 06 MR/H ---!i> CHILD THYROID DOSE RATE IN MR/HR AT 1 MILE l 2.2371365-04 UC/C ) i ATDR= l l 2.4608501 05 CTDR= MR/H ) SAME AS AB0VE AT 2 MILES
)
! 4.9217002 05 MR/H \ J Attachment 1 Page 6 of 9
e 4, i. ,, s <. T i 23 AD 1827.10. 1 6.7114094-05 UC/C - - ATDR= 7.3825503 04 MR/H.' SAME AS ABOVE AT 5 MILES CTDR= 1.4765101 05 MR/H ' 2.4608501-05 UC/C , ATDR= 2.7069351 04 MR/H SAME AS ABOVE AT 10 MILES CTDR= . 5.4138702 04 MR/H' i s 1.1409396-05 UC/C ATDR= ., ; 1.2550336 04 MR/H SAME AS ABOVE AT 20 MILES CTDR= 2.5100671 04 MR/H 4 i P L 5 t s
,ic ,
,a t-i Attaclunent 1 /<
Page 7 of'9 y r
- E
~~
l a , _ _ c_ __ _
. s !. ,. .r
l l 24 AD 1827.10.11 11 CONDENSED INSTRUCTIONS FOR PERFORMING TI PROGRAMMABLE CALCIJLATOR DOSE CALCULjTIONS LOAD:
- 1) Turn on printer and calculator, then press; 1, 2nd, OP, 17 on the calculator, the calculator should display 879.09.
- 2) Press "1" and "+/ ", load side 1 NOTE: If the calculator read the card properly, the (-1) will be shown in the display.
- 3) Repeat step 2, pressing the corresponding number for side 2, 3, and 4
- 4) Press,either ":U or "B"; then press "E" and then "2nd A'" below, to test the program of errors (compare your printout with the one listed with this procedure).
PRESS "A" FOR NOBLE GAS RELEASE RATE 11 Enter: Countrate from RE2024C or 2025C, Press R/S Enter: Stack flow in KCFM, Press R/S _ Output: Noble gas release rate in curies /see PRESS "B" FOR IODINE RELEASE RATE 11 Enter: Initial countrate from RE2024B or 2025B, Press R/S Enter: Time between readings, Press R/S Enter: Final countrate from RE2024B or 2025B, Press R/S Outpat: Iodine release rate in curies /sec PRESS "C" FOR WHOLE BODY DOSE RATES FROM NOBLE GASES 11 Enter: Wind speed in miles per hour, Press R/S Enter: Stability class *, Press R/S Enter: Release rate in curies /sec, Press R/S Output: Wind speed in meters /sec Output: Noble gas concentration in pCi/cc and whole body dose rate in L mr/hr at 1, 2, 5,10, and 20 miles PRESS "D" FOR THYROID DOSE RATES FROM IODINE l 11 Enter: Wind speed in miles per hour, Press R/S l Enter: Stability class *, Press R/S Enter: Release rate in caries /sec, Press R/S Output: Wind speed in meters /sec Output: Iodine concentration in pCi/cc, adult thyroid dose rate in ar/hr and child thyroid dose rate in mr/hr at 1, 2, 5, 10, and 20 miles
*Use numerical value for stability class: A=1, B=2, C=3, D=4', E=5, F=6 Attachment 1 Page ~ 8_ of 9 t-
+
25 AD 1827.10.11 PRESS "E" TO TEST "C" FOR WHOLE BODY DOSE RATES FROM NOBLE GASES Enter: No Data Input is needed 11 Output: Whole body dose rate in mr/hr, compare with data on page 5 of 9 PRESS "2nd, A'" TO TEST "D" FOR THYROID DOSE RATES FROM IODINE Enter: No Data Input is needed 11 Output: Adult and child thyroid dose rates, both in ar/hr, compare with data on page 6 of 9 1 i 4 Attachment 1 Page 9 of 9
- - , , . . ~ . s-,.
J 26 AD 1827.10.11 Instructions For Accessing DEC PDP 11/03 For Meterological Data
- 1. Turn phone accessed data terminal on.
- 2. Ensure unit is in ready mode (Press the LOCAL / TALK button on Model 43 terminal).
- 3. Check three options:
a) PARITY - off b) DUPLEX - fu.'l c) BAUD - 300 or 30 CPS
- 4. Dial phone number 898-6240 (Oak Harbor). When the frequency tone is heard, press the DATA button on Model 43 terminal or insert receiver into the acoustic coupler on other models.
- 5. Correspondence between Computer and Terminal Operator:
- a. Computer will type: WHO ARE YOU? ,
- b. Type in: t (an up arrow)
- c. Computer will type: H = HR, M = MIN, C = CAL
- d. Type-in: ' H, M, or C (Type only one for either hourly, minute or cal-ibration check)
Type "H" to request data, by hourly intervals, for the date specified. Type "M" to request data, by 15 ! minute intervals, for the date specified.~ Type "C" to request calibration check (not normally used)
- e. Computer will type: ACCESSED COMPUTER.
TYPE JULIAN DATE REQ.
- f. Type in: Three digit Julian date (e.g.
001, 072, 365)
- g. Computer will print TRANSMISSION COMPLETE.
out data requested and ALL DONE?...Y or N then type: Attachment 2 Page 1 of 3
27 AD 1827.10.11
- h. Type in: N (if more data is needed, then proceed through steps c g again),
or
- i. Type in: Y (if no further data is needed)
- j. Computer will type: TERMINATING COMMUNICATION.,
GOOD DAY
- k. Hang up the phone and turn the terminal off, as required.
c Attachment 2 Page 2 of 3
a i l 28 AD 1827.10.11 Sample Output of Meteorological Data (While Accessing DEC PDP 11/03) For Technical Specification 4.3.3.4 Elev 821' wind speed Elev 821' wind direction Elev 612' wind speed Elev 612' wind direction
\'\/ \/ \Y Elev 821'-612' temperature differential REV2 <--100M---><---755---><---10M---><100M)<75n><-TEMPERATURE->< PRE ><SSSDDADS HR:MN US UD SD US UD SD us UD SD DT DT AMB 100DU 10DU CIP DDDFFPun 1: 27.7 2.,24.4 3. 13.0 7. 0.1 30.6 15.4 1 0 195. 202. 196. 0.0 11.7 0.00 1 0 2: 26.8 2. 23.4 2. 12.6 7. 0.3 31.5 17.0 1 0 199. 204. 196. 0.0 13.4 . 0.00 1 0 3: 25.3 2. 21.7 2. 10.4 7. 2.0 31.7 18.9 1 0 210. 213. 196. 1.1 15.5 0.00 1 0 4: 27.6 3. 24.4 3. 13.9 6. 0.5 35.8 19.7 1 0 220. 227. 215. 0.4 17.5 0.00 1 0 5: 31.'O 3. 27.9 3. 17.5 6. -0.1 37.1 20.7 1 0 221. 228. 216. -0.0 19.5 0.00 1 0 6: 32.2 3. 2?.2 3. 18.5 5. -0.3 37.6 23.4 1 0 222. 230. 219. -0.1 22.5 0.00 1 0
~7: 34.3 3. 31.5 3. 22.9 4. -0.7 37.9 26.3 1 0 230. 238. 227. -0.5 25.8 0.00 1 0 8: 31.6 3. 29.0 3. 20.7 4. -0.4 36.4 28.2 1 0 236. 245. 235. -0.1 28.0 0.00 1 0 9: 31.3 3. 29.0 3. 21.2 4. -0.5 35.3 28.8 1 0 241, 250. 239. -0.3 28.6 0.00 1 0 10: 29.2 4. 27.4 4. 20.5 5. -1.1 35.2 29.1 1 0 256. 265. 255. -0.8 28.7 0.00 1 0 11: 27.2 3. 25.6 4. 19.2 5. -1.2 35.0 29.1 1 0 256. 264. 254. -0.8 28.7 0.00 1 0 12: 28.0 4. 26.7 4. 21.1 4. -1.2 34.2 29.1 1 0
~ 248, 257. 246. -0.9 28.6 0.00 1 0 LEGEND l
HR:MN hour, minute (Eastern Standard NOTE: Data for PDP 11/03 is Time) read from the Met Tower 100M 100M elev (917') and stored for three l 75M 75M elev (821') days only. If Met Tower i 10M 10M elev (612') is down, only previous WS wind speed (MPH) information can be WD wind direction (degrees) accessed. SD standard deviation l DT differential temperature *F amb ambient dry bulb temperature *F DW dewpoint temperature 'F l precip precipitation Attachment 2 END Page 3 of 3
i l l l [ AD 1827,11 . l . l l Davis-Eccce Nuclear Preer Station i l 1 l Unit No. 1 Administrative Procedure AD 1827.11 Assembly, A:counhhility ard Subsequent Evacuation jg . W " Record of Approvsl and Changes Prepared by R. P. Wathen/W. H. Green 12/29/75 Date
. Subnitted by D. W. Briden 5/12/76 Section Maad Date Reco=: ended by Jack Evans 5/25/78 SRB Chairman Date NA QA Approved Manager of Q2ality Assurance Date App- oved by, Jack Evaas 5/25/78 Station Superintendent Date Revision SE3 qp S ta . S ue t .
No. Reco ::stadation Date Approved Date Approved Date e ewr .o 4 #*vom /a/;/;-, pgs , apys, a.9
. - sem 3 ,a m alale2Lol)4t/p,Ho. romin,p In po g pin c r 3 4 M L ilnlu w " ~ a d' '
l l
i l l 2 1 AD 1827.11.3
- 1. PURPOSE & SCOPE 1
)
The procedure establishes measures and actions to affect the prompt and orderly assembly of and accounting for personnel located at the Davis-Besse Nuclear Power Station and subsequent evacuation of the 3 station if conditions warrant. Personnel covered by this procedure are TED employees, onsite suppliers / contractors, visitors, or any other individuals within the owner controlled area at the time an emergency is declared.
- 2. REFERENCES 2.1 10 CFR 50, Appendix E, " Emergency Plans for Production and Utilization Facilities" 2.2 Davis-Besse Nuclear Power Station Emergency Plan 2.3 AD 1808.01, " Emergency Duties" 2.4 ,
'AD 1808.04, " Personnel Identification" 2.5 AD 1808.08, " Access Control" 2.6 AD 1808.11, " Security Inspection Procedures" 2.7 AD 1808.12, " Vehicle Control Procedures" 2.8 AD 1827.01, " Annual Radiation Emergency Medical Exercise" 2.9 AD 1827.10, " Emergency Offsite Dose Estimates" 2.10 AD 1827.12, " Protective Action Guidelines" 4
2.11 AD 1827.13, " Containment Evacuation" 2.12 EI 1300 Series, Davis-Besse Emergency Plan Implementing Procedures
- 3. ORGANIZATION AND RESPONSIBILITIES The DBNPS Organization for coping with emergencies is described in the DBNPS Emergency Plan and Implementing Procedures. Specific 3 responsibilities for hau ? ling assembly and/or evacuation are des-cribed as follows:
3.1 The Shift Supervisor on duty is the interim EDO when an emergency condition exists until relieved by the designated EDO. , 3.2 The Shift Supervisor /EDO is responsible for controlling the orderly evacuation of personnel. 6 e
e 2 AD 1827.11.4 3.3 Descriptions of the types of emergencies that can require , assembly or station evacuation are described in the DBNPS Emergency Plan.
- 4. ASSEMBLY AREAS Definition Those areas designated by this procedure or other procedures to garner personnel resources or to serve as a collection point for performing personnel accountability.
Personnel with Emergency Response Functions shall respond as directed by the Emergency Implementing Procedure, EI 1300 series. Personnel not assigned Emergency Response Functions shall proceed to the following assembly areas (refer to Enclosure 1 & 2). 4.1 Protected Area Six areas have been designated as assembly areas within the protected area. 4.1.1 4th floor Turbine Building
- a. Two areas in the Turbine Building have been designated assembly areas (see Enclosure 3).
- b. The area directly adjacent to the Operations Support Center (Lunchroom) is designated for 4 on-shift Fire Brigade Teams (FBT's), First Aid Teams (FAT's), and Radiation Monitoring Teams (RMT's (excluding C&HP members).
- c. Office personnel and staff ,(clerical, TED management, and QC) should assembly on the
,, east side of the turbine by the train bay.
- d. Only FBT leaders, FAT leaders, and RMT leaders should aasemble in the OSC along with the OSC manager and his support personnel.
4.1.2 Health Physics Monitor Room (603' level)
- a. All C&HP personnel no.t assigned specific
. emergency duties should assemble in the Health Physics Monitor Room. 4.1.3 I&C Lab (623' level)
- a. All I&C personnel not assigned' specific l emergency duties should assemble in the I&C Lab.
3 AD 1827.11.3 4.1.4 Maintenance Shop (585' level)
- a. All Maintenance personnel not assigned specific emergency duties should assemble in the Maintenance Shop.
- b. All Station Service personnel should assemble in the Maintenance Shop. .
4.1.5 Fab Shop (Service Bldg. #6) (refer to Enclosure 1)
- a. All contractor employees will assemble in the Fab Shop.
4.1.6 PPF
- a. Security personnel without specific emergency duties should report.to the PPF.
NOTE: All visitors should assembly 1 with their escorts and any miscellaneous personnel should assemble on the turbine deck in the area designated for the office personnel. 4.2 Cwner Controlled Area Outside of the Protected Area, personnel should assemble in Service Bldg. #2 (Weld Shop), the Construction Office Building, the Warehouse / Storeroom 33, or the Davis-Besse Administration Building. Personnel located outdoors should report to the closest assembly point. 4.3 Alternate Assembly Areas 4.3.1 Alternate assembly areas shall be designated when conditions warrant by the Shift Supervisor or EDO utilizing the Station Gai-tronics (PA system) and/or security vehicles' PA systems. 4.3.2 During off-normal hours (6 p.m. - 8 a.m.), the facilities outside of the protected area are not normally manned. Therefore all personnel with the exception of those in the DBAB, shall report to the PPF, second floor. NOTE: The Nuclear Security Supervisor should also assign a roving patrol as necessary l i
4 AD 1827.11.3 to announce any subsequent personnel actions that may be required for those individuals located at construction work areas, warehouses, valve stations, the fire training area, or trailers, etc. Announcements should be made through the
. use of bull horns or PA system equipped on the Security vehicles.
- 5. ACCOUNTABILITY The following actions should be initiated at the declaration of a Site or General emergency or as directed by the EDO or Shift Supervisor at lower classifications.
5.1 All personnel should assemble as per Section 4 of this procedure. 5.2 The Nuclear Security Supervisor should assign an individual to contact facilities outside of the protected area to , inform them of the classification and actions to be taken t as per the EDO or Shift Supervisor. l l 5.3 If accountability of the protected area is requested, the ! Nuclear Security Supervisor should perform or direct the CAS Operator to perform an accountability check. 5.4 Within the Protected Area 5.4.1 The senior man present at each assembly area should make a roster of personnel present. 5.4.2 Rosters should be completed as quickly as possible and forwarded to the OSC. l l 5.4.3 The OSC manager will compare assembly rosters with the computer accountability printout to confirm and/or identify accountability problems l within the protected area. (Refer to 1827.16, Search & Rescue if necessary.) l 5.4.4 Once accomplished, accountability may be maintained l by the following guidelines:
- a. Limit travel throughout the protected area.
. b. Evacuate all unnecessary personnel.
- c. Limit access to the protected area only to l those individuals with emergency response
l 5 AD 1827.11.3 functions or to those individuals needed to perform actions to mitigate or terminate the emergency situation. 5.4.5 In the event that the security computer is not functional, accountability may be accomplished by the following method:
- a. The Nuclear Security Supervisor is responsible for performing a manual accountability check.
- b. As many security personnel as available will check the card racks located in the PPF for missing cards.
- c. Visitors log books will also be checked.
- d. This list of personnel will be sent to the OSC manager for comparison with the assembly rosters.
5.5 Outside the Protected Area accountability will be attempted utilizing the following guidelines: 5.5.1 Warehouse / Storeroom 33
- a. If assembly is required, personnel should assemble in the office area.
- b. The Storeroom Foreman or his alternate should be contacted for information receipt and dissemination or for performing accountability within the storeroom.
5.5.2 Weld Shop (Service Bldg. #2)
- a. If required, personnel in the area of Service Bldg. #2 should assemble in the Weld Shop.
- b. The Welding Department Foreman or his alternate should be contacted for information receipt and dissemination or for performing accountability l within this area.
5.5.3 COB
- a. If required, personnel should assemble in the lunchroom area located on the first floor.
1 6 AD 1827.11.4 4 b. The Facility Modifications Manager or his alternate should be contacted for informa- 1 tion receipt and dissemination or for perform- l ing accountability within the COB. I 5.5.4 DBAB
- a. If required, personnel should assemble in the lunchroom located on the second floor.
4 b. If the Emergency Control Center or Technical. Support Center located on the first floor are activated, personnel located in these areas need not assemble in the lunchroom.
- c. The DBAB Facilities Services Manager or the DBAB Office Services Supervisor should be contacted for information receipt and dissemination or for performing accountability within the DBAB. .
5.5.5 Results of accountability checks outside.the 4 protected area will be relayed to the EDO by phone on ext. 210 or 478. NOTE: Number for personnel to be contacted can be found in Section X of Admin. Memo 37.
- 6. EVACUATION PROCEDURES 6.1 Limited Evacuation Procedures 6.1.1 Localized emergencies do NOT normally require a general evacuation, however, conditions such as
! explosion, fire, toxic gas release, or radioactive material spills or leakage may require that personnel leave a specific building or area. Instructions or directions will be either announced over the PA system (Gai-tronics) or disseminated in the assembly area. 6.2 A limited evacuation will require personnel involved with the emergency to leave the area or building by the near-est safe exit and assemble as directed by the Shift Supervisor. 6.3 In case of a limited evacuation, evacuees will NOT leave l the protected area unless released by their supervisor and shall maintain a safe distance away from the emergency scene and roadway to allow for safe passage and access by emergency equipment.
7 AD 1827.11.4 6.4 In the event of limited evacuation of site buildings or areas, evacuees will NOT leave the Owner Controlled Area unless released by their supervisor and shall maintain a I safe distance away from the emergency scene and roadway to ' allow for safe passage and access by emergency equipment.
- 7. GENERAL EVACUATION PROCEDURE 7.1 If the announcement for a station evacuation is made, visitors and station personnel NOT assigned Emergency Response Functions wil1~ proceed out of -buildings follow-ing the evacuation plan (Enclosure 1) to the PPF for evacuation from the station unless otherwise directed. In the case of non-radiation emergencies or exercises, security badges and TLD's shall be collected by security as personnel pass out the gate. When personnel may have been exposed to radiation, they will keep assigned monitoring devices until they have been checked by C&HP personnel at the DBAB l '
Radiological Testing Laboratory, or other designated locations. Evacuated station personnel and visitors will be directed to leave by the main access road via their private automobiles to their home or designated assembly point to await instructions from the EDO. The hard surface roads, State Route 2, Duff Washa, and State Route 19 may be used for evacuation away from the site proper, 4l if a General Emergency is declared (see Enclosure 4). I a 7.2. Station personnel who are required to remain in the station to perform emergency duties shall remain in their
; designated areas, for direction, subsequent evacuation or to assume emergency duties. If directed to evacuate, station personnel will proceed to depart the building (s) following the nearest safe evacuation route unless other-wise notified (see Enclosure 1 and 2).
7.2.3 Nuclear Security Force
! 7.2.3.a The Security shall be responsible for directing personnel leaving the protected Area during the general evacuation. In-an emergency, the security officers may bypass normal procedures for the exit of employees and visitors, except that personnel should be monitored for con-tamination. PEE Security Officers shall remain on post and maintain communications with the Shift Supervisor in o
m
..,a 9 m. ., ~g .,. g . . ,. ~ .m. , , - - ,,-s. .- - m -
8 AD 1827.11.3 the control room and the EDO in the ECC, until relieved. Other security officers shall open gates as necessary. 3 7.2.3.b The Security Force, under the direction of the Nuclear Security Supervisor, shall perform the following:
- 1. Open Protected Area gates as necessary for evacuation while maintaining security of opening in accordance with AD 1808, Industrial Security Plan.
- 2. Direct evacuees to a safe area upon exit through the protected area gates.
- 3. Ensure personnel are monitored for contamination unless directed by the EDO, Shift Supervisor, or senior staff member to eliminate monitoring.
- 4. Direct traffic as needed in the parking area.
- 5. Direct all personnel leaving the station to proceed either di'rectly away from-tbe station 3 or to a selected assembly point. (Ascertain the assembly point from the Shift Supervisor /EDO).
- 6. Notify the Operations Support Center of the number of personnel within the protected area.
- 7. Collect all dosimeters and TLD's from evacuating personnel for evaluation and/or further use.
l 8 9 AD 1827.11.3 3 8. Proceed to the DBAB Radiological Testing Lab with the dosimeters and TLD's upon notification to do so by the Shift Super-visor /EDO. 3 9. The Security shall maintain surveillance over protected area gates or fences during and after the evacuation to prevent unauthorized access. As soon as possible, unless a radiation hazard exists, all opened and/or unguarded gates shall be closed and secured according to AD 1808.08, " Access Control". Emergency vehicles shall be controlled during the emergency and evacuation in accordance with AD 1808.12, " Vehicle Control Procedures". 3 7.2.3.c The Security Officers.shall NOT:
- 1. Delay the evacuation.
- 2. Require those persons evacuating the station to sign the visitor's. log. ,
- 8. RE-ENTRY 3 8.1 The ELO and Station Operations Manager, under the direction of the Operations Director, have the joint responsibility for determining and declaring when an emergency situation
-is stable and the station is ready to be re-entered.
t 8.2 Re-entry of personnel shall be through the PPF entrances only according to normal procedures described in AD 1808.04, " Personnel Identification", and EI 1300.10,_ Re-entry. t i l t l i.
10 AD 1827.11.3 wl go = ~M t E8 58 41 t .4e
=Y ~
5 25 is w5 nrwAsh r d_ _ ( 1 d* r
~ '
k2 osw u. '
- g g{$= ,
/ < H > , i ~
! ; u : s 4
= , , c: m ,
e /< _
, ,... - . a l
>s
< :c, ie- /- - = y, -
o as il l s gg a we a ut. ,
. . w g =
4.g
, , -u
==a / 3 g\ u
. A. ) * =
, 'i
.@ 0 _ o j- y
>q
[i
' ) l x",, ,
)
I 9 e T a p
, ,, oj
- g. . " .. .4 3 * - ~ '
~
a "jl E 23.1 - _~ $ i h e/ m ,, l l c o o(
'i!E 4
x Pb cc C E" E l . 1 Davis-Besse Nuclear Power Station Limited Evacuation Chart-ENCLOSURE 1
g AD 1827.11.3
'2: Q _
f *
==
N
~
' =
"W ' '
=
[/. -L M I I I I % \ = ".r.5 :m5 - - I L J i! " 'd;r_ "' "' ' " ' ' ' " -Q- - 3 r -- 3 i
~'
it i F ( .g*
* (
Pond [
- w. _-.,
I, _. L, ' wa -. -- O s' .
*~ M .D M Nb Pond Warehouse
.---m Ek71 l l Ta
* .'N
- .NParkin O .E. P' -3 ',a
- e. '.v
. . . . ,. 2'.t, s,ms eond coot ma [; ---l ,] ' ' '
'o g.
l m g . .'.i2-
-( , -;p(
i , A j . Tower (- ^( - 'i , \ , Pond i
' % r - r n
. C3 J ,
- C ;
% r Heteorological n de h
- g.
.g; -
3
.'L, .
s 1' 2r - r O
!! seace a4.ca 2 DAVIS-BESSE NUCLEAR POWER STATION SITE ARRANGEMENT t
ENCLOSURE 2
. l 1
* [C
@eh-
$B p i
gah - I /
.yn ] ,
f ;p l gf t 1 h N,
=
jyi , 4
/ ' '
b' d ,-
)
- - b F A g n< ) S R F A T
, i ,
) f y l b n E B
M S
- 0 fQl',
i , E M ( T L E N f
/
- 3 .,. h B N
O +
,, F S a I R d '
~
J' T
, E P
- A F E d e / ' T M
R C I F F O
. f+ hh
/
O/ g ' f g?= J /
./ R E
,b -
,l E
N I G e S R SE RC N E 4 ' E EN
$ e )
A E D DA AN EE
,e }. U(W i r
L r N R h LT TI BA FM N
, : \' . 4
9 6 t 13 AD 1827.11.4 ENCLOSURE 4 , d I I
~
G
~
3 . A \ --
. . i -
O i
- = .=
- l
~ ~
'/
== 4- .
-h a3 N =5:QvN
~
~
. " .3
===% =lr-
.% s .,,: ' ,
- p'a .
7
. w,
>=
=
/\
, /
[ .
~~" "
s,, b s , t 2, i*
* , a 3
g l l i 9P eE '
-. ---.t w .
i
~
s
. , , , - -.I j
j . 1 - l e /
~
'AD 1827.12 Davic-Bosse Nucicar Po.ier Station Unit No. 1 Administrative Procedure AD 1827.12 Protective Action Guidelines L ,
Record of Approval and Changes Prepared by C. Doyel/W. Green 2/27/76 Date Subnitted by E . Ld . 3 /11 /'7 6 Seaflon llaad Date Recou: mended by ' - I SRB Chairman Date QA Approved - AMA- / M ' V } ger - uality'ATsurance Date Approved by '
. /d d
~ Wa'Eion Superintendent bate Revision SRB QA Sta. Supt.
No. Re c:::=en' fon Date Approved Date Apprev Date 3 via t 4 r(p ,to / + in<nE dm , , gc'"-in
$ '96 b',y ,
2 u 44g is/ze/ 27 3 A Y 3/77 ,,.n.,., f p WWh caC ' , uho Elu /* f g psy ppo c.. a pr W /n rom
'" % 'I'*/
f 3. o e.,A 4/16 /s3 J 6 iz- S i P '*- J 'I'r/at rj p2 _5 3)< *] s' M $3htk2- T W "/lM N/ > l g p ., ogg saApe2hht vee g ,a. ,oj,,j n c.ua(t/M niitt= v m "3 */n- '"
1 AD 1827.12.6
- 1. PURPOSE To define a specific set of guidelines to be followed in determin-ing protective actions to be taken in the event of emergencie:
involving radioactivity releases at the Davis-Besse Nuclear Power Station (DBNPS).
- 2. REFERENCES 2.1 10 CFR 20, Standards for Protection Against Radiation 2.2 10 CFR 100, Reactor Site Criteria 6 2.3 USAEC TID-14844, Calculation of Distance Factors for Power ij and Test Reactor Sites 2.4 AD 1808.00, Industrial Security Plan 2.5 Davis-Besse Nuclear Power Station Emergency Plan 2.6 AD 1827.10, Emergency Off-Site Dose Estimates 2.7 SAND 77-1725, Public Protection Strategies for Potential Nuclear Reactor Accidents - Sheltering Concepts with Existing Public and Private Structures 2.8 EPA Guidelines - September 1975, EPA-520/1-75-001 2.9 U.S. Food and Drug Administration, Federal Register, Vol.
43, No. 242, Dec. 15, 1978 2.10 Reg Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the purpose of Evaluating Compliance with 10 CFR Part 50 Appendix I
- 3. DEFINITIONS 6 3.1 Decision Dose 4
That value of projected thyroid dose above which evacua-tion is beneficial. l 3.2 Evacuation Dose That dose that a potential evacuee would receive if he j were openly exposed during the evacuation. 3.3 Evacuation Exposure Period The period during which the evacuee is exposed to the radioactive plume. l h
2 AD 1827.12.7 3.4 Off-Site The area outside the Owner Controlled Area as defined in AD 1808.00, Industrial Security Plan. 3.5 Projected Exposure Time That period of time in which the population surrounding DBNPS will be exposed to radiation as a result of an accidental airborne radioactive release. Projected Exposure Time starts when the airborne radioactivity released crosses the Owner Controlled Area Boundary and ends when radiation levels off-site return to normal. 3.6 Sheltering Dose That dose that an individual would receive if he were to remain within a shelter having ventilation control during the passage of the plume. The method of calculating the sheltering dose is significantly different for the whole body and thyroid dose. This is because a ventilation controlled shelter, i.e. door, windows and ventilation shut, provides thyroid protection for only two hours. After two hours the inhabitant receives the full thyroid dose. For the whole body exposure there is no limit on the resident's time in the shelter.
- 4. RESPONSIBILITIES 4.1 In the event an emergency is declared at DBNPS that involves the release of radioactivity or radiation, the Emergency Duty Officer (EDO) and his assisting personnel shall use the calculating methods found in AD 1827.10, Emergency Off-Site Dose Estimates, to calculate the t instantaneous radiation exposur~e rates for variou~s offsite i
locations. (In the event of an emergency during off-normal hours, this calculation is the responsibility of the Shift Supervisor while acting as EDO until such time as he is relieved by the EDO.) ! The results of these calculations should be utilized as i specified in Section 6. for evacuation and shelter recom-l , i mendations, and compared with the guidelines given in l j Sections 5. and 7. to determine the proper protective l actions required to protect the health and safety of l 7: Station personnel and the general public. However, in the event that time does not permit the use of the Section 6 l Data Sheets (i.e., if the plume is moving relatively fast l towards the public and especially large population centers),
; protective actions should be based on an immediate com- , parison of the dose projections calculated in AD 1827.10 ; with the criteria given in Section 5.1 of this procedure.
3 AD 1827.12.7 The EDO shall then implement those actions for Station personnel and communicate the recdamended off-site actions to the Ottawa County Sheriff's Department (or the State and County Emergency Operations Centers if they have been activated), t 4.2 In order to simplify evacuation instructions for the public, evacuation " subareas"'(see Figure 1) have been - established by municipal and geographical boundaries. When making evacuation decisions in an emergency.situa-tion, the EDO shall consider the time available (based on. plume travel speed) to evacuate the affected subarea (s), in comparison to the estimated evacuation times as given ,
; in Table 1. The data sheets used in Section 6. assist in this process.
- 5. PROTECTIVE ACTION GUIDELINES 7 5.1 Recommended Protective Actions for the Plume Exposure l Pathway (10 mile) Emergency Planning Zone to avoid whole 4
body and thyroid dose from exposure to a gaseous plume: , Projected Dose (Rem) to the Population Recommended Actions (*} Comments
! Whole body <1 Noplannyg) protective Previously actions. Issue an recommended Thyroid <5 advisory to seek protective shelter and await actions may further instructions. be recon-Monitor environmental sidered or
,, radiation levels. terminated.
Whole body 1 to <5 Seek shelter as a min- If con-imum. Consider evacu- straints ation. Evacuate unless exists, Thyroid 5 to <25 constraints make it special-impractical. Monitor considera-environmental radia- should be tion levels. Control given for access. evacuation of children
- and preg-nant women.
Whole body 5 and above Conduct mandatory Seeking i evacuation. Monitor . shelter environmental radia- would be an Thyroid 25 and above tion levels and adjust alternative area for mandatory if evacua-evacuation based on tion were these levels. not immedi-l- Control access. ately pos-l sible.
4 AD 1827.12.9 (a) These actions are recommended for planning purposes. Protective action decisions at the time of the incident must take existing conditions into con-sideration. (b) At the time of the incident, officials may implement low-impact protection actions in keeping with the principle of maintaining radiation exposures as low as reasonably achievable. 5.2 Guidelines for . protection against ingestion of contamina-tion for the Ingestion Exposure Pathway (50 mile) Emergency Planning Zone: I. Ground Contamination A. Action Levels 9 1. Projected whole body dose above the ground 21 rem
- 2. Ground Contamination levels 22000 pCi/m2 at t = 1 hr post-accident
- 3. Exposure rate 212 mR/Hr at 1 meter above ground at t = 1 he post-accident Recommended Protective Actions B.
- 1. Evacuation of affected areas
- 2. Restriction of entry to contaminated off-site areas until radiation level has decreased 'to State approved levels II. Food and Water Contamination A. Action Levels Concentration in Milk or Water (0.5 (5 rem WB rem WB .
or bone: or bone: Total Intake 1.5 rem 15 rem via all Pasture thyroid) thyroid) Food & Water Grass Preventive Emergency Pathways (Fresh Weight) Level Level Preventive Emergency Preventive Emergency Nuclide* (pCi/1) (pCi/1) (pCi) (uci) (pCi/kg) (mci /kg) I-131 (thyroid) 0.012 0.12 0.09 0.9 0.27 2.7
- If other nuclides are present, Reg. Guide 1.109 will be used to
9 5 AD 1827.12.7 calculate the dose to the critical organ (s). Infants are the critical segment of the population Concentration in Milk or Water (0.5 (5 rem WB rem WB or bone: or bone: Total Intake 1.5 rem 15 rem via all Pasture thyroid) thyroid) Food & Water Grass Preventive Emergency Pathways (Fresh Weight) level Level Preventive Emergency Preventive Emergency Nuclide* (pCi/1) (pCi/1) ( Ci) (pCi) (pCi/kg) (pCi/kg) Cs-137 (Whole Body) 0.34 3.4 7.0 70 3.5 35 Sr-90 (bone) 0.007 0.08 0.2 2.0 0.7 7.0 Sr-89 (bone) 0.13 1.3 2.6 26 13 130 B. Recommended Protective Actions Preventive Emergency 4
- 1. Removal of lactating Isolate food and water dairy cows from con- from its introduction taminated pasture and into commerce after substitution of uncon- considering:
taminated stored feed.
- 2. Substitute source of a. availability of uncontaminated water. other possible
- 3. Withhold contaminated actions; milk from ma-ket to b. importance of par-allow radioactive decay. ticular food in
- 4. Divert fluid milk to nutrition; production of dry whole c. time and effort to milk, butter, etc. take action;
- d. availability of other foods.
7 5.3 Representative shielding factors from airborne radio-nuclides: Structure or Loestion Shielding Factor (,) Representative Range Outside 1.0 --
'o fr me house ( 0. --
(no basement)
1:5; 6 AD 1827.12.7 l l Shielding Structure or Location Factor g) Representative Range - Basement of wood house 0.6 0.1 to 0.7(c) Masonry House (co base- 0.6 0.4 to 0.7(C) ment) - Basement of masonry house 0.4 0,1 to 0.5(*) g Large office or indus- 0.2 -0.1 to 0.3(c, d) trial building (a) - The radio of the dose ~ received inside the structure to the dose that would be received outside the structure. (b) A wood frame house with brick or stone . veneer is approximately equivaler.t to a masonry house for shield . . ing purposes. ' (c) This range is mainly due to different'vall mate' rials and different geometries. (d) The shielding factor depends on where the perronnel .q. are located within the building (e.g., the basement or an inside room). L 7 5.4 Representative shielding factors for surface deposited , * . c, radionuclides: , s 4 Representative Structure or Location Shielding Factor (*} Representative Range'" I e above an infinite 1.00 -- smooth surface
~
~
1 m above ordinary ground 0.70 ./ , 0.47-0.85 "u ' l-m above center of 50-ft 0.55 . s 0.4-0.6 # . roadways, 50% decontam-inated
%)
\
y N , U Cars on-50-ft road: \x . % Road fully contaminated c 0.5 0 *,-0.7 Road 50% decontaminated 'O.5 s 0 ,. 4 -0 . 6 Road fully decontaminated 0.25, 0[.2-0.5 g, g .~ g - 3 Trains
~
0.40 i 0'.3-0.5 4 ,%-
. s.+iq 3 .
- 5
.o b
y g N .\ , s s , }~ g-l l
=t yv^ w - ,- -
R
7 AD 1827.12.9 Representativeg) Representative Structure or Location Shielding Factor Range One and two-story wood- 0.4(b) 0.2-0.5 frame house (no basement) One and two-story block 0.2(b) 0.04-0.40 and brick house (no base-ment) Hcuse basement, one or two 0.1(b) 0.03-0.15 , walls fully exposed: One story, less than 2 0.05(b) 0.03-0.7 1 ft of basement, walls exposed g) Two stories, less than 2 0.03 0.02-0.05 ft of basement, walls
~
exposed' Three- or four-story structures, 5000 to 1 10,000 ft 2 per' floor: g) First and second floors: 0.05 0.01-0.08 m Basement 0.01 ) 0.001-0.07 4S ,
'9l Milti-story structures,
>10,000 ft2 per floor:
Upper floors 0.01(b) 0.001-0.02 Basement 0.005(b) 0.001-0.015 (a) N - The ratio of dose received inside the structure to-the dose th'at would be received outside the structure. (D) Awayfromdoorsandwindows.
- s. i .
[h . 5.5 Distribution of Potassium Iodide' Tablets t -
- 1. The EDO $ill gecoamend St.ation personnel (who have no known tiiyroid prablems) to take a KI tablet if 9 known iodine concearation will exceed 1 x 10 g pCi/cc (a) the for greater than one hour, er (b) the total known dose to an adull.' thyroid will exceed 25 rems.
,,,, p. ,w 2. Base the; distribution of KI ca actual thyroid doses, "Ql
y ,5
%R l
1,
, ' not projected doses. 'K!;is 90% effective if admin-istered within on'e hour After the uptake, and 50%
~l'
, *%g
, x D [D hg effective if administered within 4 hours after i .7 ,
q I
- j. .
- m. uptake.
- 9 ,. 3+ s Call RDiS Corporation iE KI is administered for further I
\ , directions regarding usage.
4' .
,m g q f .
s t 4 f
.- . N(,
~
- f. 'r
, < \ ' J }, w 9 ( { w
,? g, g,.x w ~ .. ; . .
yy 4 .p g J s,j 'e __
.v- -__ . . . . _ - _ - .
3-
! \ ;
l
, l /
8- AD 1827.12.7
- 6. PROCEDURE '
6.1 Whole Body Dose " i Complete Data Sheet-1. i 7 6.2 , Thyroid Dose
- Complete Data Sheet.f. '
6.3 Protective actions sh uld be recommended as devele. ped by
. Data Sheet 1 and 2. /tditional guidance is as follows:
- / 'i EXAMPLES OF ACTIONS g ' ACCIDENT PHASE EX80 SUPE PATHWAYS TO BE RECOMMENDED
' , Inhalation of Evacuatioa, 2helter, EMERGENCY gases,_ radio- access ecacrol, res-
- PHASE 1 iodine,' or' par- piratory protection,
~
(0.5 to 24 hours)* ticulate prophylaxis (thyroid 6 1 protection) . l # Direct whole body Evacuation, shelter, exposure access control Ingestion of Take cows off pas-milk ture, prevent cows from drinking sur-face water, discard contaminated milk, or divert to stored
, products such as cheese INTERMEDIATE Ingestion of Wash all produce, or PHASE 2 fruits and impound produce, vegetables delay harvest until approved, substitute uncontaminated pro-duce
, Ingestion of Cut off contaminated water supplies, substitute from other sources,-
/ filter, desineralize (24 hours to ~J' Whole body expo- Relocation, decon-30 days)* sure and inhala- tamination, fixing g '.
tion of. contamination, deep plowina 1 Emergency phase - Time period of majbr release and ' subsequent plume exposiire. - 2 Intermediate phase - Time period of moderate con-tinuous release with plume exposure and contamination of environment. i
t
. 9 AD 1827.12.9 EXAMPLES OF ACTIONS ~
ACCIDENT PHASE FXPOSURE PATHWAYS TO BE RECOMMENDED
\
4 Ingestion of food Decontamination, and water con- condemnation, or
/ . taminated from destruction of food; LONG TERM the soil either deep plowing, con-PHASE 3 by resuspension dennation, or al-
- or uptake ternate use of land N through roots Whole body expo- Relocation, access sure from deposi- control, decontam-(over 30 days)* tion material or ination, fixing of inhalation of re- contamination, deep suspended plowing material 3 Long Term Phase - Recovery period. ;
1
* " Typical" Post-accident time periods. +
A
. . ~ , _
1 10 AD 1827.12.9 DATA SHEET 1 Evacuation vs Shelter Decision Guide For Whole Body Exposure .
- 1. Evacuation Subarea from Figure 1
- 2. Approximate Distance to Population of Interest (1, 2, 5, or 10 miles) miles
~ NOTE: Use the distance in which the projected exposure levels calculated in AD 1827.10 are above the Protective Action Guidelines given in Section 5.1. A data sheet should be calculated for each affected radii.
l 3. Calculate Whole Body Dose Rate: , 1 (D=MR/HR from Step 14, Data Sheet 1 of AD 1827.10, i Emergency Off-site Dose Rate Estimate)= mR/HR 9l 4. Release Duration (If not known assume 2 hrs.) 'ours h
- 5. Projected dose = dose rate x duration = Items 3 x 4 = REM 1000 1000 .
- 6. Wind Speed MPH Distance (item 2)
- 7. Plume Travel Time = Wind Speed (item 6) = hours
- 8. Time since, or till,-beginning of release.
- a. If release has begun:
Release has been in progress hours
- b. If release wit 1 h !d 1 ster:
Release will start in hours
- 9. Time till exposure begins:
- a. If release has begun:
Time = Item 7 - Item 8a = hours t . NOTE: Show minus sign in answer if ! Item 8a is greater than Item 7.
- b. If release will begin later:
Time = Item 7 + Item 8b = hours
- 10. Evacuation Weather Conditions:
i No rmal ~ Adverse Severe (Circle One)
, . , - _, ,_ y -
o r .m- , y -- - 4~ _ - , . - y -,
11 AD 1827.12.9 DATA SKEET 1 (Continued)
- 11. Use information from Items 1 and 10 to get Estimated Evacuation Time from Table 1. hours i
- 12. Exposure Time:
Item 11 - Item 9 = hours NOTE: If Item 9 is negative, keep in mind that minus a negative number gives a positive result. If Item 9 is larger than Ites 11, enter zero hours.
- 13. Evacuation Exposure Period (EEP)
Take the smaller of Exposure Time (Item 12) or Release Duration (Item 4) _ hours ] 14. Evacuation Dose = EEP hours x Dose Rate = (Item 13) x (Item 3) = REM 1000 1000
- 15. Sheltering Dose =
Projected Dose x Structure Shielding Factor (from 5.3) = REM NOTE: Since the housing ir. the 10 mile Emergency Planning Zone is basically wood homes, a structure shielding factor of 0.9 should normally be used.
- 16. Using the above information and following table, detarmine the protective actions to be recommended:
IF_ THEN
- a. Projected Dose (Item 5) less than a. NO ACTION 1 rem
- b. Sheltering Dose (Item 15) is greater b. Evacuate children 9 than 1 rem but less than 5 rem and women of child-bearing age if possible; shelter others
- c. Sheltering Dose greater than 5 c. - Evacuate if pos-rem, and Evacuation Dose (Item sible, otherwise
- 14) less than Sheltering Dose shelter
- d. Sheltering Dosa greater than 5 rem d. SHELTER and Evacuation Dose greater than or equal to Shelter Dose i
, - - - - . , . - y
N ' c
> g h $ e@E -
t ~ i c - E T A M gD E I 5 9
- s t s N @* -
eI I T S t i nt en d e 9 " E S1 u - id si ER r es MOE - Re Rs ITR $ t TCU = t EG s nl n NSI - e ae O F n ni a os I T A 0r m aa sn 5 h1 1 U e er 8 0 _ C P ST 07 e A o - - - V - - - PST E PST yT. Y E t K r p t t i s 8 0 1 7 n 5 5 oi t, a i s g' f 1 P 1 T _ f
' P, s
i r e
\
@ /
/ \
t t o n u t t t a u A t s
/ @ _ .
2
/.
/ @ 95 2 9 81 x a
/ - -
PS 797 5 o s
/.'O g ,87
[ ~ @ 735 821 PST
~
uaa on 4 3 9 4 00 2
/ - ~ - - -
7
/ k I! PST
/
NA4 , L ~ j < f h . t s e
- il l
~
~s
'on n
v t
@ 0 T
,,gl C_
t 5-7 y) _ Q .\d7 e h 07 ST 4
- - g d- _
j r u t, i.
" ,! J."".
u 'l ,L r t s
/
t u s i a.
13 AD 1827.12.8 TABLE 1 Evacuation Time Estimates Land Sub-Areas Population
- No rmal Adverse Severe **
1 2,781 2 hr. 55 min. 829 4 hr. 10 min. 829 15-20 hr. 2 2,681 3 hr. 5 min. 877 4 hr. 50 min. 877 30-40 hr. 3 10,706 3 hr. 35 min. 3,231 6 hr. 30 min. 3,231 35-45 hr. 4 608 2 hr. 50 min.
. 608 4 hr. 15 min.
608 10-15 hr. 8 5 4,934 3 hr. 30 min. 4,934 4 hr. 30 min. 4,934 40-45 br. 6 4,916 3 hr. 30 min. 1,518 5 h:. 10 min. 1,518 30-40 hr. 7 1,885 4 hr. 1,815 6 hr. 25 min. 1,815 50-60 hr. 5 hr. 15 min. TOTAL EPZ 28,511 13,812 10 hr. 55 min. 13,812 75-100 hr. Lake Sub-Areas Boaters Normal Adverse Severe 8 thru 13 Varies 4 hr. N/A N/A l Special Case Population Normal Adverse Severe Port Clinton 10,328 4 hr. 45 min. 8 7,223 6 hr. l 7,223 24-30 tur. l l
- Population varies due to location and transient resident variations due l
to season and unfavorable weather conditions.
** Time ranges are provided due to the uncertain nature of severe weather conditions (e.g., during a severe snow fall or blizzard, the time it takes
( to evacuate can vary depending on the direction and speed of the wind).
14 AD 1827.12.9 DATA SHEET 2 Evacuation vs Shelter Decision Guide For Thyroid Dose
- 1. Evacuation subarea from Figure 1
- 2. Complete Data Sheet 1
- 3. Release Duration from Data Sheet 1. Item 4 9 (If not known assume 2 hours) hours
- 4. Evacuation Exposure Period (EEP) from Data Sheet 1, Item 13 hours
- 5. Calculated Thyroid Dose Rate (Step 12, Data mR/HR Adult Sheet 2, AD 1827.10) mR/HR Child
- 6. Projected Thyroid Dose = Item 3 x Item 5 =
1 1000 REM Adult REM Child
- 7. Decision Dose is that value of Projected Thyroid Dose above which evacuation is beneficial. The Decision Dose depends on the Release Duration as follows:
Release Duration Decision Dose (hours) (rem) 2 75 3 45 . 4 38 5 34 6 32 8 30 12 28 24 27 above 24 25 Decision Dose = REM
- 8. Using the above information and following table, determine the protective actions to be recommended:
I.{ THEN
- a. Projected Thyroid Dose (Item 6) less a. NO ACTION than 5 rem
~.
15 AD 1827.12.7 DATA SEET 2 (Continued) E TEN
- b. Projected Thyroid Dose greater than b. EVACUATE 5 rem but less than 25 rem CHILDREN AND WOMEN OF CHILD-BEARING AGE IF POSSIBLE, SELTER OTERS
- c. Projected Thyroid Dose greater than c. EVACUATE IF 25 rem, but less than the POSSIBLE OR Decision Dose (Item 7) OTHERWISE SELTER ,
- d.
- Projected Thyroid Dose greater than d. Perform action Decision Dose, then as follows:
- 1. If EEP less than Release 1. EVACUATE Duration i 2. If EEP equal to Release 2. SELTER Duration s
f i l _E_ND 1 l l
i . AD 1827.13 - Davis-Ecsse l'uclear Power Station Unit No. 1 Administrative Procedure AD 1827.13 Containment Evacuation E Bt P4 p 4p B m a p
..J ,
Record of Approval and Changes Prepared by R. P. Wachen/W. H. Green 12/30/75 Date Submitted by b.ld.@dd w d/6/76 Section Head Date Recommended by O 6!7C SRB Chairt3an 'Date QA Approved NA hl)B - Mana r of-Th2a-lity Assurance Dat Approved by [ O
~ Station Superintendent '#Date/
Revision SRB QA Sta. Sept. No. Recom=endation Date Approved Date Approved Date hf$ hlhY D.f -'! W WM hfb 5- / y v. n m~_ - -- _
) &C= =g '/l'7/80 a1sjtn t {lugn~ porn -- lsriecIao y)n/n p - .q sIup; C0 nNkt rtyyv . _ sal 2, fh p 3_- y ~ilajtv U b l*1 h0lb W11 Th W " " - -
^& 7I
- 1Ik g p -_- g sjizjn c r34/Alvluja ws -n 4IviD i
l I i
4 1 AD 1827.13.6
- 1. PURPOSE & SCOPE This procedure sets forth the actions and measures which assure that Containment (the area enclosed by the Containment Vessel and the Shield Building) is safely evacuated by station personnel working inside, in case of emergency, or increase in radiation levels in i Containment beyond allowable levels. The procedure further describes actions which assure that decontamination of exposed and contaminated personnel is accomplished.
- 2. REFERENCES 2.1 10 CFR 50 Appendix E, " Emergency Plans for Production and Utilization Facilities" 2.2 DBNPS-FSAR, Appendix 13D, " Emergency Plan" Section 7.8, " Nuclear Instrumentation" Section 11.4, " Radioactive Waste Monitors" Section 12.0, " Radiation Protection" 2.3 SP 1104.21, " Containment Purge System Procedures" l 2.4 SP 1104.41, " Containment Vessel Hatches" 2.5 MP 1402.06, " Equipment Hatch Removal and Replacement" 2.6 HP 1601.01, " Guides and Limits for Exposure to Radiation" 2.7 HP 1601.04, " Radiation, Contamination and Airborne Radioactivity Areas" 2.8 HP 1601.03, " Radiation Exposure Permit Procedure" 2.9 HP 1602.01, " External Personnel Radiation Exposure Monitoring" 2.10 PT 5179.01, " Area Radiation Surveys" 2.11 PT 5179.02, " Contamination Surveys" 2.12 PT 5179.03, " Airborne Radioactivity Surveys" 2.13 HP 1604.01, " Personnel Decontamination Procedure" 6 2.14 AD 1827.11, " Assembly, Accountability & Subsequent Evacuation" 2.15 AD 1827.12, " Protective Action Guidelines"
- 3. ORGANIZATION AND RESPONSIBILITIES 3.1 Working Personnel
2 AD 1827.13.2 Containment evacuation is the responsibility of the personnel working inside the Containment. The personnel in the Containment shall take prompt action to remove themselves from Containment whenever the Containment Evacuation Alarm is sounded or their personnel monitoring equipment indicates that a dose limit has been reached or an excessive level of radiation or airborne activity exists. 3.2 Shift Supervisor 2 The supervision of the control room operation, particularly as regards radiological monitoring during work in Containment, is the responsibility of the Shift Supervisor. He.shall evaluate any changes reported by the Control Room Operator (CRO) and the Chemist and Health Physicist (C&HP) in order to; coordinate emergency activities relating to the evacuation of Containment. He is responsible for keeping the Station Superintendent informed of emergency conditions and announcing the location and nature of emergencies over the PA System. 3.3 Control Room Operator The constant monitoring of radiation conditions in Containment is the responsibility of the CRO, particularly when personnel are working inside containment. He shall evaluate changes in radiation levels detected by containment atmosphere detectors as well as out of core neutron instrumentation in order to be able to signal evacuation. 3.4 Work Supervisor / Foreman The leader or foreman of each work group present in Containment shall assure the evacuation of any or all personnel upon hearing evacuation alarms, or upon personal verification that excessive radiation levels exist. The working supervisor will normally be the last man out of Containment. 3.5 Chemist and Health Physicist (C&HP) The monitoring of radiation dose and exposure for all personnel working in Containment is the responsibility of the C&HP in accordance with HP 1602.01, " External Persennel Radiation Exposure Monitoring". As part of the personnel monitoring i program, REP and personnel dosimeters are issued by the C&HP to all personnel entering Containment in accordance with HP 1601.03, l " Radiation Exposure Permit Procedure". I i The C&HP will not monitor or check containment during reactor l operation due to the high neutron and gamma radiation levels. l With special permission of C&HP management, entry can be made into containment for very short periods of time, according to l l l I l l 1
3 AD 1827.13.5 the FSAR, Section 12.0, " Radiation Protection", to evaluate containment radiation levels in accordance with PT 5179.01,
" Area Radiation Surveys", PT 5179.02, " Containment Surveys," and PT 5179.03, " Airborne Radioactivity Surveys".
The C&HP is further responsible for the monitoring and/or decontamination of personnel after evacuation from Containment in accordance with Section 12.3 of the FSAR, HP 1602.01, " External Personnel Radiation Exposure Monitoring", and HP 1604.01,
" Personal Decontamination Procedures".
- 4. CONTAINMENT ACCESS
~
The following paragraphs describe the accesses to the Containment which may be used for evacuation with the limitations as noted. 4.1 Personnel lock - Elevation 603, southeast side of Containment. This is the normal access for personnel entering and leaving the Containment during operation and shutdown. The lock area has room for about ten persons with an automatic pressurization and purging system. Ref: SP 1104.41, " Containment Vessel Hatches". (See 5l Enclosure 1). _ 4.2 Emergency Lock - Elevation 585, northwest side of Containment. This exit is a 5' diameter pressurized vessel for emergency access only, for personnel working at level 585, and for personnel working at lower levels during shutdown. The lock area will facilitate only 2 or 3 personnel since the access doors swing inward. (See Enclosure 2.) 4.3 Equipment Hatch - Elevation 603, southeast side of the Containment. This hatch can be used for evacuation only during reactor shutdown when the hatch has been opened for equipment handling. The hatch is normally secured and locked and is removed and replaced in accordance with MP 1402.06, " Equipment Hatch Removal and Replacement". (See Enclosure 1.) 4.4 Mechanical Penetration Hatches (205A & 201B) - Elevation 565, east and west side of the Containment and (308A & 307A) - Elevation 585 - southeast and southwest sides of Containment. (See Enclosure 2 and 3). These doors provide access and exit to and from the annulus area only but do NOT provide access to the containment vessel, and are normally secured and locked. During shutdown or emergencies, these doors may be opened for access and shall be used for evacuation from the annulus area during these periods. Since the annulus may be a high radiation area during reactor operation, these doors can be opened only in emergencies and for short periods after purging in accordance with SP 1104.21, " Containment Purge System Procedure".
. 4 AD 1827.13.4
- 5. EVACUATION ALARM AND PROCEDLRE 5.1 Alarm Criteria 5.1.1 Manual System The control room operator shall monitor containment radiation instrumentation at all times during reactor operation as described in the FSAR, Section 12.0,
" Radiation Protection", whenever personnel are in Containment. He shall initiate the Containment Evacuation Alarm and announce verbally the extent of evacuation required when the following symptoms are verified:
- Alarm for high gamma radiation on any containment radiation monitors.
- High count rate in the source range instru-mentation ,
i
- Increasing count rate (3 dpm) in the criticality monitoring system during startup (refueling only)
- High radiation level in the gaseous / airborne monitoring instrument in the containment ventilation system.
4 NOTE: Operator needs to verify that the readings are valid before evacuating Containment. Setpoints will vary with plant conditions and age. 5.1.2 Automatic Alarm System , The affected radiation monitor will automatically sound an alarm outside the entrance to the personnel hatch or outside the entrance to the equipment hatch. The Control Room Operator will receive an alarm at the FDS/RMS Console CRT and Printer. The monitors also provide a readout in the Control Room and at the personnel / equipment hatch entrance for verifying l conditions. 5.2 Personnel Evacuation Procedure 5.2.1 Upon her-ing the Containment Evacuation Alarm, personnel will immediately lay down all work equipment, secure, open, or close any critical switches or valves and proceed to the personnel lock at level 603 and/or
l l l i 5 AD 1827.13.4 evacuate through the equipment hatch at level 603, if open. (See Enclosure 1). 5.2.2 Evacuation will commence immediately through the personnel lock which will be operated in accordance with SP 1104.41, " Containment Vessel Hatches". 5.2.3 The foreman / leader / supervisor present in each work group shall assure that his personnel have been accounted for and/or entered the personnel lock before the inner door is closed and secured. He shall leave Containment only when all of his personnel have been accounted for. 5.2.4 Upon exiting the personnel lock, all personnel shall proceed immediately to the Disrobing Area for a contamination check in accordance with HP 1602.01,
" External Personnel Radiation Exposure Monitoring".
At this time, the foreman / leader shall notify the control room by phone that Containment has been evacuated, and to await action by the C&HP personnel regarding their exposure and conditions in and around Containment,
,. 5.2.5 The emergency lock at level 585 may be used for evacuation only if the route to the personnel lock is cut-off or impassable. Procedure for use of the emergency lock is also described in SP 1104.41.
4 Personnel exiting by the Emergency Lock should stay in j that area until released by C&HP, notify the Shift Supervisor of their evacuation and the conditions inside Containment. (See Enclosure 2). p ' 5.3 control Room. Action . I 5.3.1 The control room operator monitoring an unsafe condition 4 in Containment shall:
- 1. Check the instrumentation readout (s) for supporting evidence of the condition.
- 2. Check the alarm for failure.
- 3. Upon confirming the emergency condition, initiate-the Containment Evacuation Alarm.
5.3.2 The control room operator, after the evacuation alarm sounds, shall take immediate action to correct the situation, reduce the radiation levels and restore the l l - ' __ _-- - - - - ------r ~ r - e "
6 AD 1827.13.6 station to normal conditions in accordance with the Emergency Implementing Procedures, EI 1300 series. 5.3.3 Notify the Shif t Supervisor, Station Superintendent or his designee and/or the EDO of the evacuation and reasons for the alarm. 5.3.4 Log all data pertaining to the evacuation includ-ing the reports verifying evacuation of affected personnel and conditions inside Containment. 5.4 Shif t Supervisor Action _ 5.4.1 Verify the conditions reported by the control room ope'r ator and announce the emergency over. the PA System. NOTE: Check Emergency Plan Activation, EI 1300.01 to ensure the proper emergency classification and the actions accordingly. 5.4.2 Determine if it is necessary to evacuate other areas 6 of the station in accordance with AD 1827.11, " Assembly, Accountability & Subsequent Evacuation." 5.4.3 Ensure that no one re-enters Containment until it has been determined safe by Chemistry & Health Physics personnel. 5.4.4 Coordinate and monitor station recovery activity in accordance with the Emergency Implementing Procedures, EI 1300 series, and applicable operating procedures and assure tha.t conditions are restored to normal in Containment. 5.5 Action of Radiation Monitoring Team 5.5.1 Report to the Health Physics Monitoring Room for instructions. 5.5.2 Survey area immediately adjacent to the Containment l personnel lock and other areas which were used for j evacuation as determined by the EDO and/or C&HP. 5.5.3 Check evacuated personnel for contamination in accordance with HP 1602.01, " External Personnel Radiation Exposure Monitoring," and decontaminate, as necessary, in l accordance with HP 1604.01, " Personnel Decontamination". l l 5.5.4 Report results of surveys and personnel monitoring to the C&HP or EDO and the control room for evaluation. l l
7 AD 1827.13.1 5.5 Action of Radiation Monitoring Team 5.5.1 Report to the Health Physics Monitoring Room for instructions. 5.5.2 Survey area immediately adjacent to the Con-tainment personnel lock and other areas which were used for evacuation as determined by the EDO and/or C&HP. 5.5.3 Check evacuated personnel for contamination in' accordance with HP 1602.01, " External Personnel Radiation-Exposure Monitoring," and decontami-nate, as necessary, in accordance with HP 1604.01, " Personnel Decontamination". 5.5.4 Report results of surveys and personnel mon-itoring to the C&HP or EDO and the control room for evaluation. e. I l l
- 1. , _ _
- l i
~
8 AD 1827.13.5 l CONTAINMENT AND AUXILIARY BUILDING ELEVATION 603' J NOTE: The Equipment Hatch shall j be used only when opened for , maintenance during shutdown. l l N - f . Mi'
/ a
-- m . _ .,. -m.-
m .m u- I . l O
- i li t k :- 1 l f
, i -
i - ti m / 12 9 \~ l l ri i
]i iU n s,I p
l
\\ Wes 10 1 1
, u m
,I l ' Personnel j j Lock
(< - - . . - - - . _ , ( \ l b j "1MC % a l Ti , l r j i
,n
. M li
,a Q"i Iii
.l .
M M ~ - j a t > I s [ ..
\
- i
_.a 3 -r-
'; ......7, i 1 ~ '~
NIE l l 1 3 11LJ 1. I 1 G-
;J '=
p y -
)
- o. _ . . . . _ .., Decon. Area - - i .
= =.1 O
l
- i i ,, . - ,
1J w- . - _ l ENCLOSURE 1 l
._ ... .a..... ..' ..
l
~
l 9 AD 1827.13.5 CONTAINMENT AND AUXILIARY BUILDING i I ELEVATION 585' i l PRIMARY EVACUATION ROUTE:
) Use stairs up to Personnel Hatch at 603' elevation.
I \ Emergency Hatch (Secondary T Evacuatica D a"
- M i% . [# .
~
r, 5
- , O r-V I, i-
? l
. l
* .;i
( ,
.- 1 n
X ' 1 { I I l _ _, . L ,- - m _- - _
^
.. - -~ - ~ r .
h *
#3 Mech-
- lI 'E ,
j anical Pene-l i E T ' [ l tration Room
~
i Annulus Penetra-h g h - - - tion #4 Mechan-M ical Penetration I ( ]I
=_ _ .
Room Annulus Penetratiil 1
,j f o l e
,,.m , mm ,.-
j
\ ___- ._
i' l{ i b i e HM $ !! P L h ! 1 L . 1 1 1
. i l i li 1
n
\
]
rr ._ ,_ , _ _ _ ______ _ __ ! W B N b= I ENCLOSURE 2 l l . - - . - - . . .. . . ~ . . - - - .
f 10 AD 1827.13.5 ' CONTAINMENT AND AUXILIARY BUILDING -
. ELEVATION 565' 1 .
i . k
\
g
,, . ,_ Annulus Penetra-j ' tion N l
'hn ulus ratioit Q .-
).
Il
~
g
=
i (Pen - anical 4 oin ( .
~
enetr'*4- - Room l l
~
1 #1 Mechanica. g - l s ,%,, l Ponceration Rm. ;4 _ s g
'"' ~
h ._l '
' ~ ; ~ "' ""^~ ^
/ / -~
. / ?
~
. i cl R
~
E-8 Lii -
!i- EI -
l I cLEVATED PLATFORC -
- e e
O 9 ENCLOSURE 3 . e
. MD
-e
AD 1827.16 Ocvis Zesse Nuclear ?cwer Station j Unit No. 1 Administrative Procedure AD 1827.16
~
Search and Rescue
..'l, L.
l Record of Approval and Changes Prepartd by J. G. Roberts 6/15/77 Date , dubmitted by b IN < !77
. Reconst.nded by SRB Chai
[ Date b '
,QA Approved 44 n4*r / MI# 7 alttiy'Y.ssufance ta er o Dat's Approved by . M 4 tation Superincendent D'a te h
/
Revision SR3 QA S ta . S upt . No. Recoemendatica Date proved Date Approved Dats O Y# l/Wf //'//Jf hlh'b4lf/ YW Wl% vh,In
, p g +/12loa c.rD4/72 vktu nwm i
I l O
1 AD 1827.16.2
- 1. PURPOSE This procedure will be utilized by station personnel when the actual location of any person at the Davis-Besse Nuclear Power Station cannot be determined and the possibility of this person being trapped or injured exists. Directions in this procedure address the search process that will be used to locate missing personnel, as well as the actions to be taken to rescue a trapped or injured person from a previously evacuated area.
- 2. REFERENCES 2.1 10 CFR 50, Appendix E. " Emergency Plans for Production and Utilization Facilities" 2.2 "NUREG-0654 FEMA-REP-1, " Criteria for Preparation and Evafuation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" 2.3 Davis-Besse Nuclear Power Station Emergency Plan 2.4 AD 1827.02, " Medical Treatment of Injuries" 2.5 AD 1827.05, " Explosion" 2.6 AD 1827.06, " Tornado" 2.7 AD 1827.07, " Earthquake" 2.8 AD 1827.08, " Flooding" 2 2.9 AD 1827.11, " Assembly, Accountability & Subsequent Evacuation" 2.10 AD 1827.12 " Protective Action Guidalines" 2.11 AD 1827.13, " Containment Evacuation" 2.12 EP 1202.12, "High Radiation" 2.13 EP 1202.35, " Fire Emergency" 2 2.14 AB 1203.13, "High Airborne Activity" 2.15 EP 1202.40, " Radioactive Spills" 2.16 EP 1202.46, " Toxic Gas and Liquid Release"
- 3. NOTIFICATION As soon as it is recognized that a person is missing and may be
- - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . _ _ _ _ _ _ _ _ - . - . - - - - - - - - - - - - ---___________J
s
~
2 f.D 1827.16.1 disabled, the Control Room should be notified and given as much information as possible: 3.1 Name and badge number of missing person. 3.2 Location, if known. If not known, give last know location and possible present location (s). 3.3 Complicating circumstances, if any, (e.g., explosion).
- 4. SEARCH 1 The Shift Supervisor or his designee shall attempt to locate the missing person. Any or all of the following methods may be used:
1 4.1 Page the missing person over the Station gai-tronics at least 3 times. 4.2 Check the key distribution cabinet logs. 4.3 Question the person's supervisor and workmates as to where I the person was last seen. Initiate a search in these areas. If complicating circumstances exist (e.g., explosion or toxic gas), then initiate the search as a rescue attempt following the steps given in sections 5, 6, and 7 of this procedure. 4.4 Check the Radiation Exposure Permits. 4.5 Check the stores equipment or tool signout logs. 1 4.6 Check the Gatehouse Log and Security computer printout. 4.7 Check at the Construction Office Building. 4.8 Phone the pers6n's home to see that they didn't leave the station without signing out or leaving their badge with the gate guard.
- 5. RESCUE
! The following actions shall be taken in order to rescue a disabled ( person. 1 1 5.1 Shift Supervisor 5.1.1 Sound the statica " Initiate Emergency Procedures" alarm, unless already actuated. 5.1.2 Announce " Attention, First Aid Team report to (location of area) , " twice over the public
i l 4 3 AD 1827.16.1 address system. If the location is not known, the First Aid Team will report to the control room. I NOTE: If the emergency occurs during normal working hours, the unassigned First Aid Team Members shall assemble at the Operations Support Center. On the backshift, weekends and holidays, the First Air Team will be composed of personnel assigned by the Shift Supervisor. 5.1.3 Initiate other emergency procedures if needed to minimize the hazard affecting the trapped or injured person. 1 5.1.4 Contact the Operation Support Center Manager or others for support as needed. 5.2 First Aid Team Leader 5.2.1 Proceed to the designated area immediately. 5.2.2 Organize and direct the search and rescue operations. The following assignments should be given by the First Aid Team Leader. __ l. Dispatch personnel to procure the following equipment as needed: First Aid bag, two Scott Air Pacs, axe, fire extinguisher, stretcher, life lines, B -high range survey meter, portable air sampler, aluminized fire suits and any other equipment that may be useful.
- 2. Procure two volunteers familiar with that area to enter'the affected space for an initial assessment of the situation. If the area is known to be contaminated or an explosion or steam release is involved in the accident, protective clothing commensurate with the expected hazard shall be worn including a Scott Air Pac.
If the area is smoke- or steaa-filled, or if the area is in disarray because of fire or i explosion the men will use life lines or buddy system. Radiation levels should be monitored as the area !~ is entered. I l t
I 4 AD 1827.16.1 If the rescue is complicated by another hazard, the First Aid Team will retire to a safe area and plan a method of rescue. 5.2.3 Assign one person to establish phone communications with the Control Room to keep them informed of the situation. 5.2.4 Ensure that the actions specified in Section 6 are completed.
- 6. COMPLICATING CONDITIONS 6.1 High Radiation and/or High Airborne Activity 6.1.1 Changes from normal radiation protection procedures.
If an individual is trapped or disabled in an area in which the dose received during the rescue operations may result in increasing the health hazard to the person, the rescue must be carried out as expeditiously as possible. Therefore, the following modificatons are allowable to the Station's radiation protection procedure:
- 1. No prior authorization for exposure need be made 1 out, only verbal authorization from the senior TEco management individual present is required.
- 2. Exposerra in excess of 10 CFR 20 limits may be taken, keeping in mind the biological effects of large doses of radiation.
3; A dose of up to 100 rem may be received once in a lifetime to save a life. If time permits adequate i planning and protection, this dose should be limited to 12 rem. 6.1.2 Action to be Taken: i
- 1. Complete all items in Section 5.
- 2. Wearing a 0-200R self-reading dosimeter and using a high range survey instrument, enter the rescue area and attempt to complete the rescue.
6.2 Fire [ l w -- , -, , ,n < , . e n ..,- ~
5 AD 1827.16.0 6.2.1 Rescue of a victim shall,take precedence over fire-fight-ing unless necessary to suppress the fire to accomplish rescue. 6.2.2 .tction to be Taken:
- 1. Complete all items in Section 5.
- 2. Obtain aluminized clothing from fire cabinet.
- 3. One operator should spray water ahead of the other two while they perform the rescue, if required.
6.3 Steam or Hot Water 6.3.1 Rescue of a victim shall take precedence over isolation of a system unless:
- 1. It is necessary to isolate the system to perform the rescue.
J
- 2. The action of not isolating the system will place the lives of other personnel in immediate danger.
'~
6.3.2 Action to be Taken:
- 1. Complete all items in Section 5.
- 2. Obtain aluminized clothing from fire cabinet.
- 3. One operator should spray water ahead of the other two while they perform the rescue, if required.
6.4 Wreckage 6.4.1 Action to be Taken:
- 1. Obtain tools necessary to perform rescue from the maintenance shop.
, 2. Enter the area to perform rescue. l i NOTE: Exercise caution to ensure that further colltpse of building / structures will not occur upon entry. l 6.5 Toxic Gas i l
w 6 AD 1827.16.1 6.5.1 Action to be Taken:
- 1. Obtain a Scott Air Pak.
- 2. Enter area and perform rescue.
- 7. AFTER RESCUE 7.1 Remove the victim to the closest safe area and administer any required first aid.
7.2 If the victim is injured and contaminated, he should be treated - in accordance with AD 1827.02, " Medical Treatment of Injuries." 1 7.3 If not already accomplished, inform security and the Shift Supervisor that the missing person has been found and is being treated. e t l l' l 1 l l M
3 u
% + ( ,,,, 3' j
\'
m 1.'
%,s %
u' -
, t-
{Q ! C 5' , r. n
. AD 1827.17, N .%
~
4
. , - +'~M'r-s'; -s -,._ >
; l
, ,, s ~ . ! ,
Davis-Sesse Nuclear Power Station , 3 h -
'i Unit Ilo: 1 ~ U
<_y A 1 -i ADMINISTRATIVE PROCEDURES AD 1827.17 .
.s
~
A ,q, < Emergency Call System
, is
't 1t' -
' -"* sC.
(/5 , w', f ' g- -
.\
, N -
- r. .
w ,_i - - '- Y!TCgg!i?O1D[Ld;[p}\ J+ a 1: rrTilTirL/7 L . . Y~ ~% ~
. < ';> s g- *
, , c6 *; N 4
- t -
. , - g , s 3
,p,'
- : +,
,. "AA
- + */ s ,~
Record of Approval and Changes ! k- 4
-r-
,a I
, 2 \ ,.
s w-
- 4. h- % ,
G. J. Reed 4
,.e 8/ 29/80 Prept. red by ~
,e 3'N i Date s ,
,I 9/3/80 Submittad by Judith Hirsch M L , } \ i' ,,
Section Haad "i. Date , , Recc== ended by ' e [ & - -
. f cNQ
- ' ' Date SRFChsirman - , . .
N/A a QA Approved Manager of Ouniity Assurance Date.. , Approved by /O / 3./Pc --
' a Station'Superintengt Date s
y t Revision SRB QA S ta . S upt . ' [ i No. Recos:nendation Date 4p Date Approved , Date
/ M r $&/M c 3 $ proved / 9 iAsArt * * " ~ y 4k s nyri g f.4'y 3 px3 *)l4/W 1,}tra e c 7.r PfA/sL A f / fll19/2' L s'I1/ %? n T P J y% ,,
T3n" win, pw_ 2lufn C T .?nf/fL INT' < !
?
s s's" I l 4
>+. , ,9 7 1,* .
, .( w .f
; ., .s n ,r y t,, $ s
- - l~ > ~~~
sa y f, )
, . 3 .% s ,
pq* \ %. ,, v j \~ l - c g i 1 AD 1827.17.2
\'% ." > 't
; 1. PURFhSE (_ .<
,1
~-
H To. pro' vide guideliieCfor'the activation and implementa' tion of the
- i'1 Station Emergency Ci N System in order to achieve'imrediate notifica-
' " ' ,tiop and response 'of key personnel of the Nuclear flission in order to re'!Ove..cr midipte?ah abnormal plant situation. ~C '
2.
;y APPIICABILITY
)
i ' ' To by,y. -sed whenever the Emergency Plan is activated, a system test is perfgInsd, or, the Shift Supervisor deems it necessary to contact additional personnel to respond 'to a plant event.
~
u
- 3. REFEPM CES "'
,y ; x , _ .. 3.1 - Davis-Besse Nuclear Power Station Emerir,ew; Plan g s x , 3 % .. ,
.e ' W
- 3.2T -Emergency IqIementing,9;ocedure, EI 1300 series s t c.
1 3.3'hdministcativide'morandumNo.37
+
- ,!
- 4 , .,
y
.3.4 Concunication f ystem Test, PT 5108.01 4 '-t . ,. _ 2 .
.c x -.
. ,y . .
v' % .5 3 Radio Communications System, SP.1I05,19 o %, ' i 4 A PRECAUTIONS AND LI'hITATIONS s s , [_, The pr%ary function of the system is for emergency notifications 2f and shauld be tested monthly in accordance with PT 5108.01 Communica-
\
tion Syatem Test.
- 5. PREREQUI!ITES
-;. 5.1 ' Normal lineup of tl e3 Radio Control Console and its associated
~
s
, encoder (located in Control Room only) 5.1.1 ' Radio' Control, Console
)
e ,
- a. Off-On Switch - ON
\ b. Volume - At a comfortable level
- N. c. Portables /TECo/ Law Button - OUT
- d. Single Tone OFF Button depressed i e. Page/ Superintendent Button - 0UT
- f. Ottawa County Sheriff Button - OUT 1
2 AD 1827.17.0
- g. -Intercom Button - OUT
- h. Alert Tone Button - OUT 5.1.2 Encoder (Modern 36 model)
Ensure that the encoder is ON as indicated by two numbers being visible in the visual display window. 5.2 Normal lineup of the Telephone Pager (located in the Shift Supervisor's office) 5.2.1 A cassette tape must be installed in the cassette
. carriage located on the top of the machine.
5.2.2 An announcement cartridge must be installed in the slot located on the front left hand side of the machine. NOTE: Announcement Cartridges come in different lengths; 30, 60 and 120 seconds. Messages should be kept as brief as possible and a 30 second tape should be normally installed; however, if a longer message is required, the 60 or 120 second tape can be installed. 5.2.3 The CPC (Calling Party Control) switch located on the back side of the machine must be in the "on" position. 5.2.4 The Cont./ Fixed switch located on the left hand side of the machine should be in the " Cont." (Continuous) position. 5.2.5 The " Power" switch located on the front left hand side of the machine should be depressed and its associated power lamp lit indicating the machine is on. NOTE: When the machine is being used, the "In Use" lamp located just above the power lamp will be lit. 5.2.6 The orange " Automatic Answer" buttou located on the front right hand side of the machine should be depressed. 5.2.7 The associated microphone should be plugged into the T1 jack located on the left hand side of the machine. 5.3' Normel lineup of the " beeper" pagers (held by the Key Emergency Response Personnel) l l I< i
. I 1
- l 3 AD 1827.17.0 S.3.1 A charged nickle-cadmium battery should be installed in the pager.
5.3.2 The off-on-volume switch (labeled Vol.) should be rotated off the " red dot" position to a comfortable volume level. NOTE: When the pager is initially turned on, it will beep and hiss indicating the pager is operational. Push down on the push-button located just below the speaker jack (labeled Spkr) to stop the hiss. The pager is now in a standby mode for receiving any pages that may be made. Do NOT rotate the volume switch completely around to the black dot.
- 6. GENERAL 6.1 This system basically consists of a beeper " paging segment" and a telephone message " recorder segment".
. 6.1.1 Paging Segment The paging segment of the Emergency Call System should reach 11 key management positions who, upon evaluating the plant conditions, shall notify only those additional personnel under their cognizance that they feel are needed to respond. If all or a major portion of addi-tional TECo personnel are required, they shall be notified in a " call tree" type method using the staiton organization chart significantly cutting the time required to phone a large number of individuals by only one or two personnel.
6.1.2 Recorder Segment The telephone message recorder segment of the Emergency Call System should eliminate the numerous and time consuming telephone calls that would be received by the Control Room during abnormal plant conditions. This will enable the Operators to devote more of their time to controlling the plant. 6.2 The paging segement and recorder segment of the Emergency Call System work together in providing a notification system that minimizes the response time of needed off-site personnel. A basic sequence of events is as follows: l 1. A plant event occurs. l r i i
. l 4 AD 1827.17.4- l 4 2. The Station Superintendent or his designated alternate can
! be paged from the Radio Control Console located in the Control Room.
'3. The Station Superintendent or his alterncte calls the Shift Supervisor at 259-5664.
- 4. A message is recorded by either the Station Superintendent or the Shift Supervisor on the Telephone Pager.
1 , 5 The other Key Emergency Response Personnel are group paged from the Radio Control Console located in the Control Room. $ 6. These personnel call the Edison Switchboard Operator who j conferences them to the recorded message.
~
- 7. Based on the information in the message, the Key Emergency Response Personnel notify those additional personnel q required to mitigate the event as specified in Figure 3 of EI 1300.00 Station Response to Emergencies.
- 7. PROCEDURE 4 7.1 To page the Station Superintendent, the Radio Encoder must be used in conjunction with the Radio Control Console as follows:
7.1.1 Depress the Portables (Teco/ Law) pushbutton. Wait < five seconds for repeaters to function, then j 7.1.2 Depress the EAST Single Tone Generator pushbutton for the Lindsey repeater' area (call sign KTO 649). 7.1.3 Depress the mike monitor key to insure the channel is clear and then release the key. 4 7.1.4 To page the Station Superintendent: depress the number 12 on the Radio Encoder so that it appears on the visual' display. NOTE: A " steady" tone will indicate a~ group page for personnel carrying the beeper pagers. A
" beep-beep-beep" tone would indicate an individual yage.
7.1.5 Depress the-page button (labeled P) on the Radio Enccder and be sure that the page indicating -light Comes on. 7.1.6 Depress the talk button (labeled T) on the Radio. Encoder and state into the microphone "This is an . ~ 4 _ _ _ y -i .+4e + .e. -. m.y-" f y. y
4 5 AD 1827.17.1 activation of the Davis-Besse Emergency Call System. Please contact the Control Room." 7.1.7 After releasing the talk button, depress the TOL Single Tone Generator pushbutton for the Toledo repeater area (call sign KTI 854). 7.1.8 Then repeat steps 7.1.3 through 7.1.6. 7.1.9 When done, return console to a normal lineup as described in Section 5.1.1. NOTE: Detailed operation of the Radio Control Console is given in SP 1105.19, Radio Communications System. 7.2 A message can then be recorded on the Telephone Pager either locally or remotely. 7.2.1 Locally, the message should be recorded by the Shift Supervisor or his designee as follows:
- a. Depress the STOP button located on the front right hand side of the machine.
- b. Depress the PRESS TO RECORD button on its associated j microphone and dictate the desired message. Do NOT release the PRESS TO RECORD button until the cartridge tape stops rotating,
- c. Depress the AUTOMATIC ANSWER button to set the machine up for message retrieval.
7.2.2 Remotely, the message should be recorded by the Station Superintendent or his designated alternate as follows:
- a. Call the Edison Centrex Operator at "O" if inside the company, or 259-5000 if outside the Company.
1 Then ask the Operator, after giving your name and last four digits of your social security number, to access the Emergency Call System Dictaphone answering machine.
- b. When the line starts ringing, apply the Dictacall tone until the machine answers.
s
- c. Immediately press the "#" button on the telephone
, or the Touch Tone Pad (if at a rotary dial phone) and dictate the desired message.
J
- _ ~ y _ y m
)
)
l 6 AD 1827.17.1
- d. To check the announcement, stay on the line and the machine will play it back. Otherwise just hang up the phone.
NOTE: Only the Station Superintendent or his designee will have the Dictacall Tone Generator and the Touch Tone Pad for remote message recording. 7.3 To page the otner Key Emergency Response Personnel, the Radio Encoder must be used in conjunction with the Radio Control Console as follows: 7.3.1 Depress the Portables (TECo/ Law) pushbutton. Wait five seconds for repeaters to function, then 7.3.2 Depress the EAST Single Tone Generator pushbutton for the Lindsey repeater area (call sign KTO 649). 7.3.3 Depress the mike monitor key to insure the channel is clear and then release the key. 7.3.4 Depress the number 4 twice on the Radio Encoder such that 44 appears on its visual display. 7.3.5 Depress the page button (labeled P) on the Radio Encoder and note that the page indicating light comes on. 1 7.3.6 After the page indicating light goes out, depress the talk button (labeled T) and state into the microphone, "This is an activation of the Davis-Besse Emergency Call System. Please contact the Edison Operator." l 7.3.7 After releasing the talk button, depress the number 5 l twice such that 55 appears on the visual display. 7.3.8 Again depress the page button (labeled P) on the Radio i Encoder and note that the page indicating light comes on. l 1 7.3.9 After the page indicating light goes out, depress the talk button (labeled T) and state into the microphone, "This is an activation of the Davis-Besse Emergency Call System. Please contact the Edison Operator." 7.3.10 After releasing the talk button, depress the TOL Single Tone Generator Button for the Toledo repeater area (call sign KTI 854) on the Radio Control Console and repeat steps 7.3.3 through 7.3.9, then go to step 7.3.11.
7 AD 1827.17.1 1 7.3.11 After releasing the talk button, return the Radio Control Console to a normal lineup as described in section 5.1.1. NOTE: This is the group page method and personnel carrying the beeper pagers will receive a
" steady" tone indicating it is an emergency page from Davis-Besse. Individual pages can also be made to each of the Key Emergency Response Personnel by following instructions given in Administrative Memorandum No. 37.
This paging method is for non-emergency notifications and the person that is carrying the beeper pager will receive a " beep-beep-beep" tone indicating this. 7.4 The Key Emergency Response Personnel can then receive the message from the Telephone Pager as follows: 7.4.1 Call the Edison Centrex Operator at "0" if inside the company or 259-5000 if outside. 7.4.2 The Edison Operator will then check the individual's identification (name and last four digits of their social security number) and access them to the Telephone Pager. NOTE: The Edison Centrex Operator along with the Emergency Planning Supervisor or designated alternate is responsible for ensuring accountability of the Key Emergency Response Personnel. The Emergency Planning Supervisor or alternate should call the Edison Operator to ensure all Key Emergency Personnel have responded to the page. If a Key Emergency Response Person does not respond to the page (oy calling the Edison Operator), the Emergency Planning Supervisor is responsible for performing the notification requirements for that individual. If the Emergency Planning Supervisor does not respond to the page, then the Edison Operator shall attempt to make contact by telephone, both'at the office and at home. Failing to do so, the Edison Operator would then contact the Nuclear Services Director and inform him of the situation and await further instructions as required. l l 1 l
I 8 AD 1827.17.3 l l 7.5 Once the Key Emergency Response Personnel have heard the recorded < message from the Telephone Pager, they shall perform, according 3 to instructions within the recorded message, one of the following: 7.5.1 Take no action but remain in a standby status. 7.5.2 Proceed to the Station as soon as possible. 7.5.3 Contact their secondaries and then return to the station. a) Designated secondaries will remain in a standby status, or b) Contact additional personnel to respond. NOTE: Key personnel and secondaries will contact additional personnel as neces-sary. A list of names and telephone numbers of personnel that may be required to be called is found in Administrative Memorandum No. 37. t
- 8. ABNORMAL OPERATION 8.1 If either the telephone message recorder (Telephone Pager) or the Radio Control Console and Encoder become inoperable, then the Shift Supervisor shall assign an individual to contact and relay the message that would have been placed on the recorder to the Emergency Duty Officer and the Emergency Planning Supervisor or alternate by using the individual page (if available) or by telephoning their office or home.
8.2 The Emergency Planning Supervisor is then responsible for contacting the rest of the Key Emergency Response-Personnel with the message.
- 9. MAINTENANCE 9.1 The Radio Control Console and associated Encoder are made by Motorola. If they become inoperable, a phone call should be 3 made directly to Motorola Service (531-2844 or 475-5710)) to get a service representative out as soon as possible. The plant maintenance group will coordinate site activity by the vendor representative, as-may be necessary.
9.2 The " beeper" pagers are of the Pageboy II model type made by Motorola. If any pager becomes inoperable, the individual holding the pager should contact the Emergency Planning Super-visor who shall notify the local Motorola service representative and if required, issue a replacement pager until the affected pager is repaired. l l l-
l 9 AD 1827.17.0 9.3 The " beeper" pager battery charging units are made by Motorola and should also be serviced by them if there is a problem. The nickel-cadmium pager batteries should be charged eight (8) hours every day. This can be accomplished as follows: 9.3.1 Charge one battery while the other is used to allow the pager to be carried on the individual. 9.3.2 Insert the entire pager into the charger while it remains on to receive incoming pages. It will charge the battery at the same time. 9.3.3 When charging a battery or entire pager, an indicating light will come on to show that the charger is operating (one is provided for each method). . NOTE: If a page is received while the unit is plugged in, reset the pager after receiv-ing the message since the pager will discharge the battery if not reset. 9.3.4 During emergencies, the batteries can be used up to 36 hours without being charged, but must then be recharged . . , for at least 12 hours prior to being placed back into service. 9.4 The telephone message recorder is a ' Telephone Pager model made by the Dictaphone Corporation. Should it become inoperable, servicing should be performed by Dictaphone (885-3393). The plant maintenance group will coordinate site activity by the vendor representative, as may be necessary. 4 i
2 l 10 AD 1827.17.4 ECS MESSAGE FORMAT This is an activation of the Davis-Besse Nuclear Power Station Emergency
. Call System. A(n)
Classification has been declared at Davis-Besse due to: Classification Category or Explanation
- The response required for this event is as followsi (Response Required) (Response Required) i
! 4l The plant is presently l (Brief description of present plant conditions) Attachment 1 ( I END 4 l
O AD 1350.04 Davis-3 esse Nucle:r Pcver Statier. Unit No. 1 Adninistrative Procedure AD 1330.04 Post Accident Radiological Sanpling and Counting
-e
[' O O d IW l. I l I ll Y]' lkif3f]1 iN hN() b3!-} b , b Record of Approval and Changes Prepared by Eave Briden 12/19/79 Date Sub=itted by b;O- 'LW )/i7 /8O Sec:ica Ecad Date Recoc ended by '
/ ! 14 / - f/2 t/Sc M K3 Chairman '
Date QA Approved 3!9 Ao
/ Esnager of Quality Assurance Date Approved by W ^
l ,. 1 Statica Superintrf. ient Date 0 Revision S23 QA S ta . S up c . No. Reco=endaticn Date a- roved Date Approved Date
] AYf fWAO lIeNo YENYhpfY
3 pp yyn A p / s9a do ,a r.. .g vissin 3 pg _ __3 t/ufn. C C Yz-1-en &* ' ' b dsby f x m r '/ <,/s u g ~l 4 g ~, wow-
- c. /2 e .t. -
e * ,' pat /145,1a ,ee o " cia. [ 3 W . N '2./ 3 /S 3 r _.._-m . . . _ . .
-. _ . . . _ m . .- _
1 AD 1350.04.5
- 1. PURPOSE ,
The purpose of this procedure is to address short-term preparedness " in responding to radiological sampling and counting for a pctential accident which would make normal sampling and ccunting i= practical.
- 2. SCOPE 2.1 Gamma Spectral counting capability 2.1.1 In the event of such an accident, the existing counting room could not be used.
2.1.2 A temporary counting room would be set up in the
'Jater Plant lab or other suitable location for gross counting, and gamma spectroscopy.
2.2 Reactor Coolant System (RCS) sampling 2.2.1 Depending on. Radiation exposure, the normal sampling system can be used. 2.2.2 A shielded high pressure sampling sampler can;be used j for pressuriner samples when the nor: sal sampling , system cannot be used. 2.3 Containment atmosphere sampling 2.3.1 The nor=al sampling assemblies on Contaiament Monitors 5 RE 4597AA and BA are in area where the expected radia-tion levels would be too high to enter.
- 2.3.2 A high pressure sampling assembly will be used-for sampling at the Containment Hydrogen Analyzers.
2.4 Station vent sampling 2.4.1 Silver zeolite filters should be used for iodine sampling. 2.4.2 If-RE 2024C or RE 2025C indications are off scale, direct radiation dose ' rates from a Noble Gase Tube are' , converted to uCi/cc. i- 3. REFERENCES.
. 3.1 NUREG-057S, July, 1979, TMI-2 Lesson Learned Task Force Status Report and Short-Ters Recc =endations.
3.2 NUREG-0585, October, 1979, TMI-2 Lesson Learned Task Force Final Report 1
- - - vy y - -q v
7 2 AD 1350.04.5 3.3 NRC September 13, 1979 Letter (Followup Actions Resulting from the NRC Staff Reviews Regarding the TMI-2 Accident) 5' 3.4 TED September 23, 1979 Letter (TED Response to NRC September 13, 1979 Letter for DENPS) 3.5 NRC October 30, 1979 Letter (Discussion of Lessons Learned Short-Term Requirements) 5 3.6 TED November 21, 1979, Letter (TED Res'ponse to NRC October 30,
! 1979 Letter for CBNPS)
- 4. PRECAUTIONS 4.1 Individuals collecting samples sh:ll not receive in excess of 3 and 1S 3/4 rems to the whole body or extremities, respectively.
4.2 The requirements for e:: eeding 1.25 rem to the whole body during a quarter should be followed as defined in Section 6.10 of HP 1601.01 (Guides and Limits for Exposures to Radiation) 4.3 No entries shall be made into areas exceeding 100 mR/hr withcut a high range survey instrument, and an individual qualified to evaluate radiological conditions. Unless airborne activities are known, respiratory equipment is to be worn. 4.4 Since Chemistry and Health Physics personnel will collect the samples, new REP's are not required. 4.5 WARNING WHEN COLLECTING SA'!PLES Potential radiation levels durd ag accident conditions are: 4.5.1 Contaiament Atmosphere Sampling
- 1. 585' elevation in front of the high pressure-sampler may be 0.1 - 5 R/hr.
- 2. Hallway on 535' elevation adjacent to sampling may be 5 - 30 R/hr.
4.5.2 Station Vent Sampling
- 1. Inside the Non-Radwaste Ventilation Roco by -
-sampling system may be 5 R/hr.
- 2. At RE 2024 and RE 2025, the radiation could be 100=- 1000 R/hr if EVS system is-operating. -
L - - - _ _ _ _ - - _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
d 3 AD 1850.04.5 4.5.3 RCS Sampling
- 1. Sample system could be 0.1 - 5 R/hr.
- 2. Hallway to sample system could be 15 - 100 mR/hr.
- 3. Pathway to the RCS sampling system is to.take the elevator or stairs in the southeast corner of the Auxiliary Building to the 545 ft. elevation.
- 5. PROCEDURE 5.1 Containment Atmosphere Sampling -
5 The normal sample points for Containment atmosphere at RE 4597AA and BA cannot be used because the radiation levels in the Mechanical Penetration Room will be excessive. When a high pressure sample is collected, only radioactive noble gases and iodines are determined. Particulates are not applicable based on Lessons Learned Item 2.1.6.b. 5.1.1 The sampler is evacuated by connecting a vacucm pump V-2 with V-2. With gauge attached, "-1 closed, and V-2 open, evacuate the sample assembly. Close V-2 and remove from vacuum pump. 5.1.2 Connect 75cc high pressure sampler (HPS) to quick disconnect 'A' from CV 337 (CV 342) located above Hydrogen Analyner Cabinet on 585' elevation, as in Figure 1 shown below: 5 From Containment CV337 l Gauge: 30"-0" Hg
>< --e and 0-100 psig CV342 V-1 x -= =-x (75cc HP3) =a
[ Quick Quick Disconnects Disconnects Return tc 'A' 'B' Containment
+
CV337 (CV342) are-inside H2 Analyzer. -To Vacuum Cabinet but cperable from outside cabinet. Figure 1 5.1. 3 ~ . Verify flow through the hydrogen analyner. (This system is isolated during an SFAS trip and Opera-
-tions would have to open isolated valves to reestablish flow.)
4
, - ~ - -
. -t o .
~
4 AD 1S50.04.5 5.1.4 Open valve v-1 on the sampler. 5.1.5 Slowly open valve CV 337 (CV 342). After the pressure indication has stabilized as indicated on the pressure gauge, close CV 337 (CV 342) and V-1. Disconnect EPS assembly from CV 337 (CV 342) at disconnect 'A*. 5 5.1.6 Remove gauge at quick disconnec'es 'B' and count 75 cc . HPS assembly for gamma emitting radionuclides. 5.2 Station Vent Sampling The station vent is continuously monitored by RE 2024 and RE 2025, however, they do not meet the range required by. January 1, i 1981, from Items 2.'l.8.b of NUREG 0573. During a post accident condition, noble gas readings can be obtained every 15 minutes by the use of a portable high range survey instrument next to the sampling line. Interference from noble gases for measuring radioiodine can-be reduced by using silver zeolite filters. 5.2.1 If RE 2024C and RE 2025C readings are off scale, 3 the emergency station vent sampling assembly located in the non-radweste ventilation room on Elev. 623' is put inte service. Grab sampler Non-Radwaste Ventilation assembly on 'I Room off the RE 2024 (RE 2025) \ Turbine Deck
\
l Grab \ W Sample 1 CV 2024H l Filter To (CV 2025H) l l Pump < >< I l
\
l Particulate- l 1 SS 228 y }SS227 \ Silver Flow l (SS 232) 6 d.(SS 231) \ ,---l P/ 5 Z j . l l l
\ l ~ Zeolite meter 1.
\ Filter i i \ Assembly l
\ -x I t
1 T U . i
\
\
TA
\ i
\
\
\
\
l \ \ [- Noble Gas Tube I \ For \
\ \ \ Background \
i \. \ \ Reading- l\
\ \ HP-270 PROBE or \ HP-270 PROBE or \
f \ \ RD-17A PROBE _ \ . RD-17A PROBE \ l jL \\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\! Figure 2 l I
- s s-
. iI z -
5 AD 1850.04.3 NOTE: The RD-17A Probe is positioned 12-inches from the Noble Gas Tube, and the HP-270 Probe is in contact with the Noble Gas Tube. 3
- 1. Set up the interim station vent monitoring assembly as shown in Figure 2. (Either RE 2024 or RE 2025 may be used for connecting up to the nor=al grab sampling valves.)-
- 2. Remove the particulate and charcoal filters in RE 2024 (RE 2025) grab sampler, and reconnect.
4 3. Close valve CV-2024H (CV-2025H)
- 4. Connect the tygon tubing labeled " Inlet" to valve SS-227 (SS-231).
- 5. Connect the tygon tubing labeled " OUTLET" to valve SS-223 (SS-232).
- 6. Cpen valves SS-227 (SS-231) and SS-228 (SS-232).
- 7. Noble gases are monitored by a Ho-270 Probe for Xe-133 concentrations between 0.054 to 540 pCi/cc, and a RD-17A Probe for Xe-133 concentra-tions between 520 to 5.2 x 10 pCi/ce. Readouts 3 are shown in Figure 3.
- NOTE
- RE 2024C and 2025C have ranges of 1 x
- 10'7 to 0.02 pCi/cc.
High Range ,
-Low Range RM-16 Recorder RM-16'
, ~l_ 0.01-100 R/hr 0.02-200 mR/hr 17~ Connected to Samule Probes High Ranges Low Range l RM-16 Recorder RM-16 Ea'ckeround Background Connect to Back2round Probes 3
.J Figure 3 L
- 8. Determine the net close rate for the appropriate monitors used to monitor the Noble Gas Tube using Attachment 1.
- 9. Calculate the Xe-133 concentrations using Attach- ..
ment 1. e
) I
~ _
9 6 AD 1850.04~.2
- 10. If RI 2024C or 2025C reading are of acale, then
( readings f cm emergency high range or low range i probes are to be given to the Shif t Supervisor or l e mergency. Duty,0fficer every 15 minutes. i.
- .5.2.2 ' Iodine analyses can be collected at the interim
, Station Vent Samples. ( [ 1. Silver :eolite cartridges are used for iodine i sampling with a particulate filter infront of the cartridge.
- 2. Calculate the volime of air that' passed through the particulate-silver neolite filter assembly by multiplying _the sample flow rate times the collection period.
- 3. Iodine analyses and calculations can be performed by:
(1) Normal computerized gamma spectroscopy counting. (2) Emergcacy on site counting described in Section 5.4. (3) SAM-2 operation described in AD 1850.05. 5.3 Reactor Coolant- Liquid Sampling During post accident conditions the letdown system would be isolated to prevent excessive radiation levels in the Auxiliary Building resulting from high levels of radioactivity.in the reactor coolant liquid. In the interim, until the permanent RCS sampling' s/ stem i's available, a pressurizer sample will be collected at the normal sample point, provided the radiation levels within the room can be centrolled with shielding. 5.3.1 Interim RCS Sampling 2 The RC System Accident Sampling System shown in l Attachment 2 is designed to obtain a. reactor coolant sample from the pressurizer vapor or water space
- following an accident, which renders the normal sample room inaccessible, while maintaining the radiation exposure to personnel as low as practicable.
The system consists of tubing and valves to obtain the sample and return it to the Quench Tank, a sample panel with a cooler for conditioning the sample, solenoid valves for recirculation, sampling, and L flushing and a shielded sample cylinder which collects
7 AD 1850.04.5 the sample. The sample panel and its asscciated control station are designed for storage until required. The demineralined water, for cooling the sample, and the sample tubing are permanently installed at the same location.
- 1. Open demineralized water valve to the emergency sample cooler located at approximately head level at the entrance to the room where the cooler is installed.
- 2. Using quick disconnects, attach the shielded sample container to the sample panel.
- 3. Open the manual inlet and isolatica valves SV-10 and SV-11 on the shielded sample container.
- 4. Open manual sample inlet and outlet isolation valves SV-S and SV-9. (These are located on the wall above the sample panel).
5 5. Ensure RC 111 and SV-24 on interim RCS sampling return to quanchitank are open. Valves are shown on M-040-A at location F-5. These valves are physically located in Mechanical Penetratica Room No. 2 approximately 10 feet along Containment wall from area at door.
- 6. Frca the Control Rocm, open control valves RC 239B (pressurizer water sample), RC 240A, and RC 240B. (This pressurices the sample system up to solenoid valves SV-3 and SV-4.)
- 7. At the' remote contrcl panel, place switch SW-1 (sample-low) to "0N". (This opens cooling water valve SV-2, the low sample valve SV-3, and sample cylinder inlet and outlet valves SV-5 and SV-6.)
- 3. Allow the system to circulate for 20 minutes.
NOTE: Recirculation can also be accomplished with the high sample switch SW-2 which is provided to sampling at low system pressure. SW-2 opens SV-2, SV-4, SV-5 and SV-6.
- 9. To collect the sample in the cylinder, place SW-1 (SW-2) in the "0FF" position to trap the liquid.
l l i 1 l 1
_. . . . , . . ~ t 8 AD 1850.04.4.
- 10. From the Control Room,-close valves HV-2a0A and HV-2a03 to isolate the sample system from the pressurizer.
- 11. At the remote statien, place SW-3 (flush) in the "O.V" position. (This opens valves SV-1, domineralized water flush; SV-4, high sample; and SV-7, sample cylinder bypass.)
- 12. Flush until radiation levels are reduced to the lowest level.
- 13. Close inlet and outlet manual isolations valves .
SV-10 and SV-11 on the sample cylinder and > . disconnect the quick disccanects.
- 14. After disconnecting the sample cylinder, switch SW-3 _(flush) should be placed to "0FF".
5.4 Casite Counting Facility a In order to meet the 3-hour post-accident radiological sampling and analysis requirement for RCS and containment atmosphere -
.. samples, an operational, adequately equipped, onsite counting j facility must be available.
The location chosen 'for the Onsite Counting Facility must be set . up where the r,diation level is low, such as the entrance lobby on the east siae of the Office Building (5SS ft. elevation)or in 5 the Water Plant Lab. 5.4.1 Equipment A Canberra Model 8100 or 8130 multichannel pulse height analyzer (MCA), pre'sently onsite, has been
- 4 assigned for use in the Cnsite Counting Facility 4 in the event of an accident. Should utilization
.of the Facility be required, a Ce(Li) detector assembly will be removed from the Counting Roca (603'ft.
elevation) and relocated in.a low radiation area where , it will be connected with the Canberra MCA and other necessary equipment to provide the ' required gs=ma spectral analysis capability. Efficiency charts and/or data tables are available in the counting room manual to provide necessary counting information for each of the following samples:
- 1. Reactor coolant
- 2. Containment atmosphere (ncble gases)
, * - w - o..
9 AD 1850.04.4
- 3. Stack exhaust (noble gases)
- 4. Stack particulates filter
- 5. Stack icdine cartridge.
5.4.2 Procedure Upon declaratica of an emergency requiring activation of the Onsite Counting Facility, the following procedure will be followed: 4 1. If the Counting Room cannot be used transport Canberra Model 8100 or 8130 to a suitable loca-tion, i.e., the Station Lobby, Water-Plant Lab, or Radiological Testing Lab at the DBAB.
- 2. In Counting Room, gradually reduce high voltags to the Ge(Li) detector until high voltage is off.
Turn off power to the NIM bin in which the high voltage supply and amplifier are located.
- 3. Disconnect cables at the Ge(Li) detector, amplifier, and MCA.
- 4. Remove Ge(Li) detector from shield and immedi-ately place in a dewar of LN2 . Relocate in a low radiation area with NIM bin containing high_-
voltage and amplifier. Bring a sample shelf assembly along.
- 5. Reconnect high voltage, pre-amp power, and signal cables between the NIM bin components and the Ge(Li) detector per Attachment 3.
- 6. Turn on NIM bin power and gradually bring high voltage up to normal opera. ting voltage (3000 volts). Allow about 15 minutes for the system to stabilize.
- 7. To achieve 0.5 kev / channel energy calibration, adjust the amplifier fine gain until the number of channels between two reference. peaks is two times the difference between the peaks in kev.-
Then adjust the baseline until a reference peak is in the channel equal to two times the energy in key. It-is not necessary te-have exactly 0.5 kev / channel.,
-S. Determine background spectrud before counting samples. Good operating practice would recommend-the stationing of an operating thin-window G-M
. c.
~.
O' 10 AD IS50.04.4 survey meter with audible output at the Onsite Counting Facility. This would alert personnel te high atmcspheric noble gas activity which could disrupt counting.
^
- 9. After counting appropriate samples, the data reduction necessary to determine the' activity for each principal gamma emitter will be performed per RC 4502.00, Oamma Spectral Analysis.
- 10. Specific information for counting the RCS sampling system (i.e., the 40-ce bomb inside.3-inches of lead shielding).
4 (1) Remove the collimator pin from the shielding. (2) Use Attachment 4 for radionuclide data. (3) Use Attachment 5 for efficiencies. These efficiencies in Attachment 5 are for-counting at 1 1/4 inches between the.centainer (at the collimator) and the detector edge with th- collimator centered on the center of the de.ector. To get efficiencies for one foot
, diride the 1 1/4 inch efficiencies by 116.
i Tc get three foct efficiencies, divide the 1 1/4 inch efficiencies' by 1208. (4) Use Attachment 6 for instructions to_ perform calculations manually if the computer is not available. (5) If the-RCS sampling system is needed to collect another sample, the sample which , has been counted will b'e flushed out of the bomb when the next sample is to be recirculated. i i { F f I i i
11 AD 1850.04.2 Data Sheet for Calculating,the Xe-133 Concentration in the Station Vent If the low range pro'oe (HP-270) is used: Date RM-16 Sample RM-16 3ackground Net dose Xe-133 in time Reading in mR/hr Reading in cR/hr. rate in, uCi/cc equals mR/hr net mR/hr times 2.7 l
- If the high range probe (RD-17A) is used:
Data RM-16 Sample RM-16 Background Net dose Xe-133 in time Reading in R/hr Reading in R/hr rate in uCi/cc equals R/hr net R/hr ,
. times 5 2 x 10' Attachment 1 i1 . -.-. . - - _. .- .
1 . . . ii. . . , . . . .
._ , , , _ , , , , , , _ , , ,,ag
'T o Rerm ott ,,
Igoto P R E s<,u y yc g g somPt.E 76t4CL C. -l'10 C p gg h
<li~~ TU B
- ll G
/
QNOSO C-l) ( y g i j SPACE
. s /,q . j.
3/6 TulStNG DEMIN.WTR. OUTLET -
'TO FLOOR PRAW1 VIA 140SE - FLEX HOSE (TYP)
(sy , ..:
- QUICK 9}SCONNECTCrYtd y 2 ;
ii 4 kg sv SAMPLE . n S (SV 5 ) CYLIN PEK. S g h/ >
.s LO b
;1 103(ll}--> 4-
/"
"p>
1 si
-4]{V[-> .4-
.p 4- - -> Ic{
V LEAD Silip NCs- f \
,r 4 3/ [ TUBING
>j% ,
> jh tS' s"v- (Sl - g a , 4 X sv - !I i li TO 2."-11CC 8(c . 5 " CUENC.H tat 4M. ' RtiTU P. M l_.11 I E . ING ' (M 040M.F 9 ( _ PE MIN. WTR. .
. SUPPLY _
i b10CK GEU C/ N G s\Clo tt (00WM by W D C, a
.- . e 13 AD 1850.04.2 Portable GeI.i Gamma Spect: oscopy System
. .._ _ _ . _ _ _ . _ _ . . _ . - . . . . , . . , . . .. .+_ - . . - . .,
. . _ . . . - = _ _ _ , . . . .
l A. . _ .. i n .. . _ . _ . . :_.. ......i .... i a i 6.. ._ _ ._. . i Acc . . . . . . ..
- a. c. IN .
__ _1
. . ._. <> 2e .. ..._... :_ ~. i go y Ac . _ _ . - .
.___.* t.:w- ... . . _ . . , . . . . . _ .
. eo -
- ; i t
.._ c. -' . . . . .
.._;...._..... BIN -
- i _ _ . . . ..._. . ... . . . _ .
i' t._. . . . - L
.I _ _. n AMP
..! ! I __._... ... . _ . _ _ _ . . .
' e._._ _ . . _ . . . . .
_...... .._._l . .
..(
e; . . _ . _ . _ . _. _ ... . . . . ..
'..,.;... .. C _
I
! _. '_ . PREA.tip $ 1 c. N '. t. .
4 - .. :_ . . . . .2-_ ,s m.
.. e. .
. # - i *y t .
. '., v,_ .
. - .... g g.
- - _' O g PO'.YER
..i_ ..'
3
..i .. . . . .. . . . . . . . . . _..
- I l '
- 6. .. _ L i . . . . . . .. ._ . t a
. ..i;
. . . I l _ - . ..
i i i i t . ,g. .,.__ _ . . _ . . _ . i t. . i_a
.gg y ___
. .._.I. i . . .
- t. _. . . g r -
C_IWA R.,s..i _- . __ . . . . . . . . 1 1 __.. H IG H \CLTAGE
.il .
I
-LN- 04 -
l I i i! ' I t ' i_,
. 1I ! I i i i i _ _ .
' 1 l i*!
t ! j i t , i;} ;- - i . ..___ ' l t l f I 9
' Attachment 3 V-l
.~ .- . . . - . - . .
s 4 1 14 AD 1350.04.2 H4LF-L*FEtMIM .g5V-
~
Nuctz:E Ca*P* A7uMC
-et-:; 7. $CC CC O E-CO- *?293.7 ~2003 0*C -
l - PN-54 0.99970 4:0144 834.307 CD 0.99960 0.74:841E+0e 1173.01
;w-4: e.*07:0 -
3:1004a . 15.5-KR-87 0 49400 74.00C0 4C .330
- 24-95 0 34400 943*0 0 7:4.7*0
;r=9- 0.93200* 1000.00 J43.400-'-
#8-95 0.99000 20:44.0 765.790 2-131 0 8:000 11577 4 344.500
;-13; 6.98000 136 30v 447.700 "
I-133 0.870C0 1:48.00 529.89* 2-134 0.1 300 32.6000 1072 55 4
. & C. 4 v 30 ; 9'M ~~'*
4 f*133 a.27100* XE133M 0.10 00 31:5.04 033.130 XE-13: 0 90400 50.000 249.741 j 1:a30CG ;O34400 ~
.E13M 2481 06
- 0.8:000 1 57S377E+07 461.439 i C3-137 CS-138 0.7:0C0 30.0000 -1435.54
,4=t 40 6:23:CC 43417.a 3M 3Ss MR3:M 0 7:300 04S.800 1 1 130 791M 0.94900 49.7CC0 :: .570
-- 1 0=0 % a.S1:00 J334; 279- CO s SM-113 0.44000 14:440. 371.700 SR-85 1 00000 93838 0 513.980 erat 33 w747000 27" 904:E+Ce .5% 907 -
t NA-22 0.99950 1.37707::+0e 1274. : TA-18: 0.3:800 16:440. 1101 30
---*MA*: . 99993 700.00. .542740 -
I-135 0 29*00 396 440 .'1:40.41 U-157 _ 0.32300 1434.40 485.700 ' a;10300 7s**3.; ,77k
- 9 2 -
itn AR-41 ,0 99140 109 4:0 1 93 44 30-46 0.?9994 1 0744 ES9 0:3 mR*t: ,.3C0000E-03 -2 43*e:33401
- 19*0 -
RS-98 0.02100 17.3000 1336.00 EU-13: 0.24710 7.14316:E FCe 344.000 4 F*10, e.92000 e1433r0 .0 .70. . 1 CU-e4 5 000000E-03 742.400 1345.30 3R-94 0.41400 31 8000 831.400
---""T* ?1 ;.;00000E-C5 840:4 .' 4' 6:09.00 - ' . Y-92 0 137:0 211.800 - 934.500 TE-132 0.88000 44t0.00 22S.000 AE!310 2 000000E-02 ;7:43 4 ~;43;920 -
NR-90 0.:8000 C .:38 64 121 500 XE-137' O.30000 3.84000 4:5.380 e.29000 14.-1700 ;;3.-315 , at-13e XE-139 0.45000 0 47333 218.590 CS-139 . e.700000E-C 9 30000 1:53.03 em-r3; G r1*000 ~ $3.2000 .45;306
- PU-238- 3.80C0CCE-04 4.414743
- +07' 43.4:C0 NP *39 0.27830- 3384.00 104.140 n N-S 6.99000 1:3.200 s46.4CC -
SR-91 0.534C0 585 000 10:4.30
- R3-89 0.44100 15.40C0 1031.S3 L .a 434 0 89000 2.;&3737E+0e 795. 50 *-- -
C3-134 1.0C000 18700.0 .819 7C0 CD-57 -0.85:00 308300. 122.040 CE-141 0.48000 46723 0 145.4C0 i ! NR-89 0.02500 3 140C0 220.90C-PA-233 0.34C00 38980.0 - 311.390 ( i CE-143 0.41300 1980.C0 293 210 i F-18 1 94C00 109 700 311.C00 CT-144 0.10800 409:48. 133.330 l
---ntt-t f e 0.7470G 3882 04 ,11.200 -
} 340574. 854.450 i 40110M 0.7:300 ' N1-4 0.25700 1 3.400 1481.90 FE- ' 5154:00- 640:4.0 4099.07 - -- l 0.90C00 341.800 140.300 ) TC99M i LA-140 0 9:330 2415.40 196.18
----cc-S e.99440' 10:371. .10t?:7 KR-89 0 28C00. -171.400 194.300 MO-*9 0.14000 4001 40 739.5S0
-CW3e ;s40CCO. 37.1307 1640.40 N3 97 0.99000 - 73.4000 458.100 SR-92 0.90000 142.400 1383 94
- m :8 3 2:100 171w 0e t e 34.00 - .
i 2 Attachment 4 1
N 1 KEV $$4488444* ECFICIENCIES FOR GEOMETRY 30 DCTECTOR 1 ********44 40 HL.GTEEL 4 LEAD.COLLIH4TED.1.25 1HCHES
--- 10 ~ 17141E 1.037C-00 2;794E-03 4.053E-00 '5.657C-00 7.640C-00' 1.003C'07- 17206E-07 1.6150-07-'t.VYlE-07 ~
20 2.416E-07 2.090E-07 3.412C-07 3.904C-07 4.601E-07 5.270C-07 5.903C-07 6.74tE-07 7.542E-07 0.303E-07 30 9.264C-07 1.0tDE-06 1.113E-06 1.212E-06 1.313E-06 1 410C-06 1.524C-04 1. 63.lE-06 1.745E-06 1.ftbOE-06
-- 40 1 973E-06-~2.009E-04 2.206E-06 2.32SE-06 2.444C-04 2.564E-06 2.604E 2.005C-06 "2.92SE-06 3.046E-04 50 3.146E-04 3.206E-06 3.406E-06 3.525E-06 3.643E-06 3.76tE-06 3.077E-06 3.992E-04 4.107C-04 4.220E-04 do 4.33tt-04 4.442E-06 4.551C-04 4.650C-04 4.764E 04 4.040E-04 4.970E-04 5.071E-06 5.170E-06 5.267E-06
-- 5.3 62E-06 ' 5.456E-04 '5.547C-06 5.437E-06 5.72SC-06 5.1110C-06' 5.094E-06 5.976E-06 ~6.056E-06' 6.1340 00 6.210E-06 6.204C-04 6. 35 7E -06 6.427C-06 6.495C-04 6.S684'-06 6.626E-06 6.600C-06 6.7490 04 6.H00F-06 YO 6.065E-06 6.920E-04 6.Y73C-04 7.024E-06 7.074C-06 7.122L-06 7.14HC-06 7.212C-04 7.255E-06 7.2V6L-04
~~100-'7.335E-06-~7.373C-06 7.409C-04 '7.443C-06 7. 4 76E- 06 7.507E-06 ~ 7.537E 7.566E-04 7.592C-04 7.6ti1E 110 7.642E-06 7.665E-04 7.604E-05 7.706E-06 7.724C-04 7.742C-06 7.750E-06 7.772C-06 7.7060-06 7.7v0C-04 120 7.010C-06 7.020E-04 7.02HC-06 7.h36C-06 7.043E-06 7.1149C-04 7.053C-06 7.057C-06 7.4160 E-04 7.061E-06
-130 -7.062E 7.062C-06 7.H6tC-04 7.0SvC-04 7.056C-04 7.0520-06 7.013C-06 7.012C-06 7.036C-06 7.0?vC 04 -
140 7.022E-06 7.H13E-04 7.004C-06 7.775E-04 7.7040 04 7.7/3C-06 7.741C-04 7.74vC-06 7.736C-06 7.7231:-04 150 7.709E-06 7.674C-04 7.67vC-06 7.663E-06 7.447E-06 7.630C-06 7.413C-06 7.5VhF -06 7.h7?E-06 7.557L - 04
--160 -~7.5 goE 7.520E-04 7.500C-04 7.400E-06 7.4400-04 7.43YC 06" 7.417E-06 7.396C-04* 7.374C-04 7.3510 170 ~7.329E-06 7.306E-06 7.203C-06 7.259C-06 7.236C-06 7.212C-06 7.!U/C-04 7.165C-06 7.130C-06 7 ':*C-06 100 7.000E-06 7.063E-06 7.037E-04 7.011C-04 6.YDLC-04 4.959E-06 6.Y33E-06 6.90/E-06 6.H000-06 6.HS3E-06
- 190 - - 6. 027E-04 4.000E-06 6.773C-06 6.74SE-06 6.7tuE-04 6.6910 04 6.66.lE'-06 -6.636C-04 6.600C-04 6.Sl10L 200 6.552C-06 6.52SE-06 6.4Y/C-06 6.469C-04 6.44tC-06 6.4120 06 6.3H4C-04 4.354C 06 6.3?HC -06 6.3000 06 210 6.271E 6.243E-06 6.21LE-06 4.107E-06 6.15DE-04 6.130F 06 6.1020-06 4.07JC-04 6.04b0 06 4.08/E-06* **
D'
" 220 r 5.9 HOC-C6 5. 940E-06 5.9322-06 5 904E-06 5.075E-04 5.017C-065.OlvC 5;79tC-04 5.763C-06 U.735C-06 230 5.707E-06 5.679E-06 5.451C-04 5.423E-06 5.595E-06 5.54HC 04 5.5400-06 5.512E-06 5.40LC-06 5.45/C-04 240 5.430E-06 5.402E-06 5.375C-04 5.340C-04 5.321E-04 5.293C-04 5.266E-06 5.239E-04 5 213E-04 5.1060-06
' 250 5.159E-06' 5.007E-06 5.063C-06 5.03vE-06 5.016C-06 4.99 5E-06 ' 4.970E-04 4.947C-04 4.9?5E -06 ' 4.901C-06
- 260 4.000E-06 4.DS9E-04 4.037C-04 4.DILE-04 4.794E-04 4.773E-06 4.752E-04 4.7310-04 4.711E 06 4.6v00-04
- 270 4.670E-06' 4.650E-04 4.630L 06 4.610E-06 4.5YlC-04 4.571E-06 4.552E-06 4.53.5E-06 4.5141.-04 4.49Ls:-06
$k~ 200-*4.477E-06' 4.450E-04 4.440E-06 4.122C-06 4.401C-06 4.306C-06 4.360C-06 4.350E-06 4.33.5E-04 *4.3 toc-06 b gg 290 .4.299E-06 300 4.134E-06 4.202C-06 4.265E-06 4.ItHE-04 4.2400-06 4.2310-04 4 215E-04 4.lVHE-04 4.102C- 06 4.166C-06 4.150E-06 r.
m 'on- 4.103C-06 .4.007E-06 4.0/20-04' 4.054E-06 4.04tE-04 4.026C-06 4.oltC-06 3.9V60 06 p ((' 310 *3.902C-06 3.9670-06 3.953C-06 3.930E-06 ~3.Y24C-06 3.910E-06 3.0Y6C-06*3.002E-06 3.H6HE-06 3.054C-06 I$
,m *320 3.040C-04 3.027C-06 3.033E-06 3.000E-06 3.7116E-06 3.773C-06 3.7400-06 3.747C-06 3.734C-06 J./2tC-06
- _$% 330 3.709C-04 3.696E-06 3.603E-06 3.6/1C-06 3.45HE-06 3.6460-04 3.6340-06 3.6228. 06 3.610C-06 3.5711C-06 0 D '"
3 40 --3.504E 3.574C-06 3.562E-04 3.5500-04 *3.53YC-04 3.5270-06 3.514E-04 ~3.50 4C-04 ' 3. 4Y3C-06 3. 402C-06 '
- 350 3.471E-04 3.460E-06 3.449E-06 3.43HE-06 3.427C-04 3.416C-06 3.405C-06 3.394C-04 3.3f14E-04 3.17.lC -06 360 3.363E-06 3.352C-04 3.342E-06 3.332E-06 3.322C-06 3.312C-06 3.301E-06 3.29tE-06 3.2010-06 3.272C-06
'370- 3.26 E-06 3 252E-06 3.212C-04 3.233E-06 3.223E-06 3.213C-04 3.204C-06~ 3.I?5t~06 3.3H5C-06 3.1740-06 e 300 13.167E-06 3.157E-06 3.140C-06 3.13YE-04 3.130C-04 3.121C-04
~
3.112C-06 3.103E-06 3.094E-06 3.0H41 04
.3?O 3.077E-06 3.06HE-06 3.060C-04' 3.051E-06 3.0428i-06' 3.0.14F-06 3.026C-04 3.017C-06 3.00VC-06 3.001C -06 400 2.992C-04 2.904E-06 2.Y/6C-04 2.Y4HC-04 2.960E-04 2. Yn?C -04 2.Y440-062.936C 06 2.920C-06 2.V?OC-06 *
. 410 2.912C-06 2.905E-06 2.Uv/E-06 2.00VE-06 2.1102E-06 2.H74E-06 2.064E-06 2.0590-06 2.0510-06 2.044E-06 f 420 2.037E-04 2.029E-06 2.022C-06 2.015E-06 2.ud7C-04 2.0000-06 2.793E-06 2.706E-06 2.779E-04 2. 7 /2C- 04
~430~'2.76SE-06 2.75HE-04 2.75tE-04 2.744C-06 2.737E-06 2. 7.50C-06 2.724C-04 "2.7170 06 2.7100-04 2.703C-06 440 2.6Y/C-06 2.6YOC-06 2.601C-06 2.6/70-06 2.6700-04 2.6640-06 2.65/C-06 2.6'.10 06 2.6".C 06 2.4 tut- e6
'450 2.432C-04 2.626C-06 2.6tVC-06 2.613E-06 2.40/E-04 2.A010-05 2.5VLC-04 2.500C-04 2.LH2E-04 2.5/61 n$
-460-2.570E-06 2.564E-06 2.550C-06 2.bd2C 2.5470-04 2.L41E-06 2. dant?-06 '- 2.52VC 2.52.50 -06 ,. 2.517E 06 -
4/O- 2.512C-04 2.506E-06 2.500L-04 2 495C-04 2.4alvE-06 2.403E-06 2.47HE-04 2.472C-04 2.46/C-04 2.463r *,6 1 e
s 1
~"' .yb 3 0$ $*v.
6446646446545665646666466666444664646666444664 0000000000000000000000000000000000000000000000
- - - - - - - - - - - - - - - - - - - - - - 4 - - - - - - - - - - - - - - -
0EEEECEcCC0CCE0CFE0CCCCF0CLECCrE00EC rECEE1 EEEr 767052t i 360A321 1 350273Y71 1 22234A01 4H272/20S1 H5 05061 73Y4l 04l 052V431 061 1 9/S319/L320H/5421 90754 1 1 44433333322222 4332211 0 0. . O. V. 9. Y. lI. 1 4 7 7 7 7 6 6 4 6 5 5. S. 5 5 4 4 4. 222222222211 11 11111 1 111111 111111 11 1 1 1 1 111 1 1 1 11 6646644444664444664644664446444464444444444646 0000000000000000000000000000000000000000000000
- - - - - - - o - - - - - - -
EC C E E6V404L444H1 31 2506L: 0 C '4 CCCLCL0EEE000EECECCCLL0L0E0l 5052Y7h44454U036o4H304062Y5 8 Cr0rLCCC1 161627395t 1 h1 HL21441 9441 Y/S31V7L420Y/N421 0H7L4 1 4332211
. 0 0 0 9. v. 9. H. 0 0 7 7 7 7 6 6 6 6 5 5 5 5 5 4 4 41.4435 333332222 .
22222222221 11 1 1111 1 1 11 1 1 1 1 1 1 11 11 1 11 1 1 11 1 1 f 1 111 64666444444644646444464444444444444444S6444444 00000000000000000000000000000000000000O0000000
" " o - - - - - - - - - - - - - - - -
EE C E E C C r C C E C C C 0 E E C C 0 C 0 C C f E C C C C C C C C C f r C C 0 E 1 CEE: I 06794O9Y03/3037701 402041 050L1 ?41 H 16162H3V62u520529741 9642?/531 ?/444/HO2bHlY7A420?5445 0u761 1 4332211 1
. 0 0 0. Y. 9 9 010 7 7 7 7 6 6 6 6 5 5 5 5 5 4 4 4 4 4 4 3 3 3 3 3 3 3 2 2 2 2 i 222222222211 1 1111 1 1111 1 11 1 11111 1 11 1 111 11 1 1 11l1
- - ~ - - - - " - - -
666464466666' 4646646444464444446444444446644464 0000000000000000000000000000000000000000000000 EE E E E C C C C E E C C 0 C E E C C 0 C C C E C r C E C C f f C C E r E C C C C C C E E C 31 24055 34/1 431 001 36050631 Y0HH901 46V3 e1 61 72YL2Y 272720406295214307429/420/5319061?077441 1 00/64 4332211 1009990.I. 0077766644555544444433333332222 _ l 22222222221 11 111 111 1 1 11 11 1 1111 1 113 1 111 111 111 11
' ~
6446644466666466644646464646664464466464646646 0000000000000000000000000000000000000000000000 "
- EE C E E C C 0 t E C 0 L 0 E C E C l CECCCCtCCEECC0CEI 96 6 Y 3 Y / 7 u 0 4 0 6 4 3 3 4 6 Y 3 7 3 9 6 3 l 0000235H3 N C SH Rt CCC0EEEC 8 1 H40630
- 272/304043942763071 433221 . . 1 0 0 9 9.
1 277420u4420H4421 ?/6431 0Y765 Y. 0 0 0. H. 7 7. /. 6 6 6 6 6. S. 5 5 5 5 4 4 4 4 4 3 3 3 3 3 3 3 2 2 2 2
.- 2222222222111 1 11 11 1 1 1 1 1 11 1 11 11 1 1 1 11 111 1 11 111 11 6666666444446464444666446644444666444466664464 0000000000000000000000000000000000000000000000 EE E E C C E C C C E 0 C C C C E 0 C C C E C C C C C C 0 C C C L C C f C C E E C C C E C E 4213733 01 4u30/66/925051 054222235/03404Y495t H42 303039S173?43943O752075200442006431 V04431 09745 43 3 2 21 .t .10 0 9. Y. 9 0 0 0. U. 7 7 7 7 6 6 6 6 5 0 5 5 5 4 4 4 4 4 3 3 3 3 3 3 3 2 2 2 2 2222222222111111 111 1 11 111 11111 1111 111111111111 6 6 6 6 6 4 6 6 6 6 6 6' 4666646666644666664446466666444644 0000000000000000000000000000000000000000000000
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ~ - - - - - - - - - -
EE E C E E 0 E E E 0 E E E E E E E C E C C C E E 0 0 E C E C E C C E C E C E E C E E C E E Y/602t5450163099024H2D40H6544457Y1 4H261 62 / 3963 l 30 3 0 4 9 517 3 0 6 3 0 6 310 b 2 0 / 5 3 0 0 6 4 2 0 H 4 4 31 90653209765 4332211 1 0 0 0 9 9. '9 0 0 0 7 7 7 7 6 6 6. '6 5 5 5 5 5 4 4 4.'4 4 3 3 3 3. J. 3 3 2 2 0 2 22222222222111 11 111 1 11111 1 11 11 1 1 111 11 1 11 1 11 111 4666666446646666666466646464644446644444466466 0000000000000000000000000000000000000000000000 EE C E E C E C E 0 t C C C C E C r L 0 C E C E E E F E E E E C 0 E E r E F C E" C E E E C E 52 1362YHY1 50442234/050630H/664791 34Y3/2/2H40/4 4949405174073074 105300531 H6420H6S38 9H4SJ20Y045 4332221 1 0 0 0. Y. V. 9 0 0 0 7 7 7 7 4 6 6 4. L. 5 5 5 5 4 4 4 4 4 3 3 3 3 3 3 3 2 2 2 2 2222222222211 111 111111111 1 11111 111 1 1 11 11 111111 4646646446464666646664664644446666644664446644 - - -0000000000000000000000000000000000000000000000 - EE E C E E E E C E E E C E E E E C 0 E E E E E E E E E E 0 C E E E C E C C E E E E E E E E 07601 6423593975557037205209000Y82501 L94Y4Vh2H5 5949506204073074106300531 9642007531 0l 45320V065 f 4332221 1 0009990.H.077776666555554444443333332222 22222222222111111111 111111111111111 111 11 1 1111 1 6666466446666466444466666666644646664644664666 0000000000000000000000000000000000000000000000 EE E E E E 0 E E E E E E E E E E E C E E E E C E C E E E E E E C E E C 0 E E E E E E E E E 4210 610 / 7 ? 2 7 3 0 0 0 H 0 2 5 051 74210001 247?36t 50517307 50505162O41741 741V6J1 0631 97531 Y7531 0075421 Y075 4433221 1.O.0099900077776666555554444443333332222 2222222222211 111111111111 1l1 1 1 1 111 1 111111 111 11 -
- - - ~ .- - ~ .
Y E 00000000000O0000000000000000000000000000000000 2345670Y01 23456709012345670901 2345470901 23 8 44555555555S664666666677777777770001 01 1 0609999 1 1 J. 09 -01 - - ~ '- - - * - - - , ~ ! .* as r 3t[n[n$ r "' mpy N O9e
- - . - ~=-~ -c ~- ._ -. . . . _ . - . . - - . --- - -- . . - . . _ ---- .
, a to _ N_ _ . . _ - __. . _ _ _ . . . - . . . ..._. ...._.. _ .. _ _._ _ _ _ _ . ... - .v. ., 4 4 940 1.244C-06 1.243C-04 1.241C-06 1.240C-04 . 1.239C-06 1. 2.511C - 06 1.236C-co 1.235C-04 1.2J40-01 1 23JC-06
=
VLo I.23tC-06 1.230C-06 1.2290-06 1.2200-06 1.226C-06 1.22LC-06 1.224C-04 1. 22.1C--04 1.2J20 -06 1 2?Of -04
~~ Y40 1.219C-06 1.210C-06 1.28'/C-06 1.216C-04 1.2140-05 1.283C-04 1.212C-06' 1.211C-04 't . 3 (pC-04 1.200t-04 970 1.2070-04 8.2040-06 1. 20*.C - 04 1.20ec-06 1.202C-04 1.20tC-06 1.200C-06 1.1998-043 J.110r-06 g 1.1Wr r06 9H0 1 1960-04 1.IV4C-04 1.IV3C-06 1.192C-Os 1.191(:~06 1.19 0C- 04 1.1H9C-05 1.10 7C-46 ' J .~10th04 1*.1 0 58.4 0 4,-
- 990 1 10 4r-04 1. l ti.30-04 1.lH2C-04 1.1010-04 1.100C-04 1.1/40 -05 ' t .17/C 1.1748* 04, 1. 8 7-2 04, ^ 1.17 H -04
,2000 1 173C-04 1.172C-06 1.17tC-06 1.170E-04 1.14t;C- 04 1.14/t-04 1.144C-04 1.1 A*,C -ON 4.164C-04 8 8410-04 1010 1.1420-04 1 1610-04 1.160C-04 1.!'sYC-04 1.15HC-04 1.1561:-04 1.155C-04 1.1540 04 1.153C-04 1.1521.-06 i - 1020 - 1.151 C 06 - t .1500-04 1.14YC-04 a.14fjC-06 -1.I4/C-06 1. I 44C -04 1. 3 4SC 1.14 48 04 1.I4.tr 04 1.142f-04 1030 1.141C-06 1.140C-04 1.139C-04 1.1.500-04 1.1360-04 1.1.5Lt. - 06 1.1.5 4C- 06 1.1350 06 8.132C-04 n.13sC-04 1040 ~ 1.1J00-04 1.12VC-04 1.1201-04 1.12/C-04 1.124C-06 1.12*r-06 1.124C-04 1.1251'-04 1.122C-04 1.1210-04
-- 1050 - 1.1200 t .119C-04 1.1IHC-04 1.It/E 1.I160-04 8.1I$r-04 1. I 14C-04 ~ l .113C -06 1.I12F-03 1. I I II -06 1060' 3.110C-06 1.109C-04 1.101'1 -04 1 10/E-04 1.1041-06 1.10St. - 04 1.10 lC -04 1.104t. 04 1.10.10-04 1.102L-04 1070 1.1080-06 1 1000-06 1.0VvC-06 1.ov00-04 1. 09 /C-04 1.0940-06 1.0v50-04 1.014r-04 s .09.lC -04 1.072r-06
** 1000 ' t .0Ylf-06 1.0Y00-06 1.0u9C -06 1. 0Hf;C- 04 1.00/t -04 1.0H4t: 04 1.0H4C-06 ~I.00LC-04 1.01140-04 1. 00.5 C - 04 1090 1.0000-06 1.001C-06 1.0000-04 1.07YC-04 1.0/HC-06 1. 07 /C- 0 4 1.0/40-04 1.075C-04 1.074C-06 1.074C-06 1100 1 0/3C-06 1.072C-06 1.07tE-04 1.070C-06 1.06VC-04 1.0400-04 1.0470-04 1.04AC-06 1.0450-OS 1.06b0-06 *
- 114 0 ' t .0441 1.0610 -04 1.062r-04 1.041C-06 1.0404 06 1. 0LvC- 04 1.0*,11C- 04 1. 0" Jar -o4 1.OS/r 1.0*;4r-06 1820 1.0$5C-04 1.054L-04 1.0"e tC - 06 1.052C-04 1. 05 t 1: -06 1.0510 06 1.0',00-04 1.o lvt 04 1 0 4stl 04 1 04/t 04 1130 1.044C-06 1.04bC-06 1.0450-04 1.044C-OS 1. 0 I SC -06 1.042r 06 1.0410-06 1.0400-o4 1.o.lVC-04 1.0 5Y1:-04 11140 1.030C-06 '3.037C-0*. 1.034C-04 1.03L0-04 1.054C-06 1.034r 06 ~ 1.033C-04 ~ 1.0.520 -06 1.0310-04 1.0300 1150 1.02VC-06 1.0290-06 1.02ttC -04 1.02/C-04 1.024C-04 1.0.St - 04 1.02La~04 1.0244-04 1.0231-04 1.022E-OS lido 1.02tC-06 1.020L-04 1.020C-06 1.Olvr-06 1.0100-06 1.01/L -05 1.0140-04 1.0140-04 1.OILE-06 1.014r-06
-1170 1.013C-04 1 012C-06 1.012C 1.0110-06 1.0100-06 1. 00VI. - 0 6 1.00tJt:-04
- 1 00HF -oa 1.00/t-04 1. oo4tH o6
- 11H0 1.0050-0A 1.005t-04 1.004L-04 1.00.5C-04 1.0020-04 1.0010-04 1.0010-04 9.vvvr-0/ v.992t 07 v vulr-o/
1190- 9.v74r-07 9.YAHC-07 Y.votr-07 Y.95 5C-0 / 9.Yl4C 07 v.Y 5tir 07 9.Y300-0/ V.92 3r -0/ 9.YthC-0/ Y.Youl-07 ~ 1200 " 9.9001:-07 Y.HY31-07 v . Hil ,C - 0 7 9.0//C-07 9. H /0C-0 7 Y.H4T o/ 9.UUN-07 9.04 tic 07 9.H10C-07 9.H.53C-07
. 1210 V.02LC-07 9.HtHC-07 v . H l ot.-0 / 9.003C-07 9.794C-07 Y.7fmC-O/ V . 71110-O / Y.7/4t*-O/ V.7440 -0/ 9. /59t~-0 7 1220 9.752C-07 9.745C-07 9.737C-07 9.7.500-07 v.72.lC-07 9. /1/ E -0 7 V./0!iC-07 9.70lt-0/ 9.494t>07 v . 4ts /E- o / ,
- 1230- V.4H66-07 9.472F-07 9.44".C-0 7 ' V . 450C -0 7 9.4%IC-07 9.6440-07 9. 4.5 /r-07 9.4.500-O/ V.42.11-07 9.416C-07 4 1240 9.607C-07 9.402C-07 9.Lv4C-07 v . Lil /C--0 7 9 .Sii00 -0 7 9.L/11-0/ V.L4/E-07 9.540s. 0/ v .M. il - 0 / v.L46L-OI 1250 v.5.1vC-07 V.S32C-07 9.S2nC- 0 7 9.5tHC-07 7.*.110-01 9.5010-o7 Y. 4Y /r -0 / v.49tr-07 v.4H41-0/ v.47/a--o/ , i
, ~1260 9.470C-07 v.443E-07 Y.4n4C-07 Y.4 SOC-07 9. 4 41tf o/ v.4'lar-07 9.42VC-07 ~9.42.1C 07 9. 4 3 40 - 07 v . aovC- 07 1270 9.403C-07 9 3940-0/ Y.3HvC-07 V . 3si2C-0 / 9.3/40-07 9.36vC-07 9.343C-07 9.3S40-0/ Y.54VC-01 Y.34tC-07 1
1260 v.3365-07 9.32?C-07 9.3?iC-07 9. 314C- 07 9.3100-0/ Y.303C-07 9.297t>0/ 9.2Yoc-0/ v . 21:4r- 0 7 v . 2 //C- o 7 , i 'O > 1290 9.27tC-07 9.264C-07 Y.250C 07 9.251C-07 9.245C-07 9.2 iff -0 / ' 9.2.52C-07 9.224C 07 9.21vf-0/ v.213r g 1300 9.204C-07 ?.2008907 9.194C-07 v .1ll/C -0 / 5.lutC-o/ 9.17:E -0 7 9.14HC- 0 7 9.34?r of v . t S/.r - 0 / y. l avr -07 0 y 1310 9.14 3 C--07 9.13/E-07 9.1.310-0/ v.1248:-07 v.!!GC-07 9.112s:-01 Y.104C-0/ 9.0996~07 Y.091F-0/ V . 0H /L - 0 / g w *r - 1320 -?.0010-07 9.07LE-07 9.06VE-07 9.042C-07 9.054C-07 v .0S08.-0 / '9.044C-07 9.05HC 07 9.0520 07 v.024C 07 in ok mp 13:50 1340 9.000F-07 9.013E-07 9. 0Mr --0 7 v.001E-07 U . YYLC- 0 7 0.9590-07 0.9530-07 0.94/C-07 U.981C-07 U.935C-07 0.927C-07 0.Y23C-0/ 0.9870-07 0.9120-07 0.9090-07 0.vu1C-07 0.9/7C-07 11.971C-07 U.94*,L-07 0.904C-07 P o p" -1350 U.900E-07 0.0Y4E-07 0.00Hf 0/ H.HH20-07 0.H/4C-07 H.H/et,0/ H.t:4 M - 07 U.HLyL-07 H.0s st> o p is.H UC-07 ."
- u. 1360 0.041E-07 0.I1350-0/ ll . t Clot -0 7 0.024C-07 0.01HC-0/ 0.ul.'C-07 U . H0 7C -07 is. Holt -O/ 0. 77dt ?-07 u.7Hyt-07 N 1370 H.704C-07 0.7/00-07 H.7720-0/ H.76/r-07 II . 74 t C - 0 / 0. /%C -0 7 H . / 4 9C- 07 el.744C-07 H . / 30ti -0 / H. 713r-0 7
; - 1500 U.72/C-07 0.7210-07 0.716C-o/ ti . 710C-4 7 H.704r-07 t!.6vit-07 0.493C 07 U.4HHC -07 H.6H2C-07 0.6//C-07 13V0 0.671C-07 0.665E-07 0.660C-07 U. 454C- 0 7 U.64YC-07 8.643C-0/ H .6.lHC -0 / U . A .12C- 0 7 U . 42 /C-07 U.4210-07 4 1400 H.416C-07 H.4100-07 U.6oLC-07 U.6000-07 H.bv4C-0/ II.LH94 -0 / H.5030-0/ H . 5 /13( ~ 0 7 H.572t>07 H.b67C-0/
1410- U.t42C-07 U.554C-0/ H.SLir-07 H.3440 01 H.540C-07 11. *. 55r -o / H.529t%07 ' n.5240- 07 H.navr 07 H.5tir-07~ 1120 0.*iOHC-0/ H.TO3t-07 0.4YHC-07 ti . 4 V 21. -0 7 H.461/C 0/ II . 4H.'F -0 / H.4/4C-0/ O.47tE 0/ H.4448-0/ H.44 tt 07 i 1430 U.4%C-07 U.450F-0/ H.4151.-07 H.440C 0/ H.15 C-O / ti. 4:"/C 07 H.4240-0/ U. 4 t Yi: - o / H.4844-0/ 18.4090-O/
-1440 H.404C-07 H . 3 YflC-0 / 0.3V14- OI U.3Htit -07 U . .lH3 C - 0 7 H.3/ tlc-O/ U. 31.50 -0 / 0.3AHC -07 0. 343C-07 0.3570 07-j 1450 H.552E-07 U.J470-O/ H.342r-01 H.33/C-07 H.3520-07 U.32/E-O/ II.522C-0/ H . 31 /t. - 0 / 13. 312L -0 / .l . 30 /r -0 /
14s0 0.302C-07 'O.297C-07 H.2v2C-07 H.237E-07 H . 2112C -07 H.27/r-0/ H . 2 /.'t.- 0 7 II.24/L-O/ U.2421-O/ If.2b/r -0 / } 14/6 ft.* .? of es. ? t /s or e s . .* 4 ?: or H.
- t /r or H. .s t as' o r .t . =? /s of H.**tt os a t . ? ns- of H . 2 3 10. of 16. "pDs e/
4 14 tN ti.2031-0/ H. l VilF O / H . I v.11 - o / H.181:n -0/ 11.1H 1r O / H.8/vl-0/ H .1/ 4t 0# 11 . 3 4 *, 8 6/ H. t a tt of H.l*..1 of k a i
- 4
u
* \
KEV
~14YO 0 7155C'07 O fl50E-07-- 0 3145C607 0 r140Cd07 0.000E-07' IJTI 16E=07~ 07131C307 O.c03C-07 D T126E-07 0.079C-07 07:28 CdO7 0.074E-07 Ust it.C=07~
0.067C-07 0 t 3 2C-07~ II.06LC-07 , 1500 0.107C-07 0.102E-07 6.090E-07 0.093E-07 0.046C-07 0.04tt-07 0 037C-07 0.0J2C-07 0.027C-07 U. 02:1C-07 0.030C-07 1510 0.060C-07 0.055E-07 0.05tE-07
" 1520 u.013E-07 ~ D . 009E-07 0.004C-07 -'H .000C 7; ??SC 7. ?v i c-07-~ 7 J 706C 7;90 tC-07-- 7.777C 7. v 72C 7.936C-0/ 7.932C-07 7.v2/r-O/
7 945C-07 7.94tE-07 ! 1L30 7.V60C-07 7 943C-07 7 959C-07 7.VL4E-07 '7.950C-07 7.076C-07 7.nytt-07 7.uu?C-07 7.fHi?C - 0 / 7.923C-07 7 v10E-07 7.?t4E-07 7.90VE-07 7.vo$C-07 7.700E-07 1540 7. 056C-0 / " 7. t152C-4 / - 7. H 4?C-0 / 7. H 41C- 0 / / .H itsC
- o r
~1550 7 070C-07 7.074C-0/' 7.06?C-07 7 04LC-01' 7.n60C-07 7 012C-0~/ 7. 00i? C-0 7 7 001C-o / 7.7?vr-07 7.795C-0/
1540 7.0JiC-0/ 7.n30C-07 7.ll2LC -0 / 7.H21E-07 7.Ht7C-07 7./L4C-07 7 752C-0/
-1570 7 79tC-07 7 706E-07 7.7H2C-07 7 77nc-0/ 7.71.lC-07 7 76YC-07 7.765C-07 7./610-0/
7.739C-07 7.735C-07 7. 7:19 t:-0 7 7. 72 /C-07 7.722C 7.7 3 6C-07 7.7140-07 " 7. 7 3 0C- o 7 -
- 1L00 7.*740C-07' 7.743C-07 7.4uaE-07 7 400E-07 7 676C-0/ 7 672C-0/ 7.6600-0/
1510, 7 '-*s C -0 7 7 701E-07 7.697C-07 7.69JC-07 7 607C-07 7.63tt-07 7 62/C-01 1600 7..s4E-07 7.660E-07 7.6L5E-0/ 7 65 t C-0 / 7 647E-07 7.643C-07 7.639C-07 7.635C-07 7.Lv00-0 / - 7.Luar -0 / - 606C-07 7.602C-07 - 7 5?nC-07 -7 594C-07
--1610 -* 7 623E 7 610E-0 7 ' 7.614C-0 7 7 6t0E-07 -7 67.5640-0/ 7.562E-07 7 550C-07 7.554C-07 7 5500-07 7.54 6r-0 /
1620 7 502E-07 7 57HC-07 7.L74C-07 7 5/0E-07 1630 7 540E-07 7.51HE-07 7.bj4C-07 7.530C-07 7,.5?6E-07 7. 7 522C-07 7 514C-07 7.584C-07 7.5100-0/ 7.L060-0/ 4 02C-0 7 ~ 7. 4 7HC-07 "7. 4 75C-0 7 7 4 710-07 ' 7 467C-07
--1640 7.502C-07 "7 470C-07 '7.4?iC-07
- 7 470E 7 406C-07 1650 7.463E-07 7.457E-07 7 455E-07 7 451E-07 7 447C-07 7 413E-07 7.440E-07 7 436C-07i 7 432C-07 7 4200-0/
1660 7.424E-07 7 420C-07 7 416C-07 7 4tJC-07 7 409C-07 7 405C-07 7 40tE-07 7 37/C-01 7 3 var-07 7.Jvoc-07 7. 35?C- 0 7 *
- 1670- -7 304E-07 "7 302E-07
- 7.3 70C-07 -7.375C 7 37 t C 7 347C 7 343C-07 --7. 359C-078"7.356C-07 7.J22C-07 7.3 titC-07 7. J l br - 0 /
1600 7.34HE-07 7 344C-07 7 348C-07 7 337C-07 7.33:lC-07 7 32vC-07 7.326E-07 7 21:1C-07 1690 7.3ttE-O/ 7.307E-07 7 304C-07 7 300C-07 7.276C-07 7.29?C-07 7.2avC-07 7.?oLC-07 7.2/ut-o/ 7 249C-07 7 24LC-07 7.24 t t -o /-
-1700- 7.274C-07 "7.270C-07 -- 7.267C-07' 7 263E 7.25?C 7 256C-07
- 7.252C-07 7.214E-07 7.2t?C-0/ 7.20?C-0/ 7 2c5C-0/
1710 7.230E-07 7 234C-07 7 230C-07 7 227C-07 7 22JE-07 7.220C-07 7.tH4C-07 7.100C-07 7.177C-07 7 3/ac-o/ 7.37o0-07 1720*7.202C-07 7 1VDC-07 7.195E-07 7 19tC-07 7.3H7C-47
-1730 -- 7 ; t a6E-07 ' 7 3 43E-07 "7 159E-01 7 154C-07 ~ 7. t s?E-01. 7 14?E-0 7. -7.14GE-07 --7 & l 42C-0 7 '
- 7. 3 :tHC-0 / - 7.13LC- 07 1740 7.13tE-07 7.12nC-07 7.124C-07 7.12tE-07 7.it7C-07 77114C-07 079C-0/
7.lt0C-07 7.107C-07 7.101r-0 7.076t-07 7 0/2C-0/ 7.06vC-07 ,7.onet-0/ ~
/ 7.toeC-07 1750 7.096E-07 7 0V3E-07 7.0900-07 7.006E-07 7.00tE-07
- 1760-- 7.062E-0 7 - 7.05?C 7. 055E-07 7.052C-07 7.0 4HC 7.015C-0 7 - 7 4 042C-07-- 7.0100-07. 7. 0 35r-0 /- 7. 032r -o / m
- 1770 7.020C-07 7.025E-07 7.021C-07 7 010E-07 7.015C-01 6.7/DC-07 7.000C-07 7.011C-0/ 7.005C-0/ 7.00tC-0/ 6.vync-07 4.975C-07 4.7710-07 6.v6nq-07 6.9650 0/ -
1700 6.975C-07 6.99)E-07 6.90nE-07 4.905E-07 6.tutE-07 6.9 4 5E-0 7 ' 4 4 7 4 2E-07 --6.9 37C-07 . 6.93r.C-0 / 6.93?C-07 1790"6.962r-07 -6.950E-07 -6.vn5C-07 6.952E-0 7 6. 7 40E-07 6.916C-07 6.vt3E-07 6.70?C-07 6.906C-07 6.votC-0/ 4.900r-0 / 6.V2VE-07 6 926E-07 6.9220-07 6.vi 9C '07
,o y 1000 4.0V6C-07 6.093E-07 6.070E-07 6.007E-07 6.004C-07 4. OOOC -07 6.077E-07 6.074C-07 6.H/ C-07 6.040r-0/
p n 1010 b
$ C -1020"- 6.86 4C-07 --6.061E 6. 05HE 6.055E-0 7 - 6.052C 6. 0 4YC- 0 7- 6. 0 4tC-07-o 6.0tlE-07 ; 0 42C 6. n3?C-07r 6.036 _-0 7 6.000C-07 6.005C-o7 -
q lil30 4.0.13E-07 6.030E-07 6.026E-07 6.0236-07 6.020C-07 6.H17C-07 -6.014E-07 6.700C-07 6.777C-07 6.7/4C-0/0. p b 1040 6.UOtE-07 6.790C-0/ 6.775C-07 6.792E-07 6.7a?C-07 4.7a&E-07 6.703C-07 6.761C 6.750C-07 4.75LC-0 7 "- 6. 752E 6.747C-0 7
- 6.746C-07 6. / 4 3r -01 o *
, k $ IU50- 4.7/0C 4.767C-07 " 6.76 4C-07 6.73tC-07 6. 72nt -07 6.725C-0/ 6.722C-07 4./tvC-07 6.716C-07 6.78 tt o/ o 6.7J4C-07 n 1060 6.740C-07 6.737C-07 v.3070 6.7100-07 6.707E-07 6.704C-0/ 6.703C-07 6.6v0C-07 6.675C-07 6.672C-07 6.4HvC-0 7 6.6 Hot-07 6.603C-0/f'
-1000 - 6. 600E-07 ~ 6.4770-0 / ' 6. 67 4C 6. 6 /I E-07 -- A6.630C-07 . 660E-0 7 - 6. 645C-0 7 ' 6. 642E-07 -6 4 45?C-0 7"-6. 6L6C-0 /-- 6. 65 tC-0 7 u
- 6. 6:tLE-0 7 6.632C-07 6.62VC-01 4.627C-0/ 6.624r-07 1870 6.6 SOC-07 4.647C-07 6.644C-07 6.64E-07 6.603C-07 6. 4 00C- 0 7 6.Lv/C-07 6.Lv5C-o/
6.604E-07 1900 6.62 E-07 6.610E-07 6.6tGE-0/ 6.612C-07 6.60?E-07
- ! ? t o - 4.592E-07 ' 6.50?C-07,'6.5H4C-07 6.503C-07 6.500C-07' 6.51/C-07 6.574C 6.572C-07 4.513C-07
6.56?C-0 7 - 6.L46C-07 6.563C-07 6 560C-0/ 6.LL/C-07 6.554C-07 6.552C-07 6.54?C-0/ 6.546C-07 6.040C-0/ 6.51/C-07
1920 6.500C 07 4.LluC-07 6.LILC-07 6.512C-07 4.Lovt.o/
I?JO +4.L.15C-07 4.532E-07 6.5?vE-07 6.L26C-07 6.523C-01 6.473E-07-*6.4v0E-07 6.4H/C-07" 6.404C-07 6.4Har-67 1940 - 4.506C-07 ** 6.504C-07 '
- A.50 t C-0/
- 6. 470C-0 /
- 6. 47LC-07 6.457C-07 4.454r-o/
!?do 6.4??C-07 6.476E-07 6.473E-07 6.470C-07 6.460C-07 6.465C-07 6.462E-07 6.459r-07 6.42VC-07 6.42 /C ai?
.1960 6 45tC-07 6.44DC-07 6.446C-07 6.443C-07 6.440C-07 6.43HC-07 6.435C-07 6.432C-07 6. 402L 6. 4m U - o /
- 17/0 -6.424C-07 6.4210-07 4.4tvE-07 6. 416E-07 ' 6.6.306E-07 4 8 3C- 0/ - 6. 410E-07
- 6. 400C 6. 40%C-07 6.304E-07 6.3 HIC-07 4.3/HC-0/ 6.3/At-07 6.1/.9 - o /
19H0 6.37/C-07 6.374C-07 4.312C-07 4.301E-07 Ivv0 6.370C-07 6.34HC-07 6.36Lr-07 6.J62C-0/ 6.360C-01 6.L7C-0/ 4.3L tC 07 6.L21-0/ 4.349: -0/ 6. t m or 6.1204 o'
-200 *.. 344C-0/ 4.341C-0/ 6 33?E-07 6.336C 6.333C - 6.J3 t t 07 * *6.320C-07 --6.32 6C-0 7 6 . 3 2 .11.- o /
I
19 AD 1850.04.3 Manual Calculations for Gamma Scectroscopy Sample No. Description Sample Date and Time Counting Date and Time Decay Time min Volume al Count Time see Detector Geometry Nuclide Energy key C- D pCi/ml = A~ *( 2
)
3.7 x 104 xExyaGx5xJ
'4he re :
A = Counts in total peak area 3 = Number of channels integrated C = Caunts in first ch2nnel of peak D = Counts in last channel of peak E = Efficiency for the detector and geometry used F = Volume of sample in milliliters G = Gamma abundance of photoreak (decimal fraction) H = Decay factor e-Att. Wherel equals ~0.693147 divided by the half life and t t is the decay time in the sa=e, units as the half-life. J = (1 - cAte) -here t2 is the count time in seconds and A is in inverse A seconds. If the count time is less than 10% of the half-life, simply enter the count time in seconds for "J". _END Attachment 6.
AD 1850.06 - Davis-Besse h - Power Station
- t. hit Ib.1 Mninistrative Procedure AD 1850.06 Padiation, Contamination and Jirborne Ihdimet.ivity obnitoring during Emergencies at the Davis-Besse Adninistration Ani Ming (DBAB) j r1 . . ,
. . . , f .[1
<J , n..,; ...a .U Beoord of Approval and Changes Prc M By Michael P. IIorne 6/8/82 Date Sutmitted By h. D 10 /15 / $2.
Section Head Date lhM By YF // MM p- - Date on Approved C. 7 .htd /d6 Quality Assurance Director
/2./r/72.-
'D9tte Approvod By Y 9M / Z--! 2! A Statica Supenntenepe Date Itvision SBS QA Sta. Supt.
No. Raccmnerdaticn Date 4 proved Date Approval Date i l l
1 AD 1850.06.0
- 1. PURPOSE 1.1 To provide instructions for radiation, contamination and airborne radioactivity monitoring during emergencies at the Davis-Besse Administration Building after it has been determined by the Chemist and Health Physicist or designee.
1.2 To provide instructions for issuing personal dosimetery for emergency response personnel at the DBAB. 1.3 Section 3.1 through 3.5 are to be implemented after the Chemist & Health Physicist or designee has declared that higher than radiological background levels are detected, as determined from a radiation reading, contamination smear, and an airborne I-131 sample collected outside the North Exit of the DBAB. ~
- 2. REFERENCES 2.1 HP 1601.04, Radiation, Contamination and Airborne Radio-activity Areas 2.2 HP 1602.01, External Pe'rsonnel Radiation Exposure Monitor-ing 2.3 HP 1604.01, Personnel Decontamination 2.4 Code of Federal Regulations 10 CFR 20 2.5 LI 4768.00, Stabilized Assay Meter SAM-2 2.6 EI 1300.07, Technical Support Center Activation
. 3. PROCEDURE -
3.1 Airborne Radioactivity Surveys NOTE: Airborne Radioactivity Samples will only be taken when installed building monitors are not working, or as a check of the installed monitors, or to monitor areas not monitored by installed monitors. 3.1.1 Collect air sample using a Low-Volume air sampler, place a charcoal and particulate paper in the sampler. 3.1.2 Collect the sample for 10 minutes. Record start and stop time. Record Sample Flow Rate and Times 5 on the Lab Data Card. ) i l i l l
2 AD 1850.06.0 , 3.1.3 When sample has been collected, remove charcoal and parti,culate filters from sampler and place in plastic bag and deliver to C&HP lab in the DBAB with Lab Data Card. 3.1.4 Sample will be analyzed with the SAM-2 or another instrument of equal sensitivity as determined by C&HP personnel. 3.1.5 To determine iodine activity in pCi/ml use the following formula for the SAM-2. Total Counts w wR unt T (Efficiency)(0.9)(28317)(2.22E+6) NOTE: Other Isotopes may be' analyzed with the SAM-2 but it will require resetting the instrument voltages. This should be done by experienced H.P. Techs. or Supervisor. 3.1.6 Record all data on Attachment VI. . 3.2 Contamination Surveys 3.2.1 Contamination surveys should be completed on a routine schedule, ie once every 4-8 house during the emergency as indicated on Attachment 1. 3.2.2 Areas to be surveyed are the Chem Lab, ECC, TSC, Media Center, Lobby and as directed by the H.P. Supervisor. 3.2.3 Smears should be counted with a BC-4, Frisker-RM-14 or PRM-4A or the equivalent as determined by C&HP personnel. 3.2.4 Report contamination in dpm/100cm2or dpm/ smear. 3.2.5 To figure the activity use the following formula: (Counts per min. - background) - dpm (Equipment Efficiency) 3.2.6 Ensure that all contamination in excess of 220 dpm/100cm2 is either deconned to less than 220 dps/100cm 2 or posted in accordance with HP 1601.04, Radiation, Contamination and Airborne ( Radioactivity Areas. 3.2.7 All swipe data should be entered on Attachment IV.
3 AD 1850.06.0 3.3 Radiation Surveys 3.3.1 Radiation surveys should be run on a routine basis in work areas and areas where radioactive , material might accululate, ie vent ducts, vent filters and the C&HP lab. 3.3.2 Areas should be posted in accordance with HP 1601.04, Radiation, Contamination and Airborne Radioactivity Areas. NOTE: Radiation survey points are indicated on Attachment 1. 3.3.3 All survey data should be entered on Attachment V. 3.4 Personnel Monitoring 3.4.1 TLD's and dosimeters will be issued by C&HP per-sonnel during emergencies to the following people listed on Attachment II. 3.4.2 Personal dosimetry will be picked up when arriving on site and returned prior to leaving site. 3.4.3 Emergency Personnel Dosimetry Issue Log (Attachment III) will be filled out for all persons issued dosimetry during the emergency. 3.4.4 Dosimetry shall be worn for duration of emergency and controlled by C&HP persons at DBAB. 3.5 Personnel Decon during Emergencies 3.5.1 Personnel are required to monitor their entire body with a frisker to ensure there is no exces-sive contamination on the body before leaving the control area between the Security Stations in the lower north half of the DBAB. 3.5.2 If contamination exist in amounts of 350 to 500 cpm above background, then personnel decon must be performed in accordance with HP 1604.01. NOTE: Use Radiac Toweletts and/or. Spray Foam for initial decon. 3.5.3 Simple decon methods should be used whenever possible. Rinse skin with demin water and catch excess in sink or bucket.
4 AD 1850.06.0 NOTE: This will normally be performed in the Radio-logical Testing Laboratory. 3.5.4 Recheck decon effort after each decon so as to minimize water use. 3.5.5 Clothes should be bagged and saved, shoe and hands may be deconed with tape. NOTE: Personnel or personal items are deconed when contamination levels decrease below 200 cpm above background during the emergency. 3.5.6 If further decon is required the individual (s) may be sent back on the station when possible. 3.5.7 If decon can't be accomplished or the-individual can't reenter the station and or injuries exist the individual may be sent to.the Magruder Hospital or St. Charles and treated. NOTE: If iodine contamination of skin is suspected and can not be removed from skin by normal , decon and the contamination level is greater 4 than 2000 d/m an evaluation will be made by the medical physician. Otherwise the iodine can be confirmed by using the SAM-2.to measure the , contamination. Iodine contamination can be absorbed through the skin. I I i f e
O e 5 AD 1850.06.0 e-------------.-------------------------------3, Attachment 1 ! y 6
- g ::
d
\ ! E 2 I = . il :.
zu A, s a2 . #1 4 E' l i!n .; :: . 3
- b '
' N S l ' v. s.-
. EX Z:::i :
'El Y 1
g r., l
, ll >
jj $ s, ! ! I N, . e N- :
- 4, N, .
j @ ! N.1 l j'i
/i f- i J l a
. I 3
r --D 0-- ; i 1 u o a.
- i. c 8.=
4~~ 2
= ,
$ v }
b 6 (2 h k*f
$l
. j 2 i 3
= >
5 O h .e y i *
* .LL 1 El
= + F~g 8 5 ys! . w.mne :
- C -
e be
= -
>*h we--
L 1 Hi e
; .a 5:
14 03 , d il i 0 5 N $ II g e,s 8 ! s 1 ei - 8 il L 1A 3 j
; 2 -
p(M p : 2 5 it ~* e q 91 ' l
$5 u e s d]g ae i 5- !
3 s 3:g3) "# 4 l g e 004 11 0 -l , ! h .- b i S : 2
~2 .a . ; ;
fg _** q
'$L--
1- E ;
,,, $1rl d
u } ,.,. h izd g : u , 6 a e j z . S :
---------------------------------------------s
--- . , . - _ - - - _ - , . - - _ . . , . , , _ . , ~ . . - , - - . . ,
l l 6 AD 1850.06.0 i Attachment II Persons Who Require Dosimetry
- 1) ECC a) Emergency Duty Officer e) County Communicator b) NRC Communicator f) Corporate Mgt. Communicator c) State Communicator g) Emergenc'y Ops.
d) Public Relations h) RMT's (8 to 10)
- 2) Technical Support Center a) Station Ops Manager e) C&HP Staff I
b) Station Ops Manager f) Nuc. Engr. Manager c) Plant Staff (3) g) Plant I&C Systems Engr. d) Technical-Engr. h) Plant Nuc. Systems Engr.
- 3) Persons not on the above list will be issued dosimetry on a need basis approved by the senior Chem and Health Physics individual at the DBAB.
l l i + I-Attachment II l Sheet I of I l I
.. . =. ..
t i r
;- ! 7 AD 1850.06.0 4
Attachment III Emergency ) 4 I Personnel Dosimetry Issue Log j NAME (Last, First, Mi.) SSil Company / Address i i i i 1 i 1 4 1 k 1 1 4 I I J l i i. 1 ( i t . ,I t 1 l l 1 l l Attachment III Page 1 of 1
I l DAVIS-8 ESSE S AD 1850.06.0 SPECIAL SMEAR SURVEY RESULTS ATTACIIMENT IV EO 6423 - SURVEY MADE SY OATE 7ggg INSTRUMENT USEO ISetas INSTRUMENT USEO (Alonal LEVEL BLOG. ROCM NOJNAME 'g, NO Beta Alpha
=
l i l I t VERIFICATION SIGN ATU R E/ TITLE DATE The contamenation teve4s are estner wetnin iemits orescribed EE E N in PT 5179.02, or tne action requered nos been enitiated, p
9 AD 1850.06.0 Attachment V OAVIS-BESSE NUCLEAR POWER STATION RADIATION /CONTAMIN ATION SURVEY O RouTmE uNiTNo. SPECIAL ALL READINGS /MR HR SUILOING LEVEL RCOM NAME N O. SURVEY SY CATE TIME INSTRUMENT USEC L. I. No. CALISRATICN OUE CATE INSTRUMENT USEO L. I. No. CAL 18R ATION OUE CATE CONTACT READINGS CIRCLEO CONTAMIN ATION LOCATIONS "SOXED ATIACHMENT V PAGE: 1 of 1 AREAS PCSTED AS RECUlREO SY HP 1601.04
$1GNATURE TITLE DATE
10 AD 1850.06.0 ATTACHMENT VI 't SPECIAL-AIRBORNE ACTIVITY ANALYSIS Date Tester Sample ID No. Room / Area Surveyed Level Equipment Used: Air Sampler LI No. Next Calibration Date Alpha Counter Used: LI No. S/y Counter Used: LI No'. Spectrometer Used: LI No. Tritium Analyzer Used: LI No. Sample: Start Stop Flow RESULTS FROM MPCAIR:
- NUCLIDE ACTIVITY pCi/cc %MPC a 1)
! 2) 3)
; 4) l
- 5) !
6) j ,
- 7) !
l a 8)I i I
- 9) i 10) i 11)i f 12 )'
13)! 14)l $ + 15)l, i i CAM Readings (I2) Total % MPC l l (Particulates) l
'(Noble Gases)
Attachment VI
- Page 1 of 2 l -
- l l
I- ___ .. ,_. _ _ _ ._
11 AD 1850.06.0 ATTACHMENT VI TRITIUM Sample: Start Time Stop Time ml in Bubbler Activity = ( pCi/ce) ( ml in bubbler) ( min) ( L/M) (1000 cc/L)(0.9 buffler eff)* pCi/cc PARTICULATES Filter Size 2" , 4" Sample: Start Time Stop Time (net PM) = pCi/cc Activity = (
- cc) ( min) (2.22 x 106) ( eff)
- Calculate volume in cc by:
Time x cfm x 2.8317 x 104 3 cc cc/ft = 3 Time x L/M x 1000 cc/L = cc If airborne radioactivity levels are less than 1x10-10 pCi/cc for I181; no action is required. If airborne radioactivity levels are greater than 1x10~10 pCi/ce, follow actions given in AD 1827.12. j Attachment VI END Page 2 of 2
r- . 6 cAra j INTMA.CQMPANY MEMONANCUM *
%: Rev. 12 - November 29, 1982
)
All Davis-Besse Station Personnel vnou suaaect Terrv Murray D # \y-First Aid Resoonse i ADMINISTRATIVE MD'.ORANDUM NO. 38-12 To meet the requirements of the Station Emergency Plan, its implementing prccedures, ana OSHA Standards, the following describes the organization of, and details the m nning for first aid response activities at DBNPS. I. ORGANIZATION A. During Normal Working Hours
. - First aid response shan consist of at least two first aid qualified employees. . Designated responders shan be assigned on a weekly basis
,' with postings in both SAS and the Control Room.
- 3. During Off-Normal Werking Hours
- First Aid Responders shall consist of at least two first aid qualified operators. The responders and a designated leader will be assignesd by * , the duty Shift Supervisor. Other department personnel qualified in first aid shan be identified and posted in both SAS and the Control Room when they are assigned to weekend or back shift coverage. These persons shall be recognized as support to the non-licensed operators responding. , ,
Ihe following personnel hold first aid qualifications in American Red Cross multi-media. standard first aid or the equivalent, and are qualified to be First Aid Responders at Davis-Besse Nuclear Power Station:
. Ron Scott ** Roger Fox Tom Given Rodney Lawrence Tom Isley** Mike Widner Suichi Kato Jim Fawcett Ted Lang** Rick Eibert Vern Patton Sam Childress Rich Jarosi** John Michalski Terry Smith John Bialorucki Bill Marce* Mary Ann Groot Chris Burns Larry Kaller Randy Baum* Jim Adams Larry Myers Jim Weaver John Staton* Erdal Caba Craig Gillig i Steve Henn* Jim Faris Richard Walleman Earl Murphy Ron Durdel Mark Klein Ray Zychowicz Fred Conn Jeff Malag Teresa Scott Al e eam Leaders u, Don Fox John House Bill Smith Tom Eiggins Al Coons Gary Schnabel Marty Migot Paul Haugh Steve Hill Tom Hansen -
Rudy Martin Denes Cousino Steve Fahrmann Bob Morrison
) George Buder Randy Patrick Neil Wilson Al Kohlenberg Ron Clark Jim Theisen
. . , John Hartigan Jeff Cleveland Tom Schell O'Nein Tate Carlo Pocino~ -
Mike McCloskey
r- . __ t Administrative Memorandum No. 38-12 Rev. 12 - November 29, 1982 First Aid Response Page Two Other station personnel qualified to creat an injured employee, through off-site certification (i.e., First Aid Responders, EMT, etc.). I Larry Kremke Dave Haley Clarence DeTray Dan Lenke Duane Jess Bill Nissen During the immediacy of the moment, in the absence of a designated First Aid ; Team Leader or assigned alternate leader, a team member can and should perform such function so as to ensure prompt and proper care for the injured. REFEEINCES: , AD 1827.02, Medical Treatment of Injuries AD 1827.01, Annual Radiation E=ergency Medical' Exercise Special Order No. 19 - Site Nurse AD 1827.16, Search and Rescue
- HP 1604.01, Personnel Decontamination EI 1300.12, AAm4a4=trative Controls ese 9
4 e
- TDM/JL3/mdb i -
- 1. .
l
DATE N BA COMPANY MEMORANDUM ~ Rev. 11 - January 4, 1982 g nev. a .w c.a 4, isd Rev. 13 - July 15, 1982 l All Davis-Besse Station Fersonnel Tu Terry Murray USJECT Fire Brigade ADt1INISTRATIVE MEMORANDUM NO. 39-13
- 1. In accordance with the Station Emergency Flan and Technical Specification 6.0 1.1. Bill Nissen is the Fire Chief and Tom Almendinger is the Assistant Fire Chief.
1.2 The following named non art Fire Captains: Bob Mo h on John House (Asst. Capt.) Rick Walleman Larry Myers (Asst. Capt.) Terry Smith Larry Keller (Asst. Capt.) Mike McCloskey (Asst. Capt.) Greg Schumaker { Jim Fawcett Steve Fehrmann (Asst. Capt.) L'un Lenke (Security) Dave Haley (Ass t. Capt.) NOTE: In the absence of a Fire Captain on Shift, the Fire Chief or Asst. Fire Chief or Fire Marshall shall assume the duties of the Fire Captain. 1.3 The following named persons are the Fire Brigade Members necessary to nest the five member brigade: OPERATIONS
' Bob Mo d on Rod L&wrence ~Craig G1111g' Al Coons Dave Barker Larr/ Myers Don Bondy Tom Higgins Rick Welleman Neil Wilson Den Staude Vern Facton Paul Haugh Larry Keller Mark Klein 3 John House Mike Migot Ron Clark Steve Laeng Don Fox Kim Stiger Jim Theisen Tom Hansen Greg Schumaker Tom Schell Gene Hillebracht Tom Given Jim Fawcett Brian Young John 31alorucki Suichi Kato Stave Fehrmann I
i
~
l
Administrativo Memorcadum Na. 39-13 Rev. 13 - July 15, 1982 ._ Page Two SECURITY 0700-1500 1500-2300 2300-0700 . Jim Bilgen Neil Ammons 4 Bill Britenburg l Dave Haley Greg Hannan Jim Burr ' Jim Meisner Dan Lenke . Phil Shingledecker 4 1 1.4 The following named persons will be support Fire Brigade Members: Nelson Karafa Jim Magers Bill Merce Art Lewis , John Staton Ron Flood Mike Widner Bob Mizik
- 1 Ray Zychowicz Kent Rhubright Jim Michaelis Ted Bergner Steve Fessel Ted Lehman Bill Klippstein Terry Wagner i Rex Dietz Bob Bechtel Tom Almendinger k Nate Wahl Paul Timmerman Dennis Snyder Curry Lammon Scott Wise Doug Ricci Dennis Gordon Ted Poremski Larry Isbell Cal Hoffer
. 2. Fred Ross is the Fire Marshall Q /}'h W g Terry D. Murray ,
TDM/WLN/jas m
% s b
f
- i
.o ,. O -
DATE March 25, 1983 Rev. 27 if s, ' . COMPANY 42 MEMOftANDUM Page L l-' All Davis-Besse Station Personnel
%uu 7 Q @(.
.-- Terry Murray E .uacT v Emergency Duty Officer (EDO) and Other Emergency Duties AD M ISTRATIVE MEMORANDUM NO. 41-27
;, 1. Emergenev Dutv Officers (ED0's) 1.1 In accordance with the Davis-Besse Emergency Plan, the following named individuals are qualified and designated as Emergency Duty Officers:
. C. T. Dafr D. A. Euffman t R. R. Durdal R. F. Peters J. A. Faris D. L. Rhodes
.' J. L. Freels J. H. Syrowski L, 3. L. Geddes J. L. Scott-Wasilk C. J. Greer S. G. Wideman L. A. Gri=e W. L. Yarosz S. A. Hall 1.2 Emerge-i.cy Duty Officers, in addition to the requirements in the Station Emergency Plan, are responsible for the administrative t- items as given in Section 5 of EI 1300.12, Administrative Controls.
1.3 The following persons have been trained and are qualified as Emergency Assistants, to assist the EDO in the Emergency Control Center (ECC), if necessary. Gary Downing Rex Rutledge Richard Vollmar Joyce Badik Larry Konopka Rick Sharpe Judy Vineyard Debra Goetz Marie Frazer Dennis Gordon Charles Rupp James Adams Kelly Clayton Jeff Lieczov L 2. Other E=argenev Duties l- 2.1 The Station Superintendent or his designee is to be notified by I the Shift Supervisor of any condition which requires an
'~
immediate report and/or notification to the NRC. 4
- 3. EDO Schedule l
l , A revised EDO schedule for the second quarter of 1983 is attached. TDM:nif enc 1. . O
-.m- *- -z. g ar- - + - - v ----eev ~ ----- - --
.+ .- o _
1 oATe ! if~ '. COMPANY MEMORANDUM March 25, 1983 Rev. 27 e on Page 1
,'" All Davis-Besse Station Personnel EnOM
.- Terry Murray / d @e r -
T.l . ueci u Emergency Duty Officer (EDO) and Other Emergency Duties ADMINISTRATIVE MEMORANDUM NO. 41-27
'_ l. Emergenev Dutv Officers (ED0's) 1.1 In accordance with the Davis-Besse Emergency Plan, the following named individuals are qualified and designated as Emergency Duty Officers:
. C. T. Daft D. A. Euffman i R. R. Durdal R. F. Peters J. A. Faris D. L. Rhodes J. L. Freels J. E. Syrowski L. B. L. Geddes J. L. Scott-Wasilk C. J. Greer S. G. Wideman L. A. Grime W. L. Yarosz S. A. Hall 1.2 Emergency Duty Officers, in addition to the requirements in the
- Station Emergency Plan, are responsible for the administrative L- items as given in Section 5 of EI 1300.12, Administrative Centrols.
1.3 The folicwing persons have been trained and are qualified as Emergency Assistants, to assist the EDO in'the Emergency Control Center (ECC), if necessary. Gary Downing Rex Eucledge Richard Vollmar Joyce Badik Larry Konopka Rick Sharpe Judy Vineyard Debra Goetz Marie Frazer Dennis Gordon Charles Rupp James Adams Kelly Clayton Jeff Lieczov L 2. Other E=ergency Duties
;- 2.1 The Station Superintendent or his designee is te be notified by I the Shift Supervisor of any condition which requires an l
- immediate report and/or notification to the NRC.
f 3. EDO Schedule A revised EDO schedule for the second quarter of 1983 is attached. L TDM:nif encl. , _ _ _ - . r__.__ _- _ _ _ _ , _ _ - _ - .
, _ . , . , , _ f ,,p , _ . , , . . . , - .
a i.
.I -
Admin. Memo No. 41-27 Rev. 27 - Mar. 25, 1983 Attachment Page 2 EDO 2nd QUARTER SCHEDULE - 1983 . I-Weeklv Dates Individual Assigned Mar. 28 - April 4 Steve Wideman April 4 - April 11
- Bill Yarosz April 11 - April 18 Chuck Daft ,
,' April 18 - April 25 Bruce Geddes April 25 -
May 2 Larry Grime May 2 - May 9
- Jim Greer May 9 - May 16 Stu Hall May 16 - May 23 Dave Euffman
, May 23 -
May 30 Bob Peters May 30 - June 6 Don Rhodes June 6 - June 13
- Jim Faris June 13 -
June 20 Ron Durdal June 20 - June 27 Jim Freels June 27 - Ju?y 4 Bill Yares: July 4 - July 11
- Jim Syrowski July 11 -
July 18 Steve Wideman July 18 Chuck Daft July 25 l_ I f,
- Denotes that week in which the EDO must perform the Monthly -
Communications Link Test, in accordance with PT 5108 . 01 . The
;- Emergency Planning Group will be present to assist with the j Communications Test each month.
o L WLY:nif. 03/23/83 r-l n. 87
.L N O I
w - . . > - - , , , , - - e y- , . -.=w
~
l
, . cara NTRA-COMPANY MEMORANDUM Rev. 17 - August 31, 1982
* *2 l ,_ _
Rev. 18 - October 16. 1082 Rev. 19 - February 28, 1983 % _- All Davis-Besse Station Fersennei
- nc i Terry D. Murray 9 MW- ~ =p i aus scT v ,
t. Radiation Monitoring Tea =s !,
. 4 ADMINISTRATIVE MEMORANDIDf NO. 42-19 In accordance with the Davis-Besse Emergency Plan, the following named people are qualified to be Radiation Monitoring Team Me=bers. AD 1850.05, Radiation Monitoring Team Surveys, provides instructions for collecting samples.
Sill Armstrong Bob Finneran John Tapley Mike Beier Randy Baus Tim Thompson ' Larry Bonker Jim Kal=back Tony Wakulenko ! Rick Edwards Greg McKarns Wayne Wiedenhef
; 9 Joan Niese Mark Rowland
(, Jack Ferguson Chuck Rider John Blankemeyer I Bill Frazer Reggie Rogers Bilal Sarsour (( Dennis Hennen Ed Rohrer Pete Senuik 1 Russ Hofer John Sankovich Mike Parker Dave Jazwiecki 2H11 Strahm Ted Lang Ford Kebker Jim Syrowski Ron Wolfe
. Linda Makatura Sy Syslo Jennifer Scott-Wasilk Lynn Harder Kevin Melstad Gary Downing Terry Tate Jeff Lietzow M
L I
, . bus I l TDM/DWB/14s t
l_ : e s . s. h em l __ _ _ >}}