ML20065U150
| ML20065U150 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 09/21/1982 |
| From: | Schuelke D NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20065U135 | List: |
| References | |
| PROC-820921-01, NUDOCS 8211030606 | |
| Download: ML20065U150 (249) | |
Text
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, _ PAGE 1 OF 2 l l EMERGENCY PLAN IMPLEMENTING l
^
l PRAIRIE ISLAND NUCLEAR JPROCEDURES l
( , l GENERATING PLANT l l
~I l NORTHERN STATES POWER COMPANY _ Jiumber: TABLE OF CONTENTS Rev: 15 l l History Copy l l n , lRetentien Time: Lifetime l l Reviewed By: [ ] // /. //, l l l
l h//". Miul/d/.
Supt. Rad Protection l TITLE:
l EMERGENCY PLAN l
l l
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_ gf., [. -
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IMPLEMENTING PROCEDURES TABLE OF CONTENTS l
l l l l l l l l ___l_ l l I l NUMBER TI T_L_E REV # l l 1 Onsite Errergency Organization 2 l I l l 2 Classifications of Emergencies 2 l l l l 3 Responsibilit.ies During a Notification of l l Unusual Event 2 l l 1 l 4 Responsibilities I;uring m Alert, Site Area, l l or General Emergency 6 l l l l 5 Emergency Notifications 5 !
'x_ / ! l l 6 Activation and Operatioa of Technical l l Support Center 2 l l l l 7 Activation and Operation of Operational l l Support Center 3 l 1 l l 8 Recommendationis for offsite Protective l l Actions 1 l l 1 l 9 Emergency Evacuation 1 l l l l 10 Personnel Accountability 2 l 1 l l
l 11 Search and Rescue 1 l I I l 12 Emergency Exposure Control 2 l 1 l l 13 Offsite Dose Calculations 3 l I 1 l 14.1 Onsite Radiological Monitoring 2 l l l l 14.2 Operations Emergency Surveys 0 l l l fQ C,1 l 15 Responsibilities of the Radiation Survey Teams During a Radioactive Airborne Release 5 l
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l l l l l IBM 8211030606 821025 PDR ADOCK 05000282 F PDR
Table of Contents
(, , Page 2 Rev. 15 NUMBER TITLE REV p 16 Responsibilities of the Radiat ion Survey Teams During a Radioactive Liquid Release 3 17 DELETED 18 Thyroid Iodine Blocking Agent (Potassium Iodide) 1 19 Personnel and Equipment tionitoring and Decontamination 0 20 Manual Determination of Railioactive Release Concent rations 2 21 Establishment of a Secoadary Access Control Point 2 22 Prairie Island Radiation Protec tion Group Response to a Monticello Emergency I m
23 Emergency Sampling 3 24 Record Keeping DurinF an Emergency 1 25 Re-Entry 2 26 DELETED 27 DELETED 28 Review and Revision of Emergency Plans 0 29 Emergency Security Procedures 1 O
v IBM
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, PAGE 1'OF 18 l l EMERGENCY PLAN IMPLEMENTING l p l PRAIRIE ISLAND NUCLEAR l PROCEDURES l Q l GENERATING PLANT l NORTHERN STATES POWER COMPANY l
Numbe r: F3-1 Rev: 2l l
l History Copy l l A ) J , Retention Time: Lifetime l M TITLE: l l Suptg Rad Protection l ONSITE EMERGENCY l l Approved By: y./,/f -7f l ORGANIZATION l l -(
a t . E 's l l l Plant Manager l l l OC#: ?- 2 /o - 72 l l l l l l l l l l 1.0 PURPOSE l l l l The purpose of this instruction is to: l l l l (1) Specify the onsite emergency organization during normal and l l off normal hours. l 1 l
- l (2) Specify primary designates and alternates for key emergency l i l organization positions, and l l l l (3) Establish individual responsibilities and duties. l 6 l 1 L ./ l The onsite emergency organization is illustrated in Figure 2, and l l is comprised of personnel from the normal plant organization l l (Figure 1). The detailed organization discussed in this procedure l l may be further augmented or decreased as the needs of the emergency l l condition dictate. Various responsibilities assigned to emergency l l organization personnel are shown in Figure 3. l l l l l l 2.0 PRECAUTIONS l l l l (1) Prairie Island plant staf f shall not make any information l i releases to members of the news media or the public. All l l l inquiries by the news media shall be directed to the NSP l l Communications Department at NSP Headquarters or to the Joint l l Public Information Center (JPIC) located at the Minnesota l l State Capitol in St. Paul. l l l l (2) In order to provide a sufficient number of alternates to fill l l the various Prairie Island emergency organization positions, l l some individuals (by title) are listed in more than one l l emergency organization position. In the event that an l l individual is assigned to more than one emergency organization l l position, the position required to implement immediate actions l l by the onsite emergency organization shall take precedence over l l all other positions. l (Q,) l l l l l l IBM
F3-1 Rev. 2 Page 2 l
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3.0 APPLICABILITY This procedure is applicable to all plant personnel.
4.0 RESPONSIBILITIES 4.1 DIRECTION AND CONTROL 4.1.1 Emergency Director (ED)
During the initial stages of an emergency condition, the Emergency Director lias overall coordinating auth-ority for HSP. The Emergency Director has the auth-ority and responsibility to immediately initiate any emergency actions including providing protective action recommendations to offsite authorities respon-sible for implementing offsite emergency measures.
Following activation of the corporate emergency organization, the Emergency Manager shall assume the offsite coordinating authority and the Emergency
. Director shall retain the responsibility for onsite operations.
(~'h During an emergency, the Duty Shift Supervisor of the
\_ ,/ unaffected unit assumes the responsibility of the Emergency Director.
The Shift Supervisor of the unaffected unit shall be relieved of the Emergency Director responsibilities when the designated Emergency Director arrives on-
- site. The Plant Manager shall be the designated Emer--
l gency Director and will be available with a pager on I
a twenty-four (24) hour basis. When he is unavailable, (e.g., out of town), the designated Emergency Director responsibility and pager will be passed down to the next individual in the line of succession.
J Any of the individuals above the Shift Supervisor in the line of succession may take over the responsibil-ty of the Emergency Director until the designated Emergency Director arrives onsite.
A. The line of succession for the Emergency Director position is as follows:
j (1) Plant Manager
- (2) Plant Supt. Engr. and Rad Prot.
(3) Plant Supt. Operations & Maintenance tg (4) Supt. Radiation Protection
(_,) (5) Duty Shift Supervisor of Unaffected Unit IBM k
F3-1
, Rev. 2
, Page 3 l NOTE: (a) The duty Shif t Supervisor of the l l affected unit, until relieved, shall l l remain in the Control Room at all l l times during accident situations l l to direct the activities of the l l Control Room operators. l I I l (b) Exceptions to the line of success- l l ion for the Emergency Director pos- l l Ition are individuals serving as l l STA. The STA shall not assume l l other emergency organization posit- l l ions until he is formally relieved l l by an alternate STA. l l- l B. The responsibilities of the Emergency Director are:
(1) Coordinate response of the plant onsite emergency organization; (2) Notify offsite authorities;
(- (3) Recommend offsite protective actions (this responsibility may not be dele-
! gated; -
(4) Direct the activation of all onsite emergency response centers, delegate coordinators for all onsite emergency response centers, and ensure that the emergency response center's envi-ronment is being monitored for habit-ability (5) Direct onsite protective actions as necessary; (6) Insure twenty-four (24) hour coverage for key positions in the onsite emer-gency organization;
, (7) During plant evacuations, initiate and i ensure that personnel accountability is completed within thirty (30) min-utes of declaration of emergency and maintained throughout the emergency condition;
( ,) (8) Authorize radiation exposure in excess of normal limits; IBM
l 1
F3-1
. Rev. 2 Page 4 (9) Ensure that radiological monitoring (onsite and offsite) is initiated (when required).
4.1.2 Emergency Manager (EM)
During an Alert, Site Area or General Emergency, the Corporate Nuclear Emergency Organization will be activated. It is expected that the Corporate Organization can be fully activated within approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of notification.
The Corporate Organization will base their oper-ations at the Near-Site EOF, under the dir-ection of the Emergency Manager (EM). A designated EOF Coordinator will be available at the EOF within I hour and may assume the Emergency Manager responsiblities until the designated Emergency Manager arrives.
The Emergency Manager will assume, from the Emergency Director, responsibility for overall management of f all offsite support efforts. This includes efforts performed to enhance control of the plant and efforts performed to determine the potential or actual radiological impact in the er.virons g of the plant.
A. Emergency Manager - alternates The Emergency Manager position should normally l be staffed by the General Manager, Nuclear Plants. In his absence the position shall be filled in a timely fashion by use of a call List. A designated EOF Coordinator may fill the role of Emergency Manager until one of the following ar, rives at the EOF.
(1) General Manager Nuclear Plants (2) General Manager Headquarters Nuclear Group (3) General Supt. Technical Services (4) Manager Production Training B. The responsibilities of the Emergency Manager are:
(1) Determine the extent of the offsite response.
(2) Make recommendations for the potential need for protective actions.
(3) Supervise the operation of the EOF.
IBM
F3-1 Rev. 2 Page 5 (s
(_,) (4) Direct personnel to provide the necessary offsite support for the plant as requested by the Emergency 1
Director.
(5) Provide technical support as necessary.
(6) Provide direction to personnel performing offsite radiation surveys and dose estimates as to the desired types of samples and sample location.
(7) Direct the activation of the Emergency Radiological Environmental Monitoring Program (EREMP) as needed.
(8) Direct personnel to provide the necessary logistics support for the plant and EOF operation.
(9) Provide information to the Power Production Management, as necessary, to assist in deve-lopment of news releases.
(10) Provide a direct interface with NRC rep-resentatives assigned to the EOF.
(11) Provide overall guidance to the corporate staff operating the IfQEC in the event that the Power Production Management is not available to assume control of HQEC oper-
,, ations.
1 (< l 4.2 EMERGENCY ORGANIZATION COORDINATORS 4.2.1 Technical Support Center Coordinator The Technical Support Center Coordinator shall be responsible for the general activation, operation and coordination of activities in the Technical Support Center (TSC).
A. The Technical Support Center Coordinator alternates are as follows:
(1) Supt. Operations Engineering (2) Supt. Technical Engineering (3) Supt. Nuclear Engineering (4) Supt. QA Engineering 1
(5) Senior Operations Engineer B. The responsibilities of the TSC Coordinator are:
(1) Establish and verify radiological monitor-i ing for the TSC; (2) Assist personnel performing the accountabil-ity check by completing the TSC personnel x_, accountability sheet; IBM i
F3-1 Rev. 2 Page 6 (3) Maintain or designate individuals to maintain records throughout the emergency condition.
(4) Coordinate activities of plant and non-plant personnel located in the TSC; (5) Establish or ensure that communications are established between all onsite emergency facilities and the EOF; (6) Periodically update personnel located in the TSC with appropriate informat-ion; (7) Maintain any necessary status boards; i
(8) Control the use of equipment located in the emergency locker; (9) Provide technical guidance to the Emer-gency Director and Control Room oper-
- ators on plant operations; (10) Obtain technical tssistance as required to support the Control Room operations.
i \s,/ 4.2.2 Operational Support Center Coordinator The Operational Support Center Coordinator shall be responsible for the general activation, oper-ation, and coordination of activities in the Operational Support Center (OSC).
A. The Operational Support Center Coordinator alternates are as.follows:
r (1) Maintenance Supervisor (2) Chief Station Electrician (3) I.& C Supervisor (4) I & C Coordinators B. The responsibilities of the OSC Coordinator are:
(1) Establish and verify radiological mon-l itoring for the OSC and the Control Room; (2) Coordinate activities of plant personnel located in the OSC to support plant oper-O ations as requested by the Control Room and TSC.
l IBM
F3-1 Rev. 2 6 j Page 7 b- (3) Assist personnel performing the account-ability check by completing the OSC accountability sheet.
(4) Maintain the communications systems in the OSC. A person may be des-ignated to act as a communicator.
{ (5) Periodically update personnel loc-ated in the OSC with appropriate information.
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(6) Control the use of equipment located in the emergency locker.
]l j 4.2.3 Assembly Point Coordinator I
The Assembly Point Coordinator shall be res-i ponsible for the general operation of the ass-embly area.
i l A. The Assembly Point Coordinator alternates are as follows:
l.
} (1) Radiation Protection Specialists (2) As directed by the Emergency Director B. The responsibilities of the Assembly Point i Coordinator are:
(1) Verify that radiological monitoring has been established for the Assembly Point.
(2) Coordinate activities of all personnel (plant and non plant) located at the Assembly Point.
(3) Assist the Emergency Director in performing the accountability check, as necessary.
(4) Maintain the communication systems. A person may be designated as the communicator, if necessary.
! (5) Control the use of equipment located in the Emergency Locker.
(6) Update all personnel with appropriate information when directed by the Emergency Director.
(7) Provide instructions to personnel when they are released from the assembly i point for reent ry or transport of fsite, IBM E _ , _ . _ _ _ . _ _ , , . - , _ . . _ . _ . _ _ _ _ _ _ , . - - - , _ , . . , _ _ _ , . - . _ _ , , _ _ _ _ _ . -
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F3-1
, Rev. 2 Page 8 g-'s b 4.2.4 Radiological Emergency Coordinator The Radiological Emergency Coordinator (REC) shall be responsible for radiological accident assessment, onsite and offsite. The REC shall report to the Technical Support Center when the TSC is activated. Upon activation of the Near-Site EOF, the Radiation Protection Support Super-visor will assume responsibility for the offsite surveys. The offsite survey teams will be comp-rised of individuals from the Monticello Nuclear Generating Plant. The REC shall maintain the responsibility for offsite dose projections and shall transmit all dose projection information to the Radiation Protection Support Supervisor at the Near-Site EOF.
A. The Radiological Emergency Coordinator (REC) alternates are as follows:
(1) Supt. Rad Protection (2) Senior Prod Engr - haa Prot Section (3) Rad Protection Supervisor (4) Radio-Chemistry Supervisor B. The responsibilitics of the REC are:
(1) Offsite dose assessment (2) Formulating offsite protective action recommendations (3) Offsite surveys (4) Onsite surveys (5) Chemistry (6) Radiochemistry (7) Onsite Radiation Protection for:
(a) access control (b) damage control and repair (c) search and rescue (d) first-aid (e) fire fighting (f) personnel monitoring & decontamination (g) dosimetry 4.3 SHIFT ORGANIZATION 4.3.1 Operations Group The Operations Group consist of the Supt. Operations, Shif t Supervisors, and all operators.
i IBM
F3-1
. Rev. 2 Page 9 A. Group Leader - Line of Sucession (1) Supt. Ope ra tions (2) Duty Shift Supervisor (3) Senior Shif t Supervisor present (4) Senior Lead or Reactor operator present B. Responsibilities The Operations Group shall have responsibil-ity for:
(1) Plant Operations and assessment of operational aspects of the emergency.
(2) Rad Waste equipment operation (3) Emergency radiation surveys (4) Short term damage control and repair for elect rical, mechanical, and I & C equipment (y
( ) 4.3.2 Security Group The Security Group consists of the Supervisor, Security and Services, the Shift Security Supervisor and the contract Guard Force.
A. Group Leader - Line of Succession (1) Supervisor Security and Services (2) Shift Security Supervisor (3) Guard Force B. Responsibilities The Guard Force shall:
(1) Carry out the plant security and Access Control program.
(2) Maintain strict personnel accountability onsite.
(3) Assist communications efforts when nec-essary.
O IBM
F3-1 i
Rev. 2 l l -Page 10 j 4.3.3 Shift Technical Advisor (STA)
The Shift Technical Advisor (STA) shall be onsite continuously. The STA acts as an ad-visor to the Shift Supervisor when on shift.
J j A. STA - Line of Succession-STA duty roster l B. Responsibilities 4 (1) Provide technical support to'the Shift Supervisor in the area of j operational event evaluation.
,f (2) Provide the Shift Supervisor-tech-nical and engineering support in the j area of accident assessment.
I l l l NOTE: The Shift Technical Advisor shall not l l l be assigned or assume duties which l l l could in any way inhibit his accident l j -
l assessment advisory function during l r
l an emergency, until properly relieved l
- l of his STA duties by another Shift l l Technical Advisor. l l l 4
4.3.4 Shift Emergency Communicator (SEC)
! The Shift Emergency Communicator (SEC) shall be i
- onsite continuously. The SEC is responsible i for initial notification and maintaining comm-i unications during emergency conditions.
I i A. SEC - Line of Succession 4
SEC duty roster t f
- B. Responsibilities 5
(1) Initial aotification of offsite agenc-
} ies and personnel.
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- -.. _ . - . _ = _ _ - . -. . . . - - - . . - . . . -
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2 F3-1 Rev. 2 Page 11 ,
i l l l NOTE: When the Corporate Emergency l l Organization is activated and l l the Near-Site EOF is functional, l
, l the communications with the off- l l l site agencies and personnel will l t
' l be maintained by the EOF person- l l nel. l l l (2) Augmentation of the plant staff.
(3) Maintain communication systems throughout the emergency situation.
l l
, l NOTE: As the emergency organization i 1 l is activated, addition commun- l l icators on the SEC duty roster !
l personnel will augment the l l plant staff to assist in the l l communication efforts. l l l '
s .
N 4.3.5 Fire Brigade 4
The Fire Brigade should consist of:
(1) Brigade Chief - Unit 2 Shift Supervisor 1
(2) Assistant Chief - Turbine or Auxiliary Building APE 0 t
l l l NOTE: Usually the APE 0 from the af fected l
, l building shall fulfill the duties l l l of the Brigade Chief in his absence.l l l (3) Fire Fighters - BOP Operators and Excess l CR Operators (two operators per unit i shall remain in the Control Room. j (4) Runner - As designated to accompany fire department or operate equipment.
During normal work hours, emergency assistance shall be provided by maintenance and plant helpers. During backshifts, or at the discretion of the Brigade Chief, s the Red Wing Fire Department shall provide Emerg-
! ency assistance and shall be called immediately on
) report of any fire requiring Fire Brigade Action.
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i F3-1
, Rev. 2 Page 12 [
A. Fire Brigade Chiel - Line of Succession (1) Unit 2 Shift Supe rvi sor (2) Turbine or Auxiiiary Building APE 0 B. Responsibilities (1) The Fire Brigade shall be respons-ihle for fire fighting. .
4.3.6 Shift Radiation Protection Specialist The Shift Radiation Protection Organization consist of one Radiation Protection Specialist onsite at all times. The RPS are normally res-ponsible for conducting routine and special surveys, chemistry, radiochemistry, maintaining ,
Access Control, writing RWP's and providing job coverage as required.
A. ShiIt RPS - Line at Succession (
(1) Shift HPS (2) Control Room licensed operators are trained to perform emergency radiation
- b. surveys.
B. Responsibilities I 1
During emergency conditions, the shift l Radiation Protection Specialist shall be responsible for:
(1) In-Plant surveys (2) Chemistry (3) Radiochemistry 4.4 Emergency Staff Augmentat ion Grotjug 4.4.1 Maintenance Group The Maintenance Group consists of all maintenance crew personnel, all plant electricians, and plant helpers.
The onsite Energency
. Organization includes, the Plant Supt. Operations and Maintenance, and the Supt.
Maintenance, who shall report to the Technical Support Center (TSC); and the Maintenance Super- ,
visors, Chief Station Electrician, and designated back-up Electricians who shall report to the Oper-ational Support Center (OSC). The mechanical and electrical maintenance staff in the OSC can be fur-ther augmented or decreased as emergency conditions e dictate.
IBM
F3-1 Rev. 2 Page 13 O
V A. Group Leader - hine of Successiou (1) Supt. Maintenance (2) Haintenance Supervisors (3) Chief Station Electrician B. Responsibilities The Mechanical and Electrical Maintenance Group '
i shall have responsibility for:
(1) Supporting the repair and corrective actions for the mechanical and electrical systems in support of emergency response and re-covery actions.
1 (2) Supporting the Search and Rescue effort.
4.4.2 Instrument and Control Group The Instrument and Cont rol Group consists of all I & C Specialists including 1 & C Coor-dinators and the 1 & C Supervisor. Tne onsite emergency organization includes the Supt, Techn-ical Engineering, who shall report to the
\m Technical Support Center; and the I& C Supervisor and Coordinators who report to Operational Support Center. The I & C Group can be further augmented or decreased as emergency conditions dictate.
A. Group Leader - Line of Sucession (1) Supt. Technical Engineer
- (2) I & C Supervisor j (3) I & C Coordinators l B. Responsibilities
!, The I & C Group shall be responsible for:
r I
(1) Supporting the repair and corrective l actions for the instrument and con-
, trol systems in support of emergency ;
l response.and recovery actions. .
I
!- (2) Supporting the search and rescue effort.
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. l F3-1 l Rev. 2 Page 14 4.4.3 Radiation Protection Group The Radiation Protection Group consists of the Supt.
Radiation Protection and all members of the Radiation Protection Group.
A. Group Leader - Line of Succession (1) Supt. Radiation Protection (2) Senior Prod Engr - Rad Prot Section (3) Radiation Protection Supervisor (4) Radiochemistry Supervisor (5) Rad Protection Coordinator B. Responsibilities The respon::ibilities of the Radiation Protection r Group are:
(1) Offsite Dose Assessment (2) Offsite Surveys (3) Onsite Surveys (4) Chemistry
! (5) Radiochemistry (6) Radiation Protection for:
(a) Access Control (b) Damage control and Repair (c) Search and rescue (d) First aid (e) Fire fighting (f) Personnel monitoring and 4
decontamination I
(g) Dosimetry 4.4.4 Engineering Group The Engineering Group consists of the Operation Engineers, the Nuclear Engineers, the Radiation Protection Engineers, the Technical Engineers, and Quality Assurance Engineers.
Upon activation of the onsite emergency organ-ization, all Engineering Superintendents shall report to the Technical Support Center. Des-ignated engineers may be requested to further augment engineering support in the TSC.
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IBM
. . . . - , _.-- . -.,.~ ,.- -
4 l
j F3-1 Rev. 2 l Page 15 i
+
4 l A. Group ' Leader - 1.irie of Succession 2
(1) Plant Supt. Engineering and Rad Pro-
- tection
- , (2) Supt.. Operations Engineering
.(3) Supt. Technical Engineering !
(4) Supt. Nuclear Engineering (5). Supt. Quality Assurance Engineering B. Responsibilities l The Engineering Group shall have responsi-bility for:
4 (1) Providing technical support for emergency j repairs and cor rective actions on elect -
rical/ mechanical systems. ;
(2) Providing technical support for. plant j system engineering on electrical / mech' anical systemr., ;
1 l (3) Providing technical support for
! operating radioact ive waste con-trol systerns.
1 (4) Providing core parameter analysis ,
to determine current core status.
I j 4.4.5 Logistics Support G oup j The' Support Group consists of the Purchasing and ;
j Inventory Control Group..the Administrative l Services Group, and the Document Control Group.
A. Group Leader - Line of S: ccession -
1 (1) Plant Office Manager
- . (2) Administrative Services Supervisor i
l B. Responsibilities' i
i The Support Group shall supply logistical support in 'their area of expertise. Per-
! sonnel in these will be called in to pro-l vide support for emergency response on an as needed basis.
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i IBM i
-. . _ _ . . _ . . _ _ . _ _ _ . . . _ _ . . _ _ _ _ . . _ . _ _ _ _ . _ . . _ . . . . _ - _ _ , _ . - . ~ . . _ _ . . . _ _ _ . _ _ _ _ , -
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'\,_ b V l SUPP QUALITY ENG l PIAVf MANAGER
- l STAFF ENG l OPEFATIOJ:
COPNITTEE l SEN SCHED ENG l l OFFICE WLNAGER l 1 I i Review and Audit I g PLANT SUPERINTENDENT
, PIAVf ENGINEERING &
PIANT SUPT. RADIATION PROTECTION
- OPERATION &
MAINTENANCE
- SUW PLT SUPERVISOR OF SERVICES SECURITY & SERVICES
- I I I I I SUPr. SUPERINTENDENT SUPr SUPERINTENDENT TECH- SUPERINTENDENT MAINTENANCE
- OPERATIONS
- PADIATION NICAL ENGINEER
- l OPERATING ENGR I
- SUPP NUCLFAR
, PROTECTION
- ENGR
- l SHIPP SUPERVISOR I
IEAD PLANT EQUIPMENT & TECHNICAL i F23GINEERS FOR ft:CHNICAL E#3INEEtG MECHANICAL REACIOR OPERA'IOR SUPPORT & INSTRUMPRfATION, SUPPORf FOR FOR AND SPECIALISTS CONrrDLS & COMPUTER: OPERATION, NUCLEAR ELECTRICAL PLANT EQUIPMENT FOR RADIATION MAINTENANCE, ENGINEERING J_AND I&C SPECIALISTS MAINTENANCE & REACIOR PROPECTION & SURVEILIR3CE, GROUP OPERA'IOR(S) CHEMISPRY TFSPING AND RETRAINING ASSISTANP PLANT EQUIPMENP OPERA'IOR(S)
PRAIRIE ISIAND NUCLEAR GENERATING PLANT PIAVP FUICTIONAL ORGANIZATION FOR ATTENDANT (S) . ONSITE OPERATING GROUP CODE: * - Key Supervisor FIGURE 1 w(m
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EMERGENCY
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DIRECIOR RADIATION INITIAL SUPPORTING mNITORING OFF-SITE U NTACP
'IEAMS (OFFSITE)
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MSEMBLY POINf I shier OSc I I I SUPERVISOR ! ! !
C)ORDINATOR l l I i ! I I l I
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l t l l i I EMEMENCY ! GUARWOUSE l
l SUPr. l l I&C GROUP SUPV l l 000RDINATOR l
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i j i ! i ! l 'SUev i l l PIRTP OPS l STATION ELECTRICAN & l SHIFT EMERGENCY l SECURITY &
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- The ED may coordinate activities from either the Control Room or the Tech Support Center 04-SITE EEERGENCY ORGANIZNTION FIGURE 2 EP-ll-A,2 .?EU 4, g 4 me
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- PAGE 1 OF 43 l l EMERGENCY PLAN IMPLEMENTING l l PRAIRIE ISLAND NUCLEAR JPROCEDURES l
.v
) GENERATING PLANT l l l l NORTHERN STATES POWER COMPANY Number: F3-2 Rev: 2 l l -History Copy l l A ,
JRetention Time: Lifetime l l . 2 ([ TITLE: _ l l Supt. ITad Protection l CLASSIFICATIONS OF l l Approved By: '- >
.( EMERGENCIES f l l
.b l l l l Mana l l l OC#: P)a, n tX -M gerY2 l l l __ I __ l l l l l l 1.0 PURPOSE l l l l The purpose of this procedure is to specify the Emergency Action l l Levels that indicate that an emergency condition exists and to l l properly classify the emergency into one of the four graded levels of l l emergency classifications. l l l l 2.0 APPLICABILITY l l l l This instruction SIIALL apply to all Shif t St.pervisors, Control Room l p) l Operators, Shift. Technical Advisors and Emergency Directors.
3.0 PRECAUTIONS l
l l l l l 3.1 The operator should believe his indications and take action l l based on those indicat ions, however, he shall attempt to l l verify his indications by checking secondary or coincident l l indicators. l l l l 3.2 Continuously monitor the control room instrumentation, radia- l l tion monitors, or any other developments which would be l l indicative of further system degradation. Be prepared to l l escalate to a more severe emergency classification. l l l 1 l l 4.0 DISCUSSION l l l l 4.1 Definitions l l l l 4.1.1 Notification of Unusual Event - events that are in l l progress or have occurred which itidicate a potential l l degradation of the level of safety of the plant. l 1 I I I l No releases of radioactive material requiring offsite l f- g l response or monitoring are expected unless further l degradat. ion of sa fety systems occurs.
I I I I IBM
4 F3-2 Rev. 2
- Page 2 4.1.2 Alert - events are in progress or have occurred which involve actual or potential substantial degradation of the level of safety of the plant. It is the lowest level of emergency. classification when some necessity for emergency planning and offsite response is necessary.
Any releases expected are limited to small fractions of the EPA Protective Action Guideline exposure levels.
4.1.3 Site Emergency - events are in progress or have occurred which involve actual or likely major failure of plant functions needed for protection of the public.
Any releases are not expected to exceed the EPA Protective Action Guideline exposure levels except near the site boundary.
4.1.4 General Emergency - events are in
.m progress or have occurred which involve
('- ) actual or inminent substantial core degradation or melting with a potential for loss of containment integrity.
Releases during a General Emergency can be reasonably expected to exceed the EPA Protective Action Guideline exposure levels offsite for more than the immedi-ate site area.
4.1.5 Emergency Action Levels (EAL) - specific instrument readings, surface or airborne contamination levels or radiation dose rates that designate a specific emergency I
class requiring emergency measures for that class.
4.2 Summary 1 Attached to this procedure is a Summary of i Emergency Action Levels. This table identifies i the four emergency classifications, the initiating
!' conditions (s), emergency actions levels for each classification, and, where applicable, specific instruments and indications to be used to detect and classify an emergency.
{ }
IBM
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- Page 3 O The emergency action levels for each classification and the instrument readings and indications listed do not reflect a complete' list of instrumentation that will show abnormal indications but does list those key parameters useful in classifying the event.
l The Summary of Emergency Action levels lists all the initiating conditions as required by Appendix-1 of
- NUREG-0654 and some accidents analyzed in the Prairie i Island FSAR.
1 J
5.0 PROCEDURE 5.1 Any significant event that may be classified as an j emergency condition shall be reported to the Shift l
Supervisor immediately.
i 1
- I l 4
l NOTE: The events may be instrumentation l ;
i l readings or visual observations made l -
d l by plant personnel. l
- l '
1 l l 5.2 Attempt to verify the initial indication by comparing
- the indication to redundant instruraent-channels or to l other related parameters, visual observations, and
{ field reports as applicable. ;
i
- . 5.3 Assess the situation and determine the emergency i classification, using the guidelines of Attachment 1.
i
! I I l NOTE: Personnel should .become familiar with l
,, l Attachment I during training sessions. l 1 l l 5.4 Take immediate' actions, using applicable plant operating j procedures, Sections C and E of the Operations Manual, l to return the plant to normal (or cold shutdown, 'if
- determined to be necessary).
- 5.5 Declare the appropriate emergency classification and l perform actions as specified in the appropriate !'
, responsibility procedure applicable to emergency classification:
i 5.5.1 For a Notification of Unusual Event, proceed to F3-3 .
l l 5.5.2 For an Alert, Site or General Emergency,
- proceed to F3-4.
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b 5.6 Continue to assess and respond to the emergency condition.
l .l l NOTE: Watch for changing parameters or l l visual indication of further system l l degradation and be prepared to es- l l calate to a more severe emergency l l classification as indicated by the l l Emergency Action Levels in Attach- l l ment 1. l l l 5.7 As plant conditions stabilize, downgrade or terminate the emergency classification, as appropriate, as per the guidelines of Attach-ment 1.
I l l NOTE: Deperiding upon the severity of the l l accident, it may not be possible to l I downgrade the emergency classification l l following the guidelines of Attach-(~. I m(nt 1. Therefore, once the plant l
l l is in a stable mode and long-term l l cooling has commenced, the emergency l l condition may be reclassified and/or l l terminated and long-term recovery l l initiated. The Emergency Director l l should consult the Emergency Manager l l prior to reclassification and/or l l termination and initiation of the l l long-term recovery. l l l
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Attachment 1
SUMMARY
OF EMERGENCY ACTION LEVELS i
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. Page 6 l ATTACitMENT 1 INITIATING CONDITION INDEX t
No. Condition Description Page 1 Safety System Functions 7 2 Abnormal Primary Leak Rate 10
) 3 Abnormal Coolant Temperature / Pressure 13 1
, 4 Abnormal Primary / Secondary Leak 14
{ 5 Core Fuel Damage 16 6 Secondary Coolant Anomaly 19 7 Radiological Effluents 22 J
8 Major Electrical Failures 25 9 Centrol Room Evacuations 28 10 Fires 29 f 11 Plant Shutdcun Functions 30 12 Fuel Handling Accidents 33 13 Coolant Pump 35 j 14 Serious or Fatal Injury 36 i 15 Security Threats 37 16 Hazards to Plant Operations 38 i 17 Natural Events ~41 l 18 Other 43
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F3-2
- Rev. 2 Page 7 Attachment 1 CORDITION #1 SAFETY SYSTEM FUNCTIONS Initiating Condition Indication Used Classification ECCS initiated and dis- 1. First out on reactor trip panel: Alert charge to vessel. c. Containment High Pressure NOTE: FSAR Sections SI-Reactor Trip; or 14.2.4 b. A Steam Generator Lo-Lo 14.2.5 Pressure SI; or 14.2.6 c. B Steam Generator Lo-Lo 14.3 Pressure SI; or
- d. Pressurizer to Pressure SI and
- 2. Confirmation from indicators:
- a. 2/3 High Containment Pressure (4psig) PI-345. PI-947, PI-949; or
- b. 2/3 Lo Steam Line Press. Loop A (500 psig) PI-468, PI-469,
, -s s PI-482A; or
) c. 2/3 Lo Steam Line Press. Loop B
(%d (500 psig) ~ PI-478, PI-479, PI-483A; or
- d. Lo Prz. Presa (1815 psig)
PI-429, P1-430, PI-431 1 and
- 3. Confirmation of SI Flow indicated by FI-925 and FI-924.
EE
- 4. Manual SI-Reactor Trip initiated if Auto SI did not occur at confirmed indicator setpoints (#2 above) or when pressurizer level is off scale low on at least 2/3 channels, LI-426, LI-427, LI-428.
Loss of Containment Loss of Containment Integrity, defined Notification of integrity requiring by Technical Specification 3.8, Unusual Event shutdown by technical which requires a unit shutdown, specification as determined by the Shift Supervisor.
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%, 1 Attachment 1 CONDITION #1 (Cont'd) ,
)
\
j SAFETY SYSTEM FUNCTIONS , ,
. m ss I
Initiating Condition Iridication Used 1 T
Cfa'ssification 4
4 .
Loss of engineered safety. Engineered Safety Feature found Notification of
, feature requiring shutdown inoperable, as defined by Unusual Event by Technical Specification Technical Specification 3.3, '
which requires a unit shutdown, i as ctetermined by the Shift Supervisor.
- 1 1
i r l Loss of fire protection Loss of fire protection systems, Notification of i system function requiring defined by Technical Specification Unusual Event '
l shutdown by Technical 3.14,.which requires a unit shutdown, '
Specification as determined by the Shift Supervisor. 't y;' '
- l_ L-
'N Failure of a safety or Pressurizer safety or relief; valve Notiffcation of
. relief valve in a safety opens and then fails to reset, as Unusual Event
l related system to close indicated by:
following reduction of .
applicable pressure. 1. (a) Annunciator " Pressurizer. y Safety / Relief Valve Flow"; and '
l- ,
- \ \
(b) Annunciators; s (1) " Pressurizer Power Relief '
line High Temp; or l (2) " Pressurizer Safety Valve
, line A or B High Temp" s or s .w l
(c) Safety /RelieflinehighgeNper- '
ature indicated by C 3
(1) Pressurizer safety yalve outlet temperature, TI-436')
225*F; or s c (2) Pressurizer safety valve outlet temperature, TI-437 >
225*F; or
[~' (3) Pressurizer relie'f valve
\s. ou.tlet tempbratdre, TI-438 >
225*F.
IBM I ,__ _ _ . _ _ _ _ , _ _ _ - . - , , _ . _,, .,
_ _ , . . .x. _ , . - . . . . . . . _ . = - - . - . - . - - - - _ _ _ _ - - . - _ . - - . - - . . .-_ .- . . . . - . .
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- Attachment 1 l n
CONDITION #1 (Cont'd)
I i
! SAFETY SYSTEM FUNCTIONS Initiating Condition Indication Used Classification
. Steam Generator safety or relief valve opens and then fails to reset, as i indicated by:
- 1. Visual and/or audible indication i
at vent stacks of open steam i generator safety or relief valve; j'I and f 2. Shift Supervisor's opinion
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F3-2 Rev. 2 Page 10 Attachment 1 CONDITION #2 ABNORMAL PRIMARY LEAK RATE Initiating Condition Indication Used Classification Primary system leak rate 1. Primary system leak rate, other Notification of from unidentified or uncon- than controlled leakage sources, Unusual Event trolled sources exceeding exceeds Technical Specification '
Technical Specifications 3.1.c; and
- 2. Requires a unit shutdown, as determined by the Shift Supervisor.
Primary coolant leak rate 1. (a) Decreasing pressurizer level, Alert greater than 50 gpm as indicated by LI-42.6, LI-427, LI-428; or_
(b) High radiation levels in contain-ment, as indicated by:
[ R2 High Alarm - 50mR/hr; or N R7 High Alarm - 50mR/hr; or R-11 (Containment Positiog)
High Alarm - 5 x 10 cpm, or R-12 (Containment Positiog)
High Alarm - 6 x 10 cpm; and
- 2. Annunciator " Charging Pump in Auto High/ Low Speed"; and
- 3. Charging line flow (FI-128B) greater than 50 gpm more than Letdown Flow (FI-134).
l NOTE: Rapid Temperature decrease l l in RCS results in same l l indications however no l l primary coolant leak rate.l l l O
IBM
F3-2 Rev. 2 Page 11
[_s
\ms Attachment 1 CONDITION #2 (Cont'd)
ABNORMAL PRIMARY LEAK RATE
. Initiating Condition Indication Used Classification Loss of coolant accident 1. No Pressurizer Level indicated Site Area Emergency with leak rate in excess of by LI-426, LI-427, LI-428 available pump capacity (Charging, High Head In- and jection, and Low Head In-jection). 2. All available pumps running as i indicated by the red light at the switch.
i Small LOCA and initially 1. LOCA has occurred; and General Emergency successful ECCS. Subsequent failure of containment heat 2. Inadequate containment cooling removal systems over several exists, as indicated by:
hours could lead to core melt and likely failure of (a) Containment temperature has containment. become excessive, ) 300 F, and is still rising; or (b) Containment pressure > 23 psig with minimum containment pressure suppres-sion equipment not available:
, (1) No fan cooler units operating and less than two spray pumps; 2E
- j. (2) No spray pumps operating and less than four fan cooler units;
, or l
(3) Less than two fan cooler units running with one spray pump.
Small and large LOCA's 1. Loss of coolant indicated by: General Emergency
, with failure of ECCS to perform leading to (a) (1) Pressurizer low pressure severe core degradation trip (1900 psig); or or melt in from minutes RCS pressure decreasing to hours. Ultimate failure uncontrollably; of containment likely for 7_ melt sequences. and IBM
_. . ~ - . ,_. ~. - . _ . _ _ - . - - -
F3-2 Rev. 2 s Page 12 Attachment 1 CONDITION #2 (Cont'd) l ABNORMAL PRIMARY LEAK RATE Initiating Condition Indication Used Classification
} (2) High containment pressure; or High containment humidity; or i High containment sump levels; or i
High containment radiation levels and (3) Steam Generator's A and B pressures equal BI i
, (b) (1) Decreasing RCS pressure; and l (2) Loss of subcooling margin j ((10 F) and
- 2. Fuel Damage indicated by:
- a. R48 IIigh Alarm - 200 R/hr; or l R49 liigh Alarm - 200 R/hr l ?!
( by sample anaylsis and
(b) Low head SI failure.
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( Attachment 1 CONDITION #3 ABNORMAL COOLANT TEMPERATURE / PRESSURE Initiating Condition Indication Used Classification Abnormal coolant tempera- At Steady State Power Operations; Notification of ture and/or pressure or Unusual Event abnormal fuel temperatures 1. T av8 > 564 F; or-outside of Technical Specification limits. 2. RCS pressure > 2385 psig; or
- 3. RCS pressure ( 2205 psig, and core exit temperature > 620*F, as J
indicated by a valid thermocouple; i EE
- 4. Core Subcooling Margin ( 10 F.
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F3-2 Rev. 2 Page 14 rs Attachment 1 CONDITION #4 ABNORMAL PRIMARY / SECONDARY LEAK
' Initiating Condition Indication Used Classification Primary / Secondary leak When shutdown con,mences, as deter- Notification of rate exceding Technical mined by the Shift Supervisor Unusual Event Specification of 1.0 gpm and Duty Engineer requiring a unit shutdown Failure of steam generator 1. First out on reactor trip panel: Alert tube (s) resulting in " Pressurizer Low Press SI" ECCS initiation and
- 2. Confirmation from Prz. Press indi-cators, PI-429, PI-420, PI-431, (2/3 Low pressure, 1815 psig).
and 7-~ 3. Annunciators:
- a. "A SG liigh Water Level" or
- b. "B SG liigh Water Level" and
- 4. Confirmation from SG 1evel indi-cators:
- a. LI-461, LI-462, LI-463
- (2/3 greater than 67%)
j or i b. LI-471, LI-472, LI-473 (2/3 greater than 67%)
- 5. Safety injection flow indicated by FI-925 and FI-924 and pump discharge pressure corresponding to flow Failure of steam generator 1. First out on reactor trip panel: Site Area Emergency tube (s) resulting in ECCS " Pressurizer low pressure SI" initiation and loss of offsite power and IBM
F3-2
, Rev. 2 Page 15 1
/. Attachment I
- - CONDITION #4 (Cont'd)
ABNORMAL PRIMARY / SECONDARY LEAK Initiating Condition Indication Used Classification 4
- 2. Confirmation from Prz. Press indicators: PI-429, PI-430, PI- j 431 (2/3 low pressure, 1815 psig) i 1 and 3 3. Annunciators:
- a. "A SG Water Level High" or
- b. "B SG Water Level High" a_ n_d
- 4. Confirmation from SG level indi-cators:
- a. LI-461, LI-462, LI-463 (2/3 greater than 67%)
or
, f'~ b. LI-471, LI-472, LI-473 (2/3 greater than 67%)
and
- 5. Safety injection flow indicated by FI-626 and FI-928 i
t and
- 6. All of the following indicators:
) a. 4.16 KV bus voltage (0 Volts)
Buses 11-14 and 21-24 and
- b. D1 and D2 generators running and closed in on safeguard 4
buses:
(1) D1 & D2 Tach, (N 900 rpm)
(2) D1 & D2 Volts, (4260-4380 Volts)
(3) Safeguard breakers closed Bus 15, Breaker 15-2
) Bus 26, Breaker 26-2 i Bus 16, Breaker 25-6 f(,,N) l Bus 25, Breaker 16-7 1
IBM :
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F3-2 Rev. 2 Page 16 i Attachment 1
' CONDITION #5 CORE FUEL DAMAGE j Initiating Condition Indication Used Classification Fuel Damage Indication 1. Hi Alarm on letdown line radiation monitor, R-9, indicating greater Notification of than 1 R/hr and confirmed by Unusual Event portable instrumentation EE
- 2. High coolant activity sample:
- a. exceeding Technical Specifi-cation for total specific activity in primary coolant EE
- b. exceeding Technical Specifi-cation limit on primary coolant iodine activity which l requires a unit shutdown.
Severe loss of fuel 1. Very high coolant activity sample; Alert cladding 1000 pCi/cc iodine equivalent, as determined by chemical analysis E
- 2. Letdown line radiation monitor R-9 in alarm mode and indicating greater than 10 R/hr, as con-
, firmed by portable instrumentation Degraded core with 1. Degraded core, indicated by: Site Area Emergency possible loss of coolable geometry (a) High primary coolant activity,
> 1000 pCi/cc; or (b) High core exit temperature, indicated by exit thermocouples,
) 700 F; or (c) Inadequate subcooling margin,
( 10 F; or (d) Indication of core uncovered (Shift Supervisor's opinion) and
~s 2. Loss of coolable geometry, indicated by:
'/ (a) Core AT increasing; or (b) No core AT; or (c) Shift Supervisor's opinion IBM
- . - _ = - - .- - . -.
l F3-2 Rev. 2 Page 17 O
\-s Attachment 1 CONDITION #5 (Cont'd)
CORE FUEL DAMAGE Initiating Condition Indication Used Classification Loss of 2 of 3 fission The first two of the Initiating General Emergency product barriers with a Conditions exist and the third potential loss of 3rd is possible.
barrier (e.g., loss of primary coolant boundary, 1. (a) Very high coolant activity sample, clad failure, and high 1000 pCi/cc Iodine equivalent as deter-potential for loss of mined by chemical analysis; and containment).
(b) Primary system leak in excess of 1000 gpm as indicated by safety injection flow greater than 1000 gpm (FI-924 and F1-925) and pump discharge pressure corresponding to flow EE
\
- 2. Valid high radiation levels in
' _) containment, as indicated by:
(a) R-48 High Alarm - 200 R/hr; or (b) R-49 liigh Alarm - 200 R/hr; and i 3. Minimum containment pressure suppression equipment is not available:
- a. No fan cooler units operating and less than two spray pumps EI
- b. No spray pumps operating and less than four. fan cooler units EE
- c. Less than two fan cooler units running with one spray pump with ;
(1) Annunciator "High Containment i Pressure" with 2/3 greater than
()
4 psig, PI-945, PI-947, PI-949 and containment pressure increasing w
i IBM i
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^
Attachment 1 i
l CONDITION #5 (Cont'd)
{ CORE FUEL DAMAGE
- Initiating Condition Indication Used Classification i
I (2) Annunciator " Containment Spray l Activated", with 2/3 greater than ;
, 23 psig PI-945, PI-947, PI-946, i
PI-948, PI-950 l 1
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F3-2
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Attachment 1 CONDITION #6 SECONDARY COOLANT ANOMALY .
l Initiating Condition Indication Used Classification Rapid depressurization of 1. (a) Steam General A/B Pressure Notification of Secondary Side Differential, > 100 psig; and Unusual Event (b) High Containment Pressure, 4 psig; EE 6
- 2. (a) lli Steam Flow, .745 x 10 lb/hr; and (b) Lo-Lo T,y ,540 F El
- 3. Steam line pressure Safety Injection Signal; BE O' 4. Failed Open Steam Dump, Relief, or Safety Valve; EE
- 5. Shift Supervisors Opinion Rapid depressurization 1. First out on reactor trip panel: Alert of secondary side (any a. "A Steam Generator Lo-Lo
- Steam Line Break with pressure SI" 0-50 gpm primary to or secondary leak rate) b. "B Steam Generator Lo-Lo Note
- FSAR 14.2.5 Pressure SI" and
- 2. Confirmation from Steam Generator pressure indicators:
- a. PI-468, PI-469, PI-482 (2/3 I
less than 500 psig),
Ef
- b. PI-478, PI-479, PI-483 (2/3 less than 500 psig) i IBM
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Attachment 1 CONDITION #6 (Cont'd)
SECONDARY COOLANT ANOMALY ,
Initiating Condition Indication Used Classification and, if primary to secondary 1cak rate is occurring:
3.111 radiation on:
- a. R-15 Air Ejector Rad Monitor inalarmmogereadinggreater than 5 x 10 cpm; and
- 4. Leak rate as calculated Steam line break with 1. First out on reactor trip panel: Site Area Emergency greater than 50 gpm pri- a. "A Steam Generator Lo-Lo mary to secondary Pressure SI" leakage and indication b. "B Steam Generator Lo-Lo of fuel E age Pressure SI" and
- 2. Confirmation from Steam Generator pressure indicators:
, a. PI-468, PI-469, PI-482 (2/3 less than 500 psig),
- b. PI-478, PI-479, PI-483, (2/3 less than 500 psig) and
- 3. Primary to secondary leakage indicated by:
- a. R-15 Air Ejector Rad Monitor,
, in alarm mode reading i
> 5 x 104cpm; and
- b. leak rate calculation > 50 gom; and
- 4. Indication of fuel damage:
- a. Primary sample > 1000 pCi/cc Iodine 131 equivalent; or
{\
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- b. Steam Line Monitor in valid high alarm mode:
R-51, > 100 mR/hr; or R-52, > 100 mR/hr.
IBM
F3-2 Rev. 2
_, Page 21
) Attachment 1 CONDITION #6 (Cont'd)
SECONDARY COOLANT ANOMALY Initiating Condition Indication Used Classification or
- c. High Containment Radiation levels indicated by:
R48 High Alarm - 200 R/hr; or
- R49 High Alarm - 200 R/hr; i
Transient initiated by 1. a. Loss of main condenser which General Emergency loss of feedwater and includes all Condensate and condensate systems Main Feed Pumps; and (principal heat removal b. Loss of all Aux Feedwater; and system) followed by c. No High Head Safety Injection failure of emergency feedwater system for or extended period. Core melting possible in 2. a. Successful High Head Safety several hours. Ultimate injection with
-) failure of containment (1) Loss of main condenser which likely if core melts. includes all Condensate and Main Feed Pumps; and (2) Loss of all Aux Feedwater and
- b. Either of the following not established within 30 minutes:
) (1) Aux Feedwater; or (2) Normal RHR Cooling l
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F3-2 Rev. 2
_, Page 22 Attachment 1 CONDITION #7 RADIOLOGICAL EFFLUENTS Initiating Condition Indication Used Classification Airborne Radiological Any of the following gaseous effluent Notification of effluent Technical monitors in valid alarm mode reading Unusual Event Specification limits greater than:
exceeded 3
Note: FSAR Section 1. 1R-22 (5 x 10 cp,)
14.2.2 3
- 2. 2R-22 (5 x 10 cpm)
Due to release rate of radioactive gases (except halogen and particulates with T 1/2 > 8 days) averaged over I hour exceed I 1.1 x 10 m /sec (fC)1.
per Technical Specification 3.9.B.1.b Liquid Radiological Any of the following valid liquid Notification of
(N s_, effluent Technical effluent monitor readings which Unusual Event Specification limits exceed:
exceeded (1) R-18 High alarm setpoint and Note: FSAR Section isolation valve fails to 14.2.2 close.
(2) R-19 High alarm setpoint (while blowdown is directed to river) and isolation valve fails to close.
Due to release rate of radioactive liquids exceeding vaines listed in 10CFR20, Appendix B, Table II, Column 2, per Technical Specifica-tion 3.9.A.1.b.
I Airborne Radiological Any of the following valid gaseous Alert effluents greater than effluent monitor readings:
i ten times Technical Specification instantan- 1. 1R-22 Hi-Hi Alarm (> 5 x 10 44cpm) eous limits (an instan- 2. 2R-22 Hi-Hi Alarm (> 5 x 10 cpm) taneous rate which, if 3. 1R-50 Greater Than 1.2 mR/hr f'~} continued for over two 4. 2R-50 Greater Than 1.2 mR/hr i,,j hours, would result in about 1 mR at the site Due to release rate of gases exceeding boundary under average Technical Specification 3.9.B.1.b by meterological conditions) a factor of 10.
IBM
F3-2 Rev. 2 Attachment I CONDITION #7 (Cont'd)
RADIOLOGICAL EFFLUENTS Initiating Condition Indication Used Classification Airborne Effluent 1. Any of the following valid gaseous Site Area Emergency monitors detect levels effluent monitor readings:
corresponding to greater than: (a) 1R-50 Hi Alarm (70 mR/hr)
- 1. 50 mR/hr whole body (b) 2R-50 Hi Alarm (70 mR/hr) for one-half hour or
- 2. 250 mR/hr for one-half or hour for the thyroid, or
- 3. 500 mR/hr whole body 2. Offsite dose projection calculations for two minutes, or result in the following dose projec-
- 4. 2500 mR/hr to the tions at the site boundary, greater thyroid for two minutes than:
at the site boundary for adverse meterology (a) 50 mR/hr whole body for 1/2 hour; or (b) 550 mR/hr thyroid for 1/2 hour; or g (c) 500 mR/hr whole body for 2 minutes; (d) 00 mR/hr thyroid for 2 minutes or,
- 3. Radiation Survey Teams measure dose rates greater than 50 mR/hr for ,
1/2 hour or greater than 500 mR/hr for 2 minutes (beta + gamma) at the site boundary; 0.E
- 4. Radiation Survey Teams measure i
thyroid dose rates (equivalent j I-131 Concentrations),'t a the l site boundary, which are greater than:
(a) 250 mR/hr for 1/2 hour, or (b) 2500 mR/hr for 2 minutes.
1
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F3-2 Rev. 2 Page 24 f'
CONDITION #7 (Cont'd)
Attachment 1 RADIOLOGICAL EFFLUENTS Initiating Condition Indication Used Classification Effluent monitors detect 1. Any of the following valid gaseous General Emergency levels corresponding to: effluent monitor readings in alarm mode, reading greater than:
- 1. IR/hr whole body, or
- 2. SR/hr thyroid (a) 1R-50 (1000 mR/hr) at the site boundary (b) 2R-50 (1000 mR/hr) under actual meteorologi-cal conditions or,
- 2. Offsite dose projection calcula-tions result in the following dose projections at the site boundary, greater than:
(a) 1R/hr whole body; or (b) SR/hr thyroid; or
?!s.
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- 3. Radiation Survey Teams measure dose rates greater than IR/hr whole body or
- 4. Radiation Survey Teams measure thyroid dose rates (equivalent I-131 Concentrations), at the site boundary, which are greater than 5R/hr.
Radiation levels or 1. Unexpected radiation levels Alert airborne contamination above 1000 mR/hr which indicate a severe degradation in the control or l
of radioactive materials (e.g., increase of factor 2.Widespreadcontamjnationabove of 1000 in direct radia- 10,000 dpm/1002 cm beta-gamma or tion readings within 500 dpm/100 cm alpha activity fa cility) .
IBM
F3-2 Rev. 2 Page 25
() Attachment 1 CONDITION #8 MAJOR ELECTRICAL FAILURES Initiating Condition Indication Used Classification Loss of Offsite Power All of the following indicators: Notification of Note: FSAR Section 1. 4.16 KV Bus Voltage (0 Volts) Unusual Event 14.1.9 a. Bus 11(21), 4119304 (4172804)
- b. Bus 12(22), 4119305 (4172805)
- c. Bus 13(23), 4119306 (4172806)
- d. Bus 14(24), 4119307 (4172807) and
- 2. D1 & D2 Generators up to Speed and Voltage and Supplying Safe-guard buses:
- a. D1 (D2) Tach (900 rpm)
- b. D1 (D2) Gen. Volts (4260-4380 Volts)
- c. Safeguard bus breakers closed:
(N Bus 15, Breaker 15-2 Bus 26, Breaker 26-2 (m.)
Bus 16, Breaker 25-6 Bus 25, Breaker 16-7 ,
Loss of onsite AC Power Loss of both diesel generators Notification of Capability Unusual Event Loss of offsite power All of the following indicators: Alert and loss of all onsite 1. 4.16 KV Bus Voltage (0 Volts)
AC power (See Site Area a. Bus 11(21), 4119304 (4172804)
Emergency for extended b. Bus 12(22), 4119305 (4172805) loss). c. Bus 13(23), 4119306 (4172806)
Note: FSAR Section d. Bus 14(24), 4119307 (4172807) 14.1.11 and
- 2. Loss of both diesel generators Loss of offsite power All of the following indicators: Site Area Emergency and loss of onsite AC 1. 4.16 KV Bus Voltage (0 Volts)
/"'N power for more than a. Bus 11(21), 4119304 (4172804)
(,,,) 15 minutes b. Bus 12(22), 4119305 (4172805)
IBM
i F3-2
. Rev. 2 i Page 26 l Attachment 1 CONDITION #8 (Cont'd) i MAJOR ELECTRICAL FAILURES Initiating Condition Indication Used Classification l
- c. Bus 13(23), 4119306 (4172806)
- d. Bus 14(24), 4119307 (4172807)
I and 4
- 2. Loss of both diesel generators and l
j 3. Blackout has occuted for more
- than 15 minutes. '
t Failure of offsite and 1. Loss of AC power, (offsite & General Emergency !
j onsite power along with onsite) indicated by:
! total loss of emergency .
! feedwater makeup capability a. 4.16 KV Bus Voltage (0 Volts)
I s- for several hours. This (1) Bus 11(21), 4119304 (4172804) would lead to eventual (2) Bus 12(22), 4119305 (4172805) i core melt and likely (3) Bus 13(23), 4119306 (4172806) failure of containment. (4) Bus 14(24), 4119307 (4172807) f and
- b. Loss of both diesel generators and
- 2. Turbine driven Aux Feedwater pumps
. inoperable for several hours.
1
! Loss of all onsite DC All of the following annunciators Alert power (See Site Area received:
Emergency for extended j.' loss).
- l. " Safeguard Train A DC Control Power Supply Failure" and
- 2. " Safeguard Train B DC Control i .
Power Supply Failure" IBM
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4 F3-2 '
. Rev. 2 i
Page 27
() Attachment 1 CONDITION #8 (Cont'd) 1 MAJOR ELECTRICAL FAILURES Initiating Condition Indication Used Classification NOTE: 4 annunciators numbered:
i 47018-0501 47018-0502 47518-0501 47518-0502 1
Site Area Emergency 1 Loss of all vital onsite All of the following annunciators i DC power for more than received:
15 minutes. 1. " Safeguard Train A DC Control Power Supply Failure" and
- 2. " Safeguard Train B DC Control Power Supply Failure" NOTE: 4 annunciators numbered:
47018-0501 47018-0502 47518-0501 47518-0502 and
- 3. Loss of DC Power has lasted more than 15 minutes.
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I F3-2 l
, Rev. 2 Page 28 Attachment 1 W
CONDITION #9 CONTROL ROOM EVACUATIONS Initiating Condition Indication Used Classification Evacuation of the control As required by the Shift Supervisor Alert
- room anticipated or re-
! quired with control of shutdown systems estab-lished from Hot Shutdown i
Panels and local stations i
1
- Evacuation of the control As required by the Shift Supervisor Site Area i i room and control of shutdown Emergency j systems not established from l hot shutdown panel and local j stations within 15 minutes i
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F3-2 ,
, Rev. 2 Page 29
() Attachment 1 i CONDITION #10 FIRES '
Initiating Condition Indication Used Classification Fire within the plant As reported by Fire Brigade Chief Notification of lasting more than 10 Unusual Event minutes after initial use of fire extinguishing equipment Fire potentially affecting 1. Observation that fire could Alert safety systems affect safety systems; and
- 2. Shift Supervisor's opinion i
Fire comprising the func- 1. Observation of major fire that Site Area tions of safety systems. defeats safety systems Emergency
- or functions; and
- 2. Shift Supervisor's opinion 4
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i 4
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IBM
F3-2 Rev. 2 Page 30 Attachment 1 CONDITION #11 PLANT SHUTDOWN FUNCTIONS Initiating Condition Indication Used Classification Nonfunctional indications 1. Annunciators: Notification of or alarms in the Control a. "NSSS Annunciator System Unusual Event Room requiring a plant Power Failure" shutdown or
- b. "B0P Annunciator System Power Failure" and
- 2. Failed indication as determined by the Shift Supervisor All alarm (annunciators) Annunciators received: Alert lost 1. "NSSS Annunciator System Power Failure" C1 and
- 2. " BOP Annunciator System Power Failure" Most or all alarms (annunc- Annunciators received: Site Area iators) lost while unit is 1. "NSSS Annunciator System Power Emergency not in cold shutdown or Failure" during plant transient or
- 2. " BOP Annunciator System Power Failure" during a transient, as determined by the Shift Supervisor a
Complete loss of any As determined by Shift Supervisor Alert function needed for plant l
cold shutdown g'~5 Complete loss of any As determined by Shif t Supervisor Site Area
(_,) function needed for plant Emergency hot shutdown IBM
F3-2
. Rev. 2 Page 31 (D
( ,) Attachment 1 CONDITION #11__(Cont'd)
PLANT SHUTDOWN FUNCTIONS Initiating Condition Indication Used Classification Turbine Failure requiring 1. High Vibration (7 mils) Notification of a reactor / turbine trip Unusual Event and
- 2. High-High Vibration (14 mils) as indicated by Control Room recorder and alarms 1
Turbine Failure causing 1. High Vibration (7 mils) Alert casing penetration and f-- 2. High-High Vibration (14 mils)
I as indicated by Control Room
\ 'y recorder and alarms i and
- 3. As determined by Visual Inspection Failure of the reactor 1. Any Reactor Trip Setpoint and Alert protection system to redundancy requiring a reactor initiate and complete trip has been exceeded a trip which brings the reactor suberitical and
- 2. Intermediate range detector output not decaying Transient requiring 1. Failure to bring reactor subcriti- Site Area Emergency operation of shutdown cal with control rods; and systems with failure to scram (continued power 2. No indication of core damage; and generation but no core damage immediately evi- 3. Shift Supervisor's opinion that dent). a transient is in progress b)
U IBM
F3-2 Rev. 2 j
s Page 32 Attachment 1 CONDITION #11 (Cont'd)
PLANT SHUTDOWN FUNCTIONS Initiating Condition Indication Used Classification Transient requiring opera- 1. Reactor remains critical after General Emergency Lion of shutdown systems trip; with failure to scram which results in core and damage or additional failure of core cooling 2. Indication of overpressurization and makeup systems (which of RCS because of inability to could lead to core melt) remove heat, as indicated by:
(a) RCS pressure greater than safety valve setpoint (2485 psig); or (b) Rapidly increasing containment pressure and temperature
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l l F3-2 i .
Rev. 2 1 j
4 Page 33
) Attachment 1 '
1 CONDI_ TION #12 FUEL HANDLING ACCIDENTS Initiating Condition Indication Used Classification d
- Fuel damage accident 1. Any of the following containment Alert with release of radio- rad monitors in valid alarm mode activity to contain- and reading greater than
ment
, (a) R2 - 350 mR/hr; or i Note: FSAR Section (b) R7 - 350 mR/hr i 14.2.1 or
- 2. The containment vent monitor in valid alarm mode, reading greater
- l. than:
6 (a) Ril - 10 cpm; or 4
(b) R12 - 10'5 cpm .
i and
- 3. Shift Supervisor's opinion Fuel damage accident with 1. Any of the following valid Alert 4
release of radioactivity radiation monitor readings:
to the fuel handling
- building (a) R-22 liiHi Alarm, > 5 x 10 4cpm; or Note
- FSAR Section (b) E50, > 1.2 mR/hr 14.2.1 4
and 1
! 2. Spent Fuel Pool Area Monitor i R-5 in valid alarm mode i reading > 350 mR/hr ,
and f
i
- j. 3. Shift Supervisor's opinion l
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F3-2 Rcy. 2 Page 34
() Attachment 1 CONDITION #2 (Cont'd)
FUEL HANDLING ACCIDENTS Initiating Condition Indication Used Classification
. Major damage to spent 1. For fuel damage in containment: Site Area fuel in containment or (a) Any of the following valid Emergency fuel handling building radiation monitor readings:
(e.g., large object (1) R48 Hi Alarm - 200 R/hr; or damages fuel or water (2) R49 Hi Alarm - 200 R/hr loss below fuel level) and (b) Shift Supervisor's opinion OI
- 2. For fuel damage in the Spent Fuel Pool:
(a) Valid Radiation Monitor readings on:
t (1) R50 Hi Alarm, > 70 mR/hr; or
\ (2) R5, in alarm mode reading
> 1R/hr ,
and (b) Shift Supervisor's opinion aS* g 3
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Rev. 2 f i Page 35 e i Attachment 1 1
?
j CONDITION #13 '
i i COOLANT PUMP i i
l Initiating Condition Indication Used Classification !
i e j Coolant pump seizure 1. RCP Trip (over current 86 Alert f
{
- leading to fuel failure lock-out); j l Note
- FSAR Section (
! 14.1.8 and !
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4 2. Primary sample analysis indicating I fuel failure (> 1000 pCi/cc iodine 131 equivalent) i k-
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F3-2
, Rev. 2 Page 36 Attachment 1 CONDITION #14 SERIOUS OR FATAL INJURY Initiating Condition Indication Used Classification Transportation of a As determined by the Shift Supervisor Notificatiou of seriously or fatally Unusual Event injured (may or may not NOTE: Serious injury is considered involve contamination) to be one that will require individual from site to admission for treatment or hospital for treatment observation for an extended period of time (greater than
] 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />)
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1 F3-2 .
Rev. 2 Page 37 Attachment 1 i
I CONDITION #15 l
} SECURITY THREATS j Initiating Condition Indication Used Classification 4
Security threat or Per security plan Notification of attempted sabotage Unusual Event Ongoing security Per security plan Alert compromise 4
j Imminent loss of Per security plan Site Area Emergency physical control of l plant i
4 Loss of physical control Per security plan General Emergency of plant k
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F3-2
, Rev. 2 Page 38
( ) Attachment 1 CONDITION #16
-HAZARDS TO PLANT OPERATIONS Initiating Condition Indication Used Classification Aircraft crash onsite 1. Visual observation by plant Notification of or unusual aircraft personnel and/or plant security Unusual Event activity over facility personnel; and
- 2. Reported to the Shift Supervisor Aircraft crash in the Visual observation by plant Alert protected area personnel and/or plant security personnel c
Aircraft crash within Visual observation by plant Site Area Emergency protected area and affect- personnel and/or plant security ing vital structures by personnel impact or fires with plant not in cold shutdown v
Near or onsite 1. Visual observation by plant Notification of explosion personnel and/or plant security Unusual Event personnel; and i
- 2. Reported to the Shi f t Supervisor I
Known explosion damage Visual observation by plant Alert
( to facility affecting personnel l plant operation l Severe damage to engi- Visual observation by plant Site Area Emergency 1
neered safety system personnel l equipment from explo-l sions with plant not in cold shutdown i
Near or onsite toxic or Gaseous hazards being experienced Notification of flammable gas release or projected, onsite (out of plant), Unusual Event as detected by portable instrumentation,
! which exists in concentrations greater I
/"'\ than:
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F3-2 Rev. 2 Page 39 Attachment 1 CONDITION #16 (Cont'd)
HAZARDS TO PLANT OPERATIONS Initiating Condition Indication Used Classification (1) 80 ppm hydrazine; o_rr (2) 25 ppm chlorine; or (3) 500 ppm ammonia; or (4) explosive limits as detected by explosive meter, and, reported to the Shift Supervisor Entry into the plant Gaseous hazads being experienced Alert environs of toxic or or projected, within the plant, flammable gases as detected by portable instru-mentation, which exists in concen-trations greater than:
(1) 80 ppm hydrazine; or (2) 25 ppm chlorine; or (3) 500 ppm ammonia; or h
V (4) explosive limits 5 detected by explosive meter, and, reported to the Shif t Supervisor Entry of toxic or Gaseous hazards being experienced or. Site Area Emergency flammable gases into projected within vital areas of the vital areas with plant plant, as detected by portable instru-not in cold shutdown mentation, which exists in concentrations greater than:
(1) 80 ppm hydrazine; or (2) 25 ppm chlorine; or (3) 500 ppm ammonia; or (4) explosive limits as detected by explosive meter, and, reported to the Shift Supervisor Missible impacts from Visual observation by plant personnel Alert whatever source on and/or plant security personnel facility J
IBM
1 1 F3-2
- , Rev. 2 Page 40 Attachment 1 t
CONDITION #16 (Cont'd) l l HAZARDS TO PLANT OPERATIONS Initiating Condition Indication Used '
Classification j
Severe damage to engin- Visual observation by plant personnel Site Area Emergency eered safety system from missiles with plant not in cold shutdown i
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- I F3-2
- Rev. 2
,, Page 41
\s / Attachment I s CONDITION #17
- NATURAL EVENTS Initiating Condition Indication Used Classification Any earthquake Annunciator " Seismic Event" received Notification of on the seismograph Unusual Event Earthquake greater than Annunciator " Operational Earthquake" Alert Operational Basis Earth- received on the seismograph quake ,
i Earthquake greater than Annunciator " Design Basis Earthquake" Site Area Emergency Design Basis Earthquake received on the. seismograph with plant not in cold shutdown s
4 Any tornado visible from Visual observation by plant personnel Notification of site and/or plant security and reported Unusual Event to the Shift Supervisor.
1
! Any tornado striking the Visual observation by plant personnel Alert facility and/or plant security and reported to the Shift Supervisor.
50 year flood 686' elevation Notification of Unusual Event 1
Flood levels approaching 692' elevation - requires both units Alert 1
design levels to be shut down l Flood levels exceeding 698' elevation - highest level Site Area Emergency design levels with plant transformers will function
. not in cold shutdown i
- Low water levels being 672.5' elevation - (At 672.5' Notification of.
experienced or projected elevation, both 11 and 21 cooling
~
Unusual Event beyond usual levels water pumps trip)
(m IBM
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e F3-2
. Rev. 2 Page 42
{
(,j' Attachment I CONDITION #17 (Cont'd)
NATURAL EVENTS Initiating Condition Indication Used Classification Low water levels being Approximately 669.5' elevation Alert experienced or projected to be near design levels Low water. levels being I. Approximately 666.5' elevation Site Area Emergency experienced or projecte d corresponding to loss of set of to be greater than design miter gates or loss of one spill-levels or failure of vital way gate equipment with plant not in cold shutdown. or
- 2. tiajor vital equipment failure at low water level Sustained winds being Sustained wind speed indicated by Alert
experienced or projected met tower in excess of 90 mph near design levels Sustained winds being in Sustained wind speed indicated by Site Area Emergency excess of design levels me t t owe r , in excess of 100 mph being experienced or pro-jected with plant not in cold shutdown I Any major internal or As determined by the Shift General Emergency
! ex'ernal events (e.g., Supervisor and/or Emergency fires, earthquake, sab- Director stantially beyond design levels) which could or has caused massive damage to plant systems re-sulting or potential for resulting in large
! releases to the offsite environment in excess of the EPA Protective Action Guides
, i _ _ _ _
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IBM i
o F3-2
. Rev. 2 Page 43 f~%
Attachment 1 CONDITION #18 OTHER Initiating Conditions Indication Used Classification Conditions that warrant Duty Engineer and Shift Supervisor Notification of increased awareness on the concurrence Unusual Event part of a plant operating staff or state and/or local offsite authorities Conditions that require Duty Engineer and Shift Supervisor Notification of plant shutdown under concurrence Unusual Event Technical Specification requirements or involve other than normal con-trolled shutdown Conditions that warrant Duty Engineer and Shif t Supervisor Alert
,-s activation of Technical concurrence Support Center and near-(N -)s site Emergency Operating s
Facility Other plant conditions Shift Supervisor opinion Site Area Emergency that warrant activation of emergency operating centers and monitoring teams or a precautionary notification to the public near the site Other plant conditions Shift Supervisor's opinien General Emergency exist, from whatever source, that make release of large amounts of radio-activity in a short time period possible, e.g., any core melt situation.
U IBM
I i
PAGE 1 OF 30 l l EMERGENCY PLAN 1MPLEMENTING Q
V l
l.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT
' PROCEDURES l
l l
l NORTHERN-STATES POWER COMPANY JNumber: F3-4 Rev: 6 l
.I l History Copy l l /l f Retention Time: Lifetime l
l
( [ .
l TITLE: l l f(apt.,Ra'd Protection l RESPONSIBILITIES DURING AN' l l Approved By: /,. / , , _i l ALERT, SITE AREA OR GENERAL l l ( _ 1)
- l EMERGENCY l l Plant Manager l l l OC#: f-24-82 '
l l l I- I i .,
l 1.0 PURPOSE l
l l
l The purpose of this instruct. ion is to delineate the responsibilities of l l various emergency organization personnel and onsite organizations l l required to respond to an Alert, a Site Area Emergency or a General l-l Emergency. l l
l l
l l 2.0
SUMMARY
l l
l l A graded scale of response is provided for the different classes of l l emergencies, each re<pti ring a speci fi c response by emergency O l l
organization personnel for the protectinn of the public health and.
safety.
l l
l l
l-
- l. 2.1 Alert l
l l
l A. Definition l l
l l The Alert Conditions are events which are in progress or have l l occurred which involve actual or potential substantial. l l degradation of the Icvel of safety of the plant. l l
l l Some releases of -radioactive material to offsite areas are l l probable. Hence there is some necessity for errergency l l planning and response by offsite agencies. Any radioactive l
- l release will be limited to a small fraction of the EPA l l Protective Act. ion Guideline exposure levels. l l' l l l B. Purpose e f Alert Class l
- l l l The purpose of the Alert Emergency classification is to (1) l l assure that emergency personnel are readily available to l l l respond if the situation becomes more serious or to perform l l l confirmatory radiation monitoring, if required; (2) provide l 1
l offsite authorities current status information. l
- l O _l C. Plant Actions and Responsibilities:
l l
l l l l l 1
[ IBM i
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- F3-4 Rev. 6 Page 2 s_ /
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- 1. Promptly inform State and/or local authorities of Alert status and reason for Alert as soon as discovered.
} 2. Augment resources by activating onsite Technical Support Center, onsite Operational Support Center and Near-Site Emergency Operations Facility (EOF).
l
- 3. Assess and respond to the Alert condition.
- 4. Dispatch onsite or offsite survey teams and associated communications (if needed).
- 5. Provide periodic plant status updates to offsite authorities.
- 6. Provide periodic meteorological assessments to offsite authorities and, if any releases are occurring, dose estimates for actual relea.scs.
- 7. Close out by verbal summary to of fsite authorities.
- or i \
- 8. Escalate to a more severe class.
1 I
{ D. State and/or Local Offsite Authority Actions:
- 1. Provide fire or security assistance, if required.
- 2. Augment resouces by act ivating Emergency Operating
- Centers and EBS to standby status.
1 3. Alert to standby status key emergency personnel J including monitoring teams and associated
- communications.
1
) 4. Provide confirmatory offsite radiation monitoring and ingestion pathway dose projections if actual releases substantially exceed technical specification limits.
(
i
- 5. Maintain alert status until verbal closeout.
or i,
- 6. Escalate to a more severe class.
1
! 2.2 Site Area E _mer.ge.ncy-I
\s../ A. Definition IBM
F3-4 Rev. 6 Page 3
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The Site Area Emergency describes events which are in progress or have occurred which involve actual or likely major failures of plant functions needed for protection of the public.
4 Significant offsite releases are likely to occur or 'are occurring but where a core melt situation is not expected although severe fuel damage may have occurred.
Any radioactive releases are not expected to exceed the EPA Protective Action Guideline exposure IcVels except near the site boundary.
B. Purpose of Site Area Emergency Class 1
The purpose of the Site Area Emergency classification is to (1) assure that response centers are manned; (2) assure that monitoring teams are dispatched; (3) assure that personnel required for evacuation of Near-Site areas are at duty stations if the situation becomes more serious; (4) provide current information for and consultation with offsite J
/, s authorities, and (5) provide updates for the public through i offsite authorities.
-C#
C. Plant Actions and Responsibilities:
- 1. Promptly inform State and/or local offsite authorities of Site Area Emergency status and reason for emergency as soon as discovered.
- 2. Augment resources by activating onsite Technical Support Center, onsite Operational Support Center and the Near-Site Emergency Operations Facility (EOF).
- 3. Assess and respond to the Site Area Emergency.
- 4. Dispatch onsite and offsite survey teams and associated communications (if needed).
- 5. Provide a dedicated individual for plant status updates to offsite authorities.
, 6. Make senior technical and management staff onsite available for consultation with NRC and State on a periodic basis.
f
- 7. Provide meteorological and dose estimates to offsite authorities for actual releases via a dedicated
( individual.
IBM
F3-4 .
Rev. 6 Page 4
/N b'
- 8. Provide release and dose projections based on available plant condition information and foreseeable contingencies.
- 9. Close out or recommend reduction in emergency class by contacting offsite authorities, or
- 10. Escalate to General Emergency class.
D. State and/or Local Offsite Authority Action:
- 1. Provide any assistance requested.
- 2. If sheltering near the site is desirable, activate the Public Notification System within at least 2 miles of the plant.
- 3. Provide public within at least 10 miles, periodic updates on emergency status.
- 4. Augment resources by activating Emergency Operating
\/ '
Centers and EBS to standby status.
- 5. Dispatch key emergency personnel including monitoring teams and associated communications.
- 6. Alert to standby status other emergency personeel (e.g.,
those needed for evacuation) and dispatch personnel to Near-Site duty stations.
- 7. Provide offsite monitoring results to licensee and others and jointly assess them.
- 8. Continuously assess information f rom licensee and offsite monitoring with regard to changes to protective actions already initiated for public and mobilizing evacuation resources.
- 9. Recommend placing milk animals within 2 miles on stored feed and assess need to extend distance.
- 10. Provide press briefings, perhaps with licensee.
- 11. Maintain Site Area Emergency status until closeout or reduction of emergency class.
m t, or IBM
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F3-4 Rev. 6 Page 5
- 12. Escalate to General Emergency class.
2.3 General Emergency A. Definition The General Emergency describes events in progress or which have occurred which involve actual or imminent substantial core degradation or melting with the potential for loss of containment integrity. Radioactive releases can be reasonably expected to exceed the EPA Protective Action Guideline exposure levels of fsite for more than the immediate site area, hence, Protective Actions may have to be taken for protection of the general publie.
B. Purpose of General Emergency Class The purpose of the General Emergency classification is to (1) initiate predetermined protective actions for the public; (2) provide continuous assessment of information from licensee and offsite measurements; (3) initiate additional measures as indicated by actual or potential releases; (4) provide
/' \ current informatien for the public and consultation with
-- offsite authorities, and (5) provide updates for the public through offsite authorit.ies.
C. Plant Actions and Responsibilities
- 1. Promptly inform state and local offsite authorities of General Emergency status and reason for emergency as i
soon as discovered.
- 2. Augment resources by activating onsite Technical Support Center, onsite Operational Support Center and Near-Site Emergency Operations Facility (EOF).
i
- 3. Assess and respond to General Emergency.
l 4. Dispatch onsite and offsite survey teams and associated l communications.
- 5. Provide a dedicated individual for plant status updates I to offsite authorities.
- 6. Make senior technical and management staff onsite available for consultation with NRC and State on a periodic basis.
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F3-4 Rev. 6 Page 6-
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- 7. Provide meteorological and dose estimates to offsite authorities for~ actual releases via a dedicated individual.
- 8. -Provide release and dose projections based on available plant condition information and foreseeable contingencies.
- 9. Close out or recommend reduction of emergency class by briefing of offsite authorities at EOC by phone.
D. State and/or Local Offsite Authority Actions
- 1. Provide any assistance requested.
- 2. Activate immediate public notification of emergency status and provide public periodic updates.
- 3. Recommend sheltering for 2 mile radius and 5 miles downwind and assess'need to extend distances. Consider advisability of evacuation (projected time available vs estimated evacuat ion times) .
A/ 4. Augment resources by activating Near-Site EOC and any
- . other primary response centers.
- 5. Dispatch key emergency personnel including monitoring teams and associated communications.
- 6. Dispatch other emergency personnel to duty stations within 5 mile radius and alert all others to standby status.
! 7. Provide offsite monitoring results to licensee and others and jointly assess these.
- 8. Continuously assess information from licensee and offsite monitoring with regard to changes to protective actions already initiated for public and mobilizing evacuation resources.
- 9. Recommend placing milk animals within 10 miles on stored feed and assess need to extend distance.
- 10. Provide press briefings, perhaps with licensee.
I
- 11. Maintain General Emergency status.until closcout or
{}
s-reduction of emergency class.
1 IBM
F3-4 Rev. 6 Page 7 O
O 3.0 PRECAUTIONS (1) All personnel shall stay clear of any areas as announced over the public address system.
(2) All personnel shall refrain from using the public address system or telephone system during an emergency.
(3) When the evacuation alarm is sounded, listen for instructions over the public address system before evacuating.
(4) Anyone working in a contaminated area when the evacuation alarm sounds should remove as much protective clothing as time permits, especially gloves, bootics or rubbers. If wearing a double suit, removal of outside clothing would only be necessary. Proceed to the designated assembly area. If unable to remove all protective clothing, inform personnel in charge at the assembly area of your condition.
l NOTE: When the evacuation alarm scunds during a DRILL, l f' g l remove ALL protective clothing prior to evacuating. l (w) l - I (5) When exiting the Protected Area via the Guard House, proceed through the portal monitor quickly. Step through without stopping. All 1.D. cards (badges) shall be collected and checked out by the Guard Force, so an early printout of all personnel within the Protected Area can be obtained.
(6) Everyone shall remain at assembly area for monitoring and accountability checks until released by the Emergency Director or directed for reassignment for duty within the plant. Follow instructions from the Assembly Point Coordinator. When departing the site property, obey all instructions f rom traffic control personnel.
4.0 APPLICABILITY i
This instruction shall apply to all plant personnel.
5.0 ORGANIZATIONAL CONTROL 5.1 Overall Responsibility - Emergency Director 5.2 In-Charge, Control Room - Shift Supervisor
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Technical Support Center - TSC Coordinator Operational Support Center - OSC Coordinator Assembly Point - Assembly Point Coordinator '
5.3 Assistance, Control Room - Control Room Operators
- Shift Technical Advisor
- - Supt Operations TSC - Operations Committee
, - Shift Emergency Communicator 1
i
- Radiological Emergency Coordinator
- Engineering support as needed (i.e. ,
systems experts) 4 OSC - Ext ra Operators
- Rad Survey Teams
- Maintenance Supervisors
- 1 & C Supv & Coor'inators d
- Chief Station Electrician and Alternates
- Additional Support as needed
\~ 6.0 RESPONSIBILITIES i
6.1 Shif t Supervisor of the af fected unit.
(1) Proceed to the Control Room (if not already there) l 1 i
l NOTE: The Shift Supervisor of the affected l i
l unit shall remain in the Control Room l
} } at all times during' accident conditions l l until properly relieved. l l l 1,
i (2) Implement the appropriate Emergency Operating Procedures and i
respond to the emergency condition with the objective of l returning the plant to a normal safe condition (or cold shutdown, if determined to be necessary).
3 (3) Monitor plant conditions to determine when the threat to plant safety has passed. Be prepared to escalate to a more severe emergency class, if required.
I.
l (4) Coordinate, with the Emergency Director, all plant operations-which may impact on radioactivity releases.
\s 6.2 Shif t Supervisor of the una f fected unit:
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1 (1) Assume the position as Emergency Director.
(2) Start the dut'ies and responsibilities as assigned to'the Emergency Di rector. as specified in Section 6.3. . Use. Attach- l ment A, Emergency Director's Checklist.
(3) When the designated Emergency Director arrives onsite, update him on the current plant status and formally transfer the j Emergency Director responsibilities over to that individual, i (4) Assist the Shif t Supervisor of the affected tulit, as required in section 6.1. ,
, 6.3 Emergency Director
]
(1) Assume the role as Emergency Director. Use Att,chment A, Emergency Director's Checklist..
I (2) Determine the plant status. Report to the Control Room and l become familiarized with the situation and sequence of events preceeding and propagating the Emergency Condition.
i (3) Announce, or ensure that the following message is announced
} over the public address system:
ATTENTION ALL PLANT PERSONNEL: '
A (N) (pick correct class):
ALERT, or SITE AREA EMERGENCY, or j GENERAL EMERGENCY
, HAS BEEN DECLARED.
4 I
i ALL MEMBERS OF THE ONSITE EMERGENCY ORGANIZATION REPORT
, TO YOUR EMERGENCY DUTY STATIONS. ALL OTHER PERSONNEL
- STANDBY FOR FURTilER INSTRUCTIONS.
Repeat announcement.
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l l l NOTE: A plant evacuation will normally be l l initiated during an Alert, a Site Area l l Emergency, or a General Emergency, l l however, the Emergency Director must l l consider special conditions, (e.g., l l high winds or tornado) where an evacu- l l ation is not feasible or when the on- l l site assembly point is not habitable. l l See procedure F3-9, " Emergency Evacua- l
, I tion", for specific evacuation l l criteria. l l l (4) Contact the STA and SEC (if not already done so), and have them report to the Control Room immediately.
(5) Assist the SEC in completing the Notification Report Form, Figure 1, F3-5.
(6) Designate the SEC to complete the notification of state,
/N local, and NSP personnel, in accordance with F3-5, " Emergency 5, / Notifications".
l l l NOTE: State and local authorities shall be notified l l within 15 minutes of the declaration of the l l emergency class. l l l (7) Direct the SEC to activate the onsite emergency organization, in accordance with F3-5, " Emergency Notifications", and to i notify any other appropriate plant personnel, as deemed necessary.
(8) Notify any other offsite support agencies required to provide assistance to respond to the emergency condition, e.g., local support services, such as fire fighting, ambulance, hospital, etc. See F3-5, " Emergency Notifications for local support services phone numbers.
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t i l l l NOTE: These contacts should be coordinated with l
l the SEC and the Control Room to ensure that l l l the contacts required are made in a timely l l manner. l
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- (9) Direct the Shift RPS to
a) perform the appropriate sampling and analysis as j necessary, e.g. , primary system, containment air, steam generator liquid, shield building stack, etc.,
and/or b) perform offsite dose calculations, if the high range effluent stack monitors (R-50) are in valid alarm mode. ,
(10) Direct the RPS and/or operator to conduct onsite and in plant radiation surveys, as necessary.
(11) If the first notification of an emergency is a General Emergency, call the County Sheriff and make the initial !
Protective Action recommendation:
i [ (a) Recommend activation of the public notification system, r
and d
(b) Recommend sheltering of the public within a two mile radius of the plant.
4
] (12) Ensure that the NRC has been notified and designate an individual to maintain communications with the NRC via the '
ENS phone, as necessary.
I I I l NOTE: Notification of the NRC via the ENS l l required within I hour. l l l (13) During plant evacuations, direct the evacuation of all non-essential personnel from the plant site to the designated j assembly point (per F3-9).
(a) Normally the Construction Office Building will be the
- designated assembly point. However, the Screenhouse can
! be used if conditions make the Construction Office f Building uninhabitable.
(b) Direct the Security Force to warn all personnel within
i the Owner Controlled Area and outside the Protected Area.
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F3-4 Rev. 6
- Page 12 (14) Account for all personnel (Plant personnel, visitors and construction personnel) onsite, within 30 minutes following the evacuation. (This responsibility may be delegated). See Procedure F3-9.
(15) Determine if the assembly point and guardhouse are safe and watch for changing conditions which would require further evacuation.
(16) Complete a turnover of Emergency Director responsibilities from the Shift Supervisor of the unaffected unit to the designated Emergency Director when that individual arrives onsite. _The Shift Supervisor of the unaffected unit shall continue with the Emergency Responsibilities until a formal turnover occurs.
(17) During plant evacuations, direct monitoring of all personnel-for contamination (adequate instrumentation is available at both assembly points for this task).
(18) Direct the activation of the Technical Support Center and Operational Support Center per procedure F3-6, and F3-7, and ensure that coordinators are assigned to the emergency response centers.
( (19) Verify that communications have been established between all the onsite emergency operating centers. (Control Room, OSC, and TSC).
(20) If necessary, based on plant conditions, initiate monitoring of onsite and offsite areas. This responsibility may be delegated to the Radiation Protection Group.
(21) If offsite releases may or are occurring, direct the calculation of projected offsite dose rates as per F3-13.
This responsibility may be delegated to the Radiological-i Emergency Coordinator.
(22) Make appropriate protective action recommendations to the offsite authorities. (See F3-8, " Recommendations for Offsite Protection Actions").
(23) Ensure that continuous updates (approximately every half-hour) are provided to the State E0C's (Wisc and Minn) which were activated by the intial notification. (See F3-5) l l l NOTE: When the EOF is activated, communications with l l tte offsite authorities will be transferred to l the EOF.
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l l I I (24) Authorize overexposures in accordance with F3-12, " Emergency Exposure Control".
IBM
F3-4 Rev. 6 Page 13 (25) Direct operations at the assembly point via the Assembly Point Coordinator and arrange for any assistance required at the assembly area.
(26) If conditions indicate that. further system degradation has occurred, escalate to a more severe emergency classification and direct the notification of all offsite agencies and personnel of such action, per F3-5. Announce, or have
, announced, the re-classification and escalation to a higher emergency classification, over the public address system.
(27) As conditions permit, terminate the emergency condition or downgrade the emergency classification to a lower classification. Direct the notification of all offsite agencies and personnel, per F3-5. Announce or have announced the downgrading or termination of the emergency condition over the public address system.
(28) When the Near-Site EOF has been activated, the Emergency Manager will inform the Emergency Director. The Emergency Director will then transfer control of all offsite activities over to the Emergency Manager.
J (29) Coordinate with all group Superintendents to insure that plant manpower requirements for all subsequent workshif ts are determined and that the necessary personnel are scheduled.
- (30) When the emergency condition is terminated, ensure that all offsite and onsite personnel are notified of the termination of the emergency condition and initiation of recovery ope ra tions .
6.4 Operations Group (1) Utilize applicable operations manual procedures to respond to l the Emergency Condition as appropriate, with the objective of returning the plant to a normal safe status (or cold shutdown, if necessary).
(2) Assist the. Shif t Supervisor as requested.
(3) Announce the location and nature of the Emergency over the public address system. When an evacuation is declared, sound the evacuation alarm and direct all non-essential personnel to evacuate to the designated assembly point. Direct all personnel to remain clear of the affected area (if applicable). See F3-9, " Emergency Evacuation."
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F3-4 Rev. 6 Page 14 1
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(4) Assist in the activation of onsite emergency centers and organization.
(5) Assist individual performing the personnel accountability check as necessary, per F3-10, " Personnel Accountability".
(6) Continuously monitor the Control Room instrumentation, radiation monitors, or any other developments which could be indicative of further system degradation. Inform the Shift.
Supervisor immediately of any changes in plant status.
(7) Operators shall remain at their watch stations and perform required operations. If necessary, they will be given instructions for evacuation and/or the use of protective clothing and respiratory protection.
I I l NOTE: If liigh Radiation levels exist in the Aux- l l iliary Building / Turbine Building, operators l
, l shall be evacuated to the OSC, as instructed l l by the Emergency Director. l l l (8) Perform the necessary onsite and in plant radiation surveys as requested by the Shift Supervisor.
(9) Relief Shif t and Training Operators should proceed to the Operational Support Center for further instructions to support operations in the Control Room.
(10) The Superintendent, Operations, if on site, should report to the Control Room and provide assistance where necessary.
6.5 Shift Technical Advisor (1) Report to the Control Room imn.ediately upon notification of the Emergency Condition.
(2) Assist the Shif t Supervisor and Emergency Director in assessing the emergency condition and safety related aspects of the plant.
6.6 Shift Emergency Communicator (1) Report to the Control Room immediately upon notification.
(2) Complete the Notification Report Form, Figure 1, F3-5, with
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assistance from the Emergency Director /Shif t Supervisor of l s,, the unaffected unit.
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(3) Complete the required notification of state and local authorities, and NSP personnel in accordance with F3-5,
" Emergency Notifications".
l l 1 NOTE: State and local authorities shall be notified l within 15 minutes of the declaration of the 1
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l l emergency classification. I I I (4) Notify applicable offsite authorities if conditions escalate to a more severe emergency class or whenever the emergency class is downgraded in accordance with F3-5, " Emergency Notifications".
(5) When the emergency classification has been terminated, close-out the emergency classification, by notifying the state, local, and NSP personnel in accordance with F3-5,
" Emergency Noti fications".
I I l NOTE: If the EOF has been activated, notifications l l of offsite agencies for an escalation, l
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x_, I downgrade or termination of the emergency l l condition will be completed by EOF personnel.1 1 I 6.7 Technical Support Center Coordinator The Technical Support Center Coordinator shall be responsible for the general activation, operation and coordination of activities j in the Technical Support Center (TSC).
The TSC Coordinator shall:
1 (1) Report to the TSC and assume the position as TSC Coordinator.
Use Attachment C, Technical Support Center Coordinator Checklist. .
l (2) Coordinate activities of plant and non plant personnel located in the TSC.
(3) Designate an individual to maintain the Emergency Directors
, Log.
l (4) Establish and verify radiological monitoring for the TSC, in accordance with F3-6.
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i (5) Ensure that the TSC doors are closed and initiate the TSC 3
cleanup system.
! (6) Assist personnel performing the accountability check by i
completing the TSC personne] accountability sheet, as per F3-10.
(7) Establish or ensure that communications are established with all onsite emergency operating 1acilities (Control Room, OSC
~
f and assembly area).
, (8) Periodically update personnel located in the TSC with appropriate information.
(9) Maintain any necessary status boards.
(10) Control the use of equipment located in the emergency locker.
- (11) Provide technical guidance to the Emergency Director and Control Room operators on plant operations.
1 l (12) Obtain and provide technical assistance as required to-(, support the Technical Support Center and Control Room operations.
( (13) When the Near-Site EOF has been activated, establish communications between the TSC and the EOF.
6.8 Operational Support Center Coordinator l The Operational Support Center Coordinator shall be responsible for the general activation, operation, and coordination of activities in the Operational Support Center (OSC).
The OSC Coordinator shall:
(1) Report to the OSC and assume the role as OSC. Coordinator. ,
Use Attachment D, Operational Support Center Coordinator
! Checklist.
l (2) Coordinate activitier of plant personnel located in the OSC l to support plant operations as requested by the Control Room and TSC.
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l . direction for the Radiation Protection Spe- l l l ialists located in the OSC. l 1 l l j
i (3) Establish and verify radiological monitoring for the-OSC and i the Control Room, as per F3-7.
I
- (4) Assist personnel performing the accountability check by-completing the OSC accountability sheet,~as per F3-10.
(5) Establish connunications between the OSC, the TSC and the Control Room.
(6) Periodically update personnel located in the OSC with j appropriate plant status information.
(7) Control the use of equipment located in the emergency locker.
f- 6.9 Assembly Point Coordinator I e i The Assembly Point Coordinator shall be responsible for the
! general operation of the assembly area.
-The Assembly Point Coordinator shall:
! (1) Verify that radiological monitoring has been established for the Assembly Point.
- (2) Coordinate activities of all personnel (plant and non plant) .
located at the Assembly Point.
4 4 (3) Assist the Emergency Director in performing the i accountability check, as necessary, per F3-10.
- j. (4) Maintain the communication systems. A person may be
- designated as the communicator, if necessary.
(5) Control the use of equipment located in the Emergency Locker.
i (6) -Update all personnel with appropriate information when j directed by the Emergency Director.
) (7) Provide instructions to personnel when they are released from the assembly point for reent ry or transport offsite.
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Rev. 6 Page 18 6.10 Radiological Emergency Coordinator (REC)
The Radiological Emergency Coordinator (REC) shall be responsible for accident assessment, onsite and offsite. The REC shall:
(1) Report to the Technical Support Center and assume responsibility for the Radiological Emergency Coordinator position. Use Attachment B, Radiological Emergency Coordinator Checklist.
1 (2) Determine the current plant status.
(3) If radiological releases are occurring, airborne or liquid, verify that the Radiation Survey teams have been dispatched in accordance with F3-15 or F3-16.
(4) If radiological airborne releases may or are occurring, initiate offsite dose projections in accordance with F3-13.
(5) Assist the Emergency Director in performing the personnel
, accountability check of the Radiation Survey Teams, as per F3-10 " Personnel Accountability".
(6) Designate or ensure that an RPS is designated to proceed to the EOF Count Room to perform any required analysis in the backup countroom, as necessary.
(7) Maintain communications with the offsite survey teams. Based
- on current meteorological data, release data and survey team results, dispatch the survey teams in.the affected areas of the plume.
(8) Ensure that all Radiation Survey Team Members (onsite & l offsite) are informed of the current plant status and are i informed of any emergency condition changes.
(9) When the Radiation Survey Teams forward survey results to the l
- TSC, log the data and supervise the development of the plume map.
l (10) If the wind is from the East or West such that the plume is
[' traveling towards the Minnesota or Wisconsin bluffs, consider that plume diversion is likely to occur. Deploy the survey teams to conduct a plume search both beyond the bluffs and up
! and down the valley, where plume diversion is likely to occur.
l (11) Direct the activities of the onsite radiation survey teams, (i.e., samples required, surveys required, analysis, etc.).
i
. (12) Based on the meteorological data, release data, and surveys
- s (onsite and offsite), determine the necessary radiation
! protection for the various segments of the plant emergency organization.
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F3-4 Rev. 6 Page 19 f
g (13) Verify that the Radiation Protection Status Board is periodically updated.
l (14) Based on offsite dose projections and offsite survey
, results, provide the Emergency Director with recommendations 4
for Protective Actions in accordance with F3-8,
" Recommendations For Offsite Protective Actions".
(15) Periodically update the Minnesota Department of Health and the Wisconsin Section of Radiation Protection with information required by Figure 6 (F3-5) " Emergency Notification Followup Message".
I l-l NOTE: When the EOF is activated, this responsibil- l l ity will be transferred to the Radiation l l Protection Support Supervisor (RPSS). l l l (16) When the Near-Site EOF is activated, transfer control of the offsite survey teams to the Radiation Protection Support Supervisor (RPSS).
I I l NOTE: Dose projections will still be a responsi- l-('~') l bility of the REC and dose projection infor-l
() l mation will be forwarded to the Radiation l l Protection Support Supervisor (RPSS). l 1 -
l (17) Acknowledge the Health Physics Network HPN) phone when it rings and update the NRC with release data, dose projections and meteorological data, as required by Figure 6 (F3-5)
" Emergency Notification Followup Message" or as requested.
6.11 Radiation Protection Group (1) The Shift Radiation Protection Specialist shall provide assistance (e.g., sampling, chemistry, radio-chemistry, surveys, etc.) as requested by the Shift Supervisor.
(2) The Radiation Survey Teams shall be dispatched to initiate offsite surveys as directed per F3-15 and/or F3-16.
(3) All other Radiation Survey Team members shall report to the plant site for further instructions. The Radiation Survey Team members reporting to the plant site shall:
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(a) Unless directed by the Emergency Director or Radio-logical Emergency Coordinator, proceed to the Oper-4 ational Support Center and wait for further instruc-tions.
(b) Supervise any checks for personnel contamination and direct decontamination at the assembly point.
(c) Provide recommendations-to the Emergency Director regarding radiation exposure control to ensure that applicable limits are not exceeded.
(d) Provide radiation protection coverage for:
(1) Damage control and repair teams (2) First aid (3) Search and Rescue Teams (4) Reentry Teams (e) Perform emergency sampling (air and liquid), chemistry, radio-chemistry, surveys, etc. , as directed by the Emergency Director or the Radiological Emergency
(}
V Coordinator.
- 6.12 Security Force (1) Continue with normal duties unless otherwise notified. !
- (2) When the evacuation alarm sounds, all guards, with-the 1 exception of the SAS guard, evacuate to the guardhouse for further instructions.
l I l NOTE: The SAS guard will evacuate when directed 'l l by the Emergency Director. l l l (3) Assist with the evacuation of personnel to the designated assembly point which will normally be the Construction Office Building, in accordance with F3-29, " Emergency Security Procedures".
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1 l 1 l NOTE: (1) It will be necessary for personnel to exitl l quickly thru the portal monitor and turn- l l stile. Collect all I.D.'s and process l l badges so an Employee Onsite List of per- l l so mel inside Protected Area can be ob- l l tained. l l l l (2) To speed evacuat. ion from the Protected l l Area, it may be beneficial to open the l l vehicle gates and allow personnel to exit l l there. l l l l (3) The Security Force shall ensure that all l l personnel onsite, witt'iiit the protected l l a'rea , have heard the evacuation alarm. l l _ l (4) Perform a check of all areas ivmediately surrounding the Protected Area 'ao that all per sonnel are notified of the evacuation in progress.
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l l NOTE: The owner Controdied Area will be checked whenl l directed by the Emerghacy Dir,ector. l l __
y I (5) Contrcl access to Protected .)rea\ per instructions from the Emergengy Director. lie prepared to obtain a printout for an accountability check in accerdance with F3-10, " Personnel Accountability".
3 (6) Assist the Radiation Protection Group in establishing a ,
secondary access control point when directed by the Emergency Director.
(7) Station a guard, With dosimetry, at the plant entrance, if conditions permit, to control access to the plant site.
6.13 Logistic Support Gruup The Logistic Suppert Group includes the Administrative Services Group, Purchasing & Inventory. Control Group and the Document Control Group.
During emergency conditions, the Logistics Support Group shall:
IN (1) Continue with normal duties unless directed otherwise.
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F3-4
- Rev. 6 Page 22 (2) Immediately vacate any emergency operating center (Control f3; Room, OSC, or TSC) when an emergency is declared.
(3) Remain clear of any areas, as announced over the public address system.
t
, (4) When requested by the Shift Emergency Communicator (SEC),
f transfer control of the telephone switchboard to the TSC.
) /
l l l NOTE: The switchboard operator should report l
- i l- to tiie TSC to control the switchboard l l from the TSC until relieved by an l l alternate communicator. l 1 l (5) When the evacuation alarm sounds, proceed to the designated assembly point.
, (6) Follow instructions from the Assembly Point Coordinator for either reentry into the plant or departure from the site property.
6.14 Instrument & Control Group (1) The I&C Supervisor and Coordinators shall report to the Operational Support Center (OSC) to provide support for: <
(a) Repair and corrective actions for instrument and control systems, and;
!^ (b) Search and rescue efforts.
(2) The I&C Specialists shall:
(a) Continue with normal duties unless directed otherwise.
(b) Immediately vacate any emergency operating center
, (Control Room, OSC or TSC) when an emergency is
- declared.
(c)' Remain clear of any areas, as announced over the public address system.
(d) When the evacuation alarm sounds, proceed to the designated assembly point.
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F3-4 Rev. 6 Page 23 1
p (Gl (e) Follow instructions from the Assembly Point Coordinator for either reentry into the plant or departure from the site property.
6.15 Maintenance Group The maintenance group consists of all maintenance personnel, plant electricians and plant helpers.
(1) The Maintenance Supervisors, Chief Station Electrician, and designated station electrician alternates shall report to the OSC to provide support for:
(a) Repair and correct ive actions for mechanical and electrical systems and; J
(b) Search and rescue efforts.
(2) All other maintenance personnel, electricians and plant l helpers shall:
_s (a) Continue with normal duties unless directed otherwise.
(b) Immediately vacate any emergency operating center (Control Room, OSC, or TSC) when an emergency is declared.
j (c) Remain clear of any areas, as announced over the public address system.
. (d) When the evacuation alarm sounds, proceed to the designated assembly point.
]
3 (e) Follow instructions from the Assembly Point Coordinator for either reentry into the plant or departure from the site property.
6.16 Engineering Group ,
(1) All Superintendents, lead engineers and system experts (as requested by their supervisor) shall report to the Technical Support Center (TSC). The Engineering Group shall:
(a) Provide technical support for emergency repairs and corrective action on electrical and mechanical systems.
(b) Provide technical & engineering support for plant i
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systems.
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1 (c) Provide technical & engineering support for operating radioactive waste systems.
J (d) Provide technical & engineering support on core '
parameter analysis.
l (2) All other engineers (unless specifically requested to remain in the TSC) shall:
(a) Continue with normal duties unless directed otherwise. l
) (b) Immediately vacate any emergency operating center (Control Room, OSC, or TSC) when an emergency is declared. ,
1' (c) Remain clear of any areas, as announced over the public address system.
(d) When the evacuation alarm sounds, proceed to the designated assembly point.
(e) Follow instructions from the Assembly Point Coordinator
/
for either reentry into the plant or departure from the 4
site property.
6.17 Contact, Temporary Personnel and Visitors (1) Continue with normal duties unless directed otherwise.
4 (2) Immediately vacate any emergency operating center (Control Room, OSC, or TSC) when an emergency is declared.
(3) Remain clear of any areas, as announced over the public j address system.
$ (4) When the evacuation alarm sounds,. proceed to the designated
- assembly point.
! (5) Follow instructions from the Assembly Point Coordinator for either reentry into the plant or departure from the site property.
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F3-4 Rev. 6 Page 25 Q(3 ATTACHMENT A EMERGENCY DIRECTOR CHECKLIST "" ""= ws W em INIT (1) Determine Plant Status (2) Announce Emergency Class over PA System (3) Contact STA & SEC to report to Control Room (4) Assist SEC & sign notification report. Direct SEC to:
(a) Notify offsite authorities (F3-5)
(b) Augment onsite emergency organization (F3-5)
(5) If the first notification of an emergency is a General Emergency, call the County Sheriff immediately and recommend:
(a) Activation of Public Notification System, and; (b) Sheltering within 2 mile radius of plant
/ (6) Assure communications established & maintained with NRC.
(7) Direct Shift RPS to:
a) conduct onsite sampling, as necessary.
b) perform dose calculations, if R-50 in alarm mode.
(8) Direct RPS/ Plant Operations to conduct onsite/in-plant surveys, as necessary.
(9) Determine need to evacuate nonessential personnel (F3-9)
(10) If evacuation is necessary, designate assembly point.
(a) Designate assembly point coordinator
! (b) Complete accountability within 30 minutes after l evacuation (F3-10)
(c) Determine habitability of assembly area (11) The Shift Supervisor of the unaffected unit should complete a turnover to the designated Emergency Director at this point. If the designated Emergency Director is not available, proceed with the checklist.
(12) Direct activation of TSC & OSC (F3-6 F F3-7) and assign the
, responsibilicy for TSC Coordinator, OSC Coordinator and REC to j
l Q appropriate individuals.
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F3-4 l
' Rev. 6 l Page 26 ATTAClit!ENT A (Cont.'d)
EMERGENCY DIRECTOR CilECKLIST (13) Establish communication links between onsite emergency centers 1 (14) Dispatch offsite survey teams as necessary (F3-15 & F3-16)
(15) Direct offsite dor.e assessment activities (F3-13)
(16) Plake protective action reconunendations (F3-8)
(17) Provide continuing updates to State EOC's (18) Authorize overexposurcs as necessary (F3-12)
(19) Establish communications wite EOF (20) Transfer of fsite responsibilities to EOF p (21) Determine long-term manning requirements (22) Escalate / downgrade emergency class, as appropriate (23) Review Emergency Director's responsibilities to ensure all required actions are c omplet e.
Emergency Director Date/ Time b
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F3-4 Rev. 6 Page 27 a ATTACHMENT B RADIOLOGICAL EMERGENCY COORDINATOR CHECKLIST INIT (1) Determine Plant Status (2) Determine additional TSC support required for accident assessment functions & assign, as necessary.
(3) Designate Rad Protection Coordinator for OSC (4) Determine if releases are occurring (5) Obtain meteorological data & radiation monitor readings (6) Direct offsite dose projection calculations (F3-13)
(7) Recommend protective action recommendations for Emergency Director (F3-8)
(8) Instruct, dispatch & coordinate offsite radiation survey m teams, as necessary (F3-15 & F3-16)
(9) Ensure an RPS is designated to operate the EOF countroom facility and perform the required analysis, as necessary.
(10) Consider plume diversion along valley if plume is traveling towards Minnesota or Wisconsin bluffs and instruct Survey Teams appropriately.
(11) Instruct, dispatch & coordinate onsite radiation survey teams, as necessary (F3-14)
(12) Determine RPS sampling priorities per F3-23 (number in order) l I Primary Sample - Pressurized /Unpressurized i
l l Secondary Sample R Shield Building Stack Sample Containment Air Sample O Liquid Filtered Gas O NBMZ" BND@ DIE IBM i
l
F3-4
- Rev. 6 Page 28
(~h O
ATTACHMENT B (Cont'd)
RADIOLOGICAL EMERGENCY COORDINATOR CHECKLIST
[Zl Unfiltered Gas Ej Iodine / Particulate
[__l Other INIT (13) Establish / Maintain communications with offsite survey teams (14) Evaluate survey data and develop plume map (15) Request alternate reteorological data and weather forecast information as necessary (16) Recommend overexposure limits to Emergency Director (F3-12)
(17) Update the Radiation Protection Status Board (18) Provide periodic updates to the Emergency Director & TSC U'
Staff (19) Update the State Health Departments (Minn & Wisc)
(20) Establish / Maintain communications with the RPSS (21) Turnover the offsite survey responsibilities to the RPSS (22) Acknowledge the HPN phone and update the NRC as appropriate.
(23) Review the REC responsiblities to ensure all required actions are complete Radiological Emergency Coordinator Date/ Time cXAMPLE ONLY
~
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_ _ ___m. _ _ _ _ _ - . _ . . _. __ _ __
1
- F3-4 L
Rev. 6 Page 29
)
i ATTACllMENT C TEClfNICAL SUPPORT CENTER COORDINATOR CllECKLIST INIT (1) Shut TSC Door and Start. TSC Clean Up System (2) Designate an individual (s) to c.stablish communication between i TSC, OSC & Control Room.
(3) Designate an individual to maintain the Emergency Director's Log.
, (4) Designate an individual (s) to prrform a TSC personnel -
i accountability and assist C.D. in overall plant
] accountahi1ity. (F3-10)
(5) Activate & verifij proper operation of Vamp. (F3-6 Section 4.2.1)
(6) Activate & veri fy proper operation of CAtt (F3-6, Section 4.2.2)
(7) Designate an individual to operate the Data Recall System l (8) Evacuate all unnecessary personnel (9) Up-date Status Boards h Personnel (10) Control use of equipment located in Emergency Locker (11) Review F3-4 & F3-6 (12) Establish rout ine sampliny, & monitoring as necessary (13) Establish appropriate of fire space for Emergency Personnel TSC Coordinator Date/ Time EXAMPLE ONLY 181 1s Gft M C M D@:169
a F3-4 Rev. 6 Page 30
(
U ATTACHMENT _D OPERATION SUPPORT CENTER COORDINATOR CHECKLIST INIT (1) Designate an individual (s) to establish communication between OSC, TSC and Control Room.
(2) Designate an individual (s) to perform an OSC personnel accountability and report results to Emergency Director.
(3) Activate and verify proper operation of Vamp (F3-7, Section 4.2.1)
(4) Activate & verify proper operation of the Control Room CAM (F3-7, Section 4.2.2)
(5) Designate een individual (s) to cont rol use of equipment in Emergency Lockers.
(6) Evacuate all unnecessary personnel.
(7) Control use of food in OSC until directed by Radiation Protection Group.
(8) Establish a routine sampling .uid monitoring of OSC and Control Room as necessary.
(9) Review F3-4 & F3-7.
(10) Periodically update Status Board and Personnel.
OSC Coordinator Date/ Time EXAMPLE ONLY rh
.21 u 3 BBH " B ND@ DIGS IBM
i
. PAGE 1 0F 8 l l EMERGENCY PLAN IMPLEMENTING l
/~3 l PRAIRIE ISLAND NUCLEAR PROCEDURES l Q l GENERATING PLANT l NORTHERN STATES POWER COMPANY Number: F3-7 Rev: 3 l
l l History Copy l l /3 , a , Retention Time: Lifetime I
( (t/ l TITLE:
l Supt Ra'd, Protection l l l Approved By: (g ,/ /,, -
l ACTIVATION AND OPERATION OF l l ' i ', ? ., , l OPERATIONAL SUPPORT CENTER l l Plant Manager l l l OC#: 9 - 2 /n - 2? & l l l l l l l l 1.0 PURPOSE l l l l The Operational Support Center (OSC) is located in the Plant Operating l l Records Room adjacent. to the Control Room. The OSC provides a central l l location to assemble the necessary operators, Radiation Survey Teams, l l I & C Supervisor and Coordinators, Chief Station Electrician, and back l l electricians, and Maintenance Supervisors, to support the operations of l l the plant during emergency conditions, without causing undue congestion l l in the Control Room. The Operational Support Center SHALL be activated l l whenever an Alert, Site Area or General Emergency is declared. l l l l The purpose of this instruct. ion is to describe the activation, staffing l hV l
I and monitoring requirements of the Operational Support Center. l l
l 2.0 APPLICABILITY l l l l This Instruction SHALL apply to all plant personnel. l 1 l l l 3.0 PRECAUTIONS l 1 l l (a) Only those personnel designated by this Instruction or as request- l l ed by plant Supervisors, shall assemble'in the Operational Support l l Center. All other personnel in Records Room SHALL evacuate the l l Records Room when the OSC is act.:vated. l l l l (b) All personnel assigned to the OSC SHALL remain in the OSC unless l l specifically directed to report elsewhere. DO NOT congregate in l l the Control Room. l ,
l l l (c) Monitoring of the Operational Support Center for direct radiation l l levels SHALL be performed to ensure continued habitability of the l l Operational Support Center. l l l l 4.0 PROCEDURE l l l l 4.1 Activation and Operation of the OSC l l i l 4.1.1 The Operational Support Center shall be activated l V,CN I I I I l I IBM
F3-7 Rev. 3 Page 2
/~'\
whenever an Alert, Site Area or General Emergency is k -)
s declared. Activation may occur during normal work hours or during off-normal work hours:
o (a) During normal work hours, the following personnel SHALL immediately report to the Operational Support Center, whenever an Alert, Site Area or General Emergency is announced over the Public Address System. ,
(1) Operations personnel onsite, but not assigned to the on-shift crew.
(2) Maintenance Supervisors (3) Chief Station Electrician and backup electricians (4) I & C Supervisor and Coordinators (5) Radiation Survey Teams (unless directed otherwise by the Emergency Director or Radiological Emergen-cy Coordinator).
(6) Anyone as requested by their supervisor or the Emergency Director.
(b) If activation occurs during off-normal work hours, the s j Shift Supervisor or Emergency Director shall direct the Shift Emergency Communicator (SEC) to notify and activate the onsite emergency organization in accordance with F3-5. The following personnel shall report to the OSC to establish an initial compliment of support personnel to assist in the emergency:
(1) Maintenance Supervisors (2) I & C Supervisor and I & C Coordinators (3) Chief Electrician and backup Electricians (4) Radiation Survey Team Members
! (5) Extra operations personnel considered ,
I necessary by the Shift Supervisor to respond to the emergency condition.
4.1.2 All non-essential personnel SHALL evacuate the Records Room when the OSC is activated.
4.1.3 Additional personnel may augment the Operational Support Center staff as deemed necessary.
v IBM
F3-7 Rev. 3 Page 3
'I 4.1.4 The Operational Support Center SHALL remain activated until the emergency situation has been terminated or as otherwise directed by the Emergency Director. .
4.1.5 The Operational Support Center Coordinator shall:
(a) Designate an individual to establish monitoring of OSC environment for direct radiation and operation of the Control Room CAM and take protective actions as specified in Section 4.2.
(b) Designate an individual to act as communications per-son for the Operational Support Center and ensure that communications have been established between the Control Room and the Technical Support Center.
(c) Perform or designate an individual to perform an OSC personnel accountability check and inform the Emergen-cy Director of all personnel present for overall plant personnel accountability. (See procedure F3-10)
(d) Inform the Radiation Protection Group or the Radiological Emergency Coordinator (REC) of any significant changes in radiation levels.
( (e) Ensure that the Radiation Protection Group has established a routine sampling and monitoring program for the OSC and the Control Room, as conditions permit.
l l l NOTE: (1) Air Sampling for the OSC shall be l l completed with portable air samplers. l l l l (2) Air Sampling for the Control Room l l should be completed with the Control l l Room CAM initially and later, backed l l up with portable air samples by the l l Radiation Protection Group. l l l (f) Control the use of equipment stored in the emergency locker (protective clothing, respiratory equipment, dosimeters, etc.).
(g) Conduct periodic briefings to update all personnel in the OSC of the current plant status.
(h) Control the use of food preparation in the OSC until directed by the Radiation Protection Group.
('
(i) Designate an individual to issue dosimetry to all in-dividuals in the OSC and the Control Room.
IBM
. .-- . - . . _ _ - - ._- - = _. ._. - - _ - - -_ _
F3-7 Rev. 3 Page 4 i
4.2 Radiological Monitoring 4.2.1 Verify or establish radiological monitoring in the Operational Support Center (OSC) as follows:
(a) Direction Radiation:
- 1. Obtain the VAMP from the OSC Emergency Locker.
] 2. Plug the VAMP in and verify the white power light j is on.
- 3. If the VAMP fails (power loss, incorrect reading, etc.) contact the Radiation Protection Group for additional radiation monitors.
- 4. At about 15 mR/hr, consider evacuating all non-essential l personnel to a low dose rate area, such as 1 & C shop.
(b) Airborne Activity:
- 1. Ensure that air samples are being taken by the Radiation i Protection Group.
()
- 2. Take the following protection action based on the particu-late activity in the OSC:
' ~9
< 1 x 10 pCi/cc - no protective action necessary
~
> 1 x 10" but < 1 x 10 pCi/cc -
consider use of respiratory protection and evacuation of unnecessary personnel .
-6
> 1 x 10 Ci/cc - evacuation to the Control Room i is recommended.
- 3. Take the following protective action based on the iodine activity in the OSC:
1 at about 40 MPC hours - consider evacuation of unnecessary personnel at 200 MPC hours - consider evacuation to the Control Room i
at about 3000 MPC hours - consider use of potassium iodide pills (thyroid blocking agent)
IBM
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F3-7
. Rev. 3
. Page 5 p
d i I l NOTE: The Radiological Emergency Coordinator (REC) l l will recommend the use of potassium iodide pills l l (thyroid blocking agent) if the project thyroid l l exposure approaches 10 Rem, which is equivalent l l to approximately 3000 MPC hours. l l l 4.2.2 Establish operation of the Control Room CAM.
(a) The CAM is in a hot standby condition in the back of the Control Room, with the electronics energized and the blower, chart, and filter paper off. Perform the following:
(1) Turn the blower switch (located next to the recorder) to the ON position to start the blower, strip chart recorder, and the filter paper.
(2) Adjust the blower flow rate to 3 SCFM using the toggle switch located on the right side of the CAM.
(3) Verify the CAM is in operation (i.e. , verify the blower, filter, and strip charts are operating, meters are on scale, etc.).
(4) If the CAM fails to operate properly contact the Radiation Protection Group for additional sampling.
(b) ) Periodically monitor the Control Room CAM for airborne particulate and iodine activity.
(c) Recommend the following Protective Actions for Control Room personnel, based on reading from the CAM.
(1) CAM - Particulate (1x10 pCi/cc - no protective action necessary.
>1x10 but (1x10 pCi/cc -
consider use of respiratory protection and evacuation of unnecessary personnel.
>1x10 pCi/cc - respiratory protection required
\_
IBM
1 F3-7 l Rev. 3 l Page 6
~s (2) CAM - iodine (See Figure 1) at about 40 MPC hours - consider evacuation of unecessary personnel.
at 200 MPC hours - evacuation of unnecessary personnel required, at about 3000 MPC hours - consider use of potassium iodide pills (thyroid blocking agent).
l I l NOTE: The Radiological Emergency Coordin- l l ator (REC) will recommend the use l l of potassium iodide pills (thyroid l l blocking agent) if the project l l thyroid exposure approaches 10 Rem, l l which is equivalent to approxi- l l mately 3000 MPC hours. l l l
() 4.3 Dosimetry Issue 4.3.1 An RPS should read and record dosimeter readings for each individual issued a dosimeter in the OSC and the Control Room.
4.3.2 An RP-112 (Figure 2) should be issued for each Individual issued a dosimeter.
4.3.3 Dosimeters should be issued for the exposure that is to be expected.
l l l NOTE: Radiation Protection personnel, out l l plant operators and other individuals l l expected to be involved in high exposurel I tasks should be issued high range dos- l l imeters and be equipped with a dose l l rate instrument. l I l O
IBM
- F3-7 Rev. 3
. . Page 7 FIGURE 1 DETERMINATION OF MPC HOURS VS. INTEGRATED COUNT RATE 10,6 - .% .w .., ..a ...
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l l
Y NOTES: (1) Based on I-131, MPC = 9 x 10-9 pCi/cc.
i (2) Curve valid only for init.ial period following CAM startup (0-6 ho6rs).
(3) Curve is not, valid for silver zeolite absorber is changed.
4 m
TIMEKEEPERS WORKSHEET RP-112 A PINGP 275 Rev. 4 Qualified to wear CLEARVUE CLEARVUE W/ AIR following respirators- NAME: TLD:
O utTRavUr utTRivuE W/ AIR DOSE RATE C NORTON O noon "^"""
o (cR/ Min): - _.
PAGE: OF TIME TOTAL AVAIL LIMIT EXP DATE TIME IN DOSIM DOSIM DOSIM THIS AVAIL EXP (MIN) TIME IN TIME OUT RPS LOCATION IN OUT ENTRY EXP INIT g 0-IR
- _ _.0-5R g 0-200 0 0-1R
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- 0-5R The highect em ureboreach otry will be used for calculating the available exposure for the next entry.
I I
PAGE 1 0F 7 l l EMERGENCY PLAN IMPLEMENTING l l PRAIRIE ISLAND NUCLEAR PROCEDURES l l GENERATING PLANT l l NORTl!ERN STATES POWER COMPANY JNumber: F3-9 Rev: 1 l l l History Copy l l /) , q , , Retention Time: Lifetime ll l Reviewed By: f/ g / f7 '
l l /V #7-2 [(8( ' ' .N - l TITLE: l l Supt, R 'd Protection l l l Approved By: Ig . , .
l EMERGENCY EVACUATION _ l l bi ' i,f l l l Plant Mana l l l OC#: T-3h
- gerQ_.. l l 1 l l l l 1 l l 1.0 PURPOSE l l l l This procedure provides instructions for implementing an emergency l l
l evacuation of affected areas within the plant buildings or areas within the site boundaries. This procedure does not apply to ll l
l evacuation of the general public located in aftected areas beyond the l l site boundaries. l l l l This instruction shall apply to evacuations caused by radiological l l hazards, fire, toxic gas, etc. l The Emergency Director has three options for evacuation determined by l l the type of emergency condition and/or magnitude of the release. The l- l l options are: l l
l i l 1. Local Evacuation l l l l l This is an evacuation of a speci fic area of a plant building to a l l safe area within the building. l l l l 2. Plant Evacuation l l l l This is an evacuation of plant buildings to a designated assembly l l point onsite. l l l l 3. Site Evacuation l I l l This is an evacuation of the plant site to a designated area l
- l offsite. l l l l The Emergency Director (Shift Supervisor until relieved) is l l responsible for ensuring that an appropriate evacuation (local, plant l-l l or site) is implemented when radiological or other conditions warrant l l such action. l l l l The Emergency Director shall, based on the best information available, l l
h b l l
determine that evacuation is the protective action that will result in the lowest personnel exposure.
l l
I l l l IBM
F3-9 i Rev. 1 Page 2 O
O 2.0 APPLICABILITY This instruction shall apply to all plant personnel.
3.0 PRECAUTIONS 3.1 This procedure does not apply to the evacuation of the general public located in af fected areas beyond the site boundary, i
3.2 The Emergency Director shall consider radiation shine from the containments as well as natural hazards when determining the habitability requirements of the assembly areas.
4.0 PROCEDURES 4.1 Local Evacuation A local evacuation of a specific area of the plant may be necessary because of local hazards. A local evacuation shall proceed as follows:
,,_ 4.1.1 Alarms / indications or visual observations indicate
(} unacceptable conditions in an area of the plant.
4.1.2 The Emergency Director / Shift Supervisor shall direct the Control Room operator to announce over the public address' system the location of the problem and any evacuation instructions, as follows:
" ATTENTION, ALL PLANT PERSONNEL. THERE IS A (hazard)
OCCURRING IN (specify area) . ALL PERSONNEL SHOULD EVACUATE FROM TIIE (specify area) AND STAY CLEAR OF l THAT AREA UNTIL FURTIIER NOTIFIED.
Repeat the message several times to ensure that all personnel are warned.
l l l NOTE: During a local evacuation, the evacuation l l alarm should not be sounded. l l l 4.1.3 The Emergency Director / Shift Supervisor shall ensure that all personnel have exited the specified area by completing or directing the completion of a brief search of the area.
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l F3-9 6
Rev. 1 Page 3 a
4.1.4 The Radiation Protection Group shall assume control of entry into the area for exposure control purposes.
4.1.5 The Radiation Protection Group shall complete surveys in the area and when conditions are returned to normal, the Radiation Protection Group shall recommend to the Emergency D ' irector or Shift Supervisor that the area be returned to normal use or relax access control to that area.
4.2 Plant Evacuation
, A plant evacuation during an Alert, Site Area, or General Emergency may occur because radiological or other conditions make or potentially make large areas of the plant buildings uninhabitable. All non-essential personnel shall evacuate to a designated onsite assembly area for monitoring, accountability, and dose assessment while emergency response personnel proceed to their respective emergency operating centers.
A plant evacuation shall proceed as follows:
4.2.1 When an emergency is classified as an Alert, Site Area, or General Emergency and when conditions make large areas of (p), _ the plant site uninhabitable, the Emergency Director shall order a plant evacuation.
4.2.2 The Emergency Director shall determine the wind direction and possible habitability problems at the onsite assembly areas.
I I l NOTE: When considering the habitability re- l l quirements of the-Construction Office l l Building, the Emergency Director should l l consider the radiation levels resulting l l from direct shine from the containments. l l l 4.2.3 If conditions are acceptable, the Emergency Director shall inform the Control Room operator of the designated assembly area and direct the operator to sound the plant evacuation alarm.
4.2.4 Upon sounding the alarm, the operator shall announce the evacuation instructions over the public address system, as follows: .
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F3-9 g Rev. 1 Page 4
() " ATTENTION ALL PLANT PERSONNEL. AN EVACUATION HAS BEEN DECLARED. ALL PERSONNEL SHALL EVACUATE TO THE (specify assembly area). ALL EMERGENCY ORGANIZATION PERSONNEL SHOULD REMAIN AT YOUR EMERGENCY OPERATING CENTERS."
Repeat the message several times to ensure that all personnel are warned.
4.2.5 The Emergency Director shall activate the onsite emergency operating centers in accordance with F3-6, " Activation of TSC" and F3-7, " Activation of OSC".
4.2.6 The Emergency Director shall implement F3-10, " Personnel Accountability". Personnel accountability shall be
- completed within 30 minutes.
4.2.7 The Emergency Director shall designate the Radiation Protection Group responsible for supervising any required monitoring or decontamination at the assembly point in accordance with F3-14.
4.2.8 The Emergency Direct.or shall designate an Assembly Point Coordinator who will control operations at the Assembly point.
4.2.9 If the completion of the accountability check results in O_s s missing persons, the Emergency Director shall direct a search of the plant buildings in accordance with F3-11,
" Search and Rescue and F3-12, " Emergency Exposure Control".
4.2.10 The Emergency Director shall continuously monitor conditions at the assembly point and take action if conditions deteriorate. The Radiation Protection Group shall be responsible for establishment of a sampling program.
4.2.11 When plant conditions have stabilized, the Emergency Director shall direct a reentry into selected areas of the plant in accordance with F3-5, " Reentry".
4.2.12 The Emergency Director shall release all personnel at the assembly area when conditions allow. The Radiation Protection Group shall monitor all vehicles departing the site if contamination is highly likely in accordance with F3-14.
I I l NOTE: Key personnel may be authorized reentry l l into the plant to augment the TSC and/or l f^~g l OSC staff when requested. l i (_-) l I
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F3-9 i Rev. 1 Page 5 O 4.3 Site Evacuation A Site Evacuation of non-essential personnal shall be required when unacceptable conditions extend outside the plant buildings to areas offsite making the normal assembly areas uninhabitable.
1 Personnel shall be directed to evacuate to the parking lot and then using personal cars or NSP vehicles, proceed to an upwind remote assembly area which should'be selected in cooperation with
- the Emergency Manager.
4 t I I l NOTE: Monitoring of personnel and equipment prior to l departure from site is not necessary because of l
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A site evacuation is highly unlikely but may be necessary in cases of Site Area or General Emergency when conditions worsen.
i A Site Evacuation shall proceed as follows:
4.3.1 An Alert, Site Area or General Emergency condition exists
- and the Emergency Director has ordered an evacuation of non-essential personnel from the-plant site, and the
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i primary onsite assembly points are uninhabitable.
, 4.3.2 When conditions indicate that the onsite assembly areas are not habitable, the Emergency Director shall designate an area offsite for congregating non-essential personnel
, evacuated from the plant site. A site should be chosen in
- cooperation with the Emergency Manager at the Near-site EOF. (Possible upwind assembly areas are the NSP Red Wing i
Service Center or the Prairie Island Near-site EOF).
l 4.3.3 The Emergency Director shall inform the Control Room l operator of the designated assembly area and the traffic routes to use and direct the operator to sound the evacuation alarm.
4.3.4 The operator shall sound the alarm and announce over the public address system:
" ATTENTION, ALL PLANT PERSONNEL. ALL PERSONNEL WITHOUT EMERGENCY ASSIGNMENTS SHALL EVACUATE THE PLANT SITE i IMMEDIATELY. EVACUATE TO THE PARKING LOT AND YOUR CAR OR
- NSP VEHICLES AND PROCEED TO THE (specify assembly area) VIA (designated traffic route) FOR PERSONNEL MONITORING. ALL EMERGENCY PERSONNEL SHOULD REMAIN AT YOUR EMERGENCY OPERATING CENTERS".
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F3-9
[ Rev. 1 Page 6 Repeat the message several times to ensure that all personnel are warned.
4.3.5 The Emergency Director shall provide additional instructions to Guard Force personnel who will be able to advise the people as they exit the guardhouse on the proper traffic route and assembly area locations.
Instruct the Guard Force to hand out evacuation instructions, Figure 1, to all personnel.
4.3.6 The Emergency Director shall implement F3-10, Personnel Accountability and direct any required follow-up actions in accordance with applicable procedures.
4.3.7 The Emergency Director shall ensure that the Guard Force has warned all personnel within the owner controlled area, including all trailers, warehouses and construction sites.
4.3.8 The Emergency Director shall direct the Radiation Protection Group responsible for personnel monitoring and decentamination at the assembly area.
4.3.9 The Emergency Director shall coordinate arrival of the s evacuated personnel at the assembly area.
4.3.10 The Radiation Protection Group shall supervise all monitoring and decontamination per the guidelines of F3-19, " Personnel and Equipment Monitoring and Decontamination".
4.3.11 When conditions allow, release personnel from the assembly area or issue further instructions. Key personnel may be authorized reentry to the plant site upon request from the site emergency organization.
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. F3-9 i Rev. 1 Page 7 FIGURE 1 ,
SITE EVACUATION INSTRUCTIONS I
HASTINGS Y
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ty Uk 18 O dd ~* INGP PI
< EOF EVACUATION ROUTES 61
- 1. Exit Plant Parking Lot RED WING
- 2. Turn left on County 18
- 3. Proceed to PI Training Center
- 4. Use West Entrance INSTRUCTIONS
! To NSP Red Wing Service Center l
- 1. Proceed to offsite Assembly
- 1. Exit Plant Parking Lot via Point along designated route.
County 18 to Hwy 61.
- 2. Turn Left on Hwy 61. 2. Keep windows rolled up; turn
- 3. Proceed to Red Wing heaters and air conditioners off.
- 4. Turn left on Cannon River Road. 3. Do not smoke, eat or drink.
- 5. Turn Left on Pepin St. to O NSP Service Center. 4. Do not leave Assembly Point until released.
IBM
, PAGE 1 OF 6 l l l EMERGENCY PLAN IMPLEMENTING l l PRAIRIE ISLAND NUCLEAR PROCEDURES
[m' l GENERATING PLANT l
l l NORTHERN STATES POWER COMPANY Number: F3-10 Rev: 2 l l History Copy.l l n . A , , Retention Time: Lifetime l l l' TITLE: l ad Protpction
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l Supt. l l l Approved By: .4-f PERSONNEL ACCOUNTABILITY l l r l l l OC#: Plant'Mana T ,9h- . '
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(% l l l l l l l l 1.0 PURPOSE l l l l The Instruction SHALL delineate the procedure to perform the l l personnel accountability check within the Protected Area, l l following a plant evacuation. l l l 1 l l 2.0
SUMMARY
l l l l In the event of a plant evacuation, the personnel accountability l l
l check within the Protected Area SHALL be completed within thirty (30) minutes following the evacuation to allow an orderly search ll l
[S l for missing personnel. The Emergency Director is responsible for l b l the completion of this personnel accountability and may delegate l l
l this authority to the Guard Force and the respective Coordinators at each of the emergency operating centers. All personnel ll l
l accountability results SilALL be forwarded to the Emergency l l Director. l l 1 l
l When the evacuation alarm sounds, the Guard Force will immediately obtain an employee onsite list from the Guardhouse Computer. All l ll l individuals evacuating the plant will have their ID badges l l collected by the Guard Force. If the Construction Building is the l l designated assembly area, the Guard Force will collect all ID l l badges at the Guardhouse as the personnel exit the plant site. l l All badges will then be inserted into the Card Readers, thus l l producing a Computer Printout of all remaining individuals on- l l site. If the Screenhouse is the Assembly Point, the Guard Force l l will collect all ID badges at the Screenhouse and manually check l l off individuals from the employee onsite list, thereby producing a l l roster of all remaining individuals onsite. Each coordinator at l l each onsite emergency operating center, including the Radiological l l Emergency Coordinators, will be responsible for compiling a roster l l of personnel remaining onsite in their respective area. Each of l l these rosters will then be compared to the computer printout l l obtained by the Guard Force, thereby either indicating all l l personnel accounted for or indicating missing personnel. The !
l status of missing personnel SifALL be rechecked and appropriate l g l searches for missing personnel initiated. l l l l l l IBM i
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F3-10 Rev. 2 Page 2 3.0 APPLICABILITY The Instruction SHALL apply to all Emergency Directors and all Emergency Organization Coordinators.
4.0 PRECAUTIONS (1) All individuals remaining in the Protected area following a plant evacuation SHALL be verified by a direct contact (either in person or verbally) and their location, nase and TLD # recorded on the personnel accountability sheet, Figure 1..
(2) The Emergency Director SHALL ensure that this instruction is completed.
(3) Wen the initial accountability is completed, access to the Protected Area shall require Coordination between the Emergency Director, Radiation Protection Group, and the Guard Force to ensure an ongoing personnel accountability throughout the duration of the emergency situation.
(4) An accountability check SHALL be completed once per shift (every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />) to ensure a continuous personnel account-ability, or when requested by the Emergency Director.
s 5.0 PROCEDURE 5.1 During an evacuation, all nonessential personnel SHALL proceed to the designated assembly area.
I I l NOTE: The designated assembly area may be either the l l Screenhouse or the Construction Office Building. l l l Listen for instructions over the public address l l address system prior to evacuating. I I I 5.2 Wen the evacuation alarm sounds, the Guard Force will l immediately obtain an employee onsite list from the Security Computer.
5.3 The Guard Force SHALL collect all ID badges from personnel evacuating the plant as follows:
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F3-10 Pev. 2 Page 3 (a) If the Screenhouse is the designated assembly point, Security personnel SHALL proceed to the Screenhouse and collect all ID badges i
from personnel as they enter the Screenhouse.
(b) If the Construction Office Building is the designated assembly point, the Guard Force SHALL collect all ID badges from personnel as ,
they pass through the Guard flouse.
I I I t
l NOTE: Evacuating personnel need not l l stop at the Portal Monitor in l l the Guard !!ouse or at Access l l Control. I I l 5.4 When all ID hadges have been collected, the Guards SHALL l obtain a personnel accountability sheet as follows:
(a) 11 the Screenhouse is the designated assembly point, the Guard Force SHALL manually account for personnel by checking off the collected ID badges from the employee on-site list initially obtained when the eva-cuation alarm sounded. When all ID badges have been checked off, the employee onsite list should reflect only those personnel remaining within the protected area.
(b) If the Construction Office Building is the designated assembly area, the Guard Force SHALL insert all collected ID badges into the card reader, and then obtain an updated employee onsite list from the Security computer, which will list all personnel remaining within the protected area.
I I l NOTE: The Guard Force S!!ALL update the computer l l printout indicating any personnel who may l l have been allowed ent ry or who may have l l exited the Protected Area after the printout l l was obtained. l l 1 5.5 Emergency Operating Center Coordinators, which includes:
(a) Control Room (includes Aux Bldg & Turb b1dg Operators) l'
\ (b) Technical Support Center (c) Operational Support Center i
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F3-10 Rev. 2 Page 4
' GIALL complete a roster of personnel in their designated area. Use Figure 1, " Emergency Operating Center Personnel Accountability Check Sheet".
I l l NOTE: The Radiological Emergency Coordinator l l should use this checksheet to account l l for all members of the Radiation Pro- l l , tection Group (onsite and offsite). l 1
l 1E l 4
5.6 After all non-essential personnel at the assembly $
point have beenichecked off the Employee Onsite list, the updated Employee onsite list obtained, and the Emergency Operating Center Checksheets SEALL be brought to the Emergency Director or his ' designee, in the Technical Support Center.
- ; )
. 5.7 The Emergency Director or his designee SHALL compare the Emergency Operating Center Checksheets against the Computer Printout to account for all remaining persoanel onsite.
5.8 All emergency operating centers and the assembly point -
SHALL be rechecked for missing personnel.
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[ 5.9 If all personnel cannot be accounted for, the Emergency 1 ;
Director SHALL initiate a search for missing personnel, in e>
accordance with F3-11, " Search and Rescue".
5.10 Once each shift (every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />) or when requested by the Emergency Director, a personnel account- '
ability check onsite shall be conducted as follows: ,
(a) Request the Guard Force to obtain current
' Employee onsite list from the Security' computer.
(b) Request all emergency operating center coordin-s ators, which includes:
\i (1) Control Room \
(rj Technical Support Center l
(3) Operational Support Center e (4) Radiation Protection Group l x
to complete a roster of personnel in their des-ignated areas. Use Figure 1, " Emergency Oper- 1
^
ating Center Personnel Accountability Check i
Sheet".
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I F3-10
. , . .s Rev. 2 Page 5 (c) The Emergency Director or designee SHALL compare the Emergency Operating Checksheet against the Employee onsite list to account for all personnel onsite.
(d) Initiate a search for missing personnel in acc-ordance with F3-11, " Search and Rescue."
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F3-10 Rev. 2 Page 6 FIGURE 1 EMERGENCY OPERATING CENTER PERSONNEL ACCOUNTABILITY CllECK LOCATION: Control Room i I Technical Support Center i l Operational Support Center I i ;
Radiation Protection Group i i Date: Time:
1 NAME TLD# NAME TLD# 1 I I I I I I I I l i I I I I i i l I I I I I I I I l 1 1 I I I I I I l Yh ! !
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PAGE 1 OP 12 l l EMERGENCY PLAN IMPLEMENTING l O l PRAIRIE ISLAND NUCLEAR PROCEDURES l l GENERATING PLANT l l NORTHERN STATES POWER COMPANY Number: F3-12 Rev:2 l l History Copy l l /) s ) / , Retention Time: Lifetime l l Reviewed By: / l l .
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l TITLE: l l d Rro ction l l l Approved By: (r/ '/ j ) e " l EMERGENCY EXPOSURE l l ( ~ [_ U N l CONTROL l l Plgnt Manayet l l l OC#: 5 - )/77- & ~> l l l l l l l l 1.0 PURPOSE l
l l l This procedure provides guidance and criteria for the authorization of l l personnel exposures in excess of the 10 CFR 20 limits or administrative l l limits during an emergency. It also delineates the procedures for l l follow up action following a planned or unplanned excessive exposure. l 1 l l This instruction will delinate the responsibilities of the Emergency l l Director and Radiation Protection Group in carrying out a program of l l exposure control under adverse conditions.
l l l l l
[ l l NOTE: The radiological controls specified in this l l v l l procedure are applicable only when l l l l there are indications of' fuel damage. l l l l Normal radiological control practices l l l l should be used if there is no fuel l l l l damage. l l l 1 I I l l l 2.0 APPLICABILITY l l l l This instruction shall apply to the Emergency Director, Shift l l Supervisors, and the Radiation Protection Group. l l l l 3.0 PRECAUTIONS l l l l (1) Appropriate dosimetry equipment, which is capable of measuring the l l anticipated maximum exposure, shall be worn. l l 1 l (2) Extremity exposure shall be controlled through the l l use of extremity TLD badges. l l l l (3) An individual shall be allowed only one excessive l l exposure in a lifetime. l l l l l O I I U l l I I I I IBM
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F3-12 Rev. 2 4
Page 2 (4) Women of children bearing age shall be advised not to receive an excessive exposure.
(5) Internal exposure should be controlled through the use of respiratory equipment to every extent practical.
I (6) All personnel who may exceed or have exceeded the normal exposure limits shall be made aware of the effects of significant radiation exposure and must undergo a medical evaluation of the exposure.
(7) The Emergency Director is the sole individual allowed to authorize radiation exposure in excess of normal guidelines. The Radiological Emergency Coordinator i
shall make recommendations to the Emergency Director.
(8) Whole body exposure should be limited to about 75 Rem for life saving activities.
(9) Volunteers above the age of 45 are recommended.
(10) Extremity Exposure should be limited to 300 Rems for life saving activities.
4.0 GENERAL DISCUSSION i
(
, The exposure of all personnel during emergency ' conditions shall be maintained as low as reasonably achievable (ALARA),
and should be maintained less than the administrative limits of the Operations Manual, Section F2, Radiation Safety, and/or less than the 10 CFR 20 exposure limits.
During emergency conditions, normal exposure practices may
, have to be waived to protect equipment and/or life. The Emergency Director has the authority to authorize exposure i above the normal exposure guidelines. The Radiation Protection Group shall assist the Emergency Director in exposure control.
5.0 PROCEDURE In the event of a planned exposure in excess of the normal limits, the following procedure shall be followed. If necessary, the Emergency Director may verbally authorize increased exposure when time is a limiting factor and documentation shall be completed as a follow up.
The Emergency Director shall authorize all exposure in excess of 10 CFR 20 limits. Whole body exposure should g be limited to 25 Rem for search and rescue missions and s_ / vital plant operation. Whole body exposures for life savings missions should be limited to 75 Rem.
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F3-12 Rev. 2 Page 3 f%
() 5.1 The Emergency Director (or his designee) should complete Part I of the Emergency Exposure Authorization Form (Figure 2).
5.2 The individual (s) should complete Part II of the Exposure Authorization Form (Figure 2).
5.3 The individual (s) shall be briefed on the expected radiation levels to be encountered based on actual measured readings or expected values. Use procedure F3-25, Reentry if necessary.
5.4 The individual (s) should be briefed on the expected effects of high exposure. See Figure 2.
5.5 The individual (s) shall be instructed to use all ALARA concepts available.
5.6 The Radiation Protection Group shall issue dosimetry (TLD's, dosimeters, extremity badges) and survey meters (as applicable) to all individuals as necessary.
5.7 The Radiation Protection Group shall designate the required protective clothing and respiratory protection.
[v) l NOTE: If the use of SCBA lengthens the time l l required to complete the micsion, it mayl l be ALARA to not wear the respiratory l l protection and thereby accept a higher l l internal exposure, and keep the overall l l exposure lower. Thyroid Blocking Agents l l may be considered. l l l 5.8 When the mission (emergency exposure) is completed, the Radiation Protection Group shall:
(1) Restrict the individual (s) from further exposure until the exposure evaluation is completed.
(2) Complete an exposure evaluation of each individual based on dosimetry results, measured dose rates, airborne activity measurements, whole body counts, and stay times in the area.
(3) Complete Part I}J of the Exposure Authorization Form.
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l F3-12 Rev. 2 5.9 If the dose equivalent exceeds 12 Rem whole body, 60 Rem skin, or 150 Rem extremity, the details of the exposure shall be evaluated by a physician.
5.10 If the dose equivalent exceeds 24 Rem whole body, 150 Rem skin, or 300 Rem extremity, the individual shall be examined by a physician and appropriate tests completed.
l NOTE: For purposes of this procedure, the l l dose equivalent is exposure received l l from external and internal sources. l l l 5.11 The Emergency Director shall be informed of all results including the medical evaluation if necessary.
5.12 The Radiological Emergency Coordinator should complete Part IV of the Exposure Authorization Form.
l NOTE: 10CFR 20 requires NRC notification of l l all overexposures. l I l (n)
- ' 5.13 A Secondary Access Control Point should be established in accordanc.e with F3-21 " Establishment of a Secondary Access Control Point" whenever a site evacuation is necessary.
5.14 All entries into the Aux Building should be controlled by the Radiation Protection Group through the Operational Support Center (OSC).
I 5.15 The Radiation Protection Specialist (RPS) stationed at the Secondary Access Control Point should write Radiation Work Permits (RWP) for all entries made beyond the Secondary Access Control Point except for Aux. Building RWP's, which should be written by the RPS in the OSC. RWP numbers should stary at 5000 for the Secondary Access Control Point and 60QD for the RWP's issued in the OEC.
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F3-12 Rev. 2 Page 5 A
k) m 5.16 An RPS should accompany all entries made into areas where the radiological conditions are unknown.
5.17 All normal dosimetry should be issued at the Secondary Access Point with the exception of initial accident dosimetry.
5.18 Initial accident dosimetry should be issued in the TSC for all personnel if the dose rate exceeds about 15mR/hr. Dosimeter readings are recorded on the Emergency Center Activation Exposure Record and forwarded to the Secondary Access Control Point.
5.19 Initial accident dosimetry should be issued to all personnel in the OSC and the Control Room, whenever the OSC is activated.
5.20 When an individual approaches his maximum allowable exposure limit, his Access Control Card (RP-133) should be marked "N0 FURTHER EXPOSURE". Only the Emergency Director can authorize additional exposure.
6.0 DOCUMENTATION OF EXPOSURE 6.1 (J)
~
Issuing TLD's.
(1) The RPS should have temporary personnel complete a NRC-4 and NRC-5 forms.
(2) The RPS should issue consecutively numbered TLD's starting at number 1100.
(3) The RPS should put the assigned number on the TLD and the Access Control Card and complete the appropriate sections of the TLD Assignments Sheets (RP-100).
(4) The RPS should calculate the individuals available quarterly exposure and record on the top line of the Access Control Card.
(a) When calculating the available quarterly exposure, the RPS should ensure the individual will not exceed 5 (N-18).
(b) An individual should be limited to 300 mrem if he doesn't have quarterly exposure history available.
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(c) An individual should be limited to 1000 mrem if his quarterly exposure history is available but his lifetime exposure is unavailable.
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F3-12 Rev. 2 Page 6 n
ss/ (d) An individual should be limited to 2250 mrem in the quarter if all exposure history is available.
I l l NOTE: The Emergency Director mayl l authorize individuals to l l receive greater exposures l l in accordance with l l Section 5.0. l l l (5) If the individual is reporting to the OSC, the RPS at Secondary Access Control should complete a Timekeepers Worksheet (RP-112) and have the individual take it with him to the OSC.
(6) The RPS in the OSC should issue a Timekeepers Worksheet for each individual who enters the Aux Building.
(7) If the NSP Computer is available, the individual's personal and exposure data should be added to the s computer exposure system as per the Radiation g j Protection Manual.
(8) If the computer is not available, the individual's data should be added to the Emergency Exposure Record as per Attachment A.
(9) An "X" should be placed behind the TLD number, on the TLD of anyone who is issued a TLD who has already been issued a TLD for the month when the original TLD is unavailable.
6.2 Recording Exposure (1) After each entry into the controlled area, the RPS should read and record the dosimeter readings. The lowest range dosimeter on scale should be the reading for exposure records. The RPS should then calculate the new available quarterly exposure and record on the next line of the Access Control Card.
(2) Low range dosimeter readings should be logged in mR and high range dosimeters in R. The lowest range dosimeter should be logged on the top and the highest range on the bottom.
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N-(3) At the end of each shift, the RPS should record the exposures from the cards, and enter in the computer l as per the Radiation Protection Manual.
IBM
l 3
F3-12
. Rev. 2 '
Page 7 (4) If the computer is not available, the RPS should add the exposure to the Emergency Weekly Exposure Record as per Attachment A.
(5) The RPS should !imit each individuals exposure to 3 Rems and lifetime exposure to 5 (N-18) unless the Emergency Director authorizes higher exposure.
(6) The RPS should add the exposures from the Emergency Center Activation Exposure Records to the computer system or the manual system of Attachment A.
(7) If an individual has received his maximum allowable exposure, the RPS should mark the individuals Access Control Card "N0 FURTHER EXPOSURE" and place the card in the normal card use file.
Authorization by the Emergency Director should e issued prior to allowing any further exposure.
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1 F3-12 Rev. 2 Page 8 ATTACHMENT A A. Adding Individuals (1) The RPS should record the following information on the Emergency Weekly Exposure Record (Figure 3).
(a) The individual's name, TLD number, lifetime permissible exposure and accumulated quarterly exposure.
J (b) -The lifetime permissible exposure is equal to 5(N-18) minus lifetime exposure. This number should be equal to the number in block 13C of the NRC-4 form.
B. Adding Daily Exposure (1) The exposure total for the day is placed in the upper i
half of the block for the day.
(2) The exposure for the day is added to the previous
- quarterly exposure (lower half of previous days column number 3) to give the new accumulated quarterly exposure which is recorded in the lower half of the daily column number 3.
(3) New forms are started at the beginning of each week. The quarterly exposure total from column number 4 is placed in column number 2 for new week. The previous weeks total exposure is subtracted from the previous weeks lifetime permissible - column no 1 - and the resultant place in column number 1 for the new week.
The weekly total can also be added to the previous weeks dose for the quarter - column number 2 - to yield the accumulated for quarter, which should be equal to the
- number in column number 4.
(4) The RPS shall save all exposure work for further reference and microfilmipg. .
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F3-12 Rev. 2
, ,, Page 9
\s / FIGURE 1 1
CRITERIA FOR EMERGENCY EXPOSURES WHOLE BODY EXTREMITY THYROID Saving Human Life 75 Rem 300 Rem NO LIMIT
! vital equipment)
Medical Treatment, First 3 Rem 7.5 Rem Aid, Ambulance Service and Decon. Personnel
- No upper thyroid is specified for life saving activities since complete loss of thyroid function may be considered an acceptable risk for saving life. Ilowever, thyroid exposure should be minimized to the expent feasible by the use of respiratory protection and/or thyroid blocking agents.
5 IBM
F3-12 Rev. 2 FIGURE 2 EMERGENCY EXPOSURE AUTHORIZATION FORM PART I
- 1. Name of Individual to Receive Exposure:
Soc. Sec. No:
- 2. Individual TLD Number:
Employer / Department:
- 3. Task (s) to be Performed:
- 4. Date of Authorization:
Authorized Limit:
- 5. Conditions:
Individual is a volunteer or professional rescue person Individual is broadly familiar with radiological consequences of exposure Woman capable of reproduction has been advised not to take part. (Req. Guide 8.13)
Individual has not received an emergency exposure before Dose rates in area known/measureable Saving Human Life r Protection of Health and Safety of the Public
( Protection of Property or Medical / Decontamination s_
- 6. Emergency Director:
(Signature)
PART II EFFECTS OF ACUTE EXPOSURE Acute Dose (Rem) Probable Effect 0-25 (a) No detectable clinical effects (b) Some reduced fertility at upper range 25-100 (a) Slight transient blood changes (b) Fatigue but no serious disability (c) Reduced to marked reduction in fertility across the range 100-200 (a) Vomiting and nausea in 25%
(b) Marked changes in blood (c) Sterility for period of time (weeks) 200-300 (a) Nausea and vomiting for one day in all cases (b) Fatigue and malaise for 2 weeks
[)
N-(c)
(d)
Full recovery in 3 months Sterility for approximately one year IBM
F3-12
. Rev. 2 Page 11
^
(,_,) FIGURE 2 (CON'T)
- 'ERGENCY EXPOSURE AUTHORIZATION FORM PART II (CON'T)
I have been briefed in the radiological consequences of the proposed emergency exposure, and I have volunteered to perform the emergency measures during which I will receive the emergency exposure.
- 7. Signature:
Date:
PART III (Attach exposure evaluation)
- 1. Dose equivalent assigned for entry:
- 2. TLD/ Dosimeter Results:
- 3. Bioassay Results:
- 4. Medical Evaluation / Action:
(N k-- Doctor Report Attached: YES/NO
- 5. Rad Prot. Specialist Date:
PART IV
- 1. Disposition (Allow additional exposure, restricted access, etc.)
- 2. Radiological Emergency Coordinator:
Date:
l NOTE: 10CFR 20 requires notification of all l l overexposures. l I 1 1
u, IBM
,, , , - - - , - - ~ ~ ~ - - -
F3-12 FIGURE 3 a 12 O EMERGENCY WEEKLY EXPOSURE RECORD N]
DATE: TO:
t 1 2 3 4
n 18 L etime or QTR.
Accumulato! Q t r*. l -
7 y TOT.
3
/ // // //
o ///////
/
// / ////
///////
/ //////
///////
// // ///
/ //////
'NJ' ///////
The quarterly exposure limit is 3000 mrem in accident situations.
a PAGE 1 OF 23 l l EMERGENCY PLAN IMPLEMENTING l N PRAIRIE ISLAND NUCLEAR PROCEDURES (h
l l l GENERATING PLANT I l NORTHERN STATES POWER COMPANY Number: F3-13 Rev: 3 l l History Copy l l j, , o, a ! Retention Time: Lifetime l b TITLE: l l ction l l l Approved By: Sup[t.'KadProt 4 -
l OFFSITE DOSE CALCULATION l 1 o J [l)n /, 1 I l Plant Managet l , l l OC#: ?_ M -52 l l l I I I I l 1.0 PURPOSK l 1 1' l The projected offsite dose rates at various distances from the plant l l SHALL be calculated during an emergency involving a release or a l l potential release to the environment.
l l 1 l The offsite dose projections will be used by plant management and l l offsite officials as a basis for determining protective actions such l l as sheltering or evacuation when the Protective Action Guides (PAG's) l l are exceeded. l l l l This Instruction SHALL describe the method to obtain the required b
O l information and to calculate the offsite dose projections at various l l
l distances from the plant, by two methods: l 1 l l a. computer method, and l l l l b. hand calculation method when the computer l l is unavailable. -
l l 1 l 2.0 APPLICABILITY l l l l This Instruction SHALL apply to the Radiation Protection Group and all l l Radiological Smergency Coordinators. l l l l 3.0 REQUIRED EQUIPMENT l l l l (1) Radiation Monitoring System l l (2) Meteorological Equipment l l (3) Apple Computer System l l l l 4.0 PRECAUTIONS l l l l (1) Use care when reading log scales on the radiation monitors and l l their calibration curves. l l 1 l (2) Use care when working with exponents. l I I U'N l l l l l l IBM
F3-13 Rev. 3 Page 2
(_,) (3) Use a calculator whenever possible and check all calculations.
(4) Inform the Emergency Director of all projected dose rate calculations.
5.0 PROCEDURE 5.1 Computer Method 5.1.1 When it has been determined that a release to the atmosphere has occurred or there is a potential for a release to the atmosphere, the Emergency Director SHALL designate the Radiation Protection Group responsible for projecting offsite dose rates.
5.1.2 Determine the exact flow path and the release rate from the plant.
Aux Bldg Special 8000 cfm/ stack Containment Purge 32,250 cfm Containment In-Service Purge 4000 cfm SFP Special 5000 cfm/ stack Steam Dump 4000 cfm Shield Building Vent 200 cfm per train (400 cfm/ stack)
[)
\s '
PORV's SG Safeties 2500 cfm 5500 cfm 5.1.3 Determine the concentration of activity being released from the plant by either of the following methods:
(1) Radiation Monitors: The release concentration may be determined by obtaining the count rate or dose rate from the affected radiation monitor on the
! release path (e.g. R-22, R-50, etc.).
l l
l l l NOTE: Input the Radiation Monitor reading in CPM l
! or mR/hr into the computer. The computer l l l will calculate the release concentration l l l in pCi/cc. l l l l (2) Manual Determination: The activity being released j via the steam headers, the air ejectors, or the shield building vent may be determined manually, in accordance with procedure, F3-20, " Manual Determin-ation of Radioactive Release Concentrations". .
I O
v IBM
~
F3-13 Rev. 3 Page 3 Th k.)m (3) Sample Analysis: Sample analysis on the release path may be used to determine the isotopes for noble gas, iodines, and particulates being released.
I I l NOTE: See Figure 1 fcr complete list of I l Isotopes contained in the dose l l assessment computer library. l l l 5.1.4 Obtain the meteorological data from the following locations:
(a) New Met Tower - (Prints out 15 minute average data on met tower printer in TSC)
(b) Alternate meteorological sources as delineated in Figure 4.
5.1.5 Perform all offsite dose rate calculations on the Apple computer in the Technical Support Center, as follows:
(1) Insert or insure that the floppy dish labeled " Met
-) Twr Dose Cales" is inserted into the Apple disk drive. Close the disk door.
1 I l NOTE: The computer is normally on. The l l monitor may or may not be on. If the l l computer is on and displaying met l l tower information in the monitor, l l proceed to St.ep'(4). l l l (2) Insure that the computer and the monitor are plugged into 115 VAC.
(3) Turn the monitor "0N" (on-off pushbutton) and the Apple computer "0N" (rocker switch on rear, near AC cord receptacle).
O V
IBM
l l
F3-13 Rev. 3 Page 4 (4) The computer may be in one of two modes, as denoted by the character to the left of the cursor. If there are no characters on the screen, or the cursor is not present, push " RESET". The two characters are:
a) Asterisk (*): This indicates that the computer is in machine language mode.
Then: push: " RESET" type: "RUN DOSE" push: " RETURN" b) Square Bracket (}): This indicates that the computer has been loaded with basic language.
Then: type: "RUN DOSE" push: " RETURN" (5) If a printout of the offsite dose projections is I
required, verify the printer is plugged in and turned on.
(6) The computer will now display a series of questions i on the monitor screen (with the required input format, such as sph, pCi/cc, CFM, etc.) which the operator must answer by inputting the data into the computer. The end of each response is signalled by pressing " RETURN".
l NOTE: (a) The program is divided into l l several logical sections. At the l l conclusion of each section, the l
! operator is asked to examine his l l l responses and will be allowed to l l l make corrections. l l l l (b) Responses in any other units or l .
l form will yield invalid results. l
- l In most instances, no checking is l l l done for input format other than l
, l a check for numeric information l I when requested. l l l l l (c) If a response is in alphanumeric l l notation or contains illegal l l l characters, the computer will l l print the word "RE-ENTER" and l l allow the data to be re-inputed. l l
l l
IBM l
,_-,m_-,_,-w,. ..-,_-_.---,_._,,,.m .--,.,mr, . , _ _ .- , .
,--,,we-r. ,- ---rw ,-4,,,-,,,.,_----f,,-w- , , _ ,, ~ . . , _ , --,.,e ,=,,,ww o w , , , _ , _ - , . _ . . _
F3-13 Pev. 3 Page 5 s_,- (7) The computer will ask for the isotopes and the concentration of each isotope being released.
Enter the isotope in a format similar to the example for each of the isotopes identified.
After the isotope is entered, a check is made to insure that data for that isotope has been previously stored. Upon completion of the isotope list, type "END".
l' l l NOTE: If the dose projections are based on l l either a potential release from con- l l tainment or on radiation monitor l l readings, all dose projections will l l be based on Xe-133 equivaient. l
- l. l (8) The computer will ask for iodine isotopes released and the amount of iodine (pCi) which has and is expected to be released. Enter all iodine isotopes and their respective activities. At the completion of the iodine list, type "END".
(' -) l l NOTE: If N0 iodine analysis is avaliable, l
l l type "NO" for the first iodine isotope.l l See Figure 1 for complete list of l l iodine isotopes. l l l (9) The computer will ask for the particulates released and the activity which has or is expected to be released. Enter all particulate isotopes and their respective activities. At the completion of the particulate list, type "END".
I l l NOTE: If no particulate analysis is avail- l l able, type "N0" for the first l l particulate isotope. See Figure 1 for l l complete list of particulate isotopes. l l l IBM l _ _,- , - _ - - . - . - . ~ . - - - - -
1 F3-13 Rev. 3 Page 6 (10) The computer will compute and display projected plume centerline offsite whole body dose rates (mR/hr) due to noble gas releases at various distances from plant site (0.5 miles to 10 miles).
The computer will also compute and display plume centerline doses (mR) to the thyroid when iodine is released, and a lung dose (mR) and whole body dose (mR) due to inhalation of particulates when particulates are being released. If particulates or iodines have been released, the dose assessment computer will calculate and display the projected ground deposition (dpm/100 sq. cm.) due to iodines or particulates.
(11) To repeat the projected offsite dose calculations, type "RUN DOSE" and " RETURN".
5.1.6 Report all results to the Emergency Director on a periodic basis. Inform the Emergency Director immed-iately of any significant projected offsite dose rates.
5.1.7 Continue to calculate the projected offsite dose rates at approximately 15 minute intervals, as per this Instruction, until the emergency situation is termin-ated or until such time as determined by the Emergency O Director or his designee.
b 5.1.8 The Radiological Emergency Coordinator SHALL notify the offsite officials of all projected offsite dose rates on a periodic basis or when requested.
5.2 Hand Calculation Method 5.2.1 Centerline Whole Body Dose Rates, D C
1 I l NOTE: Use Dose Rate Calculation Worksheets, I l Figure 2 and 3. l I I (1) Obtain the following meteorological data and insert on Figure 2:
(a) Wind Speed (mph @ Ground Elevation)
(b) Wind Direction (Degrees @ Ground Elevation)
(c) Stability Class l I I NOTE: Figure 4 lists various sources of I l meteorological data and methods of l p l stability class determination. l b I I IBM
F3-13 Rev. 3 Page 7 O)
\s_ (2) Using Figure 5, determine the values for XU/Q for that Stability Class, at various distances from the plant, beginning at the site boundary (0.5 miles), out to the 10 mile boundary. List xU/Q values on Figure 2.
(3) Determine each release path of gases and assume a release rate (R) of noble gases from the plant or estimate a potential release rate. Use the following known values. Insert those values on the calculation worksheet Attachment, Figure 3:
i (Use one (1) worksheet attachment for each known release path):
Aux Building Special 8,000 cfm per stack Containment Purge 32,250 cfm Containment In-Service Purge 4,000 cfm SFP Special 5,000 cfm Shield Building Vent 200 cfm per train (400 cfm/ stack)
Steam Dump 4,000 cfm PORV's 2,500 cfm SG Safeties 5,500 cfm
() (4) Determine the release concentration of Noble Gases being released from the plant for each release path, using either of the following methods, and insert those values on the appropriate calculation Worksheet Attachment, Figure 3:
(a) Obtain the count rate or dose rate from.the applicable Rad Monitor. Refer to the applicable Calibration Curve to obtain the release concentration in pCi/cc.
(b) If the applicable Rad Monitor is out of service, determine the release concentration in accordance with F3-20, " Manual Determin-ation of Radioactive Release Concentrations".
t (c) If Grab Samples have been obtained and i analyzed for the Release Path, use the l individual Isotopes obtained from the analysis.
j IBM 1 ,
I %
F3-13
- Rev. 3
- Page 8 1
s l l l NOTE: When using the Rad Monitor Reading or l ,
l the Manual Determination Method (F3-20)l I
l to determine the release concentra- l l tions, the release concentration result l l l is Xe-133 equivalent. l l l 1
(5) For each Release Path, complete the calculation
. Worksheet Attachment Figure 3, as follows:
- (a) Multiply each Isotope release concentration, 1
C. (pCi/cc) times its respective Whole Body dose factor, K g.
j (b) Sum the K gg C column.
(c) Multiply the IK.C. 1 1 obtained in (b) i times the Released Rate (R) in CFM.
i i (d) Transfer RIK gg C to the Dose Rate Calculation 4
Worksheet, Figure 2.
I
\
f (6) When all the results from each Worksheet Attachment i has been transferred to Figure 2, total the results toobtained{[R g{(KC)]. gg (7) Calculate the Centerline Whole Body Dose Rate as follows (use Calculation Worksheet, Figure 2): j DC mrem /hr = 0.12035 (XU/Q) I[R.
- I(K.C.)]
- U l l l NOTE
- Complete the Dose Rate Calculation for l
- l each distance indicated, from the Plant l l l Site (0.5 miles) out to the 10 mile. l 1 l boundary, or as otherwise directed by l l the REC. l l l l 1
5.2.2 Whole Body Dose Rates Off Centerline (1) To calculate the Whole Body Dose Rate at any point off the Centerline, the Centerline Dose Rate must first be calculated in accordance with 5.2.1.
1
!. IBM
F3-13 Rev. 3 Page 9 (2) Determine the Horizontal Dispercion Coefficient, ay (meters) from Figure 6, at the desired distance 2
downwind from the Plant Site for the given Stability Class.
(3) Determine the crosswind distance, Y (meters),
- where the dose rate is to be determined.
1 l NOTE: 1 Mile = 1.6094 Km l (4) Calculate the dose rate (raRem/hr) off the Centerline, as follows:
2 a Y D =D eXP -1/2 oy C
Where D C
= enterline Dose Rate (mrem /hr) at a given Downwind Distance as determined by Section 5.2.1.
l Y = Croswind Distance off the Center- !
line (meters). >
i ay = Horizontal Dispersion Coefficient at a given Downwind Distance for the particular Stability Class (meters).
from Figure 6.
- 5.2.3 Calculating Thyroid Dose (1) Vnen sample analysis indicates that iodine has been
, released, determine the total amount of iodine released, in pCi.
(2) Using Figure 5, determine a value for XU/Q (m" ) based
~
- on a Downwind Distance and the applicable Stability l Class.
t (3) Obtain the ground level wind speed, U, in mph and convert wind speed to mps as follows:
mph x 0.447 = mps (4) Determine the Thyroid Dose Factors, R., from the following table:
1 Nuclide !"
R.i * *"Ci/m p
l I-131 1.62 E07 I-132 5.87 E05
- I-133 4.39 E06 l I-134 2.50 E04 g I-135 1.36 E06 i IBM '
l
F3-13 Rev. 3 Page 10 O
Q (5) Calculate the Offsite Dose from Iodine (mrem) as follows:
D (mrem) = 3.17x10
-8 /Q pgq f Where: 3.17x10" = conversion factor (year /sec) xU/Q = (m~ determined from Figure 5, as a function of Downwind Distance and Stability Class U = Wind speed mps [mps = mph x 0.447]
Rg
= Thyroid Dose fgetor (mrem /yr/pCi/m ]
q = quantity of Iodine released (pCi) f 5.2.4 Off-Site Ground Deposition of Radioiodine and Particulates (1) Determine mean wind direction. This determines
, applicable sectors.
(2) Determine distance in kilometers, from the plant site to point of interest. This is the R value. (Convert miles to km if necessary using 1.609 km/ mile factor.)
i (3) Determine deposition rate, D, from Figure 7 for R chosen.
(4) Determine fraction of release, F, from Figure 8 for R chosen.
(5) Determine amount of iodine and/or particulates released, Q, in microcuries.
(6) Find deposition of iodine and/or particulates in (dpm/100 sq. cm) at R using the following equations:
f (a) Iodine: d = 28.26[DFQ/R]
f .
(b) Particulates: d = 76.52[DFQ/R]
where d - is the deposition of radioiodine or particulates onto ground at location R (in km) from the release point. The deposition occurs in the mean wind direction downwind from the release point. The value of R determines the sector location.
Equations (a) & (b) assume that the desposition in p a given sector is uniform across the sector at a t given R value. Units are dpm/100 sq. cm.
t IBM i
F3-13 Rev. 3 Page 11
( D - is the acceptgble value of relative deposition rate (meters ) as a function of distance from the source. The relative deposition rate is the deposition rate per unit downwind distance (Ci/sec per meter) divided by the source strength (Ci/sec), and represents a plume depletion factor due to dry deposition of elemental radioiodines and other particulates. This factor is obtained from Figure 7.
F - is the acceptable value of the fraction of the release transported into the sector in question as located by the value for R and determined according to the distribution of wind direction.
This factor is obtained from Figure 8.
Q - is the total radioiodine (elemental and non-elemental) or particulates released per event in units of microcuries.
R - is the distance in kilometers downwind from the release point where the deposition value is to be determined.
28.26 - is a factor which (1) accounts for only elemental radioiodine, (2) converts 22.5 degrees to radians,
(/
s-m T
(3) allows R to be entgred in equatiog (a) as km, and (4) converts pCi/m to dpm/100 cm .
56.52 - is a factor which (1) accounts for particulates, (2) converts 22.5 degrees to radians, (3) allows Rtobeentereginequation(g)askm,and(4) converts pCi/m to dpm/100 cm .
5.3 Total Population Exposure Estimate (1) Obtain the Dose (D) to the Offsite Population.
(2) If sheltering is the recommended protective action in effect, obtain the' sheltering factor (SF). See F3-8.
(3) From the Population Distribution Map, obtain the number of persons in the Plume Pathway (P).
(4) Calculate the Total Population Exposure (TPE) as follows:
TPE = D x SF x P where TPE = Total Population Exposure D = Dose to the Offsite Population (Rem)
SF = Sheltering Factor Oe P = Population in Plume Pathway IBM i
L
l
]
F3-13 Rev. 3 Page 12 _
FIGURE 1 '
LIST OF ISOTOPES IN LIBRARY i
a
', Noble Gases Iodine Particulates Kr-83m I-131 Te-132 Kr-85m I-132 Cs-134 ;
Kr-90 Xe-131m i Xe-133m
- Xe-133 -
i Xe-135m Xe-135 Xe-137 Xe-138
, Ar-41 4
k i
4 e
l-t i
i r i
f l
a
- IBM 1
F3-13 FIGURE 2 Rev. 3 Page 13
/7, DOSE RATE CALCULATION WORKSilEET
'%.Y DATE TIME MET DATA: WIND SPEED U = MPH WIND DIRECTION DEG. SECTOR AT C STABILITY CLASS
. DISTANCE X U/Q DISTANCE xU/Q 0.5 5.0 I i 1.0 6.0 !
1.5 7.0 ! !
2.0 8.0 '
3.0 9.0 l 4.0 l 10.0 l R1EK C (TRANSFER RESULTS FROM WORKSHEET ATTACiDIENTS) 1 ii 4 1i -
( ) R KC 1
= R .K C = ,
t R [i i 3 "6 ii TOTAL I[RgKC] =
CALCULATE DOSE RATE AS FOLLOWS:
D = 0.12035 IX " - E[R 1E(4.C )]
C 1 U i i
(
C =
0.12035 ( )
( )
l l DISTANCE D (mR/hr) DISTANCE D (mR/hr)
C C 0.5 5.0 1.0 6.0 1
1.5 7.0 l 2.0 8.0 3.0 9.0
%,) 4.0 10.0 l CALCULATIONS:
l COMPLETED BY
I F3-13 Rev. 3 Page 14
, FIGURE 3 ;
CALCULATION WORKSliEET ATTACliMENT T
RELEASE PATil ,
RELEASE RATE R= CFM i l K. I C. I I I I l I I 3
l l W110LE BODY l l I K.C' l ISOTOPE l DOSE FACTOR l pCi/cc l l l 1 l I i Kr-83m l 7.56E-2 l l l 1 1 I I Kr-85m 1.17E3 l l l 1 l Kr-85 l 1.61El l l 1 1 l l l Kr-87 I 5.92E3 l l 1 l l l l Kr-88 l 1.47E4 l l l Kr-89 1.66E4 l Kr-90 l 1.56E4 l )
F
'@? l.-
1 I I i 10).5 i
} Xe-131m I 9.15El -
I Xe-133m l 2.51E2 l A A I I I l l l Xe-133 l 2.94E2 l l l l l l l l l Xe-135m l 3.12E3 I l l l l l l l l Xe-135 l 1.81E3 l l l l l l l l l Xe-137 l 1.42E3 I l l 1 I l I l l Xe-138 l 8.83E3 l l l l l l I I l Ar-41 [ 8.84E3 l l l l 1
= l l
{K Cgg i r RIK.C.
iii
=
IBM
F3-13 Rev. 3 Page 15 FIGURE 4 ALTERNATE METEOROLOGICAL DATA & STABILITY CLASS DETERMINATION (1) New Met Tower (Micromet System)
AT ('C) 60m - 10m a0 Stability Class
( .95 >23 A
.95 to -0.85 18 - 23 B
.84 to .75 13 - 18 C
.74 to .25 8 - 13 D
.24 to +.75 4-8 E
+.76 to +2.0 (4 F
>2.0 G (2) Lock & Dam #3 Ground levet wind speed and wind direction is available (24-hours / day, 365 days /y. ear) from the Lockmaster at Lock and Dam #3.
Lockmaster - Phone # ' DELETED 1 I l NOTE: Stability Class is available from the National Weather l
(/
\- l Service. See Item # 4 below. l I I (3) Stability Class is available from the Minneapolis National Weather Service and can be obtained by either of the following methods:
(a) Weather Service Information Printer (See Attachment B)
(b) Telephone - gQ (4) GO Computer - If the Met Tower printers in the TSC are not functioning, the PI meteorological information may be retrieved j from the GO Computer. See Attachment A for operating l instructions.
IBM
F3-13 Rev. 3 Page 16 FIGURE 5 TYPICAL VALUES FOR XU/Q AS A FUNCTION OF ATHOSPHERIC STABILITY CLASS AND DOWNWIND DISTANCE DOWNWIND .XU/Q (m-2)
DISTANCE AS PER STABILITY CLASS (Miles) A B C D E F 0.5 6.8E-6 2.6E-5 8E-5 2.2E-4 4E-4 9E-4 1.0 1.2E-6 5.4E-6 2.1E-5 6.8E-5 1.3E-4 2.8E-4 '
1.5 9.0E-7 2.9E-6 1.1E-5 4.0E-5 8.0E-5 1.7E-4 2.0 6.2E-7 1.5E-6 5.4E-6 2.2E-5 4.5E-5 9.5E-5 3.0 4.5E-7 7.5E-7 2.6E-6 1.2E-5 2.6E-5 5.5E-5 i 4.0 3.6E-7 4.9E-7 1.7E-6 8E-6 1.8E-5 3.8E-5
( 5.0 2.9E-7 3.8E-7 1.1E-6 5.9E-6 1.2E-5 2.9E-5 6.0 2.5E-7 3.1E-7 7.9E-7 4.2E-6 9.8E-6 2.2E-5 7.0 2.3E-7 2.8E-7 5.8E-7 3.3E-6 7.7E-6 1.9E-5 8.0 1.9E-7 2.5E-7 4.5E-7 2.8E-6 6.2E-6 .1.7E-5 9.0 1.7E-7 2.3E-7 3.6Ea7 2.2E-6 5.2E-6 1.4E-5 10.0 1.6E-7 2.1E-7 3.2E-7 1.9E-6 4.5E-6 1.2E-5 O
IBM
F3-13 Rev. 3
/
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F3-13 Rev. 3 Page 20 ATTACHMENT A NET DATA RETRIEVAL
- 1. Turn on TI printer. The printer "0N LINE" lite and the modem "DTR" lite should be lit.
- 2. Select TI printer speed:
(a) Press "CMD" button and type "C".
(b) Printer should respond with either:
CONFIG: 13; 23; 32 (indicates 300 baud)
CONFIG: 13; 25; 32 (indicates 1200 band)
(c) To change Printer speed, type either 23 (for 300 baud) or 25 (for 1200 baud); Press " RETURN". Then press " ENTER". ,
- 3. Set modem to same speed as printer, with modem center switch:
(a) Down = 300 baud (b) Up = 1200 baud
- 4. Modem right switch must be in V0 ice to dial.
O 5. Using plant ext. 331, dial 8-6850. When tone is heard, switch right toggle switch up to Data and then back to center position.
Hang up phone.
l l l NOTE: No need to wait for tone change. l l l
- 6. Type a " RETURN", observe printout.
- 7. Printer will print username. Type PRIS.SEDAR and press " RETURN".
- 8. Printer will print password. Type PRIS.SEDAR and press " RETURN". l (Password will not print.)
- 9. System will display current time in JULIAN.
l EXAMPLE: JULIAN Time of 81 3381042 44 is l l 1981 l l 338 day l l 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> l l 42 minute l l 44 second l O
IBM
F3-13 Rev. 3 Page 21 ATTACHMENT A (Cont'd)
MET DATA RETRIEVAL
- 10. Printer will now give system prompts for beginning time for report, and ending time for report. These are entered with NO SPACES in Julian time. Enter beginning time and ending time in Julian and press i, RETURN".
l NOTE: l 1 l l Report is formatted by your input to these prompts. Therefore, l 1 I l 81DDDHHMM] l l to will give finest detail - 15 minutes samples l l 81DDDHHMM] l l l l 81DDDHH] l l to gives hourly summaries l l 81DDDHH] l l l l 81DDD] l l to gives daily summary l l 81DDD]
l Data is normally available for a few days - could be as much l l as two weeks stored. l l l
- 11. The General Office Computer will always call the Met Tower to retrieve latest data. This will take time with several meaningless printouts; depending upon the type of report, the time delay could be several minutes.
, 12. The requested report will be printed.
- 13. When completed, the modem will disconnect when the computer hangs up or whenever the printer is turned off.
- 14. Leave modem right switch in the center position.
i
! IBM i
. . e F3-13 Rev. 3 Page 22 I -
ATTACl& TENT B WEATiiER INFORMATION SERVICE
- 1. Turn on TI printer. The printer "0N LINE" lite and the modem "DTR" lite should be lit.
- 2. Select TI printer speed
- (a) Press "CMD" button and type "C".
(b) Printer should respond with either:
CONFIG: 13; 23; 32 (indicates 300 baud) 4 CONFIG: 13; 25; 32 (indicates 1200 baud)
(c) To change printer speed, type either 23 (for 300 baud) or 25 (for 1200 baud); Press " RETURN". Then press " ENTER".
- 3. Set modem to same speed as printer, with modem center switch:
(a) Down = 300 baud l (b) Up = 1200 baud
- 4. Modem right switch must be in Voice to dial.
) -
s 5. Using plant ext. 331, dial 8-9-341-2459. When tone is heard, switch right toggle switch up to Data and then back to center position.
Hang up phone.
I I l NOTE: No need to wait for tone change. l l l
- 6. Press return twice.
Printer will print: Telenet t
Terminal =
i r
- 7. Type: DI Press return j Printer will print: @
- 8. Type: C 617133 Press return Printer will print: 617 133B connected l 9. Press return I Printer will print: Please Log In
- 10. Type: LOGIN NSP Press return Printer will print: PASSWORD:
v/ XXXXXX i IBM l
l
F3-13 Rev. 3 Page 23
'O ATTACHMENT B (Con't)
WEATHER INFORMATION SERVICE
- 11. Type: POWER Press return (Note: Password will not print)
Printer will print: Logged into weather service
+
l l
l NOTE: The + sign will always indicate that the l l computer is waiting for instructions. l l
1
- 12. Type command for desired weather information, as follows:
(a) Wind speed & direction map Type: MWQ A Press return ;
(b) Weather-sky cover Type: MWQ X Press return i
() (c) Precipitatioa last 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Type: MWQ (
Press return (d) Last hour radar map showing intensity of 3 precipitation Type: RADMAP MSP Press return (e) Forecast Type: ZONES MN
- Press return (f) PASQUILL Stability Index Type
- -PASQ MSP Press return 4
(g) SPECIAL LOG P.I. Type: -REDW Press return
- 13. When finished:
Type: LOGOUT
- Press return L i Printer will print: Logged Out from WSI
Disconnected
- 14. Turn Printer Off
(h s s/ 15. Leave modem right switch in the center position.
I IBM
7 e
i PAGE 1 OF18 l l EMERGENCY PLAN IMPLEMENTING l Cj 3 l l
PRAIRIE ISLAND NUCLEAR GENERATING PLANT PROCEDURES l l
l NORTHERN STATES POWER COMPANY Number: F3-14.1 Rev:2 l l History Copy l l [ / n , , Retention Time: Lifetime l l l TITLE:
l Supt.' Rad Pro e tion l l l Approved By: I /' l ONSITE RADIOLOGICAL l C[_)):!bth l l MONITORING l l Playt Mana(erp l l l OC#: T- M- yiX
~
l l l l l l 1 l 1.0 PURPOSE l l l l The purpose of this instruction is to delineate the responsibil- l l ities of the onsite Radiation Survey Team in radiation exposure l l control (inplant and out of plant), contamination control, l l respiratory protection control, and food and water control. l l l l The Radiation Survey Team will be available onsite within 30 l l minutes after the emergency has been declared to augment the shift l l Radiation Protection Specialist. The Radiological Emergency l l Coordinator (REC) will direct the onsite response actions of the l q l Radiation Survey Team. Additional Radiation Protection personnel l
) l will assume onsite responsibilities when they are relieved of l l offsite sampling responsibilities by sister plant personnel. l l l l l l 2.0 APPLICABILITY l l l l This instruction is applicable to all Prairie Island Radiation l l Protection Group members. l l l 1 l l 3.0 PRECAUTIONS l l
l 3.1 The Radiological Emergency Coordinator shall control all li l l l radiological exposures (internal and external) occuring onsite l l as per F3-12 " EMERGENCY EXPOSURE CONTROL". l l l l 3.2 Radiological conditions may be such that a secondary access l l control point is necessary. See procedure F3-21, l l " ESTABLISHMENT OF A SECONDARY ACCESS CONTROL POINT". l l l l l l 4.0 PROCEDURE l l l l The Emergency Director shall direct the Radiological Emergency l l Coordinator (REC) to assume responsibility for onsite radiological l l controls in the following areas: l l l l l IBM a
a 2 -
F3-14.1 Rev. 2 Page 2 0 4.1 Radiation Exposure Control 4.1.1 Upon activation of the onsite emergency organization, the onsite Radiation Survey Team shall perform radiation surveys (Beta and Gamma) in various onsite areas of the plant (in plant and off plant) on a routine basis or a job specific basis ensuring that no unexpected radiation levels are encountered by emergency response personnel.
I I l NOTE: Calculated radiation levels following a design l l basis accident are contained in F3-25, " REENTRY", l l l 4.1.2 The Radiation Survey Team shall perform Beta-Gamma radiation surveys (in plant and out c,f plant) as follows:
(1) Energize instrument, observing proper precautions for cold weather (Figure 2) when conducting out of plant surveys.
O}
'%s l
l NOTE: All instruments should be response l
l l checked prior to use. l l l (2) Allow the instruments to stabilize and complete any specific instructions for the-instrument.
(3) Turn the instrument to the highest range and scale down until a reading is observed.
(4) Open the probe window and scan the area for a Beta-Gamma reading. This is the " Window Open" reading.
(5) Close the probe window and scan the area for a i
Gamma reading. This is the " Window Closed" reading.
(6) Calculate the Gamma and Beta dose reading as l follows:
Gamma (mrem /hr) = Window Closed Reading Beta (mrem /hr) = CF times (window open reading-window closed reading)
O Where CF = Beta correction factor for instrument.
If none is available, use five (5).
IBM b
_ _ _ __ .,= .-_
F3-14.1 Rev. 2 Page 3 O
l l l NOTE: The Beta dose rate is reported in l l mrem /hr assuming a quality factor of l l 1. l l l 4.1.3 Record survey results (Beta-Gamma) on survey maps and report results to REC. Use Figures 3 through Figures 11 or use the normal in plant survey maps.
I I l NOTES: (1) p radiation levels indicate high levell l contamination or airborne activity. l l l l (2) S readings greater than 100 mrem /hr l l requires SCBA. l l l l (3) Use a PIC-6A or R0-2A while perform- l l ing surveys onsite but out-of-plant. l l A S plus y reading indicates the l l plume has been encountered. Ay l l reading with no indicates the plume l l is elevated or displaced. DO NOT l
()/
x.- l linger in the plume longer than l l necessary. l l l 4.1.4 The REC shall review all survey results and advise the Emergency Director of significant radiation levels.
4.1.5 Survey results shall be reviewed prior to any entry into any areas of high radiation levels.
4.1.6 The REC shall control all radiation exposure in accordance with F3-12 " EMERGENCY EXPOSURE CONTROL".
4.1.7 The Radiation Survey Team should post all areas of high radiation and implement any further controls restricting entry to the area.
4.1.8 The Radiation Survey Team shall specify the dosimetry necessary for entry into high radiation areas of the plant and write RWP's for entry.
4.2 Contamination Control 4.2.1 Upon activation, the onsite Radiation Survey Team shall perform Beta-Gamma Contamination Surveys in various IBM
A *
, F3-14.1 Rev. 2 Page 4 q
V areas of the plant on a routine basis or a job specific basis ensuring that contamination is controlled within the limits of Figure 1.
4.2.2 The Radiation Survey Team shall perform surveys for loose surface Contamination (Beta-Gamma) via smear samples on the suspected area. The smear samples shall be counted using the various equipment available.
4.2.3 Survey results shall be recorded on floor plans and routed to the REC for review. l 4.2.4 The Radiation Survey Team should post all areas l exceeding the limits of Figure 1 and implement any controls required to restrict entry into the area.
4.2.5 Survey results shall be reviewed prior to any entry into an area of high contamination. l 4.2.6 The Secondary Access Control Point RPS should specify l all protective clothing requirements for entry into highly contaminated areas of the plant.
e 4.2.7 The Secondary Access Control Point RPS shall ensure
( that all personnel are properly monitored prior to departure into an uncontrolled area of the plant. See F3-19 " PERSONNEL AND EQUIPMENT MONITORING AND DECONTAMINATION" for requirements.
4.2.8 All equipment and vehicles exiting the controlled area
- of the plant shall be surveyed by the Radiation Survey Team for loose and fixed surface contamination as determined by the REC. See F3-19, " PERSONNEL AND EQUIPMENT MONITORING AND DECONTAMINATION" for requirements.
4.2.9 Any necessary decontamination shall be performed in accordance with F3-19, " PERSONNEL AND EQUIPMENT MONITORING AND DECONTAMINATION".
I 4.3 Respiratory Protection Program During an emergency situation, it may become necessary to expose personnel to airborne activity levels in excess of l established limits resulting in some internal exposure.
Communication difficulties, large numbers of people and l possible large areas of high airborne activity may negate the l use of respiratory protection equipment. In addition,
, personnel may be exposed to airborne activity from an l h J unexpected source. The Radiological Emergency Coordinator l
t IBM
F3-14.1 Rev. 2 Page 5 shall institute a whole body count / bioassay program for all personnel suspected as having been exposed to airborne activity significantly above MPC concentration. This may or may not be coordinated with a Thyro-Block distribution program.
i 4.3.1 The Radiation Survey Team should collect routine and/or l Job specific airborne samples (particulate, iodine, and gas) to determine respiratory equipment requirements.
4.3.2 The airborne samples should be collected and analyzed in accordance with F3-15, " RESPONSIBILITIES OF SURVEY l TEAMS DURING AIRBORNE RELEASES", if the count room and I
mobile trailer are not available.
I l l NOTE: In case of station blackout, the OSC locker l l contains a battery powered air sampler. l l 1 4.3.3 The secondary Access Control Point RPS should specify the respiratory protection requirements for entry into l any area of high airborne activity.
/
v l l l NOTE: It may be such that a respirator would l l cause additional work time resulting in l l a higher whole body dose. It may be l l beneficial not to wear a respirator, therebyl l accepting a higher internal dose with a ' l l lower whole body dose. In coordination l l with this, Thyroid-blocking agents could l j l be used as a dose reduction method. l l l 4.3.4 The REC shall implement a whole body counting program for personnel who have or may have exceeded the normal MPC hour limits (40 in a week or 260 in a quarter).
I I l NOTE: If the Prairie Island whole body counter l l is not available, the REC shall make l l
l arrangements for a mobile whole body l l counter or direct the use of Monticello l 4
l facilities. l l l 4.3.5 i O' The REC should evaluate whole body count results and determine if any further evaluation is necessary such as urinalysis and/or fecal analysis.
IBM
t 4
F3-14.1 I
I Rev. 2 Page 6 4.3.6 All whole body count results shall be filed for future l
, evaluation in cases where other followup actions are
, required.
l l l NOTE: Whole body count results exceeding 25% body l l burden require the calculation of the re- I j
I sultant whole body exposure which shall be !
l added to the individual's exposure history. l I i 4.4 Food and Water Control The Radiological Emergency Coordinator shall control .the use of all food and water onsite, following a plant evacuation when large areas of the plant site could possibly be contaminated to significant levels.
4.4.1 Food
]
(1) Following a plant evacuation, the Radiation Survey j Team should restrict entry into food storage and
~~g preparation areas of the plant. These areas
() (lunchrooms, records room, etc.) should be posted as such.
(2) The Radiation Survey Team should perform
, contamination surveys in these areas and ensure that the areas are' free of detectable contamination, defined as:
(a) < 100 dpm/100cm Beta-Gamma (3) Additionally, some random items of food should be analyzed for low level contamination using the 1 j Gamma Spectrometer system.
(4) The REC should review the survey results and take the following appropriate action: .
(a) release the food for use
-(b) dispose of the foods as radioactive waste (c) restrict entry into food storage areas until
- the area has been deconned to acceptable levels i
l -)
l IBM
. . _ . _ . _ ____ .~. _
l
- F3-14.1 Rev. 2 Page 7 4.4.2 Water (1) The REC should control the use of all water supplies used for human consumption.
(2) The Radiation Survey Team should periodically sample and analyze the potable water system for contamination. Sample results shall be reported to the REC.
(3) In addition, the Radiation Survey Team should control the use of all drinking utensils and coffee pots.
(4) The REC should evaluate the plant conditions and sample results and release the potable water system for unrestricted use when it is deemed safe.
IBM
- _ . _ . - . . . - - . -- , - . - - - - . . . . . _ . - - - _ . - _ _ - - - . .. . - . . . - . _ ~ . . . - --. .._..
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F3-14.1
- Rev. 2 l Page 8 FIGURE 1 ,
- CONTAMINATION LIMITS i
~
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l 4
EMERGENCY GUIDELINES
- ITEMS DIRECTLY ASSOCIATED ITEMS NOT DIRECTLY NORMAL BODY WITH BODY ASSOCIATED WITH !
BODY
- REMOVABLE j 2 dpm/100cm .
-y 100 100 1100 2200 a 10 10 110 220 '
t l FIXED 100 cpm 100 cpm 0.75 mr/hr 1.5 mr/hr
- NOTES
- (1) " Items Not Directly with the Body" may' include floors, roads, vehicles, truck, or trailer beds, or tires, etc.
(2) " Items Directly associated with the Body" may include desks, chairs, ;
high traffic area floors, equipment being handled by hands. '
i
+
. _ . _ . _ _ _ . _ _ _ n ------. n -
I
~ F3-14.1 Rev. 2 Page 9 l
l FIGURE 2
- COLD WEATHER OPERATION ,
(1) If outside temperature is greater than 32 F (O C), instrument use is unlimited.
(2) If outside temperature is between 32 F (O C) and 0 F (-18 C), any i instrument should be used for no more than 5 minutes.
(3) If outside temperature is between 0 F (-18 C) and -20 F (-28 C), any instrument should be used for no more than 2 minutes.
l (4) If the outside temperature is below -20 F (-28 C), no instrument i should be used unless special batteries (alkaline or Ni-CD) are in instruments and this would increase the temperature range to -40 F I (-40 C). The instrument should only be used for very short times d
(less than 30 seconds).
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i ! PAGE 1 OF _26 l l EMERGENCY PLAN IMPLEMENTING l
/^) l PRAIRIE ISLAND NUCLEAR PROCEDURES l .
( ,/ l GENERATING PLANT". .
. l l-NORTHERN STATES POWER COMPANY' Number: F3-15 Rev:5- l l History Copy l l A , /) Retention Time: Li'fe time _li ;
. TITLE:
l upC. a Protect' ion l ,
~ 1.
.l Approved By: l d/,_ RESPONSIBILITIES OF THE -1 l
l
(- lf)f[ 8 'of Plant Man'hgerf l
l l
RADIATION SURVEY TEAMS DURING A RADIOACTIVE AIRBORNE RELEASE l
l l
l OC#: X.J,6- Y L l l l .) l l . . l l 1.0 PURPOSE ;.
l l <
x l l The purpose of t'ais instruction is to describe the responsibilities of l l the Radiation Surveyt Teams during'an airborne radioactive release to l l the offsite environs. ,
l l l l 2.0
SUMMARY
\ ,
l l l l Three radiation survey teams exist, each consisting of a minimum of four l l Radiation Protection Specialists. One (1), Rad Protection Specialist is l l required per team (minimum) to perform the required offsite surveys; l l allotherteammembersshouldreporttotheRjdiologicalEmergency l g
) l Coordinator (REC) onsite, for further assignrgnts (e.g. , onsite l l sampling, monitoring, analysis, exposure control, etc.).1 l l l l In the event of an offsite airborne release, the Radiological Emergency l l Coordinator (REC) may request support for offsite surveys from the l l Monticello, Radiation Protection Group. When the Monticello Radiation l l Protection ' Group arrives at the Prairie Island NearySite EOF, they will l l accept the responsibility for offsite surveys 'from the Prairie Island l l Survey Teams. Thjs allows the Prairie Island personnel, who have l l completed the initial offsite surveys to augment Radiation Survey Team l
- 3 performing onsite surveys. All offsite su'rveys will then continue
~
l l l under the di'rection of the Emergency Manager at the Prairie Island l l Near-Site EOF. g l l 1
_l 3.0 APPLICABILITY l-1 is l l This Instruction SHALL apply to all members of the Prairie Island l l Radiation Protection Group. 2 l
s N' l ' '
l l 4.0 PRECAUTIONS E D'SPECIAL CONSIDERATIONS ( { l, l i. <
Is l (1) Each team shall obtain information pertaining to the magnitude and -l*
l the direction of the release, either from the Control Room or the l l Radiological Emergency Coordinator, i. l I I
,f3, e l y
, . 3, s 1 O l t
/
l i l l N y ( i l IBM 1 ,
3
. 2 w
, F3-15 Rev. 5 Page 2 rT (2) Radiation Survey Teams SHALL observe the respiratory protection
' ,j i N requirements and the field dose rate precautions as stated in Attachment F.
(3) Report airborne activity sample results in round numbers, (i.e.,
microcuries per cc with no decimal places).
(4) Report all radiation levels in whole number millirem per hour, e
(i.e. , three Rem per hour shall be reported as three thousand
. millirem per hour).
(5) Report all numbers individually (e.g., one hundged thirty-five SHALL be reported as one-three-five and 5 x 10 SHALL be reported as five times ten to the minus three).
(6) Preface each communication with the title or name of the receiving party and your title or name. For example: " Prairie Island TSC; Radiation Survey Team #1. . ."
After the communication is completed, request the receiving party to repeat the message, if numerical data was relayed.
j End message transmission with an appropriate termination phrase.
For example: " Radiation Survey Team #1, out".
(7) The normal means of transportation for survey teams during any
[')
's /
emergency is NSP vehicles. , Extreme environmental conditions (blocked roads, snow, bridges out, etc.) may preclude the use of these vehicles. The following alternate transportation is available:
e l l l NOTE: This does not prohibit the use of personal vehicles l l in cases where NSP vehicles are not available in l l sufficient numbers. l
, I I N
(a) Power Boats - Sheriff's Department, NSP environmental monitoring team, Red Wing Police.
- (b) Four Wheel Drive Vehicle - at Prairie Island
(
, \
(c) Amphibious Duck - at Prairie Island (d) Helicopter - available during suitable weather conditions
(. from charter services in Minneapolis and
) ).js\,
St. Paul. Arrangemenps to be made via the I
corporateEmergency0[gahizationattheEOF.
- s
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. ,i IBM
F3-15 Rav. 5 l Page 3 j g (8) The normal communication channel for the survey teams is the
(~
s- / portable radio stored in the lockers. The normal telephone system will serve as a backup communication system. Telephone numbers in the TSC for the Radiological Emergency Coordinator are:
.. *\
Q G W v.C)
(9) Periodically check dosimeter readings and report results to the Radiological Emtrgency Coordinator (REC).
5.0 EjUIPMENT AND PERSONNEL REQUIRED 5.1 Team Members TeanLI Team II Team III Marotz Pfeffer DeLong Hopl: ins Ludwig Nichols Lemnerman .loachim Maurer Der).eth licLeran Payton Propst !arly Lundquist Secrist l' +
+ +
'~
l l l NOTE: The Radiation Protection Coordinators ! HALL ~ l l report to the OSC and assume onsite responsi- l l bilities as directed by the Radiological l l Emergency Coordinator (REC). l l l 5.2 Team Equinment Required 5.2.1 Team #1 (1) Vehicle (NSP or personal)
(2) Offsite sample kit (Attachment A) 5.2.2 Team #2 l
(1) Vehicle (NSP or personal)
(2) Offsite sample kit (Attachment A) 5.2.3 Team #3 (1) Normal counting room equipment, if available (2) Back count room facility (3) All available onsite radiation protection equipment IBM
r 0 .,* .
F3-15 Rav. 5 Page 4 6.0 PROCEDURE 6.1 Team #1 6.1.1 All members of Radiation Survey Team #1 SHALL assemble at the appropriate location as follows, unless directed by the Emergency Director or the Radiological Emergency Coordinator (REC):
(1) During normal working hours, all Team #1 members SHALL assemble in the Operational Support Center (OSC).
(2) During off-normal working hours, all Team #1 members SHALL assemble at the NSP Red Wing Service Center.
l l l NOTE: During off hours, the Shift Emergency Commun- l l icator (SEC) SHALL ensure that NSP personnel l l are contacted to unlock the NSP Red Wing l l District Service Center. If personnel are not l l available at the service center when the l l Radiation Survey teams arrive, attempt to call l l one of the following: l l l
@ l ,
, pEL.ETED I
I ~ ~
1 l l l l 6.1.2 Obtain the necessary information from the Control Room Operator or TSC personnel regarding the type and amount of release, wind direction, etc.
6.1.3 Designate two (2) members of Team #1 (if available) to perform offsite surveys. The other members of Team #1 SHALL report to the OSC and assume onsite responsibilities, as directed by the REC.
l I l NOTE: Any available NSP personnel may be designated l l as the driver for a single team member. l l l 6.1.4 Obtain the necessary equipment (Attachment A) from the Emergency Lockers, as follows:
(1) During normal work hours, proceed to the Construction Office Building Emergency Locker and obtain the Field Team Survey Kits; (2) During off-normal work hours, obtain the Field Team Survey Kits f rom the NSP Red Wing Service Center Emergency Locker.
IBM
F3-15 Rev. 5 Page 5 f 's i
6.1.5 Obtain an NSP vehicle or personal vehicle.
(J 6.1.6 Obtain TLD's and dosimeters from the emergency locker.
I l l NOTE: Survey Team Members should keep their l l personal TLD's if departing from the plant l l site. l l l 6.1.7 Zero and record dosimeter readings on locker signout sheet.
6.1.8 Operationally test the portable radios and response check all meters with source, prior to departing.
6.1.9 Proceed to perform offsite surveys depending on the wind direction and time of emergency:
(1) If the wind is from the north or west, proceed on the Emergency Route from the plant, or the NSP Red Wing Service Center, through Red Wing, to Diamond Bluff, to Prescott, to Hastings, and back to the plant as shown on Figure 1.
(2) If the wind is from the south or east, proceed i
(x } on the Emergency Route from the plant, or the NSP Red Wing Service Center, to Hastings, to Prescott, to Diamond Bluff, to Red Wing, and back to the plant, as shown on Figure 1.
6.1.10 When departing the plant site or NSP Red Wing Service Center, conduct a search for the plume, in accordance with Attachment B.
6.1.11 Observe the respiratory protection and the field dose rate precautions, as stated in Attachment F, at all times while conducting a plume search, taking dose rate measurements or taking air samples.
6.1.12 At areas where the plume is encountered, or at each designated survey point, perform beta and gamma surveys in accordance with the applicable procedure, Attachment C, as directed by the Radiological Emergency Coordinator.
4 6.1.13 Identify survey locations using either:
(1) Predesignated survey location numbers, as shown on the applicable Radiological Sampling
{%
s_,) Points map; or IBM 1
F3-15 Rev. 5 Page 6 (2) Known landmarks, road intersections, grid
( coordinates, etc. to identify locations the plume is encountered and/or sampling is done i when not at a predesignated survey point.
I l l NOTE: Map coordinates and/or locations should l l also be identified as-per the mobile l l sampling locations list. l l l 6.1.14 Report results to the Radiological Emergency Coordinator via the portable radio or telephone.
6.1.15 After completing the initial emergency route (Figure 1), report to the REC for further instructions.
6.1.16 When directed by the REC, assist Team #2 in conducting a plume search and air sampling.
6.1.17 Obtain airborne samples (particulate, iodine and gas), at locations requested by the REC, as per Attachments D & E.
6.1.18 Report results to the REC via portable radio or f
(~__)
%J telephone.
6.2 Team #2 6.2.1 All members of Radiation Survey Team #2 SHALL assemble at the appropriate location as follows, unless directed by the Emergency Director or the Radiological Emergency Coordinator (REC):
l (1) During normal working hours, all Team #2 members SHALL assemble in the Operational Support Center (OSC).
(2) During off-normal working hours, all Team #2 members SHALL assemble at the NSP Red Wing Service l Center.
%./
IBM
F3-15 Rev. 5 Page 7 V' -
1 I I NOTE: During off hours, the Shift Emergency Commun- l l icator (SEC) SHALL ensure that NSP personnel l I are contacted to unlock the NSP Red Wing l l District Service Center. If personnel are not l l available at the service center when the i I Radiation Survey teams arrive, attempt to call l l one of the following: I i 1 1 1 I pE.LM 50 l I I I I I .
I 6.2.2 Obtain the necessary information from the Control Room Operator or TSC personnel regarding the type and amount of release, wind direction, etc.
6.2.3 Designate two (2) members of Team #2 (if available) to perform offsite surveys. The other members of Team #2 SHALL report to the OSC and assume onsite responsibilities, as directed by the REC.
I NOTE: Any available NSP personnel may be designated I as the driver for a single team member. l l l 6.2.4 Obtain the necessary equipment (Attachment A) from the Emergency Lockers, as follows:
(1) During normal work hours, proceed to the Construction Office Building Emergency Locker and*obtain the Field Team Survey Kits; (2) During off-normal work hours, obtain the Field Team Survey Kits from the NSP Red Wing Service Center Emergency Locker.
6.2.5 Obtain an NSP vehicle or personal vehicle.
6.2.6 Obtain TLD's and dosimeters from the emergency locker.
l , l I NOTE: Survey Team Members should keep their l l Personal TLD's if departing from the plant l l site. l I I 6.2.7 Zero and record dosimeter readings on locker signout sheet.
IBM
F3-15 Rev. 5 Page 8 6.2.8 Operationally test the portable radios and response s check all meters with source, prior to departing.
6.2.9 Proceed to the affected sector per instructions from the REC.
6.2.10 When departing the plant site or Red Wing Service Center, conduct a search for the plume, in accordance with Attachment B.
6.2.11 Observe the respiratory protection and the field dose rate precautions as stated in Attachment F, at all times while conducting a plume search, taking dose rate measurements or taking air samples.
6.2.12 At areas where the plume is encountered, or at each designated survey point, perform beta and gamma surveys in accordance with the applicable procedure, Attachment C, as directed by the Radiological Emergency Coordinator.
6.2.13 Collect airborne sample, (particulate, iodine and gas), in accordance with applicable procedures, Attachment D and E, when requested by the Radiological Emergency Coordinator.
6.2.14 Report results to the REC via the portable radio or telephone. Identify survey locations using either:
(1) Predesignated survey location numbers, as shown on the applicable Radiological Sampling Points map; or (2) Known landmarks, road intersections, grid coordinates, etc. to identify locations the plume is encountered and/or sampling is done when not at a predesignated survey point.
I I i l NOTE: Map coordinates and/or locations should l j l also be identified as per the mobile l l l sampling locations list. l l l 1 l
6.2.15 Accurately document all survey data on the Emergency Fesults Log, Figure 2. Enter the date, time, name of surveyor, instrument serial number and model for each survey data.
6.2.16 Proceed to the next survey location as per
-] instructions from the REC and take requested surveys and samples in accordance with applicable procedures.
IBM l
t
F3-15 Rev. 5 Page 9 6.2.17 Frequently check personal dosimeters and request
(" relief if cumulative exposure approaches administrative limits.
6.2.18 When directed by the REC, deliver samples to designated location for pickup by member of Team
- 3.
6.3 Team #3 6.3.1 Report to the Operational Support Center when the emergency is declared, unless directed by the Emergency Director or the Radiological Emergency Coordinator (REC).
6.3.2 Perform all operations requested by the Emergency Director or REC.
6.3.3 control radiation exposure onsite (internal and external).
6.3.4 One member of Team #3 shall proceed to the backup count room facility at the EOF and perform required analysis of offsite survey team samples and/or onsite samples as required. Store all samples for future analysis.
6.3.5 One member should be designated as a runner to pick up all samples at the designated location from Team #1 and O Team #2 and deliver samples to the EOF count room for
[V analysis.
6.3.6 Perform onsite surveys as requested by the Emergency Director and/or REC per F3-14, "Onsite Radiological Monitoring".
6.3.7 Perform required personnel monitoring at the emergency operating centers and supervise any necessary personnel decontamination per F3-19, " Personnel and Equipment Monitoring and Decontamination".
6.3.8 Obtain and process samples ,from the reactor coolant system, containment air, stack release, etc., as requested by the REC per F3-23, " Emergency Sampling" and F3-20, " Manual Determination of Release Rates".
~
{ 6.3.9 Reporta}lresultstotheRECviaavailablecommunication system.
IBM
.- F3-15 Rrv. 5 Page 10 O ATTACHMENT A OFFSITE SURVEY TEAM EQUIPMENT PACKAGE
- 1. Each offsite survey team SHALL be equipped with a kit of the following:
QUANTITY REQUIRED ITEM J
1 Dose rate instrument RO-2 or equivalent ,
1 Count rate instrument RM-14 or equivalent 2 2" GM pancake probes 1 Battery powered air sampler 2 Personnel self-reading dosimeters (low range)
- 2 Personnel self-reading dosimeters (high range) 4 2 TLD's (if individuals have a normally assigned TLD, they should wear those assigned) 1 (package) Plastic Sample Bags (approx. 100) 1 (box) Gargage bags (approx. 10) 1 (package) Paper towels or handiwipes 2 (roll) Masking tape 20 Silver zeolite cartridges 2 GMR-I cannisters
/~'i 2 Full face respirators (m,) 2 Gas sample chambers 1 Filter assembly (gas sampler) 1 Suction bulb (gas sampler) 1 (package) Filter paper (gas sampler) 10 One liter poly bottles 1 Box air sampler filter papers ~
1 (package) Survey sample labels (approx. 30) 1 Portable radio 1 Portable radio antenna 1 Flashlight 4 D-Cell batteries 1 Compass 1 Clipboard 2 Pens 1 Pad of paper (8-1/2" x 11" minimum size) 1 Road map of State of Minnesota 1 Road map of State of Wisconsin 1 Umbrella 1 Watch or clock 1 Calculator 2 (pair) Foul weather (rain) gear 1 Line (approx. 100 feet) 1 Weighted poly bottle holder 1 Procedures binder (see //2)
I IBM
F3-15 Rev. 5 Page 11 s.
ATTACHMENT A (Continued)
I 0FFSITE SURVEY TEAM EQUIPMENT PACKAGE
- 2. The Procedures Binder SHALL contain:
1 package of the following maps:
(a) Prairie Island Radiological Sampling Points Map and related list of location descriptions (b) Monticello Radiological Sampling Points Map and related list of location descriptions 1 Copy of EPIP 1.1.10, "Offsite Surveys" 10 Emergency Sample Results Forms 1 Copy of EPIP 1.1.8, " Communications Equipment and Information" 1 Copy of F3-15, " Responsibilities of the Radiation Survey Teams
. During a Radioactive Airborne Release" 1 Copy of F3-16, " Responsibilities of the Radiation Survey Teams During a Radioactive Liquid Release" lI 6
I t
.s M
1 IBM
F3-15 Rev. 5 Page 12 ATTACHMENT B PLUME SEARCH TECHNIQUE I. Precautions (1) Meter SHALL have been source response checked prior to use.
(2) Check batteries by switching to BATTERY CHECK position. Replace if necessary.
(3) Observe the cold weather operation restrictions (ATTACHMENT G).
(4) All surveys SHALL be taken at approximately one meter from ground level unless specifically directed by the REC.
(5) During inclement weather, the instrument may be placed against the inside vehicle window or on the dash.
II. Procedure (1) When departing the plant site or NSP Red Wing Service Center:
a) Energize the instrument observing proper precautions for cold weather (ATTACHMENT G).
b) Allow meter to stabilize and zero meter if necessary.
(2) Periodically hold the instrument out the vehicle window, while in transit, and watch the instrument for a meter deflection.
! l l NOTE: During inclement weather, the instrument may be placed l l against the inside vehicle window or on the dash. l l_ l (3) When a meter deflection is observed, stop the vehicle and perform a beta and gamma survey of the area as follows:
a) Hold the instrument at approximately 1 meter (3 feet) from ground level and scan around the area for maximum meter deflection b) Open the probe window for beta gamma reading c) Record the " window open" reading (Figure 2) d) Close the probe window IBM
F3-15 Rev. 5 Page 13 ATTACHMENT B (Continued)
PLUME SEARCH TECHNIQUE Record the " window closed" reading (Figure 2) e)
f) Determine the corrected beta reading (4) Record the readings and calculate the beta and gamma dose (Figure-2) l I l NOTE: A beta plus gamma reading will indicate that the l l plume has been encountered. A gamma reading with l l zero beta reading indicates the plume is elevated l l or displaced. A gamma reading and a beta reading l l indicates that the plume is at ground elevation. l l l
- /~
(5) Report the results to the Radiological Emergency Coordinator as follows:
a) Location:
l b) millirem /hr gamma c) millirem /hr True Beta l
l NOTE: If not at a predesignated survey point, use l l known landmarks, road intersections, grid l l coordinates, etc., to identify the location. l
! l l.([S) i l IBM l
,- -. - . - - . . - . . . - . . . - . - ~ - - - - -- -- - -
F3-15 Rev. 5 Page 14 ATTACHMENT C O- BETA AND GAMMA SURVEY I. Precautions
, (1) Meter shall have been source response checked prior to use.
(2) Check batteries by switching to BATTERY CHECK position.
Replace if necessary.
(3) Observe the cold weather operation restrictions (ATTACH-MENT G).
(4) All surveys shall be taken at approximately one meter from ground level unless specifically directed by the REC.
II. Procedure (1) Energize the instrument.
(2) Allow meter to stabilize and zero meter if necessary.
(3) Switch to the hightst scale and scale down until a
- onscale reading is obtained.
[u)h (4) Hold the instrument approximately one meter from ground level and scan area for maximum reading.
(a) Open probe window for beta gamma reading and record on Figure 2 as " Window Open" reading.
(b) Close the probe window for gamma reading and record on Figure 2 as " Window Closed" reading.
(5) Determine the beta and gamma dose rates as follows:
GAMMA (mrem /hr) = " Window Closed" reading BETA (mrem /hr) = " Window Open" reading minus " Window Closed" reading times CF or (w/o - ,
w/c) CF Where 1. CF = beta correction factor for meter or assume 5.
- 2. Beta dose rate reported in mrem /hr assuming a quality factor of 1.
(6) Record results on Figure 2.
(7) Report results to REC.
' IBM
l F3-15 I Rev. 5 i Page 15 l ATTACHMENT D PARTICULATE AND IODINE SAMPLING I. PRECAUTIONS
- 1. The air sampler shall be placed in an area that will ensure a representative sample. DO NOT place the sam-pler on the ground or on contaminated surfaces.
- 2. Particulate filters and silver zeolite absorbers must be installed and removed carefully to prevent cross-contamination from foreign objects.
- 3. The sample should be a standard 25 cubic foot sample.
Sample collection time may be affected if the activity is too high.
- 4. All samples SHALL be labeled properly with the required information and saved for further analysis.
I
I. PROCEDURE
- 1. Carefully install a particulate filter and silver zeo-lite absorber into the cartridge / filter paper holder.
l l l NOTE: Install the silver zeolite absorber as follows: l l l l INLET l l l l HiQ l l AgZ Flow l l N l
l Outlet l l l
- 2. Connect the air sampler (CF-18V) to the vehicle power supply as follows:
(a) Connect to 12 Volt bactery terminals. Insure there is a good connection.
i l l l NOTE: Engine should be running to main- l l tain a steady battery voltage. l .
I I b>
~~-
i IBM l
F3-15 Rev. 5 Page 16 n
v ATTACHMENT D (Continued) t (b) Set the TIMER toggle switch to either the TIME .
or the MANUAL POSITION.
l NOTE: (1) If in the TIME. position, set l l the TIMER DIAL to selected l l time. When the timer times l-l out, the sample pump will l l automatically stop. l l l l (2) If in the MANUAL position, thel l sample pump must be stopped' l l manually when a designated l l sampling time has elapsed. l (c) Set the FLOW TOGGLE switch to the VARIABLE pos-ition. The air sampler will now start. Record start time on Figure 2.
l NOTE: (1) DO NOT use HIGH switch position l j tion (causes high flow and l l motor damage). l l (2) _If the sampler begins to run .l.
j- I hot, (flow decreasing contin- l l l uously) stop the air sampler l I- to prevent damage to the unit.
l l I
(d) Adjust the flow, using the flow adjustment knob l to 2 CFM.
[ (e) When the sample collection time is complete, l l stop the air sampler. Record time on Figure 2.
l l NOTE: If the TIMER was in the TIME pos- l I l ition, the sampler will auto stop l l when the timer times out. l f
(f) If the TIMER was in the MANUAL position, the air sampler must be stopped manually by placing the FLOW toggle switch to the OFF position when the selected sample time has elapsed.
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F3-15 Rev. 5 Page 17 ATTACIDfENT D ks _, (Continued)
- 3. Average the initial sample flow rate and the final flow rate.
Calculate the total sample volume and record results on Sample Results Log, Figure 2. ,
- 4. Carefully remove the particulate filter and silver zeolite absorber and place in a plastic sample bag.
- 5. Place a sample label on the sample and ensure that all in-formation is completed.
- 6. Make gross activity estimates in the field by the following methods:
(a) Particulate Activity - count the particulate filter using an RM-14 (or equivalent) with a 2" GM pancake probe.
Estimate the gross particulate activity using the following formula:
Activity (pCi/cc)=(Background Corrected Count Rate)(4.5x10~7 pCi/dpm)
(Probe Efficiency) (Sample Volume, cc's) (CF) 4
}
l NOTE: (1) Probe efficiency =0.1 for RM-14 with l l a 2" GM pancake probe. l 1 I l (2) Place the 2" GM pancake probe about l l 1/8" from the filter, with filter l l outside poly bag. l l l
- l (3) CF= Correction factor for sample. l l CF is .3 for 4 inch paper l l counted with a 2 inch probe. l l l 1
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. . l F3-15 Rev. 5 Page 18 (b) Iodine Activity - count the silver zeolite' absorber using an RM-14 or equivalent. Calculate sample act-ivity using the following formula:
Iodine Activity (pCi/cc)= (pCi's on absorber)
(Sample Volume in cc's) l NOTE: (1) pCi's on absorber = activity on absorber l 1
l determined from Fig-l l ure 3 using the cor-l l rected count rate. l
- l l l (2) Place 2" GM pancake probe directly on l l absorber, with absorber inside poly bag.l l 1 l (3) If backgrour.J exceeds 1000 cpm, notify l l the REC and proceed to an area of lower l l background, (1000 cpm for counting, if- l l so instructed by the REC. l l
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- 7. Record the air sample results on the Sample Results Log (Figure 2) and report the results to the Radiological Emergency Coordinator.
- 8. Save all samples for future analysis.
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I- F3-15 Rev. 5 Page 19 I
(/ ATTACHMENT E GASEOUS ACTIVITY SAMPLING I. Precautions
- 1. If hands are contaminated, handle chamber with cotton liners.
II. Procedure
- 1. Remove S.S. Gas chamber, suction bulb and filter ass-embly.
- 2. Install new filter in filter assembly.
- 3. Assemble kit so air passes through filter, gas chamber, then suction bulb.
- 4. Squeeze suction bulb 10 times to obtain representative sample.
- 5. Shut petcocks on gas chamber.
('h s- /
- 6. Using an RM-14 or equivalent and a 2 inch GM pancake probe obtain a count rate of the_ chamber volume by placing the probe over the mylar window. Log the result as " gross CPM".
- 7. Obtain a second chamber labeled " Background". Do not open the stop cocks of the background chamber. Deter-mine a background count rate by placing the 2 inch GM pancake probe over the mylar window. Log the results as " Background CPM".
- 9. Using Figure 4, apply the " Net CPM" obtained to determine i
the gross gas activity in pCi/cc Xe-133 equivalent.
- 10. Record the air sample results on the Emergency Sample Results Log, (Figure 2) and report the results to the
- Radiological Emergency Coordinator using the portable radio .
- 11. Save the sample for future analysis.
IBM
F3-15 Rev. 5 Page 20 ATTACHMENT F SURVEY TEAM RADIATION PROTECTION GUIDELINES I. Respiratory Protection (1) Radiation Survey Team members should don respirators with GMR cannisters if the following conditions occur:
(a) A General Emergency is declared and the affected sectors have been evacuated; and (b) Measured dose rates are more than 100 mR/hr .
(2) Respiratory equipment may be removed if the following is indicated:
(a) field measurement of gross iodine activity indicates less than 1E-7 pCi/ce; or (b) the Radiological Emergency Coordinator indicates that no significant iodine is or has been released from the plant.
II. Plume Dose Rates
() (1) Survey Teams should not linger in areas greater than 100mR/hr (2) Survey Teams should not proceed to areas greater than 1 R/hr unless directed by the Radiological Emergency Coordinator.
(3) Survey Teams SHALL NOT proceed to areas exceeding 10 R/hr.
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F3-15 Rev. 5
- . Page 21 4
ATTACIIMENT G COLD WEATHER OPERATION 4
l 1. If outside temperature is greater than 32 F (O C), instrument use is unlimited.
- 2. If outside temperature is between 32 F (0 C) and 0 F (-18 C),
no instrument should be used for more than 5 minutes, a
- 3. 0 If outside temperature is between 0 F (-18 C) and -20 F (-28 C),
no instrument should be used for more than 2 minutes.
- 4. If the outside temperature is below -20 F (-28 C), no instrument should be used unless special batteries (alkaline or Ni-CD) are in the instrument and this would increase the temperature range ji to -40 F (-40 C). The instrument should only be used for very short times (less than 30 seconds).
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EMERGENCY SAMPLE RESULTS LOG DATE .
TIME I SAMPLE RESULTS DOSE RATE RESULTS - MREM /hr Survey Sample INSTRUMENT 3 tert Sample Sample WINDOW WINDOW TRUE BETA Point Flow Volume Model Gross BKGD Net pCi/cc Type
A A a /A h.
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- 1. Formulas listed on back l
- 2. Remarks:
- Sample type includes: Particulate, Gascous, Radioiodine, Liquid, Area Dose Rate
! N5' TECHNICIAN SIGNATURE O$'
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. F3-15 Rev. 5 Page 24 FIGURE 2 (CON'T) 1 Formulas:
- 1. Gross Counts Per Minute - Background Counts Per Minute = Net Counts Per Minute l
l CPM (gross) - CPM (bkgd) = CPM (net) j 2. Cubic feet x 2.83 x 10' = cubic centimeters Ft x 2.83E4 = cc's
- 3. pCi/cc(particulate) = [ CPM (net)] [4.5E-7 pCi/dpm]
[ inst, eff.][ sample vol.(cf)][2.83E4][CF]
2 NOTE: See notes 2 & 4 below.
4
- 4. TRUE BETA = (WINDOW OPEN READING - WINDOW CLOSED READING)
X Beta Correction factor - (see Note 1)
NOTES:
h
- 1. Assume 5.0 if correction factor is unknown.
- 2. Instrument efficiency depends on probes. If using 2" GM
, pancake probe, ASSUME 10% (0.10) efficiency; if using GM
, tube probe, ASSUME 2% (0.02) efficiency.
- 3. List factors affecting reading; height of probe, ' reading 1 inside vehicle, etc.
- 4. CF (Correction factor for air samples) = 0.3 for a 4 inch filter size paper counted with a 2 2 inch GM pancake
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t, , FIGURE 3 GROSS IODINE CURVE USING RM-14 WITH 2" GM F3-15 PANCAKE PROBE WITH SILVER ZEOLITE ABSORBER Page 25 1 Rev. 5 '
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.: PAGE 1 OF 17 l l EMERGENCY PLAN IMPLEMENTING l q l PRAIRIE ISLAND NUCLEAR PROCEDURES l Q
l GENERATING PLANT _
l l NORTHERN STATES POWER COMPANY Number: F3-16 Rev: 3 l l , History Copy l l -a , A , Retention Time: Lifetime l l /I [ l TITLE:
l Supt.. ad Prot l _
_l l Approved By:
l t
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,l (/ ,'ction l
l RESPONSIBILITIES OF THE RADIATION SURVEY TEAMS DURING l
l~
l Plag t Manager l A RADIOACTIVE LIQUID RELEASE l l OC#: )f -D l l l l l 1 l l 1.0 PURPOSE l
l l l The purpose of this instruction is to describe the l
l responsibilities of the Radiation Survey Teams during _l-l a liquid radioactive release to the offsite environment.
l l l l l l 2.0
SUMMARY
l l l l l Three radiation survey teams exist, each consisting 'of -l l a minimum of four Radiation Protection Specialists. l l One Radiation Protection Specialist is required per l
\
l team (minimum) to perform the required offsite sampling; d l all other personnel should report to the Radiological l
l l Emergency Coordinator (REC) onsite, for further assign- l l ments and/or instructions for onsite sampling, monitor-
~ 'l l l ing, analysis, exposure control, etc. l 1 I l In the event of an offsite liquid release, the Radio- l_
l logical En:ergency Coordinator may request support for ~l-l offsite sampling from the Monticello Radiation Protection l l Group. When the Monticello Radiation Protection Group l
- l arrives at the Prairie Island Near-Site EOF, they will l 3
l accept the responsibility for offsite sampling from the l l Prairie Island Survey Teams. This allows the Prairie l l l Island personnel, who have completed the initial'offsite l l l -sampling to augment the onsite Radiation Survey Team. All l l offsite monitoring will continue under the direction of the l
- l Emergency manager at the Prairie Island Near-Site EOF. l l l l
' l l l 3.0 APPLICABILITY l l l l This Instruction SHALL apply to all-members of the Prairie l
+
l Island Radiation Protection Group. l l l f I I A l 4.0 PRECAUTIONS AND SPECIAL CONSIDERATIONS l V I l (1) Each team shall obtain information pertaining to the I
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F3 Rev. 3 Page 2
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-magnitude'of the liquid release, either from the Control Room Operator or the Radiological Emergency Coordinator (REC).
(2) Report all liquid sample results to the REC in round numbers, (i.e., with.no decimal places) microcuries per milliliter.
(3) Report all numbers individually (e.g. one hundred thirty,jiveshall.bereported_asone-three-fiveand 5 x 10 shall be reported as five times ten to the minus three).
(4) Preface each communication with the title or name of the receiving party and then your. title or name. For example: " Prairie Island TSC; Radiation Survey Team
, #1...".
After the communication is complete, request the receiving party to repeat the message, if numerical data-was relayed.
End message transmission with an appropriate termi-nation phrase. For example: " Radiation Survey Team
- 1, out."
(5) The normal means of transporation for survey teams during any emergency is NSP vehicles. Extreme environmental ~
h conditions (blocked roads, snow, bridges out, etc.)
may preclude the use of these vehicles. The following alternate transportation is available.
l NOTE: This does not prohibit the use of per- l l sonal vehicles in cases where NSP l l vehicles are not available in suffici- l l cient numbers. l-1 I (a) Power Boats - Sheriff's Department, NSP environmental monitoring team, Red Wing Police (b) Four Wheel Drive Vehicle - at Prairie Island (c) . Amphibious Duck - at Prairie Island (d) Helicopter - Available during suitable weather conditions from charter services in Minneapolis and St. Paul.
Arrangements to be made via the Corporate Emergency organization at the EOF.
O IBM.
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F3-16 Rev. 3 Paga 3 7
_-g 4.0 PRECAUTIONS AND SPECIAL CONSIDERATIONS (Con't) t ,!
's./ c (6) The normal means of communication for the survey teams is the portable radios stored in the lockers.
The normal telephone system will serve as a backup communication system. Telephone numbers in the TSC for the Radiological Emergency Corrdinator (REC).are:
DELETED 5.0 EQUIPMENT AND PERSONNEL REQUIRED $
5.) Team Members Team 1 Team 11 Team I__I 1
Marotz Pfeffer DeLong Hopkins Ludwig Secrist
Lemmerman Joachim Payton Derleth McLeran Maurer Propst Early Lundquist Nichols
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l NOTE: Rad Protection Coordinators shall assume on- l l site responsibilities as directed by the l l Radiological Emergency Coordinator (REC). !
l j' 5.2. Team Equipment Required l 5.2.1 Team #1 i (1) Two vehicles (NSP or personal) l (2) Offsite sample kit (Attachment A) j 5.2.2 Team #2 l
(1) Two vehicles (NSP or personal) l <(2) Offsite sample kit (Attachment A) 1 5.2.3 Team #3 l
'(1) Normal counting room equipment, if avail-l able l -
(2) Back count room facility (3) All available onsite radiation protection i equipment t
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i F3-16 R;v. 3 Page 4 4
7
- 6.0 Procedure Lj.
6.1 Team #1
, 6.1.1 All members of Radiation Survey Team #1 SHALL assemble at the appropriate location as follows, unless directed by the Emergency Director or the Radiological Emergency Coordinator (REC):
(1) During normal working hours, all Team #1 members shall assemble in the Operational Support Center (OSC).
(2) During off-normal working hours, all Team #1 members shall assemble at the NSP Red Wing Service Center.
I i l NOTE: During off hours, the Shift l l Emergency Communicator (SEC) l l shall ensure that NSP person- l l al are contacted to talock l l the NSP Red Wing Service Cen- l l ter. If personnel are not l l available at the service centerl l when the Radiation Survey Team l
('
\/
l members arrive, attempt to call l l one of the following: l l l' l 1 l pEL ETN l 1 I I I 6.1.2 Obtain the necessary information from the Control Room Operator or TSC personnel re-garding the type and amount of release, etc.
6.1.3 Designate two (2) members of Team #1 (if available) to perform offsite sampling.
The other members of Team #1 T4"I report to the OSC and assume onsite c , <bilities as directed by the Radiological t an gency Coordinator.
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IBM
F3-16 Rev. 3
, , Page 5 4
4 O i l NOTE: Any available NSP personnel mayl i
j' l be designated as the driver l l for a single team member. l l l 6.1.4 Obtain a vehicle, and a second vehicle (if t
necessary) for transporting samples back to the EOF count room for analysis.
ll 6.1.5 Obtain the necessary equipment (Attachment A) from the NSP Red Wing District Service Center
! Emergency Locker.
! 6.1.6 Operationally test the portable radios and i response check all meters with source, prior i j to departing from the NSP Red Wing Service 2
Center.
6.1.7 Proceed to the Eisenhower Bridge and obtain a one liter sample from middle of the Minne-sota channel, and then a one liter sample from the middle of the Wisconsin channel, in accordance with Attachment B. Obtain' liquid samples at thirty minute intervals or as directed by the REC.
l l l NOTE: (1) If the river is frozen and unable l l to sample the river; contact the Ra- l l diological Emergency Coordinator for l l further instructions. l I I l (2) Traf fic control assistance on the l l Eisenhower Bridge should be obtained l l l from the Red Wing Police, if neces- l l
l l sary. l l l l 6.1.8 Document all survey data on the Emergency Results Log, Figure 1.
6.1.9 Report all results to the Radiological Emergency Coordinator via the portable radio or telephone.
6.1.10 Label bottles correctly for further analysis and storage.
6.1.11 One team member shall continue the sampling schequie while the other member transports I -
the samples to the location designated by REC for pick up and analysis by Team v3. Additional ,
bottles may also he obtained at this time.
IBM
F3-16 Rev. 3
. Page 6 y 6.1.12 Continue sampling until directed by the Radio-1 ) logical Emergency Coordinator.
v 6.2 Team #2 6.2.1 All members of Radiation Survey Team #2 SHALL assemble at the appropriate location as follows, unless directed the Emergency Director or the Radiological Emergency Coordinator (REC):
(1) During normal working hours, all Team #2 members shall assemble in the Operational Support Center (OSC).
(2) During off-normal working hours, all Team #2 members shall assemble at the Construction Office Building.
6.2.2 Obtain the necessary information from the Control Roam Operator or TSC personnel regarding the type and amount of release, etc.
6.2.3 Designate two (2) members of Team #2 (if
(~') available) to perform offsite sampling.
\_ / The other members of Team #2 SHALL report to the OSC and assume onsite responsibilities as directed by the Radiological Emergency Coordinator.
I I l NOTE: Any available NSP personnel may l l be designated as the driver l l for a single team member. l l l 6.2.4 Obtain a vehicle for sampling, and a second vehicle (if necessary) for transport of samples to the E0F count room for analysis.
6.2.5 Obtain the necessary equipment (Attach-ment A) from the Construction Office Building Emergency Locker.
6.2.6 Operationally test the portable radios and response check all meters with source, prior to departing the Construction Office Building Emeygency Locker.
,7
(_,) 6.2.7 Proceed to the outfall canal or point of dis-charge and obtain one liter samples of IBM
- - . - ~ . . _ _ . _ - .
i F3-16
- Rav. 3 Page 7 !
water flowing from the plant in accordance i with Attachment B.
- 6.2.8 Proceed to the intake canal barrier and l obtain a one liter sample on the upstream side of the barrier for background acti-
{ vity determination as per Attachment B.
l 6.2.9 Document all survey data on the Emergency '
l Results Log, Figure 1.
6.2.10 Report all results to Radiological Emer-gency Coordinator via portable radio or i
telephone.
, 6.2.11 Deliver samples to designated location for t j pickup by member of Team #3.
{
6.2.12 Proceed to Lock & Dam #3.
6.2.13 Obtain a one liter sample every 15 minutes j from the roller gate area in accordance with Attachment B. i
, 6.2.14 Document all survey data on the Emergency l Results Log, Figure 1.
() 6.2.15 Report all results to Radiological Emerg-ency Coordinator via portable radio or j telephone.
j 6.2.16 Label all sample bottles properly for storage j and further analysis. ,
l 6.2.17 When directed by REC, one team member shall j deliver semples to the location designated by the
! REC for pickup and analysis by Team #3. Additional i bottles may also be obtained at this time.
- 6.2.18 Additional samples may be required at i the discharge canal. If possible, spare team #3 members can obtain these samples and allow Team #2 to stay at Lock and Dam #3.
6.2.19 Continue sampling until directed by the Radiological Emergency Coordinator.
6.3 Team #3 6.3.1 Report to the Operational Support Center unless y- - directed by the Emergency Director or the Radio-( logical Emergency Coordinator.
t 4
i IBM
F3-16 Rev. 3 Page 8 6.3.2 One member should be designated as a runner 4
O to pickup all samples at the designated loca-tion from Team #1 and Team #2, and deliver samples to the E0F count room for analysis.
6.3.3 One member of Team #3 shall proceed to the backup count room facility at the EOF to perform required analysis of offsite survey
, team samples and/or onsite samples as required.
Store all samples for future analysis.
/
6.3.4 Assist plant operations in minimizing and con-trolling the release.
i 6.3.5 Obtain inplant samples and analyze as required by the Radiological Emergency Coordinator.
6.3.6 All results shall he reported to the Radiological Emergency Coordinator.
6.3.7 Store all sample bottles for further analysis.
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. Page 10
) FIGURE 1 (Con't) l FORMULAS:
4
! 1. Gross Counts Per Minute - Background Counts' Per Minute = Net
! Count Per Minute CPM (gross) - CPM (bkgd) = CPM (net) .
4
! 2. Cubic feet x 2.83 x 10 = cubic centimeters j- Ft3x 2.83E4= cc's 3 3.
pCi/cc (particulate) = [ CPM (net)} [4.5E-7 pCi/dpa) linst. eff.}[ sample vol.(cf)][2.83E4][CF] .
- NOTE
- See notes 2 & 4 below
- 4. TRUE BETA = (WINDOJ OPEN READING - WINDOW CLOSED READING) i X Beta Correction factor - (see Note 1)
NOTES:
i
- 1. Assume 5.0 if correction factor is unknown.
l- D 2. Instrument efficiency depends on probes. If using 2" GM pancake probe, ASSUME 10% (0.10) efficiency; if using GM tube probe, ASSUME 2% (0.02) efficiency.
. 3. List factors affecting reading; heights of probe, reading inside vehicle, etc.
- 4. CF (Correction factor for air samples) = 0.3 for a 4 inch
! filter size paper
- counted with a 2
< inch GM pancake probe.
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. . - . - - - _- _, . ~,-
F3-16 l Rnv. 3
, Page 11 i
i ATTACHMENT A '
j O- OFFSITE SURVEY TEAM EQUIPMENT PACKAGE
) 1. Each offsite survey team shall be equipped with a kit of the following:
QUANTITY REQUIRED ITEM 1 Dose rate instrument R0-2 or equivalent 1 Count rate instrument RM-14 or equivalent 2 2" GM pancake probes 1 Battery powered air sampler
- 2 Personnel self-reading dosimeters (low range) 2 Personnel self-reading dosimeters (high range) 2 TLD's (if individual have a normally assigned TLD they should wear those assigned) i 1 (package) Plastic Sample Bags -(approx.100) 4 1 (box) Garbage bags (approx.10) 1 (package) Paper towels or handiwipes 2 (roll) Masking tape 20 Silver zeolite cartridges 2 GMR-I Cannisters 2 Full Face Respirators 2 Cas Sample Chambers 1 Filter assembly (gas sampler) 1 Suction bulb (gas sampler) 1 (package) Filter paper (gas sampler) 10 One liter poly bottles 1 Box air sampler filter papers 1 (package) Survey sample labels (approx. 30) 1 Portable radio 1 Portable Radio Antenna l 3
1 Flashlight 3 t
4 D-Cell batteries 1 Compass 1 Clipboard 2 Pens 1 Pad of paper (8 1/2" x 11" minimum size) 1 Road map of State of Minnesota 1 Road map of State of Wisconsin 1 Umbrella 1
1 Watch or clock 1 Calculator 2 (pair) Foul weather (rain) gear
. 1 Line (approx. 100 feet) 1 Weighted poly bottle holder 1 Procedures binder (see # 2)
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F3-16 Rev. 3
, Page 12 1
ATTACHMENT A (Cont'd)
OFFSITE SURVEY TEAM EQUIPMENT PACKAGE
- 2. The Procedures Binder shall contain:
1 package of the following maps:
(a) Prairie Island Radiological Sampling Points Map and related list of location discriptions (b) Monticello Radiological Sampling Points Map and related list of location discriptions i
1 Copy of EPIP 1.1.10, "Offsite Surveys" 10 Emergency Sample Resulta Forms 1 Copy of EPIP 1.1.8, " Communications Equipmen,and Information" 1 Copy of F3-15, " Responsibilities of the Radiation Survey Teams During a Radioactive Airborne Release" 1 Copy of F3-16 ," Responsibilities of the Radiation Survey Teams During a Radioactive Liquid Release" i
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s F3-16 Rev. 3 Page 13 ATTACHMENT B Os LIQUID SAMPLING I. Precautions- '
- l. Always collect full one liter bottles.
- 2. For samples at the outfall or point of discharge, assume that the bottle, weighted sampler and rope could possibly become slightly contaminated.
Surgeons gloves should be worn at this sample point and bottles should be placed in a plastic bag.
- 3. Observe cold weather operation instructions (At-tachment C).
- 4. Estimation of gross liquid activity must be made with probe in position shown on applicable calibration curves.
- 5. All meter readings shall be corrected count rates (subtract background).
II. Procedure i 1. Obtain a one liter poly sample bottle of liquid from the desired sample location.
l NOTE: Place poly bottle in sample rig in such l l a position that it will not float out. 'l I
i
- 2. Throw the weighted sampler into an area of water which will supply a representative sample.
- 3. Collect a FULL one liter sample of liquid.
- 4. Withdraw the weighted sampler and cap the sample bottle.
l NOTE: Observe precautions as sampler may be l l contaminated. l l l
- 5. Label bottle properly.
- 6. Estimate the gross liquid activity by the following methods:
i IBM
F3-16 Rev. 3
. Page 14 ATTACHMENT B (Cont'd)
(a) RM-14 or equivalent with 2" GM Pancake position the probe at midpoint on the one liter sample bottle as shown on Figure 2. Using the corrected count rate obtained on the instrument, the estimated gross activity in pCi/ml can be obtained from Figure 2.
(b) E120 with HP-177C Probe -
position the probe (shield open) in a vertical position, centered on the bottle, as shown in Figure
- 3. Using the corrected count rate obtained on the E120, the estimated gross activity in pCi/ml can be obtained from Figure 3.
- 7. Record results on Sample Results Log, Figure 1.
- 8. Report results to the Radiological Emergency Coordinator (REC).
- 9. All samples SHALL be saved for further ana}ysis, using thebackupcounproomfacil{LyattheEOF.'
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F3-16 Rev. 3 Page 15 Figure 2
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F3-16 Rev. 3 Page 17 A_T_T_ ACllML.NT._C C01.0 WFATill:R OPERATION l
- 1. If outside temperature i t. greater than 32"F (0"C), instru-ment use is unlimited.
- 2. If outside temperture is between 32*F (O C) and 0*F (-18 C),
no instrument should be used for more than 5 minutes.
- 3. If outside temperature is between 0 F (-18 C) and -20 F (-28 C),
no instrument should be useil for more than 2 minutes.
- 4. If the outside temperature is below -20 F (-28 C), no inst ru-ment should be used unless special batteries (alkaline or Ni-CD) are in instrument and this would increase the temperature range to -40 F (-40 C), The instrument shoulit only be used for very short times (less than 30 seconils).
v I J t f l l i l T J \ l IBM
PAGE 1 OF 7 l l EMERGENCY PLAN IMPLEMENTING l l PRAIRIE ISLAND NUCLEAR 1 PROCEDURES l l GENERATING PLANT 1 l l NORTHERN STATES POWER COMPANY Number: F3-24 Rev:1 1 1 History Copy l l m , , Retention Time: Lifetime l l r I TITLE: l Sui >t.fRad Prots:cthrn l l l Approved By: ([-[k/is// j/- l RECORD KEEPING DURING l l , t l AN EMERGENCY l l l OC#: Plp)t Mjnap'r l l 0- &-5 h l l 1 I I I I l 1.0 PURPOSE l 1 l l This instruction will delineate the responsibilities for emergency [ l personnel in maintaining a log of events and data affecting their l l specific area of interest. l I I l The recordkeeping is necessary to provide: } I i l (1) Documentation which may be used to reconstruct the emergency for l l critique or analysis. l l 1 l i (2) Checklists to ensure that necessary tasks are completed. ll i hm l (3) Information and data collection during the emergency. I l 1 l l (4) Documentation of required action for legal purposes. ) l I l 2.0 APPLICABILITY ] I - I l This instruction is applicable to all emergency response personnel l l responsible for maintaining the assigned logs. l 1 l l 3.0 PRECAUTIONS l l l l l 3.1 Although recordkeeping & form completion is important, the l l protection of personnel, onsite and offsite is the prime concern. l t l At no time should the completion of logs or forms delay the l l implementation of protective actions. l 1 I l 4.0 PROCEDURE I I I i l 4.1 The Emergency Director shall require the following logs to be l { { maintained by emergency organization personnel during the course 1 ( l of emergency conditions at Prairie Island: l I 1 , l (a) Operations Reactor Log } l (b) Contact Report Log i 1 l (c) Emergency Directors Narrative Log i ! s l (d) Survey Summary Log l l 1 I i i IBM p .,p . m,-7,,--,.,- , , - - . m ._, . , - ,,-n. - , - - . , , -. ,,-w
= - . _
4 4 F3-24 Rev. I 1 . Page 2
# ) 4.2 The Emergency Director (Shift Supervisor until %/ relieved) shall delegate the record-keeping task to qualified individuals in their respective
. emergency operations center. 4.3 All individuals responsible for record keeping should file the reports in a loose leaf binder (with the exception of the Reactor Log). 4.4 All Emergency Logs may subsequently be used to reconstruct events. Entries may be corrected and expanded by comparison with other logs covered in the procedure. 4.5 Various Emergency Log formats are shown in Figures 1 through 3. 4.6 The following is a description of the various logs and the information required to be logged in each. (a) Operations Reactor Log The operations staff will log operational events in the Operations Reactor Log Book, located in the Control Room.
) (b) Contact Report Log Shift Emergency Communicators responsible for contacting personnel and/or organizations shall maintain a Contact Report Log, Figure 1, to log miscellaneous contacts to and from offsite authorities or personnel.
l NOTE: The Emergency Notification Call Lists l i l shall be maintained by the SEC's for i l logging notification to offsite l l emergency organizations. l I I Information required on the Contact Report Log is: i (1) Time of contact & initials of communicator (2) Contact - individ2al/ organization contacted or individual / organization calling. (3) Description - brief description of reason or purpose of contact. O i V IBM
F3-24 Rev. 1 Page 3 A (; (c) Emergency Directors Narrative Log The Emergency Director shall maintain a narrative
- log (See Figure 2) of all significant events occuring during the course of an emergency.
The Emergency Director or the TSC Coordinator may designate an individual to maintain the Emergency Directors Log.
- The individual keeping this log should locate 4
himself near the Emergency Director to facilitate the flow of information in a timely & accurate manner. The following items are examples of events and data that should be recorded in the Emergency Directors Narrative Log: (1) Significant events and the times at which they occur. (2) Reports made to the Emergency Director (plant status, radiological conditions, etc.)
\ (3) Notifications made.
I (4) llazard assessment (operational or radiological) (5) Radiological monitor alarms. (6) Survey results, area and personnel. (7) Evacuations (8) Injuries and medical care 1 (9) Meteorological information f [ (10) Emergency teams dispatched (Survey, first aid, repair, fire, etc.) (11) Reentry efforts (12) Recovery efforts ! (13) Offsite dose projections (14) Any other items deemed necessary or pertinent.
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i N,,) IBM i l
.- ~~ ~ ~ ~ ~ '
F3-24 Rev. 1
+ Page 4 (d) Survey Summary Log
( The Radiological Emergency Coordinator shall maintain a record of all significant events, both onsite and i offsite. 1 The Log shall contain the following: (1) Time - Time that the log entry is made. (2) Description - description of entry, e.g. survey results, met data, etc. (3) INIT - individuals making entries shall initial. 4.7 All records shall be maintained and consolidated (at conclusion of emergency condition) and filed to provide a permanent record of activities and events. These records shall be used to assist the Emergency Director in making decisions and to provide a history of events for final reports. 4.8 All the remaining checklists and forms listed throughout the Emergency Plan Implementing Procedures are unofficial & should be used to provide a source of notes, calculations, N and recommendations of the various groups within the plant emergency organization. All completed forms & checklists should be forwarded to the Emergency Director at the termination of the Emergency condition or when directed by the Emergency Director. l i I IPM l
F3-24 age 5 FIGURE 1 CONTACT REPORT LOG DATE: 1 TIME /INIT. I CONTACT I DESCRIPTION I I I I I I I I I I I I i l l l l l l 1 1 I I I I I I I I I I I I I I I I I I I I I i l I i l I I I i l l l EXAMFILE ONLY l l l '@g l O j_ j gggggggggg37g yg j l l 1 1 I I I I I I I I I I I I I I I I I I I I I I I l l l l l l l I I I I I I l-l l l l l l l l l l l l 1 I I I I I I I I I I I I I I I I I I I I I l l l I I I I I I I i l l IBM
F3-24 Rev. 1 FIGURE 2 EMERGENCY DIRECTORS NARRATIVE LOG DATE: 1 TIME I
SUMMARY
OF EVENT I 1 1 I I I I I I I I I I I I I I I I I I I I I I I I I I I l l l EXAMPITONLY l 0 l l @E l l l l 1 _
@EEEEMND@DH l l
l l l l 1 I I I l l l l l l l l 1 I I I I I I l l l I I l i l l l l l l l l l 1 1 I I I I I I I I I I I I I I I I I I I I I I I I O l l l l l l IBM
. i F3-24 Rev. 1 FIGURE 3 REC LOG DATE: I l TIME I DESCRIPTION l INIT l l l l I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I l l EXAMPif0NLY ! !
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i i gggggg74pfg777 l l i i I I I I I I I I I I I I I I I I I I l l ( I I 1 I I I I I i l I I I I I I I I I I I I I I I I I I I I I I I I I I l l l I I I i l l I I l l O l i l l IBM l 1 _ -
. 5 PAGE 1 OF 9 l l EMERGENCY PLAN IMPLEMENTING l T' y l PRAIRIE ISLAND NUCLEAR PROCEDURES l Q,/ l GENERATING PLANT l l NORTHERN STATES POWER COMPANY l Number: F3-25 Rev: 2 l l l History Copy l
[ d , /) a Retention Time: Lifetime l l [ f/// l TITLE: l l 'Sufs t~ s pd Prototition_ l l Approved By: fj . . REENTRY l l Plant Mana tet' l l l OC#: @ %6- W L
~
l l l l I I I l 1.0 PURPOSE l l l l This procedure provides instructions and guidelines for l l l reentry into areas of the plant or plant site, where radiological and/or environmental conditions are largely ll l l unknown. l l l l l The reentry has been preceded by: ll l l (1) An evacuation of the plant or affected areas l l of the plant, l es l l ( ) l and l v l l l (2) The magnitude and/or nature of the radiological l l hazards in the affected areas are not fully known. l l l I I l 2.0 PRECAUTIONS l l l l Because of the unknown or unexpected conditions within l l the affected areas: l 1 I l (1) Reentry teams shall be composed of a minimum of two individuals. Maximum number shall be determined ll l l l by the volume of work assigned to the reentry l l team. The team members should remain in visual / l l voice contact with each other at all times when l l in the affected areas. l l l l (2) If there is reason to believe that the air within l l the area is toxic or an oxygen deficiency exists, l l the team members shall use self contained breath- l l ing apparatus which then limits the time avail- l l able to the team. In this case, in addition to l l the original team, two or more individuals should l
^ l 1,e assigned outside of the affected area in standby l l , l (fully clothed and wearing SCBA) ready to enter j j l the area if necessary. l 1 I I I IBM
F3-25 Rev. 2 Page 2
, (3) Lifelines should be used in areas containing heavy smoke or in areas where visual contact between team members is impossible or hampered.
(4) The Reentry team shall have radiation dose rate meters when radiological conditions are unknown, or likely to change unexpectedly. Two survey meters should be used when radiation levels are expected to exceed 10 R/hr. (5) One team member shall be designated as the Team Leader. (6) Radiation exposure for the reentry team personnel l shall be controlled by the Radiation Protection Group in accordance with F3-12, " Emergency Exposure Control". (7) All reentrie.; into areas of high radiation areas (10R/hr general area) should be made with two dose rate meters. 3.0 APPLICABILITY This procedure is applicable to all individuals directing, assisting, or assigned to a reentry team. t (j 4.0 ROCEDURE The Emergency Director shall utilize all pertinent data available including area and process radiation monitor-ing channels, survey data, visual observations, observa-tions made by previous reentry teams and any other source of information applicable to determine: (1) Which plant areas are affected. (2) Conditions in affected areas (hazards, radiological, tempe ra ture , etc. ) . (3) Actions which should be taken to reduce the potential hazards to the reentry team prior to or during the reentry. 4.1 The Emergency Director shall assemble the appropriate reentry team (s). l NOTE: If excessive radiation exposures are expected l l or possible, the teams shall be composed of l l volunteers. It is highly recommended that one l l team member should be a Radiation Protection l ('N l Group member or an individual with extensive l
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F3-25 Rev. 2 Page 3 Q 4.2 The Radiological Emergency Coordinator shall ensure that preparation for the reentry teams (s) are complete, i.e., personnel are properly clothed, badged, respiratory protection is issued and exposure is controlled in accord-ance with F3-12 " Emergency Exposure Control". l NOTE: Dose rates for areas of the plant projected l l for the worst case accident assuming major l l safety system failure and significant core l l damage, are shown in Figures I-l thru I-10 l l (for Unit 1 Accident) and II-l thru II-10 l l (for Unit 2 Accident). l 4.3 The reentry team shall carry portable communication gear allowing continuous contact with the Emergency Director and/or Radiological Emergency Coordinator. 4.4 The reentry team shall continuously observe the portable l radiation instrument while approaching the affected area. l NOTE: (1) Two survey meters should be used if radiation l l levels are expected to exceed 10R/hr. l
, I l l (2) If at any time the survey instrument appears l
[h l to malfunction, or go off scale high, I k_./ l immediately return to a safe area and contact l l the Emergency Director / REC. l 4.5 A continuous dialogue should be maintained between the reentry team and the Emergency Director concerning observed dose rates and conditions observed. 4.6 Periodically, or when requested, the reentry team shall read and report dosimeter readings. l 4.7 If at anytime during the reentry, observed dose rates exceed a predetermined level or if the exposure of team members l approaches a predetermined amount, the Team Leader shall return the team to a safe area. 4.8 If exposure or dose rates are acceptable, the reentry team should complete the functions assigned to it (e.g. surveys, inspections, repairs, valve operations, etc.). 4.9 The Team Leader, upon completion of work, shall direct the team from the area to a safe area (control point). 4.10 The Radiation Protection Group should assist the team members at the control point assuring an accurate dose assessment and Q proper removal of protective clothing and respiratory
) protection equipment.
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> Page 4 !< . 4.11 The Radiation Protection Group shall complete the ;
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F3-25 Rev. 2 Page 5 ATTACHMENT A DOSE RATE CALCULATION DESCRIPTION Floor plans have been developed to show'the Design Basis Accident dose rates throughout the ' plant. The Design Basis Accident dose rates are a result of safety system failure leading to major core damage with release to the containment atmosphere of 100% of the core noble gas inventory, 50% of the core equilibrium Radioiodine inventory and 1% of all others. In all cases, the accident has been assumed to be instantaneous, and the release of the fission products from the core has occurred at time T = 0. The fission products are assumed to be uniformly mixed within the containment atmosphere. Dose rates from the containment structure itself have been included in the dose rates to the vital and general areas of the. plant. Dose rates in the Auxiliary Building have been calculated, taking credit for the floors and walls within the Auxiliary Building. Large shield penetrations have also been included in the analysis. The penetrations that have been analyzed include ventilation penetrations on the 755' level, and the Main Steam penetrations on the 715' level. Where appropriate, values shown include the sum of the dose rates from containment itself and from the shield wall portals. Feedwater penetra-tions were assumed to be filled with water, resulting in no portal effect. Two floor plans for the 695' level are shown. One shows the dose rates at T = 0 assuming the recirculation mode is not in use. Dose rates on this floor plan are from the containment and the CVCS lines. The other floor plan of 695' level shows the dose rates at T = 0 assuming recirculation mode is in use. Dose rates shown here are the totals from the containment, CVCS lines, RHR, SI, and CS lines. The dose rates from the CVCS have been calcula-ted assuming Letdown was isolated after a gap activity release accident. Dose rates in the plant from the RHR, SI and CS Systems have been calculated assuming 100% of the core equilibrium radio-active Noble Gas inventory and 50% of the core equilibrium radio-active Halogen inventory have been diluted into the combined volume of the Reactor Coolant System and the Refueling Water r Storage Tank (RWST). This assumes that the water in the RWST has been injected and that the RHR recirculation mode is in use. These dose rate calculations are conservative because they are based on a T = 0 hours activity and no degassing of the recircula-tion water by the blowdown into containment. In reality, it would take at least 15 minutes before alignment of the recirculation mode would commence and the noble gases would be stripped when the liquid depressurizes. Floor plans of the 715' and 735' levels are at T = 0 assuming the RHR recirculation mode is in progress. IBM M_
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F3-25 Rev. 2 Page 6 t#D
\j ATTACHMENT A (Continued)
Dose rates at T = 0 are shown for the 755' level. These dose rates are from the containment and include the shield wall portals. Dose rates on 755' level at T = 1/2 hour ar2 also shown. These dose rates are from the containment and the Shield Building Vent System (SBVS) and Aux. Building Special Vent Syrtem (ABSVS) filters. Dose rates from the filters peak at approximately 1/2 hour after the event due to the build-up on the charcoal beds. The design criteria leakage of .25 w/o per day from the containment vessel to the shield building was used as the basis of the SLVS filter isotope build-up. The effect of Containment Spray has been included in the analysis. Dose rates from the ABSVS were also calculated. These dose rates are based on the RHR pump seal failure in combination with the design criteria of .1 w/o per day leakage which by passes the SBVS and is deposited on the ABSVS filters. This is conservative because if the .1 w/o is deposited on the ABSVS filters only, .15% w/o would be deposited on the SBVS filters. It has been assumed that .25 w/o is deposited on the SBVS filters and .I w/o is deposited on the ABSVS filters. In addition, the RHR seal failure has also been included as a source of build-up on the ABSVS filters.
~~y Dose rates at times later than T = 0 for all levels except 755'
\-- may be determined using Dose Rate vs Time Curves and the following formula :
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