ML20107B395

Public Version of Rev 29 to Emergency Plan Inplementing Procedures,Including F3-1, Onsite Emergency Organization, F3-2, Classification of Emergencies, & F3-3, Responsibilities During Notification of Unusual Events

ML20107B395
Person / Time
Site:	Prairie Island
Issue date:	10/08/1984
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML20107B374	List: ML20107B395
References
PROC-841008-01, NUDOCS 8411020183
Download: ML20107B395 (173)

Text

{{#Wiki_filter:T I PAGE 1 OF 2 l l EMERGENCY PLAN IMPLEMENTING l l PRAIRIE ISLAND NUCLEAR PROCEDURES l ~ l GENERATING PLANT l (- l NORTHERN STATES POWER COMPANY Number: TABLE OF CONTENTS Rev: 29 l l History Copy l Retention Time: Lifetime l l l .M / I TITLE: I l Su d'P ot tion l l 4 l Approved By: 1 F3 l l l EMERGENCY PLAN l l Pl W Minag ( l IMPLEMENTING PROCEDURES l l l TABLE OF CONTENTS l l Date: 9- ) [-- l l J l l l l NUMBER TITLE REV # l l l l l l 1 Onsite Emergency Organization 4 l l l l l 2 Classifications of Emergencies 5 l l l l 3 Responsibilities During a Notification of l l Unusual Event 4 l l l l l 4 Responsibilities During an Alert, Site Area, l l or General Emergency 10 l l l l l 5 Emergency Notificaticas JO l l l l l 6 Activation and Operation of Technical l l Support Center 4 l l \\ \\ l 7 Activation and Operation of Operational l l Support Center 4 l l l l 8 Recommendations for Offsite Protective l l Actions 3 l l l l 9 Eeergency Evacuation 3 l l l l 10 Personnel Accountability 5 l l I I l 11 Search and Rescue 1 l l l l 12 Emergency Exposure Control 2 l l l l l l 13 Offsite Dose Calculations 6 l l l 1 l 14.1 Onsite Radiological Monitoring 2 l I I l 14.2 Operations Emergency Surveys 2 l f l [ l I 3 2 e4110 0 PDR A PDR F IBM

Table of Contents Page 2 l Rev. 29 / s -s 4 i NUMBER T1rLE REV # 15 Responsibilities of the Radiation Survey Teams During a Radioactive Airborne Release 7 16 Responsibilities of the Radiation Survey Teams During a Radioactive Liquid Release 5 17 Core Damage Assessment 2 18 Thyro'id Iodine Blocking Agent (Potassium Iodide) 2 19 Personnel and Equipment Monitoring and Decontamination 0 1 20 Manual Determination of Radioactive 4. Release Concentrations 4 21 Establishment of a Secondary Access Control Point 3 22 Prairie Island Radiation Protection Group Response to a Monticello Emergency 2 23 Emergency Sampling 7 23.1 Emergency Hoteell Procedure 0 23.2 Post Accident Chloride Analysis by Ion Exchange Chromatography 0 k 24 Record Keeping During an Emergency 1 25 Re-Entry 2 26 Operation of the Recall Display Computer 1 i 27 DELETED 28 Review and Revision of Emergency Plans 0 29 Emergency Security Procedures 2 l l s s> i \\ IBM g ... (

o PAGE 1 OF 16 l l EMERGENCY PLAN IMPLEMENTING l l PRAIRIE ISLAND NUCLEAR ( PROCEDURES l p l~ GENERATING PLANT l l \\I-l NORTHERN STATES POWER COMPANY INumber: F3-1 Rev: 4l ( ) History Copy l l IRetention Time: Lifetime l // l TITLE: l l

Supt, ad Prote ~ ion l

ONSITE EMERGENCY l Approved By: ORGANIZATION l Plaht M'anage f l l ~ 0.C. Date: Y-M"I l l l l 1 l 1 l 1.0 PURPOSE l 1 1 I 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 l l l (2) Specify primary designates and alternates for key emergency l l organization positions, and l I I ) (3) Establish individual responsibilities and duties. l l 1 l The onsite emergency organization is illustrated in Figure 1, and l l {t.i l is comprised of personnel from the normal plant organization. The l l detailed organization discussed in this procedure may be further l l augmented or decreased as the needs of the emergency condition dictate. l l l 1 l l 2.0 PRECAUTIONS l 1 l l (1) Prairie Island plant staff shall not make any information l l releases to members of the news media or the public. All 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. 1 I I l (2)' In order to provide a sufficient number of alternates to fill l { the various Prairie Island emergency organization positions, l l l some individuals (by title) are listed in more than one j l emergen g 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. 1 I I I l r-1 I (.. I I I I I I inn e mew-

F3-1 Rev. 4 Page 2 3 ) ~ 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 has overall coordinating auth-ority for NSP. 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. 1 During an emergency, the Duty Shift Supervisor of the unaffected unit assumes the responsibility of the a, { Emergency Director. The Shif t 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-i gency Director and shall be available with a pager on a twenty-four (24) hour basis. When he is unavailable, (e.g., out of town), the designated Emergency Director responsibility and pager shall be passed down to the l next individual in the line of succession. Any of the individuals above the Shift Supervisor in i the line of succession may take over the responsibility l of the Emergency Director until the designated Emergency Director arrives onsite. A. The line of succession for the Emergency Director position is as follows: (1) Plant Manager l (2) Plant Supt. Engr. and Rad Prot. (3) Plant Supt. Operations & Maintenance (4) Supt. Radiation Protection s l (5) Duty Shif t Supervisor of Unaffected Unit .,j IBM

'li ) F3-1 i Rev. 4 ~

Page 3 l NOTE:

(a) The duty Shift Supervisor of the. l l affected unit, until relieved, shall l _l l remain in the Control Room at all l l l Limes during accident situations l l to direc.t the activities of the l l Control Room operators. l l l l (b) Exceptions to the line of succes-l l sion for the Emergency Director posi-l l tion are individuals serving as l l STA. The STA shall not assume l l other emergency organization posi-l l tions 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) Notification of offsite authorities; p (3) Recommend offsite protective actions Qj (the responsibility to authorize offsite protective action recommendations may not be delegated); (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 l for key positions in the onsite emer-gency organization; (7) During plant evacuations, initiate and ensure that personnel accountability is completed within thirty (30) min-utes of declaration of emergency and maintained throughout the emergency 1 condition; (8) Authorize radiation exposure in excess of normal limits; IBM

~ 1. ^ F3-1 Rev. 4 Page 4 (9) Ensure that radiologict1 monitoring (onsite and offsite) is initiated 4 (when required). 4.1.2 Emergency Manager-(EM) During an Alert, Site Area or General Emergency, the Corporate Nuclear Emergency Organization shall be activated. It is expected that the Corporate Organization can be fully activated within approximately-2 hours of notification. The Corporate Organization will base their oper-ations at the Near-Site E0F, under the dir-ection of the Emergency Manager (EM). A designated EOF Coordinator will be available at the E0F within 1 hour and may assume the Emergency Manager responsibilities until the designated Emergency Manager arrives. The Emergency Manager shall assume, from the Emergency Director, responsibility for overall management of 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 environs of the plant. Q) A. Emergency Manager - alternates The Zmergency Manager position should normally 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 arrives at the EOF. (1) General Manager Nuclear Plants (2) Manager Nuclear Technical Services (3) General Supt. Rad. Prot. and Chen, j (4) Asst. to General Mgr. Nuclear Plants (5) Production Training Manager (6) General Manager Headquarters i Nuclear Group, l B. The responsibilities of the Emergency j Manager are: 1 (1) Determine the extent of the offsite response. (2) Make reccamendations for the potential -) i l need for protective actions. ) (3) Supervise the operation of the EOF. l ' t IBM t I i i ~ I., U

a i I F3-1 Rev. 4 Page 5 '( (4) Direct personnel to provide the necessary offsite support for the plant as requested by the Emergency 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 devel-opeent 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 HQEC in the event that the Power Production Management is not available to assume control of HQEC oper-ations. -3 4.2 EMERGENCY ORGANIZATION COORDINATORS 4.2.1 Technical Support Center Coordinator The Techaical Support Center Coordinator shall be responsible for the general activation, operation and coordination of activities in the Technical l Support Center (TSC). t A. The Technical Support Center Coordinator i alternates are as follows: (1) Supt. Operations Engineering (2) Supt. Technical Engineering (3) Supt. Nuclear Engineering. (4) Supt. QA Engineering B. The responsibilities of the TSC Coordinator are: (1) Establish and verify radiological monitor-ing for the TSC including startup of the TSC cleanup systems; (2) Assist personnel performing the accountabil-c:, ity check; _k IBM .------rw, .v-,- e r--< w --~rv- - --ma m-~

i: F3-1 Rev. 4 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) Ensure plant status is obtained via Data Recall computer, plant process computer and/or via the. communicator assigned to the Control Room; (7) Periodically update personnel located in the TSC with appropriate information; 4 (8) Maintain any necessary status boards; f (9) Control the use of equipment located in the emergency locker; (10) Provide technical guidance to the Emer-gency Director and Control Room oper-ators on plant operations; (11) Obtain technical assistance as required to support the Control Room operations. 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 siternates are as follows: (1) Maintenance Supervisors (Mechanical) (2) Maintenance Supervisor (Electrical) (3) I & C Supervisor B. The responsibilities of the OSC Coordinator are: (1) Establish and verify radiological non-storing for the OSC and the Control Room; i (2) Coordinate activities of plant personnel located in the OSC to support plant oper-ations as requested by the Control Room ) and TSC. IBM l l ~

k i-_ p i-F3-1 P Rev. 4 C Page 7 j ( (3) Assist personnel _ performing the account- ^ i ability check. (4) Maintain the communications systems j in the OSC. A person may be des-ignated to act as a communicator. (5) Issue dosimetry to OSC and Control Room personnel. (6) Ensure OSC status boards are updated as .l required. (7) Periodically update personnel located in the OSC with appropriate information. '(8) Control the use of equipment located in the emergency locker. 4.2.3 I~ssemblyPointCoordinator The Assembly Point Coordinator shall be responsible 'b for the general operation of the assembly area. A. The Assembly Point Coordinator alternates are as follows: (f., ' - ~ (1) Radiation Protection Specialist, as directed by the Emergency Director B. The responsibilities of the Assembly Point 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 Emcrgency Locker. (6) Update all personnel with appropriate information when directed by the Emergency Director. c a s IBM = = - - -

l F3-1 Rev. 4 Page 8 i (7) Provide instructions to personnel when ) they are released from the assembly i point for reentry or transport offsite. 4.2.4 Radiological Emergency Coordinator The Radiological Emergency Coordinator (REC) j 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 E0F, the Radiation Protection Support Super-visor shall assume responsibility for the offsite accident assessment. A. The Radiological Emergency Coordinator (REC) alternates are as follows: (1) Supt. Rad Protection (2) Principal Prod Engr - Rad Prot Section (3) Rad Protection Supervisor (4) Radio-Chemistry Supervisor B. The responsibilities of the REC are: (1) Offsite dose assessment (2) Formulating offsite protective ^ action recommendations (3) Offsite surveys (4) Onsite surveys (5) Chemistry (6). Radiochemistry i (7) Onsite Radiation Protection for: l (a) access control l (b) damage control and repair l (c) search and rescue l (d) first-aid l (e) fire fighting (f) personnel monitoring & decontamination (g) dosimetry 4.3 SHIFT ORGANIZATION l 4.3.1 Operations Group The Operations Group consist of the Supt. Operations, - Shift Supervisors, and all operators. ) IBM f ? w w w

1[' i ~~ .~ Li t 'F3-1 Rev. 4 l Page 9 i t A. Group Leader - Line of Succession (1) Supt. Operations (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 electrical, mechanical, and I & C equipment 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 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 necessary. (4) Assist in first aid treatment. l / IBM ,e.

xa F3-1 Rev. 4 Page 10 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. A. STA - Line of Succession STA duty roster B. Responsibilities (1) Provide technical support to the Shift Supervisor in the area of operational event evaluation. (2) Provide the Shift Supervisor tech-nical and engineering support in the area of accident assessment. I l l NOTE: The Shift Technical Advisor shall not l l be assigned or assume duties which l l could in any way inhibit.his accident l l assessment advisory function during l cy l an emergency, until properly relieved l l of his STA duties by another Shif t l l Technical Advisor. l l l 4.3.4 Shift Emergency Communicator (SEC) The Shift Emergency Communicator (SEC) shall be onsite continuously. The SEC is responsible for initial netification and maintaining com-munications during emergency conditions. A. SEC - Line of Succession SEC duty roster B. Responsibilities (1) Initial notification of offsite agencies and personnel. 4 l l l s l l IBM i i I 4

.e' f' F3-1 Rev. 4 Page 11 r 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 site agencies and personnel'shalll 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 l l is activated, addition communi-l l cators on the SEC duty roster l l personnel should augment the l l plant staff to assist in the l l communication efforts. l l l h,. 4.3.5 Fire Brigade The Fire Brigade should consist of: (1) Brigade Chief - Unit 2 Shift Supervisor (2) Assistant Chief - Turbine or Auxiliary Building APE 0 l l l NOTE: Usually the APE 0 from the affected l l building shall fulfill the duties l l of the Brigade Chief in his absence.l l l (3) Fire Fighters - B0P Operators and Excess CR Operators (two operators per unit shall remain in the Control Room. (4) Runner - As designated to accompany fire department or operate equipment. During normal work hours, emergency assistance may be provided by maintenance and plant helpers. During backshifts, or at the discretion of the Brigade Chief, {w-the Red Wing Fire Department shall provide Emer-gency assistance and shall be called immediately on report of any fire requiring Fire Brigade Action. IBM

F3-1 Rev. 4 Page 12 A. Fire Brigade Chief - Line of Succession ((h av .(1) Unit 2 Shift Supervisor (2) Turbine or Auxiliary Building APE 0 B. Responsibilities (1) The Fire Brigade shall be respons-ible 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. A. Shift RPS - Line of Succession (1) Shift RPS (2) Control Room licensed operators are trained to perform emergency radiation su rveys. B. Responsibilities During emergency conditions, the shift Radiation Protection Specialist shall be ,1 responsible for: (1) In-Plant surveys (2) Chemistry (3) Radiochemistry (4) Dose Assessment l l l NOTE: The Control Room licensed operators are responsible l l to ' perform emergency radiation surveys. l l l 4.4 Emergency Staff Augmentation Groups 4.4.1 Maintenance Group The Maintenance Group consists of all maintenance crew personnel, all plant electricians, and plant helpers. The onsite Emergency 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 (Mechanical & Electrical), and designated Electricians who shall report to the Operat.onal ) Support Center (OSC). The mechanical and electrical l maintenance staff in the OSC can be further augmented or decreased as emergency conditions dictate. IBM

i ? j -- F3-1 Rev. 4 Page 13 A. Group Leader - Line of Succession (1) Supt. Maintenance (2) Maintenance Supervisors B. Responsibilities The Mechanical and Electrical Maintenance Group 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. (2) Supporting the Search and Rescue effort. 4.4.2 Instrument and Control Group The Instrument and Control Group consists of all I & C Specialists including I & C Coor-dinators and the I & C Supervisor. The onsite emergency organization includes the Supt, Tech-nical Engineering, who shall report to the ('; Technical Support Center; and the I & C s Supervisor and Coordinators who report to 4 Operational Support Center. The I & C Group can be further augmented or decreased as emergency conditions dictate. A. Group Leader - Line of Succession (1) Supt. Technical Engineer (2) I & C Supervisor (3) I & C Coordinators B. Responsibilities The I & C Group shall be responsible for: (1) Supporting the repair and corrective I actions for the instrument and con-trol systems in support of emergency response and recovery actions. (2) Supporting the search and rescue effort. i IBM

1 F3-1 Rev. 4 Page 14 3 P 4.4.3 Radiation Protection Group ~ 1 The Radiation Protection Group consists of the Supt. Radiation Protection and all members of the -Radiation Protection Group. 4 A. Group Leader - Line of Succession (1) Supt. Radiation Protection (2) Principal Prod Engr - Rad Prot Section (3) Radiation Protection Supervisor (4) Radiochemistry Supervisor (5) Rad Protection Coordinator B. Responsibilities The responsibilities of the Radiation Protection Group are: (1) Offsite Dose Assessment (2) Offsite Surveys (3) Onsite Surveys (4) Chemistry (5) Radiochemistry (6) Radiation Protection for: 1 (a) Access Control '~ (b) Damage control and Repair (c) Search and rescue 7 (d) First aid (e) Fire fighting (f) Personnel monitoring and decontamination (g) Dosimetry 4.4.4 Engineering Group The Engineering Group consists of Operation Engineers, Nuclear Engineers, Radiation Protection Engineers, Technical Engineers, Quality Assurance Engineers, Staff Engineer, and Scheduling Engineer. Upon activation of the onsite emergency organ-ization, all Engineering Superintendents and engineers assigned to the emergency organization shall report to the Technical Support Center. Other designated engineers may be requested to further augment engineering support in the TSC, as required. r I.) IBM l

+. - F3-1 Rev. 4 Page 15 .(T A. Group Leader - Line of Succession (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 The Engineering Group shall have responsi-bility for: (1) Providing technical support for emergency repairs and corrective actions on elec-trical/ mechanical systems. (2) Providing technical support for plant system engineering on electrical / mech-anical systems. (3) Providing technical support for operating radioactive waste con- .i trol systems. (4) Providing core parameter analysis to determine current core status. 4.4.5 Logistics Support Group The Support Group consists of the Purchasing and Inventory Control Group, the Administrative Services Group, and the Document Control Group. A. Group Leader - Line of Succession (1) Plant Office Manager (2) Administrative Services Supervisor B. Responsibilities The Support Group shall supply logistical support in their area of expertise. Per-sonnel in these may be called in to pro-vide support for emergency response on an as needed basis. } IBM ]

EMERGENCY *l DIRECIOR l IEDIATIN INITIAL SUPPORTING ENI'IORING OFF-SITE ONTACP i 'IEAMS (OFPSITE) i + CONTROL ROOM OPERATIONAL SUPPORP CINTER 'IEGINICAL SUPPORP CENTER. r - --l- --] p -- m-c - - - ----l l MSMLY MINF I shier I I l -~l---~ 1 SuPEw1SOR mORDINA'IOR l lOCMEMBERS l f ASSEMBLY MINP l i i i l 3 i l SHIPP TEGI l l MAINTENANCE I COORDINA'IOR - l i ADVISOR l 1 I I lTSc COORDINamR l 1 t SUPeavISORS _ _. J I I l l I l I l CDNfROL ROOM RADIATION l g l M[NI'IORING TEAMS l l l OPERA'IORS l RADIOIDGICAL l l I l l I l l EMERGENCY GJARDHOUSE l SUPP. l l I&C GIOUP SUW \\ l CDORDINA'IOR l l l OPERATIONS l g & COORDINA'IOR l l l .l i l l l l l l i l l STATION ELECTRICANS - l l SHIFT EMERGENCY l l l PIAMP OPS l l l PERSONNEL OMENICA'IORS I I l I l l l l l STANDBY OPERATIONS SYSTEM ENGINEERS l OONTRACT l i i l i l FIRE l l PERSONNEL l AS REQUIRED l l l SECURITY l l l l BRIGADE l g FORCE ~ l l____________l _______a __J g l l SECURITY l l SUPERVISOR l

• 'Ihe ED may coordinate activities fran either the

[----------- I Control Roan or the Tech Support Center i; OI-SITE EMERGENCY ORGANIZATION FIGURE 1 ~ EP-11-A,2 ,yn?L .. A * /'

i i PAGE 1 0F 48 l l EMERGENCY PLAN IMPLEMENTING l l PRAIRIE ISLAND NUCLEAR l PROCEDURES l ( l GENERATING PLANT l l l NORTHERN STATES POWER COMPANY l Number: F3-2 Rev: 5 l l l History Copy l l A A l Retention Time: Lifetime l l TITLE: l Supt ad Prot tion l l l Approved By: I CLASSIFICATIONS OF l l l EMERGENCIES I Pla'TR Planagey l l 0.C. Date: f-N[- N 1 l l I I I I l 1.0 PURPOSE l 1 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 levela of l l emergency classifications. l l 1 1 2.0 APPLICABILITY l l l l This instruction SHALL apply to all Shift Supervisors, Control Room l l Operators, Shift Technical Advisors and Emergency Directors. l l (c l l 3.0 PRECAUTIONS l l l l 3.1 The operator should believe his indications and take action l l based on those indications, however, he shall attempt to l l verify his indications by checking secondary or coincident l l indicators. l l l 1 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 l l l 4.0 DISCUSSION l l l l 4.1 Definitions l 1 I l 4.1.1 Notification of Unusual Event - events that are in l l progress or have occurred which indicate a potential l l degradation of the level of safety of the plant. l l l l 1 l No releases of radioactive material requiring offsite l l response or monitoring are expected unless further l l degradation of safety systems occurs. l I I I I I IBM

c F3 " j Rev. 5 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. l 4.1.4 General Emergency - events are in progress or have occurred which involve actual or imminent substantial core 7) degradation or melting with a potential u for loss of containment integrity. Releases during a General Emergency can i 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 j instrument readings, surface or airborne l contamination levels or radiation dose l rates that designate a specific emergency class requiring emergency measures for that class. 4.2 Summary Attached to this procedure is a Summary of Emergency Action Levels. This table identifies the four emergency classifications, the initiating conditions (s), emergency actions levels for each classification, and, where applicable, 9 specific instruments and indications to be used to datect and classify an emergency. m IBM ~ L

~ F3-2 Rev. 5 Page 3 ("' i S-The emergency action levels for each classification and the instrument readings and indications listed do not reflect a complete list of instrumentation that i will show abnormal indications but does list those key parameters useful in classifying the event. The Summary of Emergency Action levels lists the initiating conditions as required by Appendix 1 of NUREG-0654 and accidents analyzed in the Prairie Island FSAR. 5.0 PROCEDURE 5.1 Any significant event that may be classified as an emergency condition shall be reported to the Shift Supervisor immediately. l l l NOTE: The events may be instrumentation l l readings or visual observations made l l by plant personnel. l ~ l l 5.2 Attempt to verify the initial indication by comparing s the indication to redundant instrument channels or to other related parameters, visual observations, and field reports as applicable. 5.3 Assess the situation and determine the emergency classification, using the guidelines of Attachment 1. l l l NOTE: Personnel should become familiar with l l during training sessions. l l l 5.4 Take immediate actions, using applicable plant operating l procedures, Sections C and E of the Operations Manual, to return the plant to normal (or cold shutdown, if determined to be necessary). 5.5 Declare the appropriate emergency classification and i perform actions as specified in the appropriate i responsibility procedure applicable to emergency i 1 classification: [ i 5.5.1 For a Notification of Unusual Event, proceed to F3-3 t 4 5.5.2 For an Alert, Site or General Emergency, proceed to F3-4. 4 IBM i

F3-2 Rev. 5 Page 4 ~ms 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 4 terminate the emergency classification, as appropriate, as per the guidelines of Attach-4 ment 1. l l l NOTE: Depending upon the severity of the l l accident, it may not be possible to l l downgrade the emergency classification l l following the guidelines of Attach-l l ment 1. Therefore, once the plant 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 l termination and initiation of the l l long-term recovery. l l l %g l IBM d

I F3-2 Rev. 5 Page 5 r [ i

SUMMARY

OF EMERGENCY ACTION LEVELS 1 N. IBM i

F3-2 Rev. 5 Page 6 i ATTACHMENT 1 n .' } INITIATING CONDITION INDEX No. Condition Description Page 1 Safety System Functions 7 2 Abnormal Primary Leak Rate 10 3 Abnormal Coolant Temperature / Pressure 13 e 4 Abnormal Primary / Secondary Leak 14 5 Core Fuel Damage 16 6 Loss of 2 of 3 Fission Product Barriers 17 7 Secondary Coolant Anomaly 24' i 8 Radiological Effluents 27 9 Major Electrical Failures 30 10 Control Room Evacuations 33 11 Fires 34 12 Plant Shutdown Functions 35 13 Fuel Handling Accidents 38 14 Coolant Pump 40 15 Serious or Fatal Injury 41 16 Security Threats 42 17 Hazards to Plant Operations 43 18 Natural Events 46 19 Other 48 / IBM i .n.,-~ - _ -... - ~.

r F3-2 Rev. 5 Page 7 [ CONDITION #1 SAFETY SYSTEM FUNCTIONS Initiatina Condition Indication Used Classification ECCS initiated and dis-1. First out on reactor trip panel: Alert charge to vessel, a. 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 Lo Pressure SI and 2. Confirmation irss indicators: a. 2/3 High Containment Pressure (4psig) PI-945, PI-947, PI-949; or b. 2/3 Lo Steam Line Press. Loop A (500 psig) PI-468, PI-469, PI-482A; or c. 2/3 Lo Steam Line Press. Loop B (500 psig) PI-478, PI-479, (" PI-483A; or d. Lo Prz. Press (1815 psig) PI-429, PI-430, PI-431 gnd 3. Confirmation of SI Flow indicated by FI-925 and FI-924. 2E 4 Manual SI-Reactor Trip initiated if Auto SI did not occur at confirmed indicator Letpoints (#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 3.6, Unusual Event shutdown by technical which requires a unit shutdown, specification as determined by the Shift Supervisor. k IBM

~ F3-2 Rev. 5 Page 8 CONDITION #1 (Cont'd) SAFETY SYSTEM FUNCTIONS Initiating Condition Indication Used Classification 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, as determined by the Shift Supervisor. Loss of fire protection Loss of fire protection systems, Notification of system function requiring defined by Technical Specification Unusual Event shutdown by Technical 3.14, which requires a unit shutdown, Specification as determined by the Shift Supervisor. Failure of a safety or Pressurizer safety or relief valve Notification of relief valve in a safety opens and then fails to reset, as Unusual Event related system to close indicated by: following reduction of applicable pressure.

1. (a) Annunciator " Pressurizer h

Safety / Relief Valve Flow"; and (b) Annunciators; (1) " Pressurizer Power Relief line High Temp; or (2) " Pressurizer Safety Valve line A or B High Temp" E (c) Safety / Relief line high Temper-i ature indicated by (1) Pressurizer safety valve outlet temperature, TI-436 > 225'F; or (2) Pressurizer safety valve l outlet temperature, TI-437 > 225*F; g (3) Pressurizer relief valve outlet temperature, TI-438 > 225'F. ) IBM y! I L

F3-2 Rev. 5 Page 9 CONDITION #1 (Cont'd) SAFETY SYSTEM FUNCTIONS Initiatina Condition Indication Used Classification Steam Generator safety or relief valve Notification of opens and then fails to reset, as Unusual Event indicated by: 1. Visual and/or audible indication at vent stacks of open steam generator safety or relief valve; and 2. As determined by Shif t Supervisor i k C i 1 IBM

F3-2 Rev. 5 Page 10 CONDITION #2 ./ ABNORMAL PRIMARY LEAK RATE Initiatina Condition Indication Used Classification Primary system leak rate 1. Primary system leak rate, other Notification of frou unidentified or uncon-than controlled leakage sources, Unusual Event trolled sources exceeding exceeds Technical Specification 4 Technical Specifications 3.1.c; and 2. Requires a unit shutdown, as determined by the Shift Supervisor. L Primary coolant leak rate

1. (a) Decreasing pressurizer level, Alert greater than 50 gpa as indicated by LI-426, LI-427, LI-428; or i

(b) High radiation levels in contain-ment, as indicated by: R2 High Alarm - 50mR/hr; g R7HighAlarm-50mR/hr;{or ,j 's R-11 (Containment Positio i High Alarm - 5 x 10 cps, or_ R-12(ContainmentPositiog) l High Alarm - 6 x 10 cpm; and

2. Annunciator " Charging Pump in Auto High/ Low Speed"; and

) j

3. Charging line flow (FI-128B) greater than 50 gpa more than Letdown Flow (FI-134).

l NOTE: Rapid Temperature decreasel l in RCS results in same l ] l indications however no l l primary coolant leak rate.l l l l ') IBM o.

Y F3-2 .l Rev. 5 I Page 11 { h CONDITION #2 (Cont'd) ABNORMAL PRIMARY LEAK RATE Initiatina 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 indicated by the red light at the switch. Small LOCA and initially 1. LOCA has occurred; and General Emergency l successful ECCS. Subsequent i 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; 2.E (2) No spray pumps operating and less than four fan cooler units; 9.E (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); o_r or melt in from minutes RCS pressure decreasing to hours. Ultimate failure uncontrollably; of containment likely for i melt sequences, and i s = i \\_ IBM

i l-E3-2 Rev. 5 Page 12 CONDITION #2 (Cont'd) ABNORMAL PRIMARY LEAK RATE Initiating Condition Indication Used Classification (2) High containment pressure; or High containment humidity; or High containment sump levels; or High containment radiation levels and (3) Steam Generator's A and B pressures equal 21 (b) (1) Decreasing RCS pressure; and (2) Loss of subcooling margin (<10*F) and 2. Fuel Damage indicated by:

a. R48 High Alarm - 2 x 10'4 R/hr; or R49 High Alarm - 2 x 10 R/hr BI

b. High RCS activity, > 300 pCi/cc iodine equivalent, as determined by sample analysis and 3.

Loss of ECCS indicated by (a) High head SI failure; or (b) Low head SI failure. )> 1 IBM t L

F3-2 Rev. 5 Page 13 '~ 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

> 564*F; or-outside of Technical avg Specification limits.

2. RCS pressure > 2385 psig; or

3. RCS pressure < 2205 psig, and core exit temperature > 620*F, as indicated by a valid thermocouple; RI

4. Core Subcooling Margin < 10*F.

i l IBM L

F3-2 Rev. 5 Page 14 4 CONDITION #4 ^ I ABNORMAL PRIMARY / SECONDARY LEAK Initiating Condition Indication Used Classification Primary / Secondary leak When shutdown commences, as deter-Notification of rate exceeding Technical mined by the Shift Supervisor Unusual Event Specification of 1.0 gps 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

3. Ainunciators:

,s

a. "A SG High Water Level" f3 or

b. "B SG High Water Level" and

4. Confirmation from SG level indi-cators:

i

a. LI-461, LI-462, LI-463 j

(2/3 greater than 67%) or

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 l

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 ) I IBM e =

F3-2 Rev. 5 Page 15 .[:.. CONDITION #4 (Cont'd) \\ ABNORMAL PRIMARY / SECONDARY LEAK Initiatina Condition Indication Used Classification

2. Confirmation from Prz. Press indicators: PI-429, PI-430, PI-431 (2/3 low pressure, 1815 psig) and

3. Annunciators:

a. "A SG Water Level High" or

b. "B SG Water Level High" 7

and

4. Confirmation from SG level indi-cators:

a. LI-461, LI-462, LI-463 (2/3 1

greater than 67%) or

b. LI-471, LI-472, LI-473 (2/3 (x

greater than 67%) Q.. and

5. Safety injection flow indicated by FI-626 and FI-928 and

6. All of the following indicators:

a. 4.16 KV bus voltage (O Volts)

Buses 11-14 and 21-24 and

b. D1 and D2 generators running and closed in on safeguard buses:

(1) D1 & D2 Tach, (* 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 Bus 25, Breaker 16-7 k.C 1 IBM

F3-2 Rev. 5 Page 16 CONDITION #5 T CORE FUEL DAMAGE Initiatina 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 SI

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 requires a unit shutdown. Severe loss of fuel

1. Very high coolant activity sample; Alert cladding 300 pCi/cc iodine equivalent, as

' s, determined by chemical analysis SI

2. Letdown line radiation monitor i

R-9 in alarm mode and indicating greater than 10 R/hr, as con-firmed by portable instrumentation i Degraded core with

1. Degraded core, indicated by:

Site Area Emergency possible loss of coolable geometry (a) High primary coolant activity, > 300 pCi/ce; 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

2. Loss of coolable geometry, indicated by:

(a) Core AT increasing; or ~~ (b) No core 6T; or (c) Shift Supervisor's opinion IBM

F3-2 Rev. 5 Page 17 CONDITION #6 LOSS OF 2 0F 3 FISSION PRODUCT BARRIERS Initiating Condition Loss of 2 of 3 fission Three permutations exist for loss of product barriers with a 2 of 3 fission product barriers with potential loss of 3rd a potential loss of 3rd barrier; barrier (e.g., loss of 1. Failure of cladding and primary primary coolant boundary coolant boundary with potential clad failure, and high loss of containment. potential for loss of 2. Failure of cladding and containment containment). with potential loss of primary coolant boundary. 3. Failure of containment and primary coolant boundary with potential loss of cladding. These 3 permutations are represented in the following 5 cases, each with its own set of EAL's: s Indication Used Classification ( CASE 1: Loss of clad, 1. LOSS OF CLAD & LOCA, INDICATED General Emergency loss of primary coolant BY: boundary (LOCA), and high A.(1)(a) Very high coolant activity potential for loss of sample; 300 pCi/cc iodine containment equivalent, as determined by chemical analysis SI (b) Letdown line radiation monitor R-9 in alarm mode and indicating greater than 10 R/hr, as con-firmed by portable instrumentation and (2)(a) Pressurizer low pressure trip (1900 psig); or RCS pressure decreasing uncontrollably; and (b) High containment pressure; or High containment humidity; or High containment sump levels; or \\ High containment radiation levels IBM

F3-2 Rev. 5 Page 18 ~ CONDITION #6 (Cost'd) LOSS OF 2 0F 3 FISSION PRODUCT BARRIERS Indication Used Classification and (c) Steam Generator's A and B pressures equal EE B. Valid high radiation levels in containment, as indicated by: (a)R-48HighAlarm-2x10fR/hr;or (b) R-49 High Alarm - 2 x 10 R/hr; ~~ and 2. POTENTIAL FOR LOSS OF CONTAINMENT, INDICATED BY: A. Containment pressure approaching -s design pressure (46 psis) and increasing. i EE B. Loss of containment cooling capability indicated by minimum containment pressure suppression equipment not available: (1) No fan cooler units operating and less than two spray pumps EE (2) No spray pumps operating and less than four fan cooler units BE l (3) Less than two fan cooler units running with one spray pump EE C. Control Room status lights indicate i both Train A and Train B Containment Isolation valves not closed for any containment penetration and Shift l.' Supervisor's opinion. s.] l Ian L

F3-2 Rev. 5 Page 19 - CONDITION #6 (Cont'd) LOSS OF 2 0F 3 FISSION PRODUCT BARRIERS Indication Used Classification CASE 2: Loss of clad,

1. LOSS OF CLAD, AND LOSS OF PRIMARY General Emergency loss of primary coolant COOLANT BOUNDARY-(SG TUBE RUPTURE),

boundary (SG tube rupture), INDICATED BY: and high potential for loss of containment. A.(1) Loss of clad (a) Very high coolant activity sample; 300 pCi/cc iodine equivalent, as determined by chemical analysis EE (b) Letdown line radiation monitor R-9 in a.' arm mode and indicating greater than 10 R/hr, as con-firmed by portable instrumentation and 77' (2) SG Tube Rupture (a) First out on reactor trip panel: " Pressurizer Low Press SI" and (b) Confirmation from Prz. Press indi-cators. PI-429, PI-420, PI-431, (2/3 Low pressure, 1815 psig) and (c) Annunciators: "A SG High Water Level" m or "B SG High Water Level" and (d) Confirmation from SG 1evel indi-cators: LI-461, LI-462, LI-463 (2/3 greater than 67%) and (e) Safety injection flow indicated by FI-925 and FI-924 and pump- .c discharge pressure corresponding .(j to flow e IBM

F3-2 Rev. 5 Page 20 ._s' i CONDITION #6 (Cont'd) LOSS OF 2 0F 3 FISSION PRODUCT BARRIERS Indication Used Classification e SI l B. Steam Line Monitor in valid high alarm mode: R-51, > 100 mR/hr; or R-52, > 100 mR/hr and 2. POTENTIAL FOR LOSS OF CONTAINMENT, INDICATED BY: A. Steam Generator safety or relief valve opens and then fails to reset, as indicated by: (1) Visual and/or audible indication at vent stacks of open steam generator safety or relief valve; and (2) As determined by Shift Supervisor ji EI B. Imminent failure of MSIV, as determined by Shift Supervisor i CASE 3: Loss of clad, 1. LOSS OF CLAD, INDICATED BY: General emergency containment failure, and ,i a high potential for loss A. Very high coolant activity sample; l* of the RCS boundary. 300 pCi/cc iodine equivalent, as l,; determined by chemical analysis OE I B. Letdown line radiation monitor R-9 in alarm mode and indicating greater than 10 R/hr, as con-i firmed by portable instrumentation i and 2. LOSS OF CONTAINMENT, INDICATED BY: A. Control Room status lights indicate both Train A and Train B Containment Isolation valves not closed for any containment penetration and Shift Supervisor's opinion. IBM l L

lI F3-2 Rev. 5 Page 21 i 1 w. CONDITION #6 (Cont'd) l LOSS OF 2 0F 3 FISSION PRODUCT BARRIERS l Indication Used Classification or ~ B. Steam line break downstream of MISV, and open-close indicator shows MSIV not closed. I E C. Steam line break between containnent and the MSIV. _a n_d 3. POTENTIAL FOR LOSS OF THE RCS BOUNDARY, INDICATED BY: l A. Loss of ECCS indicated by a loss of High head SI capability. CASE 4: Loss of RCS 1. LOSS OF RCS BOUNDARY (LOCA), General Emergency ({' boundary (LOCA), loss of INDICATED BY: 4 containment, and high potential for loss of A. Pressurizer low pressure trip cladding. (1900 psig); y RCS pressure decreasing uncontrollably; and i B. High containment pressure; g High containment humidity; g i High containment sump levels; g High containment radiation levels i and i C. Steam Generator's A and B pressures 1 equal and 1 2. LOSS OF CONTAINMENT, INDICATED BY: s A. Control Room status lights indicate 5 both Train A and Train B Containment Isolation valves not closed for any I containment penetration. [ l l and b:. l B. Shift Supervisor's Opinion t t IBM l l L. i

F3-2 Rev. 5 Page 22 ) ~ CONDITION #6 (Cont'd) j -i LOSS OF 2 OF 3 FISSION PRODUCT BARRIERS Indication Used Classification and 3. POTENTIAL FOR LOSS OF CLADDING, INDICATED BY: A. Reactor vessel level low and decreasing (Shift Supervisor's 2 opinion) EE i B. Core exit thermocouples > 700'F and increasing EE C. Loss of ECCS indicated by a loss of High head SI capability. CASE 5: Loss of RCS 1. LOSS OF RCS BOUNDARY (SG TUBE General Emergency boundary (SG Tube Rupture), RUPTURE) INDICATED BY: s loss of containment, and 5) high potential for loss of A. First out on reactor trip panel: cladding. " Pressurizer Low Press SI" ang B. Confirmation from Prz. Press ,,j ' indicators, PI-429, PI-420, PI-431, (2/3 Low pressure, 1815 psig). and C. Annunciators: ( "A SG High Water Level" j or i "B SG High Water Level" and D. Confirmation from SG level indicators: (1) LI-461, LI-462, LI-463 l (2/3 greater than 67%) r or (2) LI-471, LI-472, LI-473 l (2/3 greater than 67%) IBM w we. - -, -, - + - - - - - *+ ~ 2 -v-- w

l F3-2 Rcv. 5 Page 23 CONDITION #6 (Cont'd) t LOSS OF 2 0F 3 FISSION PRODUCT BARRIERS Indication Used Classification and E. Safety injection flow indicated by FI-925 and FI-924 and pump discharge pressure corresponding to flow. and F. High Radiation on Condenser Air Ejector and/or Steam Generator Blowdown radiation monitors. agg 2. LOSS OF CONTAINMENT, INDICATED BY: A. Steam line break downstream of MSIV, and open-close indicator shows MSIV not closed. iw or B. Steam line break between containment and the MSIV. and 3. POTENTIAL FOR LOSS OF CLADDING, INDICATED BY: A. Reactor vessel level low and decreasing (Shift Supervisor's opinion). EE B. Core exit thermocouples > 700 F and increasing. EI C. Loss of ECCS indicated by a loss of High head SI capability. l l (LL-l l IBM w ~, n.e-- r

F3-2 R;v. 5 Page 24 CONDITION #7-SECONDARY COOLANT ANOMALY Initiating Condition Indication Used Classification Rapid depressurization of

1. (a) Steam Generator A/B Pressure Notification of Secondary Side Differential, > 100 psig; and Unusual Event (b) High Containment Pressure, 4 psig; 2E 6

2.(a) Hi Steam Flow,.745 x 10 lb/hr; and (b) Lo-Lo T,y,540*F EE

3. Steam line pressure Safety Injection Signal; EE

4. Failed Open Steam Dump, Relief,

.s or Safety Valve; EI

5. Shift Supervisors Opinion 5

^ 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. "5 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 less than 500 psig),

or

b. PT-478, PI-479, PI-483 (2/3 less than 500 psig)

) .J IBM -r 4

1, ' a F3-2 Rev. 5 Page 25 CONDITION #7 (Cont'd) SECONDARY COOLANT ANOMALY Initiating Condition Indication Used Classification and, if primary to secondary leak rate is occurring:

3. Hi radiation on:

a. R-15 Air Ejector Rad Monitor in alarm moge reading greater 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 damage Pressure SI" and

2. Confirmation from Steam Generator pressure indicators:

a. PI-468, PI-469, PI-482 (2/3 less than 500 psig),

gr

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 m de reading 4

> 5 x 10 cpm; and

b. leak rate calculation > 50 gpm; and

4. Indication of fuel damage:

a. Primary sample > 300 pCi/cc Iodine 131 equivalent; or

b. Steam Line Monitor in valid high alarm mode:

( :' ~ R-51, > 100 mR/hr; or R-52, > 100 mR/hr. IBM

F3-2 Rtv. 5 Page 26 CONDITION #7 (Cont'd) m. 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; 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 -3 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 l (2) Normal RHR Cooling 1 l l IBM

t F3-2 Rev. 5 Page 27 (' CONDITION #8 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,)

3 14.2.2

2. 2R-22 (5 x 10 cpm)

Due to release rate of radioactive gaseous effluents exceeding the dose rate limits per Technical Specification 3.9.B.I.a. Liquid Radiological Any of the following valid liquid Notification of 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. L (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 values listed per Technical Specification 3.9.A.I.a. Airborne Radiological Any of the following valid gaseous Alert effluents greater than effluent monitor readings: ten times Technical 4 Specification instantan-

1. IR-22 Hi-Hi Alarm (> 5 x 10 cpm) 4 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 continued for over two

4. 2R-50 Greater Than 1.2 mR/hr 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.I.a by meteorological conditions) a factor of 10.

+ u i IBM l ]

F3-2 RLv. 5 Page 28 CONDITION #8 (Cont'd) --) J 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 l

for two minutes, or result in the following dose projec-j 4, 2500 mR/hr to the tions at the site boundary, greater j thyroid for two minutes than: at the site boundary for adverse meteorology (a) 50 mR/hr whole body for 1/2 hour; or (b) 550 mR/hr thyroid for 1/2 hour; or (c) 500 mR/hr whole body for 2 minutes; or (d) E500 mR/hr thyroid for 2 minutes ET) 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; OE

4. Radiation Survey Teams measure thyroid dose rates (equivalent I-131 Concentrations), at the j

site boundary, which are greater than: (a) 250 mR/hr for 1/2 hour, or (b) 2500 mR/hr for 2 minutes. '] l I i IBM ( Y 6 e

F3-2 Rev. 5 Page 29 CONDITION #8 (Cont'd) RADIOLOGICAL EFFI,UENTS Initiatius 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 meteorological 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; g (b) SR/hr thyroid; or or, e

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 SR/hr.

Radiation levels or

1. Unexpected radiation levels Alert airborne contamination above 1000 mR/hr which indicate a severe degradation in the control or of radioactive materials (e.g., increase of factor 2.Widespreadcontamjnationabove of 1000 in direct radia-10,000 dpm/100 cm beta gamma or 2

tion readings within 500 dpm/100 cm alpha activity facility). / 1 IBM l

F3-2 Rav. 5 Page 30 ..,'t CONDITION #9 MAJOR ELECTRICAL FAILURES I Initiating Condition Indication Used Classification i I Loss of Offsite Power All of the following indicators: Notification of j 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) l

c. Bus 13(23), 4119306 (4172806)

d. Bus 14(24), 4119307 (4172807) a3d

2. D1 & D2 Generators up to Speed and Voltage and Supplying Safe-t guard buses:

a. D1 (D2) Tach (900 rpm) l b. D1 (D2) Gen. Volts (4260-4380 l Volts) l c. Safeguard bus breakers closed: Bus 15, Breaker 15-2 Bus 26, Breaker 26-2 l Bus 16, Breaker 25-6 Bus 25, Breaker 16-7 I Loss of onsite AC Power Loss of both diesel generators Notification of l 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)

I 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 i

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) power for more than

a. Bus 11(21), 4119304 (4172804) 15 minutes

b. Bus 12(22), 4119305 (4172805)

Y IBM r e

1 F3-2 Rev. 5 l Page 31 i 'l ( ~ CONDITION #9 (Cont'd) MAJOR ELECRICAL FAILURES Initiating Condition Indication Used Classification

c. Bus 13(23), 4119306 (4172806)

d. Bus 14(24), 4119307 (4172807) and

2. Loss of both diesel generators and

3. Blackout has occurred for more than 15 minutes.

Failure of offsite and

1. Loss of AC power, (offsite &

General Emergency onsite power along with onsite) indicated by: total loss of emergency feedwater makeup capability

a. 4.16 KV Bus Voltage (0 Volts)

C ' would lead to eventual for several hours. This (1) Bus 11(21), 4119304 (4172804)' (2) Bus 12(22), 4119305 (4172805) core melt and likely (3) Bus 13(23), 4119306 (4172806) failure of containment. (4) Bus 14(24), 4119307 (4172807) and

b. Loss of both diesel generators and

2. Turbine driven Aux Feedwater pumps inoperable for several hours.

Loss of all onsite DC All of the following annunciators Alert power (See Site Area received: Emergency for extended loss).

1. " Safeguard Train A DC Control Power Supply Failure"

\\ j and

2. " Safeguard Train B DC Control Power Supply Failure" 7\\s IBM

F3-2 Rev. 5 Page 32 ~ CONDITION #9 (Cont'd) MAJOR ELECTRICAL FAILURES Initiating Condition Indication Used Classification l NOTE: 4 annunciators numbered:l l 47018-0501 l l 47018-0502 l l 47518-0501 l l 47518-0502 l Loss of all vital onsite. All'of the following annunciators Site Area Emergency DC power for more than received: 15 minutes.

1. " Safeguard Train A DC Control Power Supply Failure" a.!Ld

2. " Safeguard Train B DC Control Power Supply Failure" l NOTE: 4 annunciators numbered:l

.3 l 47018-0501 l .i j ~" l 47018-0502 l l 47518-0501 l l 47518-0502 l and

3. Loss of DC Power has lasted more than 15 minutes.

i i l l IBM E

F3-2 Rev. 5 Page 33 j.- ( CONDITION #10 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 Panels and local stations Evacuation of the control As required by the Shift Supervisor Site Area room and control of shutdown Emergency systems not established from hot shutdown panel and local stations within 15 minutes e [ f l u IBM + e- --.,.-...e 4m em---- i--m-

F3-2 Rsv. 5 Page 34 CONDITION #11 j/ 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 Fire comprising the func-

1. Ooservation of major fire that Site Area tions of safety systems.

defeats safety systems Emergency or functions; and

2. Shift Supervisor's opinion j

l "* N .J i 1 l . ~. l 1BM 1

'V ~ 1 i, i F3-2 Rev. 5 Page 35 Attachment I k' CONDITION #12 PLANT SHUTDOWN FUNCTIONS t 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. " BOP 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" and

2. " BOP Annunciator System Power Failure" Most or all alarms (annun-Annunciators received:

Site Area ciators) lost while unit is

1. "NSSS Annunciator System Power Emergency i

not in cold shutdown or Failure" during plant transient or

2. "B0P Annunciator System Power Failure" t

during a transient, as determined by the Shift Supervisor Complete loss of any As determined by Shif t Supervisor Alert r function needed for plant cold shutdown Complete loss of any As determined by Shift Supervisor Site Area function needed for plant Emergency ( hot shutdown IBM

F3-2 R.v. 5 Page 36 CONDITION #12 (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 Turbine Failure causing

1. High Vibration (7 mils)

Alert casing penetration and

2. High-High Vibration (14 mils) as indicated by Control Room recorder and alarms and

3. As determined by Visual Inspection Failure of the reactor

1. Any Reactor Trip Setpoint and Alert protection system to redandancy 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 suberiti-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 i

generation but no core damage immediately evi-

3. Shift Supervisor's opinion that dent).

a transient is in progress '\\: IBM i

F3-2 Rev. 5 Page 37 CONDITION #12 (Cont'd) PLANT SHUTDCWN FUNCTIONS Initiatina Condition Indication Used Classification Transient requiring opera-

1. Reactor remains critical after General Emergency tion 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 4 8 1 IBM y._.____ _y, ,, -- - - -. _-...--m,c,. y--r-.~ e.

F3-2 R;v. 5 Page 38 i' i =^ CONDITION #13 FUEL HANDLING ACCIDENTS Initiating Condition Indication Used Classification Fuel damage accident

1. Any of the following containment Alert with release of radio-rad monitors in valid alarm mode 4

activity to contain-and reading greater than: ment (a) R2 - 350 mR/hr; or Note: FSAR Section (b) R7 - 350 mR/hr l 14.2.1 or

2. The containment vent monitor in valid alarm mode, reading greater than:

6 (a) R11 - 10 cpm; or 5 i (b) R12 - 10 cpm and i

3. Shift Supervisor's opinion

) 1 Fuel damage accident with

1. Any of the following valid Alert release of radioactivity radiation monitor readings:

to the fuel handling 4 building (a) R-22 HiHi Alarm, > 5 x 10 cpm; 4 or Note: FSAR Section (b) R 50, > 1.2 mR/hr 14.2.1 and

2. Spent Fuel Pool Area Monitor R-5 in valid alarm mode reading > 350 mR/hr I

l ""d l [

3. Shift Supervisor's opinion l

's ) ,_/ IBM s ~

F3-2 Rev. 5 Page 39 ~. \\ CONDITION #13 (Cont'd) FUEL HANDLING ACCIDENTS Initiatina 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) ang (b) Shift Supervisor's opinion gr 2. For fuel damage in the Spent Fuel Pool: (a) Valid Radiation Monitor, readings on: (1) R50 Hi Alarm, > 70 mR/hr; or (2) RS, in alarm mode reading > 1R/hr ang (b) Shift Supervisor's opinion t i i ~. IBM l

F3-2 Rr.v. 5 Page 40 Attachment I _ _3 CONDITION #14 -19 COOLANT PUMP 1 Initiating Condition Indication Used Classification Coolant pump seizure

1. RCP Trip (over current 86 Alert leading to fuel failure lock-out);

Note: FSAR Section 14.1.8 and

2. Primary sample analysis indicating fuel failure (> 300 pCi/cc iodine 131 equivalent)

~, k .I 9 \\ IBM n

F3-2 Rsv. 5 Page 41 ( CONDITION #15 SERIOUS OR FATAL INJURY Initiating Condition Indication Used Classification Transportation of a As determined by the Shift Supervisor Notification 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 hours) l (. IBM t

F3-2 Rev. 5 Page 42 JG .I CONDITION #16 SECURITY THREATS -Initiating Condition Indication Used Classification Security threat or Per security plan Notification of attempted sabotage 'Jnusual Event - Ongoing security Per security plan Alert compromise Imminent loss of Per security plan Site Area Emergency physical control of plant Loss of physical control Per security plan General Emergency of plant F G I l 1 t l l i IBM ~ _. - _ JL.-

F3-2 Rev. 5 Page 43 y I- \\ CONDITION #17 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 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

(; Near or onsite

1. Visual observation by plant Notification of explosion personnel and/or plant security Unusual Event personnel; and

2. Reported to the Shift Supervisor Known explosion damage Visual observation by plant Alert to facility affecting personnel plant operation Severe damage to engi-Visual observation by plant Site Area Emergency i

neered safety system personnel equipment from explo-sions with plant not in cold shutdown 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 than: i I l IBM

F3-2 .R:.v. 5 Page 44 CONDITION #17~(Cont'd) 4.D %U HAZARDS TO PI. ANT OPERATIONS Initiating Condition Indication Used Classification (1) 80 ppa hydrazine; or (2) 25 ppm chlorine; or (3) 500 ppe ammonia; or (4) explosive limits as detected by explosive meter, u and, reported to the Shift Supervisor Entry into the plant Gaseous hazards being experienced-Alert environs of toxic or 'or projected, within the plant, i flammable gases as detected by portable instru-i mentation, which exists in concen-- l trations greater than: (1) 80 ppm hydrazine; or (2) 25 ppm chlorine; or (3) 500 ppe ammonia; or t (4) explosive limits as detected by explosive meter, fg J') { and, reported to the Shift Supervisor Entry of toxic or Gaseous hazards being experienced or Site Area Emergency flammable gases into projected within vital areas of the j vital areas with plant plant, as detected by portable instru-j not in cold shutdown mentation, which exists in concentrations greater than: (1) 80 ppm hydrazine; or (2) 25 ppe chlorine; o_i-l (3) 500 ppm ammonia; or (4) explosive limits as detected by explosive meter, and, reported to the Shift Supervisor i Missile impacts from Visual observation by plant personnel Alert whatever source on and/or plant security personnel facility i IBM

. ). } l F3-2. Rev. 5 Page 45 \\ CONDITION #17 (Cont'd) HAZARDS TO PLANT OPERATIONS Initiatina Condition Indication Used Classification Severe damage to engin-Visual observation by plant personnel Site Area Emergency eered safety system from missiles with plant not in cold shutdown 6 b f IBM i l

F3-2 Rsv. 5 Page 46 CONDITION #18 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 Earthquake greater than Annunciator " Design Basis Earthquake" Site Area Emergency Design Basis Earthquake received on the seismograph with plant not in cold shutdown Any tornado visible from Visual observation by plant personnel Notification of site and/or plant security and reported Unusual Event to the Shift Supervisor. ..]' 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 Flood levels approaching 692' elevation - requires both units Alert design levels to be shut down Flood levels exceeding 698' elevation - highest level Site Area Emergency design levels with plant transformers will function not in cold shutdown 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) ,s l 1 i IBM 1 a

F3-2 Rev. 5 Page CONDITION #18 (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

1. Approximately 666.5' elevation Site Area Emergency experienced or projected

. 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. Major 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 met tower, in excess of 100 mph being experienced or pro-jected with plant not in cold shutdown Auy major internal or As determined by the Shift General Emergency external events (e.g., Supervisor and/or Emergency fires, earthquake, sub-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 ,t l IBM l

F3-2 REv. 5 Page 48 Attachment I w ,? CONDITION #19 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 i 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 activation of Technical concurrence Support Center and near-site Emergency Operating ') Facility / Other plant conditions Shif t Supervisor opinion Site Area Emergency that warrant' activation of emergency operating centers and monitoring teams or a precautionary notification to the public 'l near the site l;I Other plant conditions Shift Supervisor's opinion General Emergency i exist, from whatever l; source, that make release of large amounts of radio-activity in a short time l period possible, e.g., any core melt situation. l \\ IBM

.f. ~ PAGE 1 OF 7 i l l EMERGENCY PLAN IMPLEMENTING l (' l PRAIRIE ISLAND NUCLEAR l PROCEDURES l t l GENERATING PLANT l l s' l NORTHERN STATES POWER COMPANY Number: F3-3 Rev: 4 l l History Copy l a Retention Time: Lifetime l l l .l TITLE: i l ~ Supt. ~d Prot tion l l a l Approved By: l RESPONSIBILITIES DURING A l l l NOTIFICATION OF UNUSUAL E"ENT I i PlaWMsnagepi l l OC Date: 9-M [" (( l l I I I l 1.0 PURPOSE l l 1 l The purpose of this instruction is to delineate the responsibilities l l of various emergency organization personnel and onsite organizations l l required to respond te a Notification of Unusual Event. l l l l 1 l 2.0

SUMMARY

l l l l 2.1 Notification of Unusual Event l l l l A. Definition l l l 'k l Unusual Events are events that are in progress or have occured l l which indicate a potential degradation of the level of safety l l of the plant. l l l l No release of radioactive material requiring offsite response l l or monitoring are expected unless further degradation of l l safety systems occurs. l l l l B. Purpose of the Notification of Unusual Event Class l l l l The purpose of the Notification of Unusual Event Emergency l l classification is to: l l l l (1) Have the operating staff come to a state of readiness l l from the standpoint of emergency response in the event l l the handling of the initiating condition needs to be l l escalated to a more severe action level class; l l 1 l (2) Provide for systematic handling of Unusual Events l l information. l I I l C. Plant Actions & Responsibilities: l l l l (1) Promptly inform State and/or local offsite l ( l authorities of nature of unusual condition l ( l as soon as discovered. l l l l l IBM m

F3-3 Rev. 4 Page 2 (2) Augment on-shift resources (if needed). l (3). Assess and respond to Unusual Event. i (4) Close out with verbal summary to offsite authorities. i or (5) Escalate to a more severe class. D. State and/or local offsite authority actions: (1) Provide fire or security assistance if required. (2) Standby until verbal closeout. or (3) Escalate to a more severe class. 3.0 PRECAUTIONS (1) During the Notification of Unusual Event class of emergency, the ~}) Emergency Director position will not be activated. The Shift Supervisor from the unaffected unit shall assume overall authority l for direction and control. (2) Plant personnel shall monitor plant conditions throughout the duration of the Unusual Event for indication that the level of safety of the plant has not been degraded, and shall be prepared to l escalate to a more severe class of emergency should conditions i warrant it. (3) All personnel shall stay clear of any areas as announced over the public address system. (4) All personnel shall refrain from using the public address system or telephone system during any emergency situation. 4.0 APPLICABILITY f This instruction shall apply to all NSP plant personnel. ( 5.0 PROCEDURE I OrganizadionControl 5.1 l .) \\' l IBM 0

I l F3-3 Rev. 4 - Page 3 /. -{' 5.1.1 Overall Responsibility - Shift Supervisor of unaffected unit. 5.1.2 In-Charge, Control Room - Shift Supervisor of affected unit. 5.1.3 Assistance, Control Room - Control Room Operators Shift Technical Advisor TSC - Shift Emergency Commun-icator Plant - Shift Radiation Protect-tion Specialist. 5.2 Responsibilities 5.2.1 Shift Supervisors A. Shift Supervisor of affected unit: (1) The Shift Supervisor of the affected unit shall proceed to the Control Room (if not already there). l l l NOTE: He shall remain in the Control l (T= l Room at all times during accident l s_,.. l conditions until properly relieved. l l l (2) If needed, ensure that applicable Emergency Operating l Procedures are implemented to respond to the Notification of Unusual Event condition with the objective of returning the plant to a normal, safe condition (or cold shutdown, if determined to be necessary). (3) Monitor plant conditions to determine when the threat to plant safety, if any, has passed. Be l prepared to escalate to a more severe emergency classification, if required. (4) Coordinate, with the Shift Supervisor of the 8 unaffected unit and the Shift Emergency Communi-cator, anytime the Notification of Unusual Event i class is escalated to more severe emergency class-ification or terminated, or any plant operations which may impact on radioactive releases. B. Shift Supervisor of unaffected unit: (1) Contact the STA and SEC (if not already done so), (:[' and have them report to the Control Room 3 immediately. IBM

F3-3 Rev. 4 Page 4 s, d v (2) Assist the SEC' in completing the Initial Emergency Notification Report, Figure 1 (PINGP #577), F3-5. (3) Designate the SEC to complete the notification of state, local and NSP personnel in accordance with F3-5, " Emergency Notifications". I I l NOTE: State and local authorities shall be l l notified within 15 minutes of the 1 l declaration of the emergency class. I I I (4) Ensure that the NRC has been notified. 1 I I NOTE: Notification of the NRC required l l within 1 hour. l l l (5) Determine appropriate plant staff support s notifications and requests for support. Coor- -~) requirements, if needed, and make applicable dinate the notifications of plant support with the SEC. (6) If local support services are required (e.g., fire department, hospital assistance, ambulance, etc.) ensure the required notifications are made. This may be coordinated with the SEC. (7) Assist the Shif t Supervisor of the affected unit j as required in 5.2.1 (A). l (8) Designate the SEC to complete the notifications of state, local, and NSP personnel whenever the emergency is escalated, or when the Notification of Unusual Event Classification is terminated. 1 l i IBM

'l ) f F3-3 Rev. 4 Page 5' 5.2.2 Control Room Personnel (1) Assist the Shift Supervisor as requested. (2) Utilize applicable Operations Manual pro-cedures to respond to the Notification of Unusual Event emergency classification, as I appropriate, with the object of returning the plant to a normal safe status (or cold shutdown, if determined to be necessary). (3) Announce the location and nature of the emergency over the public address system, uif applicable. Direct all non-essential personnel to remain clear of the affected area (if applicable) and to refrain from using the public address system. (4) Continuoutly monitor the Control Room instrumentation, radiation monitors, or any other developments which would be indicative of further system degradation. Inform the {nift Supervisor immediately of any changes in the plant status. 5.2.3 Shift Technical Advisor (1) Report to the Control Room immediately upon notification of the Unusual Event. (2) Assist the Shift Supervisor in assessing the emergency condition and safety related status of the plant. 5.2.4 Emergency Director (1) The Emergency Director position will not be activated during the Notification of Unusual Event. The Shift Supervisor of the unaffected unit has the overall res-ponsibility during this classification of emergency. ~ 5.2.5 Shift Emergency Communicator (1) Report to the Control Room immediately upon 1 notification. (2) Complete the " Initial Emergency Notification l Report", Figure 1 (PINGP #577), F3-5, with assistance from the Shift Supervisor. Y.- t b l IBM i L

a >,g, o s q _ne -- - e g 7-.- - e.,. a, 1 + t w F3-3 Rsv. 4 Page 6 -(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 bel l - notified within 15 minutes of the l l declaration of the ~ emergency - l l classification. l L I l (4) Assist' the Shift Supervisor in the coordination of other required communication' contacts (e.g., medical support, fire support, etc.). See the " Emergency -Preparedness Telephone Directory" for local support s services phone. numbers. i '(5) ~ Notify appropriate plant staff support personnel to augment the onsite. staff as deemed necessary by the j-Shift Supervisors. (6) Maintain communications through-out the emergency classification as required by F3-5, " Emergency l Notifications". I I l NOTE: Be prepared to notify applicable l I authorities if conditions escalate l 1 l to a more severe emergency class. l I I (7) When the Notification _of Unusual Event class has been' i terminated, close-out the emergency classification, by { notifying the state, local, and NSP personnel in j accordance with F3-5, " Emergency Notifications". l 5.2.6 Other Operations Personnel i l (1) Assistant Plant Equipment Operators and Plant Attendants should continue with as-signed duties or report to tne Control Room if requested. l (2)- Relief Shift Operators onsite, should cor.tinue with assigned operations unless L their assistance is requested. (3) The Superintendent, Operations, if on site, should report to the Control Room and pro-vide assistance where necessary. - )' - IBM i .A. - -.. / - ~

ll 's- .c F3-3 Rev. 4 Page 7 .(e 5.2.7 Radiation Protection Group (1) The Shift Radiation Protection Specialist shall provide assistance (e.g., sampling, chemistry, radio-chemistry, surveys, etc.) as requested by j the Shif t Supervisor. _(2) Other Radiation Protection Group personnel should continue with aormal duties unless directed to 'do otherwise. 5.2.8 Plant Security Force (1) Continue with normal duties unless directed to do otherwise. (2) During off-normal work hours, designate a member of f the Security Force to control the telephone 1 switchboard in the TSC, when requested by the Shift Emergency Communicator (SEC). t k 5.2.9 All Other Personnel On Site (1) Continue with normal duties unless directed to do otherwise. b. (2) Stay clear of areas as announced over the public address system. p: V.. IBM t

. ~. PAGE 1 OF 33 l l EMERGENCY PLAN IMPLEMENTING l l PRAIRIE ISLAND NUCLEAR PROCEDURES l /" l GENERATING PLANT l k l NORTHERN STATES POWER COMPANY INumber: F3-4 Rev: 10 l l History Copy l l Retention Time: Lifetime l l TITLE: I l Supt. d Protect'on l l l Approved By: 1 l RESPONSIBILITIES DURING l l k/g l AN ALERT, SITE AREA OR l l Plant -Manager gi l GENERAL EMERGENCY l bMbb l OC Date: I i l l l l 1 I l 1.0 Pb7 POSE l l I l The purpose of this instruction 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 I I i l 2.0

SUMMARY

l l 1 l A graded scale of response is provided for the different classes of (.- l l emergencies, each requiring a specific response by emergency l l organization personnel for the protection of the public health and l l safety. l 1 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 level 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 emergency 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 Action Guideline exposure levels. l l l l B. Purpose of Alert Class l l I l The purpose of the Alert Emergency classification is to (1) l l assure that emergency personnel are readily available to l l respond if the situation becomes more serious or to perform l l confirmatory radiation monitoring, if required; (2) provide [ l offsite authorities current status information. l C. Plant Actions and Responsibilities: I I IBM

a F3-4 R;v. 10 Page 2 D) 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). 3. Assess and respond to the Alert condition. 4. Dispatch casite 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 releases. 7. Close out by verbal summary to offsite authorities, or 8. Escalate to a more severe class. -) D. State and/or Local Offsite Authority Actions: 1. Provide fire or security assistance, if required. 4 2. Augment resources by activating Emergency Operating Centers and EBS to standby status. 3. Alert to standby status key emergency personnel including monitoring teams and associated communications. 4. Provide confirmatory offsite radiation monitoring and ingestion pathway dose projections if actual releases substantially exceed technical specification limits. 5. Maintain alert status until verbal closeout. or j 6. Escalate to a more severe class. i 2.2 Site Area Emergency 1 i A. Definition i ... / 1 i IBM

3. ~ F3-4 Rev. 10 Page 3 i l r F 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. 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 levels except near the site boundary. B. Purpose of Site Area Emergency Class 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 authorities, and (5) provide updates for the public through offsite authorities. s f l' 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 Neat-Site Emergency Operations Facility (EOF). 3. Assess and respond to the Site Area Emergency. 4. If radiological or environmental conditions permit, evacuate onsite, nonessential personnel. 5. Dispatch onsite and offsite survey teams and associated communications (if needed). 6. Provide a dedicated individual for plant status updates to offsite authorities. 7., Make senior technical and management staff onsite available for consultation with NRC and State on a periodic basis. r d-8. Provide meteorological and dose estimates to offsite j authorities for actual releases via a dedicated individual. l l ' IBM l l m - ~ - - - __-c. ..m-

F3-4 R:;v. 10 Page 4 'D 9. Provide release and dose projections based on available plant condition information and foreseeable contingencies. 10. Close out or recommend reduction in emergency class by contacting offsite authorities. or 11. 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. ' 'N ._) 5. Dispatch key emergency personnel including monitoring teams and associated communications. 6. Alert to standby status other emergency personnel (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 from licensee and offsite monitoring with regard to changes to protective actions already initiated for public and mobilizing l evacuation resources. l 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. 12. Escalate to General Emergency class. -) '! or IBM

Lt 'F3-4 Rev. 10 Page 5 1 - (; i 2.3 General Emergency A. Definition The General Emergency describes events in progress or which have occurred which involve actual or imminent substantial i 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 offsite for more than the immediate site area, hence, Protective Actions may have to-be taken.for protection of the general public. 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 t. current information for the public and consultation with offsite authorities, and (5) provide updates for the public through offsite authorities. C; C. Plant Actions and Responsibilities 1. Promptly inform state and local offsite authorities of General Emergency status and reason for emergency as soon as discovered. 2. Augment resources by activating onsite Technical Support Center, onsite Operational Support Center and Near-Site Emergency Operations Facility (EOF). 3. Assess and respond to General Emergency. 4. If radiological or environmental conditions permit, evacuate onsite, nonessential personnel. 5. Dispatch onsite and offsite survey teams and associated communications. 6. Provide a dedicated individual for plant status updates to offsite authorities. 7. Make senior technical and management staff onsite available for consultation with NRC and State on a periodic basis. ~ f (L. 0 IBM

53-4 Rev.~10 Page 6- .h.. - J 8. Provide meteorological and dose estimates to offsite authorities for actual releases via a dedicated individual. 9. Provide release and dose projections based on availab1e ~ plant condition information and foreseeable . contingencies. 10. 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, i 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 di.wances. Consider. ) advisability of evacuation (projected time available vs i estimated evacuation times). .. ys .,s 4. Augment resources by activating Near-Site EOC and any U j other primary response centers. h 5. Dispatch key emergency personnel including monitoring teams and associated communications. 1 4 6. Dispatch other emergency personnel to duty stations within 5 mile radius and alert all others to standby i status. i. 7. Provide offsite monitoring results to licensee and others and jointly assess these. i } i j-8. Continuously assess information from licensee and j offsite monitoring with regard to changes to protective l actions already initiated for public and mobilizing l l evacuation resources. 1 l 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 closeout or t reduction of emergency class. b] IBM l I

F3-4 Rev. 10 Page 7 ( 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, booties 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. i I l l NOTE: When the evacuation alarm sounds during a DRILL, l 2 I remove ALL protective clothing prior to evacuating. l 1 I (5) When exiting the Protected Area via the Guard House, proceed through the portal monitor quickly. Step through without stopping. All I.D. cards (badges) shall be collected and checked out by the Security 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 from traffic control personnel. (7) All entries into the Auxiliary Building should be controlled through the OSC. Aux entries made for purposes of equipment operation, search and rescue, damage control, etc., should be led by a Radiation Protection Specialist, or other qualified individual. 4.0 APPLICABILITY This instruction shall apply to all plant personnel. IBM

F3-4 ~ Rev. 10 Page 8 5.0 ORGANIZATIONAL CONTROL 5.1 Overall Responsibility - Emergency Director 5.2 In-Charge, Control Room - Shift Supervisor 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 - Radiological Emergency Coordinator - - Engineering support as needed (i.e., systems experts) OSC - Extra Operators - Rad Survey Teams - Maintenance Supervisors - I & C Supv & Coordinators

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- Chief Station Electrician ~ and Alternates - Additional Support as needed 6.0 RESPONSIBILITIES 6.1 Shift Supervisor of the affected unit. (1) Proceed to the Control Room (if not already there) l 1 l NOTE: The Shift Supervisor of the affected l l unit shall remain in the Control Roon l l at all times during accident conditions l l until properly relieved. l l l (2) Implement the appropriate Emergency Operating Procedures, as needed, and respond to the emergency condition with the I objective of returning the plant to a normal safe condition (or cold shutdown, if determined to be necessary). ) IBM 4 m a w, de 3---3 ,w%,,_,y

}{ F3-4 Rev. 10 Page 9 (T 1 t.- l (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. (4) Coordinate, with the Emergency Director, all plant operations which may impact on radioactivity releases. 6.2 Shift Supervisor of the unaffected unit: (1) Assume the position as Emergency Director. (2) Start the duties and responsibilities assigned to the Emergency Director as specified in Section 6.3. Use Attach-ment A, Emergency Director's Checklist (PINGP #571). (3) When the designated Emergency Director arrives onsite, update him on the current plant status and formally transfer the Emergency Director responsibilities over to that individual. Ensure that the Shift Supervisor of the affected unit is aware that a turnover of Emergency Director responsibilities has occurred. (4) Assist the Shift Supervisor of the affected unit, as required I in section 6.1. \\_ 6.3 Emergency Director (1) Assume the role as Emergency Director. Use Attachment A, Emergency Director's Checklist (PINGP #571). (2) Determine the plant status. Report to the Control Room and become familiarized with the situation and sequence of events preceding and propagating the Emergency Condition. (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 GENERAL EMERGENCY HAS BEEN DECLARED. ALL NEMBERS OF THE ONSITE ENERGENCY ORGANIZATION REPORT C' TO YOUR ENERGENCY DUTY STATIONS. ALL OTHER PERSONNEL STANDBY FOR FURTHER INSTRUCTIONS. Repeat acaouncement. IBM l

F3-4 Rev. 10 Page 10 ~ l l l NOTE: A plant evacuation may be initiated l l during an Alert, and shall occur duringl j l a Site Area, or General Emergency, l 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 l tion", for specific evacuation l l criteria. j l I (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 (PINGP #577). (6) Designate the SEC to complete the notification of state, local, and NSP personnel, in accordance with F3-5, " Emergency 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. I l l (7) Direct the SEC to activate the onsite emergency organization, in accordance with F3-5, " Emergency Notifications", and to 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 " Emergency Preparedness Telephone Directory" local j support services phone numbers. l 1 l NOTE: These contacts should be coordinated with l l the SEC and the Control Room to ensure that l l the contacts required are made in a timely l l l manner. l l l 1 l ) l l IBM r g.- _ -,... - y g

s F3-4 Rev. 10 Page 11 (c (9) Direct the Shift RPS to (a) perform the appropriate sampling and analysis as 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: (a) Recommend activation of the Public Alert and Notification l System, and (b) Recommend sheltering of the public within a two mile radius of the plant and 5 miles downwind. (See F3-8, " Protective Action Recommendations). ( (12) Ensure that the NRC has been notified and designate an individual to maintain communications with the NRC via the ENS phone, as necessary. l l l NOTE: Notification of the NRC via the ENS l l required within I hour. l I I (13) During plant evacuations, direct the evacuation of all non-essential personnel from the plant site to the designated assembly point (per F3-9). (a) Normally, the Construction Office Building should be the designated assembly point. However, the Screenhouse may be used if conditions make the Construction Office Building uninhabitable. (b) Direct the Security Force to warn all personnel within the Owner Controlled Area and outside the Protected Area. (14) Honitor the habitability of the Auxiliary Building and order an evacuation of the Auxiliary Building Operators to the OSC if: (a) General area radiation levels exceed 100 mR/hr; or IBM J

F3-4 R;v. 10 Page 12 3.) (b) Based upon recommendations from the Radiation Protection Group. (15) Account for all personnel (Plant personnel, visitors and construction personnel) onsite, within 30 minutes following the evacuation. (This responsibility may be delegated). See Procedare F3-9. (16) Determine if the assembly point and guardhouse are safe and watch for changing conditions which would require further evacuation. (17) Complete a turnover of Emergency Director responsibilities 1 from the Shif t Supervisor of the unaffected unit to the designated Emergency Director when that individual arrives onsite. Ensure that both Shift Supervisors are aware of the turnover of the Emergency Director responsibilities. The Shif t Supervisor of the unaffected unit shall continue with the Emergency Responsibilities until a formal turnover occurs. (18) During plant evacuations, direct monitoring of all personnel for contamination (adequate instrumentation is available at both assembly points for this task). (19) 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. (20) Update TSC personnel on plant status. (21) Verify that communications have been established between all the onsite emergency operating centers (Control Room, OSC, and TSC). Assign the TSC Coordinator responsibility to l handle the Emergency Director phones. I (22) If necessary, based on plant conditions, initiate monitoring l of onsite and offsite areas. This responsibility may be delegated to the Radiation Protection Group. (23) If offsite releases are occurring or may occur, direct the calculation of projected of fsite dose rates as per F3-13. This responsibility may be delegated to the Radiological i Emergency Coordinator. (24) Make appropriate protective action recommendations to the offsite authorities. (See F3-8, " Recommendations for Offsite s Protection Actions"). The authority to approve protective

• j action recommendations shall not be delegated.

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ry F3-4 Rev. 10 i Page 13 ( (25) Ensure that continuous updates (approximately every half-hour) are provided to the State E0C's (Wisc and Minn) which were activated by the initial notification. (See F3-5). I l l NOTE: When the EOF is activated, communications with l l the offsite authorities will be transferred to l l the EOF. l I I (26) Periodically, request TSC personnel to present an update to all TSC personnel on status of activities in their specific area. i (27) Authorize overexposures in accordance with F3-12, " Emergency l Exposure Control". (28) Direct operation of the assembly point via the Assembly Point Coordinator and arrange for any assistance required at the assembly area. (29) 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. Anncunce, or have announced, the reclassification and escalation to a higher emergency classification, over the public address system. (30) 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. 4 (31) 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. Ensure that all TSC personnel are aware that a turnover of responsibilities to the EOF has occurred. (32) Coordinate with all group Superintendents to insure that plant manpower requirements for all subsequent workshifts are determined and that the necessary personnel are scheduled. (33) When the emergency condition is terminated, ensure that all offsite and onsite personnel are notified of the termination ('- of the cmergency condition and initiation of recovery l operations. l IBM

a 2 F3-4 Rev. 10 Page 14 Q J 6.4 Operations Group (1) Utilize applicable operations manual procedures to respond to 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 Shift Supervisor as requested, l l (3) Announce the location and nature of the Emergency over the public address system. When an evacuation is declared, sound l the evacuation alarm and direct all non-essential personnel l to evacuate to the designated assembly point. Direct all l personnel to re.sain clear of the affected area (if l applicable). See F3-9, " Emergency Evacuation." t (4) Assist in the activation of onsite emergency centers and organization. (5) 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. i (6) Operators (Aux & B0P) should report to their duty station when the emergency is declared. i i (a) Aux operators shall ensure that they have a low and high range dosimeter and a dose rate indicating device for all further required operations in the Auxiliary Building. (b) Aux & B0P operators should give consideration to terminating all non-essential plant operations. (e.g., shutdown evaporators). (c) When a plant evacuation is declared, the Aux & BOP operators should immediately establish a communi-j cation channel with the OSC. l l (d) If the Auxiliary Building general rad levels exceed i 100mR/hr or upon recommendations from the Emergency Director or Radiation Protection Group, the Aux Operators shall evacuate to the OSC. For exposure et,ntrol purposes, all further Auxiliary Building entries shall be controlled thru the OSC. (7) Perform the necessary onsite and in-plant radiation surveys as requested by the Shift Supervisor. ] IBM ~

y 1: F3-4 Rev. 10 Page 15 [ s - \\, e (8) Relief Shift and Training Operators should proceed to the Operational Support Center for further instructions to support operations in the Control Room. (9) 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 immediately upon notification of the Emergency Condition. (2) Assist the Shift Supervisor and Emergency Director in assessing the emergency condition and safety related aspects j 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 (PINGP #577), F3-5, with assistance from the Emergency Director / Shift Supervisor of the unaffected unit. (3) Complete the required notification of state and local authorities, and NSP personnel in accordance with F3-5, " Emergency Notifications", i l 1 l NOTE: State and local authorities shall be notified l l within 15 minutes of the declaration of the 1 i l emergency classification. l 2 (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, i " Emergency Notifications". l l i l NOTE: If the EOF has been activated, notifications l l of offsite agencies for an escalation, l l downgrade or termination of the emergency l s-l condition will be completed by EOF personnel.l (.. l l \\ i IBM

F3-4 RIv. 10-Page 16 6.7 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). + The TSC Coordinator shall: (1) Report to the TSC and assume the position as TSC Coordinator. Use Attachment C, Technical Support Center Coordinator Checklist (PINCP #573). (2) Coordinate activities of plant and non plant personnel located in the TSC. (3) Designate individuals to fill the following positions: a. Record Keeper (Maintain Emergency Director's Log) 1 b. Control Room Technical Communicator (Transfer plant status information to TSC Technical Communicator) i c. TSC Technical Communicator (Receive plant status information from Cottrol Room Technical Communicator) 4 d. Event Status Board Recorder (Maintain status board with i information obtained from TSC Technical Communicator) 1 e. Computer Operator (Operate Engineer's console & B&W Data Re-call Computer) (4) Establish and verify radiological monitoring for the TSC, in accordance with F3-6. (5) Ensure that the TSC doors are closed and initiate the TSC cleanup system, in accordance with F3-6. (6) Issue or designate an individual to issue dosimetry to all-TSC personnel, in accordance with F3-6, Activation of the TSC. f (7) Determine if all necessary positions are adequately staffed and request the SEC to notify additional staff to augment the emergency organization, as necessary. (8) Assist the Emergency Director in performing the account-4 l-ability check as necessary as per F3-10. I (9) Establish or ensure that communications are established with all onsite emergency operating facilities (Control Room, OSC

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and assembly area) to ensure all emergency organization personnel are inforraed of current plant status. 4 IBM \\ I .J

n F3-4 Rev. 10 Page 17. j (10) Assume responsibility for the Emergency Director phones. (11) Periodically update personnel located in the TSC with appropriate information. (12) Control the use of equipment located in the emergency locker. (13) Provide technical guidance on plant operations to the Emergency Director and Control Room operators. (14) Obtain and provide technical assistance as required to support the Technical Support Center and Control Room operations. (15) Assist in the establishment of 24 hour coverage of all key a emergency organization positions. t (16) Establish appropriate office space in the TSC for all emergency ) organization personn'el (NSP and non-NSP representatives). t f Interface with the non-NSP representatives located in the Technical Support Center and lend assistance where necessary. y, (17) When the Near-Site EOF has been activated, establish communications between the TSC and the EOF. 6.8 Operational Support Center Coordinator 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 (PINGP #574). (2) Determine the status of the plant and update all OSC personnel as necessary. Plant status may be de: ermined by reporting to the Control Room and getting a briefing from the Shift Supervisor of the unaffected unit. (3) Coordinate activities of plant personnel located in the OSC to i support plant operations as requested by the Control Room and TSC. I I l NOTE: The REC shall be responsible for control and l l direction for the Radiation Protection Spec-l l ialists located in the OSC. l k i I IBM

g-F3-4 ~ Rev. 10 Page 18 5) .) ../ .t - L (4) Establish and verify radiological monitoring for the OSC and the Control Room,as per F3-7. (5) When'a plant evacuation occurs, (a) Ensure all OSC personnel insert their badges into the OSC card reader. Inform the Emergency Director upon completion. (b) Designate an individual to perform a Control Room accountability and transfer accountability sheet'to the Emergency Director. (6) Ensure that dosimetry is issued to all OSC and Control Room Personnel, in accordance with F3-7. ~ (7) Establish communications between the OSC, the.TSC and'the Control Room. (8) Designate an individual to update and maintain the OSC Status Board. (9) Periodically update personnel located in the OSC with Q appropriate plant status information. -/ 2 (10) Control the use of all food use in the OSC until directed by the Radiation Protection Group. i l (11) Control the use of equipment located in the emergency locker. 6.9 Assembly Point Coordinator 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. (3) Assist the Emergency Director in performing the l accountability check, as necessary, per F3-10. (4) Maintain the communication systems. A person may be designated as the communicator, if necessary. [ ) I a i- ,1 . IBM i I i i

}p e l F3-4 RIv. 10 Page 19 C (5) Control the use of equipment located in the E.nergency 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 point for reentry or transport offsite. 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 (PINGP #572). (2) Determine the current plant status. I (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 necessary. (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. e (8) Ensure that all Radiation Survey Team Members (onsite & offsite) are informed of the current plant status including status of releases and meteorological conditions and are informed of any emergency condition changes. (9) When the Radiation Survey Teams forward survey results to the TSC, log the data and supervise the development of the plume i l map. 7Y, IBM e I L

F3-4 RGv. 10 Page 20 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 i teams to conduct a plume search both beyond the bluffs and up and down the valley, where plume diversion is likely to occur. (11) Direct the activities of the onsite radiation survey teams, (i.e., samples required, surveys required, analysis, etc.). (12) Based on the meteorological data, release data, and surveys (onsite and offsite),' determine the necessary radiation protection for the various segments of the plant emergency organization. (13) Monitor the habitability of the Auxiliary Building. If the radiation' levels exceed 100'mR/hr or based on Rad Prot Group survey results, recommend to the Emergency Director that the Auxiliary Building Operators-be evacuated to the j OSC. All entries to the Aux Building shall be controlled thru the OSC. j (14) Verify that the Radiation Protection Status Board is " ?; ? periodically update). Lj/ i (15) Based on offsite dose projections and offsite survey results,' provide the Emergency Director with recommendations for i-Protective Actions in accordance with F3-8,." Recommendations For Offsite' Protective Actions". 1 (16) Periodically update the Minnesota Department of Health and the Wisconsin Section of Radiation Protection with infor-mation required by Figure 6 (F3-5) " Emergency Notification [ Followup Message" (PINGP #582). I I ( 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 l L (17) Once the RPSS has arrived at the EOF, designate an individual [ to proceed to the EOF to perform dose assessment functions on the EOF MIDAS System. l '.~N i IBM t- !E ,-1+

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• R:v. 10 Page 21 (18) When the Near-Site EOF is activated, transfer control of the offsite survey teams to the Radiation Protection Support Supervisor (RPSS).

(19) Periodically or as requested, update the NRC, via the HPN phone, with release data, dose projections and meteorological data, as contained on Figure 6 (F3-5) " Emergency Notification l Followup Message" (PINGP #582), or as otherwise requested. I 6.11 Radiation Protection Group (1) The Shift Radiation Protection Specialist shall provide assistance (e.g., sampling, chemistry, radio-chemistry, surveys, or dose assessment) as requested by the Emergency Director. (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: (" (a) Proceed to the Operational Support Center and wait for (, further instructions, unless otherwise directed by the Emergency Director or Radiological Emergency Coordinator. (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 Coordinator. IBM r w

e.- - F3-4 Rev. 10 Page 22 6.12 Security Group (1) The Supervisor Security and Services or designee shall report to the Technical Support Center (TSC). The Supervisor Security and Services shall: (a) Assume _ responsibility for personnel accountability following a plant evacuation and continuing accountability throughout the duration of the emergency. See procedure F3-10. (b) Coordinate security control throughout the duration of the emergency situation. (c) Evaluate aspects concerning acts or attempted acts of sabotage. (2) The Security Force shall: (a) Continue with normal duties unless otherwise notified. (b) During off-normal work hours, designate a Security Force Member to control the telephone switchboard in the TSC, when requested by the Shift Emergency Communicator (SEC). (c) When the evacuation alarm sounds, all Security Officers, with the exception of the SAS operator, evacuate to the guardhouse for further instructions. I I l NOTE: The SAS operator should evacuate when l l directed by the Emergency Director. l l l (d) Assist with the evacuation of personnel to the designated assembly point which should normally be the Construction Office Building, in accordance with F3-29, " Emergency Security Procedures". l l IBM

Y F3-4 .g Rev. 10 Page 23 i i l i f \\. l s l l l NOTE: (1) It should be necessary for personnel to l l exit quickly thru the portal monitor and l l turnstile. Collect all I.D.'s and process l l badges so an Employee Onsite List of per-l l sonnel inside Protected Area can be ob-l l l tained. l 1 I f l (D To speed evacuation from the P ntected l 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

13) The Security Force shall ensure that all l

l personnel onsite, within the protected l l area, have heard the evacuation alarm. l l l (e) Perform a check of all areas immediately surrounding the Protected Area so that all personnel are notified of the evacuation in progress. l I l NOTE: The owner Controlled Area will be checked l l when directed by the Emergency Director. l l 1 (f) Control access to Protected area per instructions from the Emergency Director. Be prepared to obtain a printout for an accountability check in accordance with F3-10, " Personnel Accountability". (g) Assist the Radiation Protection Group in establishing a secondary access control point when directed by the Emergency Director. (h) Station a Security Force Member, with dosimetry, at the plant entrance, if conditions permit, to control access to the plant site. k IBM

= F3-4 R3v. 10 4 l Page 24 l 9,=. 6.13 Logistic Support Group The Logistic Support Group includes the Administrative Services Group, Purchasing & Inventory Control Group and the Document Control Group. During emergency conditions, the Logistics Support Group shall: (1) Continue with normal duties unless directed otherwise. (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 address system. (4) When requested by the Shift Emergency Communicator (SEC), the office staff shall transfer control of the telephone switchboard to the TSC. ( I l l l NOTE: The switchboard operator should report ! l to the TSC to control the switchboard l l from the TSC until relieved by an l l alternate communicator. l l 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 l (1) The I&C Supervisor and Coordinators shall report to the Operational Support Center (OSC) to provide support for: l (a) Repair and corrective actions for instrument and control systems, and; (b) Search and rescue efforts. fsh l IBM 1 -}L

g: F3-4 Rsv. 10 Page 25 i i (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. (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 (Mechanical and Electrical), and designated electricians shall report to the OSC to provide support for: (a) Repair and corrective actions for mechanical and electrical systems and; (b) Search and rescue efforts. (2) All other maintenance personnel, electricians and plant helpers 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 j designated assembly point. l (e) Follow instructions from the Assembly Point Coordinator for either reentry into the plant or departure from the ~ site property, i \\ IBM l I

F3-4 R;v. 10 Page 26 3j 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 systems. (c) Provide technical & engineering cupport for operating radioactive waste systems. (d) Provide technical & engineering support on core parameter analysis. (2) All other engineers (unless specifically requested to remain in the TSC) 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. (e) Follow instructions from the Assembly Point Coordinator for either reentry into the plant or departure from the i site property. j l 6.17 Contact, Temporary Personnel and Visitors I ~ (1) Continue with normal duties unless directed otherwise. (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 address system. I (4) When the evacuation alarm sounds, proceed to the designated assembly point. -1 (5) Follow instructions from the Assembly Point Coordinator for i either reentry into the plant or departure from the site i property. l IBM l 1 s a L

F3-4 Rev. 10 Page 27 PINGP #571, Rev. 3 Page 1 of 2 ATTACHMENT A ( Retention: Lifetime EMERGENCY DIRECTOR CHECKLIST INIT (1) Determine Plant Status (2) Announce Emergency C1' ass 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 org 'zation (F3-5) (5) If the first notification of ency is a General Emergency, call the Count S immediat and recommend: (a) Activation of icat' m, and; (b) Shelterin y lant and 5 miles (es g ,y (6) Assure communications es ed & maintained with NRC. (7) Direct Shift RPS to a) conduct onsit ling, as necessary. b) perform dose c ulations, 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 evacuation (F3-10) (c) Determine habitability of assembly area (11) Monitor Aux Building habitability and direct evacuation of Aux Operators to OSC if: (a) General area rad levels >100 mR/hr; or (b) Based on Rad Protection Group recommendations (12) The Shift Supervisor of the unaffected unit should complete a turnover to the designated Emergency Director at l / this point. Ensure that both Shift Supervisors are aware ( that a turnover of Emergency Director responsibilities has occurred. If the designated Emergency Director is not l available, proceed with the checklist. IBM

F3-4 R;v. 10 Page 28 PINGP #571, Rev. 3 Page 2 ATTACHMENT A (Cont'd) EMERGENCY DIRECTOR CHECKLIST (13) Direct activation of TSC & OSC (F3-6 & F3-7) and assign the responsibility for TSC Coordinator, OSC Coordinator and REC to appropriate individuals. (14) Update TSC personnel.of plant status (15) Ensure communication links a blished between onsite emergency centers. Desig SC Coordinator to assume control of the Emergen or phones (16) Dispatch offsite as ne 3-15 & F3-16) (17) Direct offsi s es (F3-13) o (18) Authorize proe ctive act' r endations (F3-8). This authority may not be d. o (19) Provide continu* es to State EOC's (20) Periodically, Qu st TSC personnel to provide status reports to allow updating all TSC personnel of current plant status. (21) Authorize overexposures as necessary (F3-12) (22) Establish communications with EOF (23) Transfer offsite responsibilities to EOF (24) Determine long-term manning requirements (25) Escalate / downgrade emergency class, as appropriate (26) Review Emergency Director's responsibilities to ensure all required actions are complete. l l Emergency Director Date/ Time ,/ IBM

F3-4 Rev. 10 Page 29 PINGP 572, Rev. 4 Page 1 of 2 ( Retention: Lifetime ATTACllMENT B RADIOLOGICAL EMERGENCY COORDINATOR CHECKLISJ 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 occu ring (5) Obtain meteorological dat ) & radiation monitor readings (6) Direct offsite dose j ion calcu s (F3-13) (7) Recommend protee reco ons for Emergency Director (F3-3 (8) Instruct,% tch & i ffsite radiation survey teams, as f essary i r nee with the following: { (a) F3-15 Airbo se - Team #1 Plume Search q - Team #2 Plume Search & Sampling or (b) F3-15 Li Release - Team #1 Eisenhower Bridge Sampling - Team #2 Intake / Discharge Canal & Lock & Dam Sampling (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) Monitor the habitability of the Auxiliary Building. Recommend to the Emergency Director that the Aux Operators evacuate to the OSC if the general area rad levels are >100 mR/hr or based on Rad Protection Group surveys. (13) Determine RPS sampling priorities per F3-23 (number in order) and specify protective clothing / respiratory protection require-ments for sampling team. ( U Primary Sample - Pressurized /Unpressurized 1 I Secondary Sample i I Shield Building Stack Sample IBM

i F3-4 Rw. 10 Page 30 PINGP 572, Rev. 4 Page 2 -.s.) RADIOLOGICAL EMERGENCY COORDINATOR CHECKLIST ,i 1 R Containment Air Sample i I Liquid l l Filtered Gas l l Unfiltered Gas R Iodine / Particulate O Other INIT (14) Periodically, up ffsite a survey teams with updates on plant s tus, rel ormation, meteorolog- ) ical information, and eme assifications, as i necessary. (15) Evaluate survey data evelop plume map (16) Request alternate meteorological data and weather forecast ^' information as necessary (F3-13 Figure 4) j (17) Recommend overexposure limits to Emergency Director (F3-12) 1 (18) Update the Radiation Protection Status Board t (19) Provide periodic updates to the Emergency Director & TSC Staff (20) Update the State Health Departments (Minn & Wisc) L (21) Establish / Maintain communications with the RPSS l (22) Designate an individual to operate the MIDAS System et the E.O.F. (23) Turnover the offsite survey responsibilities to the RPSS (24) Acknowledge the HPN phone and update the NRC as appropriate. (25) Review the REC responsiblities (F3-4 Section 6.10) to ensure all required actions are complete ) Radiological Emergency Coordinator Date/ Time IBM

9 F3-4 Rev. 10 Page 31 ~ PINGP 573, (FRONT) i Rev. 5 e Retention: Lifetime ( ATTACHMENT C TECHNICAL SUPPORT CENTER COORDINATOR CHECKLIST INIT (1) Coordinate the activities of plant and non plant personnel located in the TSC. (2) Designate the following positions: a. Record Keeper: _d 4 b. Control Room Technical Communicator c. TSC Technical Communicator: A Ak d. Event Status Board Recor A M o e. Computer Operator: 6 a V (3) Shut TSC Door and Start TSC Clean m 9 (4) Designate an individual (s) to sh communication between ( TSC, OSC & Control Room. s. (5) Assume responsibility of the Emergency Director Phones. (6) Establish radiological monitoring of the TSC environment utilizing the CAM and VAMP (F3-6, Section 4.2) (7) Issue dosimetry to all TSC personnel. (8) During a plant evacuation, assist the Emergency Director in overall plant accountability (F3-10). May be designated to the Supervisor Security and Services. (9) Determine additional TSC staffing required and request SEC to to make notifications. (10) Update TSC personnel with plant status updates as requested by the Emergency Director. (11) Provide technical assistance and guidance to the Emergency Director and Control Room. l (12) Evacuate all unnecessary personnel, as requested by the Emergency Director. (13) Control use of equipment located in Emergency Locker N.. (14) Establish appropriate office space for Emery,eprv Personnel IBM

1 F3-4 R:v. 10

• E PINGP 573,'(BACK)

Rev. 5 .-c, (15) Establish routine sampling & monitoring for the TSC as necessary. (16) When the Near-Site EOF has been activated, ensure that com-munications are established between the TSC and EOF. (17), Review F3-4 & F3-6 TSC Coordinator Date/ Time l

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F3-4 l Rev. 10 l } Page 33 PINCP 574, Rev. 3 Page 1 of 1 i ! (~ Retention: Lifetime ATTACllMENT !) l J t OPERATION,S,UPPORT,CigTER COORDINATUR CllECKLIST INIT f (1) Determine plant status and update OSC personnel. l (2) Coordinate activities of plant personnel in the OSC. (3) Designate an individual (s) to establish communication between OSC, TSC and Control Room. (4) Activate and verify proper operatio Vamp (F3-7, Section 4.2.1) (5) Activate & verify ion of the Control Room CAM (F3-7, Secti (6) Issue dorimetr )SC and of el. { (7) Designate an individual o use of equipment in Emergency Lockers s. (8) When a plant ev n occurs, (a) Ensure all OSC personnel insert their badges into the OSC card reader. Inform the Emergency Director upon completion. (b) Designate an individual to perform a Control Room account-ability and transfer accountabiltiy sheet to the Emer-gency Director. (9) Evacuate all unnecessary personnel. (10) Control use of food in OSC until directed by Radiation Protection Group. (11) Establish a routine sampling and monitoring of OSC and Control Room as necessary. (12) Periodically update Status Board and Personnel. (13) Review F3-4 & F3-7. l ,r( OSC Coordinator Date/ Time IBM

] PAGE 1 OF 43 l l EMERGENCY PLAN IMPLEMENTING l l PRAIRIE ISLAND NUCLEAR l PROCEDURES l [ ~j GENERATING PLANT l l 1 NORTHERN STATES POWER COMPANY l Number: F3-5 Rev: 10 l s l l History Copy l l e l Retention Time: Lifetime l l TITLE: l Supt. "ad Prote' tion l l l Approved By: 7) l l l f l EMERGENCY NOTIFICATIONS l l Plahf flanagg' l l l l 1 I O.C. Date: hMb N l l l I I I I l l l 1.0 PURPOSE l l l l This instruction delineates the notification procedures to be used l I during emergency conditions, defines the various emergency communica-l l tions systems available at the plant, (primary and backup), and l l provides the necessary operating instructions for their proper use. 1 I I l 2.0 APPLICABILITY l l l l This instruction SHALL apply to all Radiological Emergency 1 l Coordinators, Shift Supervisors, Emergency Directors and Shift I (" l Emergency Communicators. I l I l 3.0 PRECAUTIONS l l l 1 3.1 Always speak in a clear, distinct voice. I I I l 3.2 Make messages as short and concise as possible. I l l l 3.3 Always have the information repeated if it was not completely l l understood. I l l l 4.0 PROCEDURE l l l l 4.1 The Shift Emergency Communicator (SEC) Shall: 1 I I l 4.1.1 Report to the Control Room i I I l 4.1.2 Complete the " Emergency Notification Report Form", l I Figure 1, (PINGP #577) with assistance from the l l Emergency Director or Shift Supervisor. l l l l 4.1.3 Upon completion of the " Emergency Notification Report l l Form", (PINGP #577) report to the communications area l l of the Technical Support Center. I i I r t' I I V. l l 1 1 I I IBM

F3-5 Rev. 10 Page 2 4.1.4 Request the telephone switchboard operator to transfer control of the switchboard to the TSC and request that individual to report to the TSC to control the switch-board until relieved by a backup communicator, or the emergency situation is terminated. I I l NOTE: Refer to the Nuclear Emergency Preparedness l l Telephone Directory for specific telephone l l locations and numbers. l l 1 4.1.5 Initiate and complete the notifications of state, local, and NSP personnel as listed on the Emergency Notification Call Lists, as follows: (a) For a Notification of Unusual Event, use Figure 3, PINGP #579. (b) For an Alert, Site Area, or General Emergency, use Figure 4, PINGP #580. 4.1.6 Request local offsite support as deemed necessary. Coordinate these notifications with the control room. (Refer to the Nuclear Emergency Preparedness Telephone Directory for local support telephone numbers.) 4.1.7 If the emergency has been reclassified, (i.e., escalated, down graded, or terminated) complete the Emergency Classification Change, Figure 2, PINGP #578 and complete the notifications of offsite authorities as follows: (a) For a termination from a Notification of Unusual Event, use Figure 3, PINGP #579. (b) For any classification change, use Figure 4, PINGP #580. 4.1.8 When the EOF becomes activated, transfer control of Offsite Notifications to the EOF. 4.2 The Radiological Emergency Coordinator (REC) Shall: 4.2.1 Complete the Emergency Notification Followup Message Form, Figure 6, PINGP #582. I l l l NOTE: This form does not need to be completed in l l l its entirety prior to transmitting data to l l offsite authorities. l ) l I IBM Y

( I' F3-5 Rev. 10 !~ Page 3 ~7 4.2.2 Periodically up'date the Minnesota Department of Health T and the Wisconsin Division of Radiation Protection with the information as recorded on Figure 6, PINGP #582 the " Emergency Notification Followup Message". i I I j. I NOTE: When the Nearsite EOF is activated, updates l l to the Minnesota Department of Health and 'l l Wisconsin Division of Radiation Protection l I will be handled by EOF personnel. l l I i i 4.2.3 Acknowledge the HPN phone when it rings and periodically, I update the NRC with the information as recorded on Figure 6, PINGP #582 the " Emergency Notification Followup Hessage". I I l NOTE: Be prepared to provide continuous updates l l to the NRC, as requested over the HPN phone. l l l fs (s IBM

w. F3-5 i R;v. 10 Page 4 PINGP #577, Rev. 1 FIGURE 1 i INITIAL EMERGENCY NOTIFICATION REPORT [ Verify that the organization / person called is correct prior to relaying emergency information. THIS IS , SHIFT EMERGENCY COMMUNICATOR AT THE (Name) PRAIRIE ISLAND NUCLEAR GENERATING PLANT. WE HAVE DECLARED A(N) AT HOURS. (Emergency Class) (Time) Pick one of the following: 1 I WE HAVE NOT HAD A RADI0 ACTIVE I I WE HAVE HAD A(N) e ACTIVE RELEASE. (Li ' g Airborne ATMOSPHERIC CONDITIONS AT THE letESBNT LOWS: WIND DIRECTION IS FR HE 6 AT MPH. x (Dir n)" (Speed) THE AFFECTED SECTOR (S) IS(ARE ( M ~st sector (s) by letter designation) J THE PROTECTIVE ACTION RECOMME THIS TIME IS: l I NONE t i i SHELTER IN SECTORS OUT TO MILES i 1 I EVACUATE IN SECTORS OUT TO MILES I l ACTIVATE THE PUBLIC NOTIFICATION SYSTEM Give a brief description of the emergency. i PLEASE RELAY THIS INFORMATION TO YOUR EMERGENCY ORGANIZATION PERSONNEL. l Emergency Director Approval Name/Date Shift Emergency Communicator Name/Date .) IBM L

T, I l, F3-5 Rev. 10 Page 5 PINGP #578, Rev. 1 k' FIGURE 2 EMERGENCY CLASSIFICATION CllANGE Verify that the organization / person called is correct prior to relaying emergency information. THIS IS , SHIFT EMERGENCY COMMUNICATOR AT THE (Name) PRAIRIE ISLAND NUCLEAR GENERATING PLANT. WE HAVE RE-CLASSIFIED THE EVENT AND 1 l Escalated i 1 Down-graded ~ l I The t Hay Be Terminated TO A(N): (Pick one below if escalated or dow ed is ch ) l I Notification of Unusual v %[.o? '[' I I Alert I I Site Area Emer l I General Emergene AT HOURS (Time) Atmospheric Conditions at the Present Time Are as Follows: Wind Direction is From the at MPH. (Direction) (Speed) The Affected Sector (s) is(are) (List Sector (s) by Letter Designation) Form of Precipitation (if applicable) Give a brief description of the emergency: i l PLEASE RELAY THIS INFORMATION TO YOUR EMERGENCY ORGANIZATION PERSONNEL. Emergency Director Name/Date (. Shift Emergency Communicator (. Name/Date l IBM l

F3-5 Riv. 10 Page 6 PINGP 579 Rev. 8 Page 1 of 7 Retention: Life EMERGENCY NOTIFICATION CALL LIST FOR A NOTIFICATION OF UNUSUAL EVENT GENERAL INSTRUCTIONS (1) The Shift Emergency Communicator SHALL make notifications to the individuals and organizations listed on this Emergency Call List. (2) Contact each organization or individual using the contact information I listed in this Attachment. (3) For those notifications made by telephone, make the call as follows: A l NOTE: All primary contacts contai check 1; have l I pre-programed telephone nt on the To:7-'ve tic l l l dialers. Alternate or phone must be l l manually dialed. l l J l i W QS V i a. When the party answers ead the t fNehe Initial Notification 3 l Report Form. O' b. Note the name of the indi ~ tacted and the time of the contact. (4) For those notifications made AS, transmit only the information as specified in this procedure. Specific plant data, as specified on the Initial Notificatioa Report Form, will be available to those I authorities when they call back for a verification. l (5) Proceed to the next party on the call-list. l l (6) If a party cannot be contacted in two attempts, use alternate or backup communication channels. If a party still cannot be reached, consider other means such as dispatching a courier, relay through another party { or si nilar actions. (7) The Wisconsin Division of Emergency Government (DEG) and the Minnesota l Division of Emergency Services (DES) are required to call back for verifi-cation and/or request further information. Other emergency organizations, i e.g., Minnesota and Wisconsin Health Departments may call the plant for more information. Update these organizations, as appropriate. Use the Contr.ct Report Log, PINGP #597 or the verification signoffs in this checklist to note the time and the names of the individuals calling. (8) If a party not specified on the call list requests information, refer the party to the NSP Communications Department or to the local ) emergency services organization in his/her community, as appropriate. I.lM

F3-5 Rev. 10 Page 7 PINGP 579 Rev. 8 [. Page 2 of 7 t; EMERGENCY NOTIFICATION CA!.L LIST FOR A NOTIFICATION OF UNUSUAL EVENT SHIFT EMERGENCY COMMUNICATOR DATE EMERGENCY CLASS / TIME DECLARED NOTIFICATIONS 1. Request the telephone switchboard operator to report to the TSC, by either: (a). Normal Workday ( _ t _ ) - Dial 0 and request the assigned switchboard operator to report to the TSC to control the switchboard. Time /SEC Initials (b). Offshift - Call the CAS ope o Ext. 31 equest a guard to report to the T ntrol th ard. Time /SEC Initials A l NOTE: Continue wittPthis chec irYnediately. DO NOT wait for l l the switchboard oper rrive in the TCS. l l l Notify the Minnesota Div @ day. 2. f Emergency Services. The telephone number is , night Ny (Ask for the Duty Officer) Contact Time Initial Verification Person Noti fi ca tion-Time /SEC Initials SEC INITIALS l l l, NOTE: (1) This notification shall be made within 15 minutes l l of declaration of emergency class. l l l l (2) If NO verification is received within 30 minutes. l l contact the ntate again. l l l (3) Alternate means to contact the DES Duty Offi'cer is l l l via Capitol Security (telephone no. J. l l Request Capitol Security to connect you directly to l l the Duty Of ficer or request Capitol Security to l l l contact the Duty Of ficer and have the Duty Officer l 7(. l call the Prairie Inland Plant immediately. l 1 I IBM

F3-5 ~ R v. 10 PINGP 579 Rev. 8 Page 3 of 7

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EMERGENCY NOTIFICATION CALL LIST FOR AN (-' ALERT, SITE AREA, OR GENERAL EMERGENCY 3. Using the NAWAS network, notify the Wisconsin authorities in accordance with the following procedure: (a). Pick up the NAWAS set, press the talk button and say: "THIS IS PRAIRIE ISLAND NUCLEAR PLANT CALLING WISCONSIN WARNING CENTER ONE, WEST CENTRAL WARNING CENTER AND PIERCE COUNTY WARNING CENTER, ACKNOWLEDGE." (b). When warning center one, west central warning center and Pierce County warning centers acknowledge, press the talk switch and say: PRAIRIE ISLAND NUCLEAR PLANT IS (Pick correct classification): l-l EXPERIENCING A NOTIFIC ON OF UNUSUAL EVENT. A l_l TERMINATING THE N-- IION OF UNUSUAL EVENT. / RELAY THIS INFORMATION TO CY GOVE IATELY." Warning Center I M\\ q WTi Verification a 63 ication-Time /SEC Initials j;/ Initials West Central Warning Center Inital Notification-SEC Initials Pierce County Warning Center Time Initial Notification-SEC Initials l l l l NOTE: (1) This nottfication SHALL be made within 15 l l l minutes of declaration of emergency class. l l (2) [f area or county warning centers do noc l l l acknowledge, Wisconsin Warning Center I, II or l l l [Il will ring on the circuit and relay the l l l messa;,:e to appropriate warning centers. l l (3) If the NAWAS System should become disabled, l l l alternate methods of notification to Wisconsin l l authorities should be attempted, at follows: l l (a) Wisc. DEG -- Telephone -- l l th) % st Central Warning Center -- Telephone -- l l (c) Pierce County -- Telephone -- l or l l Radio - Channel 1 l I IBM

F3-5 Rev. 10 Page 9 PINGP 579 Rev. 8 g-Page 4 of 7 is EMERGENCY NOTIFICATION CALL LIST FOR A NOTIFICATION OF UNUSUAL EVENT 4. Notify the local authorities by telephone as follows: (a) GOODHUE COUNTY SHERIFF AT Contact Time Initial Notification-SEC Initials l l l NOTES: (1) This notification SHALL be made within l l 15 minutes of declaration of. emergency class. l 'gt l I l (2) Alternate means to commu with the Goodhue l C unty Sheriff is the ystem - annel 1. l (b) DAKOTA COUNTY SilERIFF AT Contact 4 Time W nitial (i otification-(g / SEC Initials I ~ l l NOTES: (1) This notific ALL be made within 15 l l . minutes of d tion of emergency class. l 1 l l (2) Alternate n.eans to communicate with the Dakota l l County Sheriff is the Radio System - Channel 1.l l l S. Notify the Plant Manager (or designee) if not already done so, to inform nim of the situation (notify one of the following in the order shown): Name llome Phone I Time / SEC Initials / Time / SEC Initials / Time / SEC Initials l / Time / SEC Initials ? 1 l IBM i

F3-5 Rev. 10 Page 10 FINGP 579 Rev. 8 (~f.h Page 5 of'7 Af EMERGENCY NOTIFICATION CALL LIST FOR A NOTIFICATION OF UNUSUAL EVENT l l l NOTE: The Plant Manager pager number is The pager l l should be used as a backup means of notifying the Plant l l Manager. The pager is passed down the line of succes-l l sion when the Plant Manager is unavailable. l l l 6. Notify the NSP System Dispatcher (Telephone No. ). Inform him of the situation, give him the name of the acting Emergency Director (or Shift Supervisor) and the number where he can be reached (Control Room, , o r TSC, ). / Time / SEC Initials

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l NOTE: Alternate means to communicate with th h em Di l patcher should be attempted in the f ing order: l (1) Telephone: l (2) Telephone: l t l (3) Control Room Hotline l + s l (4) Channel 7 - Radio Cons l '--) l d l I 7. Notify ONE of the NRC Resident Inspectors: Plant Ext. - Ilome # / or Time /SEC Initials - Plant Ext. I - !!ame # / Time SEC Initials 8. Contact the NSP District tanager, or designee, to inform him of the emergency situation (Notif y GNE of the t'ollowing, in the order shown): Work,. Iloce # l / Time SEC Initials / Time SEC Initials Supervisor on Duty (24 hour auiroer) / Time SEC Initials I IBM

i 73-5 Rev. 10 i PAGE 11 PINGP 579 Rev. 8 h Page 6 of 7 EMERGENCY UOTIFICATION CALL LIST FOR A NOTIFICATION OF UNUSUAL EVENT 9. Update the Radio Alert Monitor System Message Cassette as follows: (a) Insert a blank tape into the tape recording unit. (b) Make sure that the remote control unit ' Mike Enable' & ' Transmit Enable' key switches are both off (Green). (c) Set tape unit selector switch to ' Record Announcement' - insert microphone in tape unit mike jack. (d) Press tape unit ' Start' switch and record the prepared message. I I l NOTE: (1) Information to be recorded shoul the l l date, time and unit status. l l (2) When recording the message, a lowly and clearly, about 3 inches cropho \\ (e) Set tape unit selector switch t Ann s ' Start' switch and listen to recording. t volume ed level with tape unit ' Monitor Volume' Contro ) If sat' ry, proceed with (f). (f) Now, remove the message cassette from 9 unit and insert it into the telephone an nit. / Time SEC Initials

10. Notify or verify the Control Room has established notification of the NRC Emergency Response Center via the ENS Hotline.

/ Time / SEC Initials I l NOTES: ', "otification of NRC required to be made within l l l une hour of event declaration. l l (2) If the ENS Network should become disabled, the NRC l Operations Center may be contacted at any of the l l following numbers, in the order shown: l 1 l l (a) (Via Bethesda Central Office) l i I l l (b) (Via Silver Spring Central Office). l l l l l l l (c) (Via Bethesda Central Office) l l l l (l l (d) (Via Health Physics Network) I l l (e) (Via NRC Operator at Bethesda l l Central Office) l l I IBM

f F3-5 R w. 10 PAGE 12 PINGP 579 Rev. 8 n 1 Page 7 of 7 EMERGENCY NOTIFICATION CALL LIST FOR A NOTIFICATION OF UNUSUAL EVENT

11. Inform the Shift Supervisor of the completion of the notifications.

/ Time /SEC Initials CALL LIST COMPLETE: TIME DATE SHIFT EMERGENCY COMMUNICATOR _d D 6 9 9 s... - IBM J

y F3-5 'Rev. 10 Page 13 'PINGP 580 Rev. 9 (. Page 1 of 10 Retention: Lifetime EMERGENCY NOTIFICATION CALL LIST FOR AN ALERT, SITE AREA, OR GENERAL EMERGENCY GENERAL INSTRUCTIONS (1) The Shif t Emergency Communicator SHALL make notifications to the individuals and organizations listed on this Emergency Call List. (2) Contact each organization or individual using the contact information listed in this Attachment. (3) For those notifications made by telephone, make the call as follows: l l l NOTE: All primary contacts contained in this ist have l l pre-programed telephone numbers on A-Matic l l dialers. Alternate or backup te h umbers mu be l i manually dialed. l l A I a. ke he pa ty answers, r xt o ification b. Note the name of the individual co nd the time of the' Contact. 9 g (4) For those notifications made hv h ransmit on1v the information as specified in this procedure. .cific plant data, as specified on the Initial Notification Report form, will be available to those authorities when they call back for a verification. (5) Proceed to the next party on the call-list.

II a party cannot be contacted in two attempts, use alternate or backup communier.tir thannels.

If a party still cannot be reached, consider other means such as dispatching a courier, relay through another party or similar actions. (7) he b'isconsin Division of Emergency Government (DEG) and the Minnesota Dirision of Emergency Services (DES) are required to call back for verification and/or request turther information. Other emergency organizations, e.g., !!innesota and Utsconsin Health Departments may call the plant for more information. Update these organizations, as appropriate. Use the Contact Report Log, PINGP #597 or the verifica-tion signoffs in this checklist to note the time and the names of the individuals calling. (8) If a party not specified on the call list requests information, refer the party to the NSP Communications Department or to the local emergency services organization in his/her community, as appropriate. IBM

+U F3-5 R;v. 10 Page 14 PINGP 580 Rev. 9 Page 2 of 10 (I; ) EMERGENCY NOTIFICATION CALL LIST FOR AN ALERT. SITE AREA, OR GENERAL EMERGENCY-SHIFT EMERGENCY COMMUNICATOR DATE EMERGENCY CLASS / TIME DECLARED NOTIFICATIONS 1. Request the telephone switchboard operator to report to the TSC, by either: (a). Normal Workday ( ) - Dial 0 and request the assigned switchboard operator to report to the TSC to control the switchboard. Time /SEC Initials (b). Offshif t - Call the CAS operator 318 and request a guard to report to the TSC to t9asTthe switc rd. e/SEC Initials -f _ _ .-h l y - l y.,.i l NOTE: Continue with this check iately. DO NOT wait for l l the switchboard opera ive in the TSC. l l ,Ak l 2. Notify the Minnesota Divi.s s .t Emergency Services. The telephone number is night o day. (Ask for the Duty Officer) Contact Time initial Verification Person Notification-Time /SEC Initials SEC UllTIALS l NOTE: (1) This notil'icatton.snall be made within 15 minutes l l of declar, tion of emergency class. l I I l (2) If NO verit'ication is received within 30 minutes, l l contact the state again. l l l l { l (3) Alternate means to contact the DES Duty Officer is l l via Capitol Security (telephone no.- ). l I l Request Capi tol Securi ty to connect. you directly to l l the I)nty of : icer or request Capitol Security to l l con t.ic t the uut v of icer an I have the Duty Officer l - s l l call toe Pr.ii rie !s tand Plant immediately. l j I_._. IllM h t t L

,s f is F3-5 Rev. 10 Page 15 PINGP 580 Rev. 9 . [. Page 3 of 10 \\ r EMERGENCY NOTIFICATION CALL LIST FOR AN ALERT. SITE AREA, OR GENERAL ~ EMERGENCY 3. Using the NAWAS network, notify the Wisconsin authorities in accordance with the following procedure: (a) Pick up the NAWAS set, press the talk. button and say: "THIS IS PRAIRIE ISLAND NUCLEAR PLANT CALLING WISCONSIN WARNING CENTER ONE, WEST CENTRAL WARNING CENTER AND PIERCE COUNTY WARNING CENTER, ACKNOWLEDGE." (b) When Warning Center One, West Central Warning Center and Pierce County Warning Centers acknowledge, press the talk: switch and say: " PRAIRIE ISLAND NUCLEAR PLANT IS EXPERIENCING A ek the correct class): l___l ALERT, or l-~~ -_-l SITE AR,L q l]l GENE ISERGENCY RELAY THIS INFORMATION TO EMERGENCY GO MMEDIATELY." Warning Center I Time itial Verification Notification-Time /SEC Initial SEC Initials West Central Warning Center Time Initial Notification-SEC Init als Pierce County Warning Center Time Initial Notification-SEC Initials l NOTE: (1) This notification SHALL be made within 15 ~l I .i.tnutes of declaration of emergency class. l ] (2) If area or county warning centers do not l l acknowledge, Wisconsin Warning Center I, II or l l III will ring on the circuit and relay the l j message to appropriate warning centers., l l (3) If the NAWAS System should become disabled, I l alternate methods of notification to Wisconsin l l authorities should be attempted, as follows: l l (1) Wisc. DEG -- Telephone -- l (, (b) West Central Warning Center -- Telephone -- l 3c_. l l (c) "ferce County -- Telephone -- l l or l l Radio - Channel 1 l l l

F3-5 Rev. 10 Page 16 PINGP 580 m Rev. 9 / Page 4 of 10 \\: EMERGENCY NOTIFICATION CALL LIST FOR AN ALERT, SITE AREA, OR GENERAL EMERGENCY

4. Notify the local authorities by telephone as follows:

(a) GOODHUE COUNTY SHERIFF AT Contact Time Initial Notification-SEC Initials l l NOTES: (1) This notification SHALL be made within l l l 15 minutes of declaration of emergency class. l l (2) Alternate means to communica h the Goodhue l l County Sheriff is the Rad - Channel 1. l l 1 (b) DAK0TA COUNTY SHERIFF AT Contact ,V 4" isl .T ^ ication- ? Initials I ~ l l NOTES: (1) This notific L be made within 15 l l minutes of d abn of emergency class. l 1 l l (2) Alternate means to communicate with the Dakota l l County Sheriff is the Radio System - Channel 1 l l l l sesessassa.eccansnwnnaanunwe.~:sedenessensnusannus. ems.-unburuch l l l NOTE: IF TiiE EllERGENCY RESPONSE CRGANIZATION HAS PREVIOUSLYl l BEEN ACTIVATED BY THIS CllECKLIST, THE FOLLOWING STEPS l l NEED NOT BE C0tiPLETED FOR FURTHER ESCALATIONS. l l l a ca.e c.<.w e-;- enwnws.e e e e c can.c ce...:.u.,n.w, car.;;;;.;; w 5 Notify the Plant Manager (or designee) if not already done so, to inform him of the situation (notify one of the following in the order shown): Name Home Phone '/ Time / SEC Initials .] / Time f SEC Inttials / Time / SEC Initials / Tom. / (;LT inieis1e

F3-5 Rev. 10 Page 17 PINGP 580 ,c Rev. 9 t. Page 5 of 10 EMERGENCY NOTIFICATION CALL 1.lST FOR AN ALERT, SITE AREA, OR GENERAL EMERGENCY I I l NOTE: The Plant Manager pager number is ihe pager l l should be used as a backup means of notifying the Plant l l Manager. The pager is passed down the line of succes-l l cion when the Plant Manager is unavailable. l 1 1 6. Notify the NSP. System Dispatcher (Telephone No. ). Inform him of the situation, give him the name of the acting Emergency Director (or Shif t Supervisor) and the number where he can be reached (Control Room, , or TSC, ). i / Time SEC Initials E I 'b i 3 l NOTE: Alternate means to communicate with the NS Dis-I l i patcher should be attempted in the fol i der-1 (1) Telephone. l (2) Telephone: 1 (3) Control Roem Hotline l [" l (4) Channel 7 - Radio Cons $$ 3.' l V' 7. Notify ONE of the NRC Resident Inspectors: - Plant Ext. - llome /! / Time /SEC Initials or - Plant Ext. - Home r! / Time SEC Initials 8. Activate the Emergency Response Organization as follows: (1) Normal Unrk Hours (1) Verify announcement to report to emergency response centers is made over public address system. Time /SEC Initials (2) Contact the PI Training Center by telephone ( ), inform them ot' the emergency classification and reque.st them to report to the EOF. Time /SEC Initials IEM IBM

.s F3-5 R;v. 10 Page 18 PINGP 580 Rev. 9 m Page 6 of 10 l j ENERGENCY NOTIFICATION CALL LIST FOR AN ALERT, SITE AREA, OR GENERAL EMERGENCY l NOTE: Alternate numbers should be attempted in the l l following order: l l l l l I 1 (3) Contact the Nuclear Technical Services Group by telephone (Ext. or Ext. ), inform them of the emergency classification and request thec: to report to the EOF. Time /51C initials l NOTE: Alternate niunbers should be attempted in the l l following order: l l l __ d k (b) Off-Normal Work liours s,s m l NOTE: NSP personnel and Civil I S!!ALL be activated by llou l Off-normal work hours.- i I 4xx I e (1) Insert the pre-recorded tape nated "ERO Callout" into the tape unit. l (2) Set the tape unit selector switch to " Answer". (3) Turn the message transmitter control unit " Transmit Enable" key switch to the ON position. The red "XMIT" tamp should light. (4) Enter Code 04 on the encoder unit and press "P". l As soon as the tones are completed, enter Code 06 l and then press "P" I I l NOTE: Several seconds af ter the last tone is l l hea rti, the tape will be transmitted l l 3 times - then the unit will shut off. ! I l ) IBM

F3-5 Rev. 10 Page 19 PINGP 580 Rev. 9 ['. Page 7 of 10 EMERGENCY NorIFICATION CALL LIST FOR AN ALERT, SITE AiEA, OR GENERAL EMERGENCY (5) Verify proper operation of the radio alert monitor system by acknowledging that the TSC Radio Alert Monitor did activate. If not, repeat steps (1) through (4). (6) If the radio alert system failed to function after 2 attempts, use the Emergency Organization Call List, PINCP #581 and call all Emergency Organization Members by telephone. (7) When the transmission has ended, turn th nsmit Enable" key switch to the OFF positio (8) Remove the message cassette fr ape unit an replace in cassette storage r /SEC Initials '9. Notify the Local Residents as fdd$ 3. v (a) Insert the pre-recorded tape designa 1 Cq_ e Notifications" into the tape unit. (b) Set the tape unit selector swi Answer". (c) Turn the message. transmitter control unit " Transmit Enable" key switch to the ON position. The red "XMIT" lamp should light. (d) Enter Code 01 on the encoder unit and press "P". ~ I l i "r*r: reveral seconds after the last tone is l i heard, the tape will be transmitted l l 3 times - then the unit will shut off. l l l (e) Verify proper operation of the radio alert monitor system by acknowledging that the TSC Radio Alert Monitor did activate. If not, repeat steps (a) through (d). l N_. ~.

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Rev. 10 Paga 20 PINGP 580 Rev. 9 Page 8 of 10 EMERGENCY NOTIFICATION CALL LIST FOR AN ) ALERT, SITE AREA, OR GENERAL EMERGENCY (f) If the Radio Alert System failed to function after 2 attempts, proceed with Step (g). (g) When the transmission has ended, turn the " Transmit Enable" key switch to the OFF position. (h) Remove the message cassette from the tape unit and insert it into the telephone answering unit. Time /SEC Initials 4 4 10. Contact the NSP District Manager, or designee, to 9 im oi.i.e P-emergency situation (Notify ONE of the.followi m e order s vn): Woek # H4k',7 M..h o 'Nh) EC Initials ime SEC Initials <: ~r Supervisor on Duty (24 hou /

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Time SF aitials l I ~ l NOTE: IF 0FF DUTY WORK HOURS, REQUEST THE NSP INDIVIDUAL, I l CONTACTED ABOVE, TO REPORT TO THE NSP RED WING SERVICE l l CENTER TO UNLOCK THE FACITLITIES FOR THE NSP RADIATION l l SURVEY TEAMS. l l 1 I

11. Notify or verify the Control Room has established notification of the NRC Emergens/ Response Center via the ENS Hotline.

/ Time /SEC Initials l ~ I i i l J IBM I l 4,

F3-5 Rev. 10 Page 21 PINGP 580 Rev. 9 c. ( Page 9 of 10 EMERGENCY NOTIFICATION CALL LIST FOR AN ALERT, SITE AREA, OR GENERAL EMERGENCY l l l NOTES: (1) Notification of NRC required to be made within l l one hour of event declaration. l l (2) If the ENS Network should become disabled, the NRC l l Operations Center may be contacted at any of the l l following numbers, in the order shown: l l l l ' (a) (Via Bethesda Central Office) l l l l (b) (Via Silver Spring Central Office) l l l l l l (c) (Via Bethesda Central Office) l l l l (d) (Via Health Physics Network) l 1 l l (e) (Via NRC Operator at Be l l Central Office) l l A%\\ cO\\ l

12. Inform one Westingnouse cont r shown, to ensure early notification t an eme at the plant.

Be prepared to discuss as man acts as a e at the time of the call. I NOTE: Unless indicated othe 1 phone numbers are area code l l Where an area c her than is shown, it l l applies to the office and home. l l l Title Name Office Home 'ite se rv3 ces Reprer.entative Operating t)lant Hegional Manager 5t Alternate 2nd Alternate Service desponse Manager Ist Alternate 2nd Alternate Emergency Response Director Emergency Response Deputy ( Director Emergency News Communic 3tions -W Contact / Time /SEC Initials

F3-5 R;v. 10 Page 22 PINGP 580 Rev. 9 -s Page 10 of 10 {i EMERGENCY NOTIFICATION CALL LIST FOR AN ALERT, SITE AREA, OR GENERAL EMERGENCY

13. Notify American Nuclear Insurers (ANI) by Telephone -

(24-Hour Number) / Time /SEC Initials l NOTES: (1) During Normal Office Hours (8:00 a.m. - 4:00 p.m.), l l this number will be answered by a receptionist who l l will transfer the call to an appropriate individual. l l l l (2) During Off Normal Office Hours, an answering machine l l will intercept the call and notify a designated l l ANI Staff Member. Please leave your name, a:apacy, i l and telephone number. The ANI member will return l l the call to obtain further informat' l l A l

14. Notify INPO by telephone at Inform INPO of plant status and that uarter Emergency Center will contact them

's necessary. / Time /SEC Initials Y: p l t%W, l 4 l NOTES: (1) Alternate emergency 4 er is l (2) After hours, an aut te dialing system will l answer and request the following information: l l l l - your name, telephone number and plant l l l l - is this an actual emergency or ririll l l l l - how can INP0 help l l l l - repeat your area code and telephone number. l l l l t l l

15. Inform the Emergency Director of the completion of the notifications.

/ Time /SEC Initials CALL LIST COMPLETE: f!ME DATE l S!!!FT EMERGENCY COMMUNICATOR s .) .u l i IBM I

t ( F3-5 Rev. 10 } Page 23 i PINGP 581, Rev. 5 Page 1 of 3 f!GURE 5 h Retention: Life EMERGENCY ORGANIZATION CALL LIST INSTRUCTIONS (1) This call list SHALL be used to activate the ONSITE Emergency Response - Organization during off-normal work hours, should the Radio Alert Monitor System Fail. (2) Use the following notification guidelines: ( (a) Contact each individual in the order shown; (b) When the individual answers, request that individual to report to the plant; (c) Proceed to the next individual on the call list; (d) If an individual cannot he contacted in two attempts, bypass that individual and proceed down the list. Af r the other notifications are complete, re-attempt to t any bypassed individuals. NOTIFICATIONS Plant Management (OC Members) PLA GER (" PLT S T ENGR & L PLT SUPT OPER SUPT RAD F SUPT MAT ~ SUPT SUPT 0 IONS SUPT QUALITY ENGR SUPT TECH ENGR SUPT NUC ENGR Radiation Protection Group RAD PROT SPEC RAD PROT SPEC RAD PROT SPEC RAD PROT SPEC RAD PROT COORD CllEMIST RAD PROT SPEC RAD PROT SPEC RAD FROT SUPV TRAINING INSTRUCTOR RADIO-CliE!!ISTRY SUPV RAD PROT SPEC l RAD PROT SPEC RAD PROT SPFC ( RAD PROT COORD RAD PROT SPEC l '~ l RAD PROT SPEC RAD PROT SPEC IBM

F3-5 R;v. 10 Page 24 PINGP 581, Rev. 5 Page 2 of 3 FIGURE 5 (Continued) (1:.J i EMERGENCY ORGANIZATION CALL LIST Radiation Protection Group (Continised) RAD PROT SPEC QUALITY SPEC RAD PROT SPEC RAD PROT SPEC RAD PROT SPEC RAD PROT SPEC PRIN PROD ENGR Maintenance / Electricians MAINT SUPV MAINT SUPV MAINT SUPV MAINT SUPV CHIEF STATION STATION EL STATIO G 1 & C Group ,j f & C SUPV 2 1&CC 1&( Engineers ENGINEER 5' ASSOC PROD ENGR ASSOC PROD ENGR LEAD PROD ENGR ASST PROD ENGR { ASST PROD EMr.R ASSOG MUD ENGR ASSOC PROD ENGR LEAD PROD ENGR I.EAll PROD ENCR f EOF Cooritinator 'c.:=l'I' TRA I N I NG \\) l.EAD PRull ENGR 4 PROD ENGR IBM iu

I ra-a Rev. 10 Page 25 PINGP 581, Rev. 5 Page 3 of 3 r-FIGUiiE 5 (Continued) ( EMERGENCY OHGANIZATION CALL LIST SIMULATOR SUPERVISOR SUPT NUC TECH SERVICES TECH SUPPORT SUPV LEAD PROD ENGR

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F3-5 Rev. 10 Page 26 PINGP 582, Rev. 2 FIGURE 6 0' h.S EMERGENCY NOTIFICATION FOLLOWUP MESSAGE * .I Date Time AM/PM 1. Location of incident: Prairie Island 2. Class of emergency: 3. Type of release ( ) actual or ( ) potential: ( ) airborne () waterborne ( ) surface spill Ud. 4. Current. release data: 1 Time: hours am/pm Release rate: pCi/sec Height of release-Ground level Relative ases uCi/sec Quantity: nes % \\%W ' uCi/sec Particulate c4N\\\\ W uCi/sec Estimated quantity of radioactive ma Ieased or being released: 5. Meteorological Conditions: Wind Ve ocity mph Wind Direction (from): degrees Tempera ture

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Atmospheric Stability Class Form of precipitation 6. Release is expected to continue for hours. 7. Dose Projections based on a release rate of pCi/sec at hours am/pm. Whole Body Thyroid Sectors Affected Projected dose rate S.B. mrem /hr mrem /hr at: 2 miles mrem /nr mrem /hr 5 miles mrem /hr mrem /hr 10 miles mrem /hr mrem /hr Projected S.B. m rem mrem integrated 2 miles mrem meem dose at: 5 miles mrrm meem to miter.

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neem ^) J 2 Complete as much of the form as informat. ion availabtitty and time allows. AlI blanks need not be complete:1. IBM

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'l;, n-s Rev. 10 Page 2/ I PINGP 582, Rev. 2 fict!RE 6 ( 0.u t. nne41 ) { EMERGENCY NOTI FICATioN f ol.l.UWilP ffESSAGE- 8. Survey Results SilRVEY TIME POINT READING t A 2 9. Estimate of any surface radi ve contamination: dpm/100 cm 10. Chemical and physical form of released material: 11. Emergency response actions underway: 12. For liquid release to the river, estimate release volume, release activity and estimated time for concentration to reach public water: 13. Recommended emergency actions, including protective actions: 14. Request for any needed support by offsite organizations: 15. Prognosis for worsening or termination of event based on plant information: ( Emergency Director IBM

F3-5 Rev. 10 Page 28 ATTACHMENT A + ,s ? TELEPHONE COMMUNICATIONS NETWORK I. SITE TELEPHONE COMMUNICATIONS 1. -Dimension 2000 PBX Normal communications are provided by a Dimension 2000 PBX. Three separate Dimension PBX attendent consoles are used in,the , j system. All have identical functions and only one can be operational at a time. For normal business hours, all incoming 3 calls are answered by the receptionist located on the 5th floor of the Administration Building. During backshifts and weekends, r the console at the secondary alarm station is activated. The third console, located in the Technical Support Center Communications area, shall be activated during emergency plan j implementation. 4 The Dimension System controls approximately 265 main stations and i 75 extensions. It is designed with a high degree of fault detection and diagnostic capabilities. Additional reliability is-provided by a backup duplicate common control unit. If there are certain PBX failures or power failure, all stations would i normally be inoperative. However, automatic operation of transfer relays in the emergency transfer panelt, bridge preassigned stations directly to the trunk lines. Assigned stations are located in control rooms, shift supervisors office, access control, administrative office, and technical support center. A key switch to manually cut over these preassigned )i stations is located within the telephone equipment room if the i need exists. i ii Terminated within the Dimension System are 7 trunk lines and 7 tie lines. The trunk lines are 388-1121 through 1127, of which 388-1121 is incoming only, while 1122 through 1127 have incoming and outgoing capabilities. The seven two-way tie lines connect ,j the Dimension 2000 PBX to the general office exchange via the NSP !j microwave relay system. f3 Normal power for the system is provided by an instrument inverter which in turn is supplied by a diesel backed 480 VAC safeguards 6 motor control center and a 125 VDC station battery. An alternate source is provided by a SKVA 480/120V transformer supplied by the e { 480 VAC diesel backed safeguards motor control center. 3 2. Gai-Tronics Page System l Gai-Tronics paging system is also available and is used to call i personnel over the plant and yard speakers as well as to issue .] plantwide instructions from GTC stations located throughout the plant. This system is tied to the Dimension 2000 PBX, making l access to the paging system possible from all telephone IBM i i l-

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F3-5 I1 ATTACHMENT A (Continued) Rev. 10 Page 29-(' ' stations on site. Any one station tying up access to the paging \\_ system can be overridden with the executive override function from the operators console or the plant manager's office. j' 3. Phillips M100 Intercom System Additional communication capability is provided by the Phillips M100 Intercom System. Stations are installed throughout the plant with a two digit number identifying its location. 4. Sound Powered Phone System Sound powered phones are available for use within the plant and are primarily used for operations and maintenance coordination. Phone jacks are located throughout the Containment, Auxiliary ~ -Building, Turbine Building and Control Room. II. TECHNICAL SUPPORT CENTER (TSC) TELEPHONE COMMUNICATIONS 1. Touch-A-Matic Dialer The TSC Communications area is equipped with two automatic dialers. They function as a 31 name and number directory with an (- automatic memory. Numbers are programmed into the memory as labeled on the face plate. Both Touch-A-Matics are connected directly to an outside line. The memory button needs only to be depressed once to automatically dial the complete number. Unit #1 has numbers preprogrammed for ell the State and County Agencies, plus the EOF Coordinators and Engineers, Maintenance, Electrical, and I&C personnel required for notification procedures. Unit #2 is programmed for Operations Committee members and all the Health Physics personnel. The last number manually dialed is autom. cally recorded into the last number dialed position of the directory. Each number in this position is automatically replaced by the number previously manually dialed. 2. Dimension PBX Attendant Console Located in the communications area, the console once activated has, complete control of all incoming communications. The console is activated by calling the console in operation and instructing them to unplug the handset receiver. Operating Console on backshifts and weekends - Secondary Alarm Station Operating Console during normal working hours - Receptionist in Administration Bldg. IBM

r k F3-5 ATTACHMENT A (Continued). Rev. 10 Page 30 The TSC console is then made-operational by plugging its handset c into the board. At no time should two consoles be operated at the same time. 3. Stations, Extensions, and Hot Lines Individual telephone communication from the TSC is provided for by fifteen separate plant stations with two extensions of these stations, four General Office extensions, and four Eau Clair FX lines. Three separate didicated circuits (auto ringdown), are also available with points of connection as follows: 1. TSC - St. Paul State Capital EOC - (REC - Minn. Health Department) 2. TSC - EOF (ED to EM) 3. TSC - EOF - (REC - RPSS) The auto ring down is initiated by picking up the receiver. Ringing ceases when one other point picks up the line. 4. Phillips M100 Intercom Two stations of the Phillips M100 intercom station are located in ' '} the TSC. One is in the Radiation Protection Area while the other s is in the communications area. 5. Emergency Notification System (ENS) The ENS is a leased private line between Prairie Island and the NRC Incident Response Center. The ENS is the primary means for 4 reporting emergencies and other significant events to the NRC/IC Headquarters. When the NRC Operations Center is activated, the ENS becomes the dedicated line to the NRC for the transmission of operational data. The ENS Red Phone, labeled (GPO 1504) is located in the Control Room, with extensions in the Technical Support Center, the near-site EOF and the NRC resident inspector's office. To activate I' the ENS line, proceed as follows: } (1) Lift receiver. This causes the telephone console in the Operation Center in Bethesda, Maryland to ring i automatically. i ) 6 IBM ( ~ lL ~ t

3-F3-5~ ATTACHMENT A (Continued) Rev. 10 Page 31 -/" (2) The NRC Duty Officer will answer. ( (3) Calmly identify yourself and give the NRC Duty Officer the required information. (4). Designate an individual to maintain continuous communication with the NRC' staff member in_the Operations Center until the NRC decides that the event has been successfully terminated or additional' communication is unnecessary. I l l NOTE: If the incident has little potential for -l l impacting the public health and safety, the NRC l l Duty Officer may only' collect relevent infor-l l mation and then terminate the conversation. l l However, if the event is of a more serious -l l nature, the Duty Officer will maintain an open l l and continuous line with the site until the l l matter is resolved. l 1 l 6. Health Physics Network (HPN) The Health Physics Network (HPN) is a leased, private line system which connects all the nuclear power plants, the NRC Operations Centar, and the NRC Regional Office (Glen Ellyn). 1 It is primarily intended for use during emergencies and will function as the dedicated line between the Health Physics personnel, the Operations Center in Bethesda, ND and the NRC Regional Office. In the event of a site emergency, the NRC will activate the HPN. Before NRC Health Physics specialists arrive on site, the NRC Operations Center connunicator may request information from plant personnel. l l l NOTE: The HPN is a restricted network and may not be used l l by nongovernment employees at any time unless a l l significant1 event has to be reported and both the l l ENS and the commercial telephone-lines are out of l l service. l l 1 A W': IBM )

F3-5 ATTACHMENT A (Continued) Rev. 10 Page 32 Extansions for the HPN are at.the following locations: f (1) HP Office (2) Technical Support Center (3) NRC Resident Inspector's Office If necessary to use the HPN phone: (1) Lift receiver. NO DIAL TONE IS HEARD. (2) Dial the required number: 22 - NRC Operations Center 23 - Region III Office i I l NOTE: a. There will be audible' ringing signal dial tone l l af ter dialing the desired code. Ringing is l l heard at the called station to indicate an l-l incoming call. This ring stops when the tele-l l phone is answered or at the end of thirty l l seconds. You may dial again if the call has l l not been answered in approximately 30 seconds. l l l l b. An automatic time-out period of six seconds is l ? l provided on the HPN to prevent a tie-up if 'only I f) s l one digit has been dialed. This means that the l l desired code must be dialed within six seconds l l or the call will not complete. l { l l 7. National Warning System (NAWAS) The National Warning System (NAWAS) is a private wire system provided by the Federal Government to disseminate emergency information of a National or International nature. The National Primary input location is the North American Air Defense (NORAD) Command Center in the Cheyenne Mountains, Colorado. There are over 2000 terminals on this system in federal, military and state designated locations. I l The Wisconsin Division of Emergency Government (DEG) is responsible for maintaining a 24-hour statewide warning system as part of the National Warning System (NAWAS). The Prairie Island NAWAS is part of the Wisconsin State National Warning System. In Wisconsin, there are three (3) state warning centers. These warning centers have operational control over all terminals serving Wisconsin (including Prairie Island). This system is so designated that only the State Warning Point can commi*icate with terminals ontside of Wisconsin. All terminals within Wisconsin Y l LBH l

y l d.: ~ F3-5 ATTACHMENT A (Continued) Rev. 10 Page 33

• [s are on a " Party Line" basis, in that any terminal talking on the circuit is heard by all other terminals on the Wisconsin circuit.

In Wisconsin, NAWAS terminals are located at all seven district State Patrol Headquarters radio dispatch rooms and Area Emergency - Government EOC's, 26 county warning centers, the five nuclear power plants and six U.S. Weather Station Offices. The State Patrol-and county warning centers relay =to and from the other 46 county non-NAWAS centers by radio. The Prairie Island NAWAS talks directly to the State Warning Centers, the Weather Station Offices, and'to the county sheriffs. The State Warning Centers and the county sheriffs further disseminate information to emergency organizations and personnel by other communications systems. The state-wide emergency telephone number 608-266-3232 is the alternate communications backup for notification to the Wisconsin i Division of Emergency Government. 8 s THE FOLLOWING WILL BE USED IN THE EVENT AN INCIDENT AT PRAIRIE ISLAND REQUIRES A RESPONSE FROM STATE AND LOCAL AGENCIES: (1) DETERMINE THE CLASS OF EMERGENCY. 'l (2) PICK UP THE NAWAS SET, PRESS TALK BUTTON AND SAY: "THIS IS PRAIRIE ISLAND NUCLEAR PLANT CALLING WISCONSIN c (- WARNING CENTER ONE, WEST CENTRAL AREA WARNING CENTER AND PIERCE COUNTY WARNING CENTER, ACKNOWLEDGE." (3) WHEN WARNING CENTER ONE, WEST CENTRAL AREA AND PIERCE COUNTY WARNING CENTERS ACKNOWLEDGE, PRESS TALK SWITCH AND SAY: " PRAIRIE ISLAND NUCLEAR POWER PLANT IS EXPERIENCING A: " NOTIFICATION OF UNUSUAL EVENT" (least serious); OR " ALERT"; OR " SITE AREA EMERGENCY"; OR " GENERAL EMERGENCY" (most serious) " RELAY THIS INFORMATION TO EMERGENCY GOVERNMENT IMMEDIATELY." NOTES: a) IF AREA OR COUNTY WARNING CENTERS DO NOT ACKNOWLEDGE, WISCONSIN WARNING CENTERS I, II, OR III WILL RING ON THE CIRCUIT AND RELAY THE MESSAGE TO APPROPRIATE WARNING CENTERS. b) DUTY OFFICERS AND EMERGENCY GOVERNMENT OFFICIALS AT STATE AND LOCAL AGENCIES WILL INITIATE RESPONSE IN ACCORDANCE WITH CURRENT PLANS AND S0P'S. 4 kl i l 1 s IBM l l )

F3-5 AT'?.tiMENT A (Continued) Rev. 10 Page 34 NATIONAL WARNING SYSTEM (NAWAS) COLORADO SPRINGS ALTERNATE PRIMARY NWC WARNING CENTER OLNEY, MD I .i lI s' / i. s / s' / i ~ 5 ll s' / / 5 i l i / 5 / STATES / WISCONSIN FEDERAL AGENCIES / WISCONSIN WARNING CENTER III MILITARY POINTS / WARNING CENTER I ALT DEG EOC / STATE PATROL TOMAH / COMM CENTER / DISTRICT I / / MADISON / f NUCLEAR / OWER WISCONSIN e

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lI WARNING CENTER II ee PLANTS DEG COMMO ROOM ~ f' e - s i l HILL FARMS e MADISON s#' N 2 1 j 8'#' 7 SP DISTRICTS AREA EOC's U.S. WEATHER SERVICE MILWAUKEE // 5: MADISON

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/ /8 I' CREEN BAY g g#g, / f,s#' 5l g LA CROSSE ,/ // il t DUBUQUE i /,8 1 MINNEAPOLIS 26 COUNTIES - - /-? - - - - 18 COUNTIES l RADAR NEENAH /' ) RADAR MARSELLES j' 7 g*p I t // I l // I l l-I i. 28 COUNTIES I ^ DEDICATED TELEPHONE (NAWAS) P T OL MOBILES e - - - - - - - - RADIO i t' o o o.. e e e e WEATHER TELETYPE l )' TELETYPE (TIME) niiiiiiiiiiiiiiiiiiiii (ALL POINTS, EXCEPT MOBILES, INTERCONNECTED BY COMMERCIAL TELEPHONE) l l t L

F3-5 ATTACHMENT A (Continued) Rev. 10 Page 35

SUMMARY

OF PRAIRIE ISLAND HOTLINE NETWORK NRC EOF (ENS) CONIROL ROOM BETHESDA o 1 5 1 NRC _pg o 1 (HPN) U TSC Tf 5 GLEN ELLYN ~ j 6 g WISC. NRC AUTHORITIES 4 5 (HPN) ? (NAWAS) BETHESDA 3 e e STATE EOC OFFICE Number Name Station 1 Emergency Primary means for reporting emergencies and Notificatica other significant events to the NRC Head-System quarters in Bethesda, Maryland. The ENS phone (ENS) is located in the Control Room with extensions in the TSC and EOF. 2 TSC - EOF (ED-EM) 2 point auto ring between the TSC and EOF. Either station can activate the circuit. 3 TSC-EOF (REC-RPSS) 2 point auto ring between the TSC and EOF. Each station can activate the circuit. 4 TSC - Minn 2 point ring on demand between the TSC State EOC and State E0C. Each station can activate the circuit. 5 Health Physics Multiple station line between the NRC and the-Network (HPN) plant. Extensions of the HPN are located in the TSC, at Access Control, and the EOF. This is a two digit ring telephone. 6 TSC - National Dedicated Line to Wisc. Warning Center I, II, Warning System and III, Regional Warning Center, and County (NAWAS) Warning Center. t t t IBM

F3-5 Rev. 10 Page 36 ATTACHMENT B RADIO COMMUNICATIONS NETWORK I. MOTOROLA RADIO SYSTEM This radio system is capable of being operated in either a normal 8 (clear-uncoded) mode or in a private (Coded-digital voice protection) mode. l In the clear mode, all communications can be monitored by scanner a receivers. In the coded mode, a standard receiver or scanner cannot monitor communications. In the coded mode, the audio quality is degraded due to the encoding / decoding process. This is a normal condition. 1. Motorola Radio Console Three radio consoles provide the heart of the radio system. They are all identical with respect to function but not appearance. The consoles are located in the Control Room, TSC, and EOF. All contain the same channels and have an intercom feature between the consoles. Indication lights on the face of the console give the status of the transmitter / receiver mode, coded or clear operation. Check the status lamp located beside the clear / coded switch on the control units. Operate it as necessary to put the system into the clear or coded mode. All, consoles are able to monitor the selected channel as well as the unselected channels. Independent volume controls are provided for both. Frequency 1 and frequency 2 are banded together and are one in the same. Call lights on the verticle portion of the console indicate which channel information is being received on. The second row of channel selection buttons on the TSC console are not connected. i f I i I i i ../ IBM

}? F3-5 .i ATTACHMENT B (Continued)- Rev. 10-lh Page 37 8 Channels give communication ability for: CH1 (60 watt Simplex) Goodhue' County EOC - Goodhue County Sheriff's office, Red Wing, MN Dakota County EOC - Dakota County Sheriff's office, Hastings, MN Pierce County EOC - Pierce County Sheriff's office,'Ellsworth, WI CH2 (100 watt' repeater) - 10 radiation monitoring team portables - F1 or F2. 9 ? .,L CH3 (100 watt repeater) - 10_ plant portables - F1. CH4 (60 watt Simplex) - 20 security portables - F1 (primary freq) CHS (60 watt Simplex) - 20 security portables - F2 (secondary I freq) CH6 (60 watt Simplex) - Yard Portables CH7 - (60 Watt Simplex) - System Dispatcher (proposed) [ CH8 (12 watt Simplex) - Auxiliary Building F2 of the plant portables. 20 SECURITY PORTABLES 10 PLANT PORTABLES (F2) AUXILIARY BLDG USE SECURITY CAS 0 's CONTROL SECURITY 5 ROOM SAS ~~~~' 8 ~ EAD SURVEY l2 TEAM MEMBERS 10 PLANT PORTABLES (F1) 10 PORTABLES EOF 7 6 1 I SYSTEM DISPATCHER YARD GOODHUE EOC i' PORTABLES DAKOTA EOC PIERCE EOC i. / ~~~~~~~~~ RADIOWAVE .HARDWIRE i IBM

F3-5 ATTACHMENT B (Continued) Rev. 10 Page 38 2. Motorola Portable Handie-T;1kie (Model MX350) A. Special Instructions _f (1) Do not separate battery pack from radio. This separation could cause loss of DVP feature and it would 5 have to be recoded. The encoder and instructions are I located in the communications area of the TSC if needed. (2) Radios may be left in charger after full charge signal (green light) is on. You may leave volume turned "on" in charger; however, you must never transmit while radio is in the charger. (3) External antenna jack located on " press to talk" switch side near the top of the radio provides an extended range when an antenna is used with this set. All Radiation Monitoring Team radios are provided with external antennas. (4) A compatable headset is available for use with this portable. When connected to the headphone plug (on top of set) the headset earphones and microphone displaces i the built in speaker and microphone. This accessory provides noise control when required. B. Radio Operation . _) s (1) Knob on top marked F1 and F2 is a frequency selector switch. On the plant portables F1 works on CH3 of radio console and should be used in the Turbine Bldg i and outplant areas. F2 works on CH8 of the radio +{ console and should be used in the Auxiliary Bldg. The radiation monitoring portables have F1 and F2 l banded together. (2) is the squelch control - it should be positioned to just remove extraneous receiving noises. (3) The knob marked Q d O Provides a choice of the coded position (left), private line position (center) and clear position (right). To protect your messages, always use the coded position. NEVER USE THE CENTER POSITION! (4) The red light on top will be on during transmitting. It is also a check for battery status. (Weak indicates low battery power.) (5) Operate radio similar to other portables, using the 2" distance between mouth and the microphone grill, speak s clearly, and say when your tran,smission is complete. ] Use reasonable volume and squelch. IBM l

3., l t-F3-5 ATTACHMENT B (Continued) Rev. 10 Page 39 ILLUSTRATION MOTOROLA PORTABLE HANDIE TALKIE MODEL MX350 t HEADSET CONTROL DO NOT USE! SQUELCH CONTROL CODED CLEAR ANTENNAN e aa o ? i O h VOLUME FREQUENCY 1 RED (c SELECTOR TRANSMITTING LIGHT 4 I m Q.}, l IBM r

F3-5 ATTACHMENT B (Continued) Rev. 10 Page 40 II. LOW BAND PAGING SYSTEM SYSTEM DISPATCHER HQEC TSC AND e CONTROL ROOM l RADIO CONSOLE / CHANNEL 7 / NSP RICE ST. r e 4 / RADIO l s HARDWIRE MINN f STATE EOC .m PROCEDURE ,.; / 1. To contact the System Dispatcher: Select channel 7, key.ne microphone, and say: " PRAIRIE ISLAND TO SYSTEM DISPATCHER." 2. To contact the Minn. State EOC (See Note f): Select channel 7, Irey the microphone, and say: " PRAIRIE ISLAND TO EMERGENCY OPERATIONS CENTER." l l l NOTES: (a) The Systeu Dispatcher can activate the receivers l l at the plant. Light alongside channel 7 will light l l and remain lit until reset. l l (b) The plant can activate the receiver at the System l l Dispatcher and the HQEC (when connected). l l (c) The state can activate the Prairie Island receiver. l l (d) Each station can ma utor eacn channel. l l (c) The liqEC can activate Lt e receiver at the plant. l l (f) The State EOC must first he manned and the l j l radio phone activated by the Duty Officer., l l l !!!M L

,; r 9-o 7 ii-F3-5 ATTACHMENT B (Continued) Rev. 10 Page 41 (' III. RADIO ALERT MONITOR SYSTEM '\\ W n .s h \\ k %g if . q,, s qr g -sb y j; ge q U N t(., \\~ / GENERAL The Radio Alert Monitor System is a one-way radio trantmission system from the plant to the receiver. The transmitter is located in the onsite Technical Support Center with receivers installed in the homes and/or offices of the following three groups: 1. Local Residents 2. Civil Defense 3. Prairie Island Emergency Organization Personnel The transmitter unit consists of: (a) message recorder; (b) message transmitter; (c)' microphone; (d) telephone answering unit; (e) telephone; and (f) code selector. When the Radio Alert Monitor System is activated, a tone will be heard by the receiver. The pre-recorded message will then be automatically played three times by the Alert Radio Message Unit. Upon completion of the trans-mission, the pre-recorded tape is then placed into the telephone answering unit. If an individual is not home when the unit is activated, a red light on the receiver will indicate that a message has been transmitted via the r Radio Alert System. That individual may then call the number indicated on ( his receiver (388-1233) and the pre-recorded tape will play the message over the phone. IBM

O F3-5 ATTACHMENT B (Crntinued) Rev. 10 Page 42 ~ The microphone will allow plant personnel to transmit messages which are not detailed and pre-recorded. The code numbers for the various receiver groups are: l. Local Residents - Ol' 2. Civil Defense - 04 3. Prairie Island Emergency Orgaaization Personnel -06 INSTRUCTIONS The following details some of the various specific operating instructions: A. To Record a Message Cassette: (1) Make sure that the remote control unit ' Mike Enable' and ' Transmit Enable' key switches are both off (Green). (2) Set tape unit selector switch to ' Record Announcement' - insert microphone in tape unit mike Jack. (3) Press tape unit ' Start' switch and record the prepared message. I (4) When recording the message, speak slowly and clearly about 3 "?g inches from the microphone. 1/. (5) Set tape unit selector switch to ' Check Announcemenc' - press ' Start' switch and listen to recording. (Adjust volume to desired level with tape unit ' Monitor Volume' Control) - if satisfactory, proceed. j B. To Test Entire Alert Sequence: (1) Insert proper recorded cassette in tape unit. 2 (2) Set tape unit selector switch to ' Answer'. (3) Set up the desired two-digit group code on encoder . Press 'P' (Page) button. Tones will be heard on the remote control unit. Adjust its volume control to the desired level. 4 (4) 18 seconds after the 2nd tone is heard, the 45 second recorded message will be heard 3 times. Then the unit will 4 j shut off. C. To Transmit an Alert Message: (1) Insert the proper recorded message cassette into the tape j unit. i IBM i t-

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F3-S ATTACHMENT H (Cont inueil) Rev. 10 } Page 43 (2) Set the tape unit selector switch to ' Answe r'. l (3) Turn the remote control unit ' Transmit Enable' key switch on. (Red 'XMIT' lamp will light.) (4) Set up' the desired two-digit group code on encoder press 'P' (Page) button. If other groups are to be alerted to receive the same message, enter the next code or codes as soon as the preceeding tones have finished. The rest of the. sequence is automatic - several seconds after the last tone has been transmitted, the recorded message will be transmitted 3 times - then the system will shut off. (5) Now, remove the message cacsette from the, tape unit and insert it into the telephone answering unit. D. To Send a I.ive Microphone Transmission: (1) Turn the remote control unit ' Mike Enable' andi' Transmit Enable' key switches both on. (Red lamps will light.) (2) Press ' Transmit' paddle on microphone and transmit desired message. l l l NOTE: (1) Any message sequence, recorded or live, l l can be aborted at any time simply by l l turning the remote control unit ' Transmit l l Enable' key switch off. (Green _' Test' l l lamp will light.) l l l l (2) None of the volume controls on any of the l l units affect the volume of the transmitted l l message. They are for your convenience l l in' monitoring the message. l l l l (3) In case the automatic alert sequence has l l been inadvertantly started without a tape l l in the message unit, simply press the l l blue ' Reset' button on the alert radio l l message unit - insert the proper tape l l message, and start the sequence over. l l l g IBM y L_. - -

0 PAGE 1 OF 12 l l EMERGENCY PLAN IMPLEMENTING l -(. l PRAIRIE ISLAND NUCLEAR JPROCEDURES l l GENERATING PLANT l l l NORTHERN STATES POWER COMPANY Number: F3-6 Rev: 4 l l History Copy l l a Retention Time: Lifetime l l l TITLE: l l Supt ad Prote ion l l l Approved By: /) l ACTIVATION AND OPERATION OF l l gh l TECHNICAL SUPPORT CENTER l l Pldn(Ranagergt l l OC Date: f-hb N l l l 1 l I I l 1.0 PURPOSE l l l l l The third floor of the Administration Building (First l l Floor Office Annex), is designated as the onsite Technical l l Support Center (TSC) and shall be used by plant management, l l technical and engineering groups, and NRC representatives l l l as a center outside the main control room from which l l support for emergency operating conditions can be provided. l l The TSC shall be activated when an Alert, Site Area, or l l General Emergency is declared. l l 1 ,e l The purpose of this instruction is to describe the activa-l (" l Support Center. l l tion, staffing and monitoring requirements of the Technical l l l l 2.0 APPLICABILITY l l l l This instruction shall apply to all Shift Supervisors, l l Emergency Directors and all members of the technical staff. l l l l 3.0 PRECAUTIONS l 1 I l (1) All unnecessary personnel shall be evacuated from the l l Technical Support Center when the Technical Support l l Center has been activated. l + l 1 l (2) Monitoring of the Technical Support Center for direct l l radiation and airborne radioactive materials (particu-l l late and iodine) shall be performed to ensure the l l habitability of the Technical Support Center. l l l l (3) Protective actions for individuals located in the l l Technical Support Center shall be taken at the pre-l l scribed levels of direct radiation or airborne radio-l l activity. l l 1 I I (_.. l I i i l l IBM

a i F3-6 I R;v. 4 ) Page 2 l 4.0 PROCEDURE

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\\ ~' 4.1 Activation & Operation of TSC 4.1.1 Activation of the Technical Support Center shall occur whenever an Alert, Site Area or General Emergency j is declared. Activation of the TSC may occur during normal work hours or during off-normal work hours: (a) During normal work hours, the Technical Support Center shall automatically be activated whenever an Alert, Site Area, or General Emergency is declared, as announced over the public address system. All members of the Operations Committee and other designated engineers and staff members shall report to the'TSC; or (b) If activation of the Technical Support Center occurs during the off normal hours of the plant technical staff, the Emergency Director shall designate the Shift Emergency Communicator (SEC) to contact all Emergency Organization personnel, in accordance with F3-5. 4.1.2 All non-essential personnel shall evacuate the TSC area, when the TSC has been activated. w u 4.1.3 The Technical Support Center Coordinator shall: ,) (a) Designate an individual to establish monitoring of the TSC. environment and take appropriate protective actions as specified in Section 4.2 (b) Designate an individual to maintain the Emer-gency Director's Log. 2 1 (c) Assume control of the Emergency Director phones. (d) Ensure that the TSC doors are closed and initiate the TSC cleanup system, in accordance with Section 4.3. (e) Issue, or designate an individual to issue dosi-metry to all personnel in the TSC. Request all a individuals to log their name, TLD # and dosimeter reading on PINGP #652, (Figure 3) Emergency Center Activation Exposure Record. 4 w i IBM

f! 11 F3-6 Rev. 4 ,4. Page 3 (f) Designate engineers to establish telephone links at f' the TSC plant status board and in the Control Room, ( for pdrposes of plant status information transfer. The TSC consunicator shall use Figure 4 (PINGP #653) to log plant status information. I l l NOTE: Telephone extensions, dedicated for the 1 4 s l Control Room communicator are behind l l each respective unit computer console, l l at the. corner of the SS Office. l I I (g) Ensure that communications have been established between all on site emergency operating centers u (Control Room, OSC and TSC area). (h) Designate an individual to operate the Data Recall System, as per F3-26. (i) Perform or designate an individual to assist the Emergency Director in the overall plant personnel accountability check, in accordance with F3-10. This should be delegated to the Supervisor Security and Services. (j) Establish appropriate office space in the TSC c~ for all emergency organization personnel (NSP and non-NSP representatives). See Figure 2. 1 (k) Interface with the-non-NSP representatives located in the Technical Support Center and lend assistance where necessary. (1) Inform the Radiological Emergency Coordinator of any significant changes in radiation levels or airborne activity. If habitability is of concern, request radiological surveys of the TSC. The REC should a::sume responsibility for establishing a routine sampling and monitoring program, as conditions permit. (m) Control the use of emergency equipment in the i TSC emergency locker (protective clothing, respiratory equipment, dosimeters, potassium iodide pills, etc.). (n) Upon the Emergency Directors request, ensure key I areas (e.g. Event Status, REC, etc) are prepared to [ conduct periodic briefings to update all personnel in the TSC of the current plant status. l (o) Update the TSC Status boards as necessary. IBM L

= ~ F3-6 Rtv. 4 Page 4 (p) When the Near-Site EOF has been activated, g establish communications between the TSC and

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) '-{ the EOF. i !h 4.1.4 Additional personnel _should be notified and requested to report to the Technical Support Center as deemed necessary. .4.1.5 As the emergency proceeds from the initial phase,. j (the period immediately following the emergency 1 initiation) into the recovery phase, all Protective Actions for radiological hazards in the Technical Support Center shall be consistent with the plant Radiation Protection Program. 4.1.6 The Technical Support Center shall remain activated 'until the emergency situation has been terminated i or as otherwise directed by the Emergency Director. 4.2 Radiological Monitoring f 4.2.1 Verify proper operation of the VAMP in the Technical Support Center: (a) Verify the VAMP in the Tech Support Center. (b) Verify or plug the VAMP in. .) 2 (c) Verify the white power light is on. A

j. i (d) If the VAMP fails (power loss, incorrect

I reading, etc.), contact the Radiation Protec-tion Group for additional radiation monitors.

4.2.2 The CAM is in a hot standby condition with the electronics energized and the blower, chart, and filter paper off. (a) Turn the blower switch to the ON position (located next to the re-i corder) to start the blower, strip chart recorder, and the filter paper l drive. l (b) Adjust the blower flow rate to 3 SCFM using the toggle switch located on the right side of the CAM. (c) Verify the CAM is in operation (i.e., 7 i verify the blower, filter, strip charts l are operating; meters are on scale, etc.). l s (4) If the CAM fails to operate properly, con- 'j tact the Radiation Protection Group for l,' additional sampling. l? (.. IBM l l 1 1 l- = - -. -L

i-j F3-6 + Rev. 4 j Page 5 i i' 4.2.3. Routinely monitor the VAMP and the CAM for h' direct radiation levels and airborne particu-late and iodine activity. l 4.2.4 Take the following Protective Actions based on readings from the VAMP or CAM. (a) VAMP (1) at about 15mR/hr - consider evacuating i all non-essential personnel from the Tech Support Center i (2) at 1 R/hr - evacuation to the Control Room is recommended. (b) CAM - particulate (1) ( 1 x 10 pCi/cc - no protective action necessary -6 (2) > 1 x 10 but ( 1 x 10 Ci/cc - consider use of respiratory '} protection and evacuation of all unnecessary personnel. -6 (3) > 1 x 10 Ci/cc - evacuation to the Control Room is recommended. (c) CAM - Iodine (See Figure 1) (1) at 40 MPC hours - consider evacuation of all unnecessary personnel (2) at 200 MPC hours - consider evacuation to the Control Room I I l NOTE: The Radiological Emergency Coor-l l dinator (REC) should recommend the l l use of potassium iodide pills l l (thyroid blocking agent) if the l l l projected thyroid exposure app-l l l roaches 25 Rem. l 7, l l k? IBM

~ F3-6 R:v. 4 Page 6 4.3 TSC Ventilation System 4.3.1 System Startup ( 37 (a) Close or ensure the TSC doors are closed. (b) At the TSC Control Panel, turn ES-82601 from " NORMAL" to " EMERGENCY". (c) Check the following indications at the TSC Control Panel (refer to Figure 5, TSC Clean-up System): (1) Filter Unit Trouble Light (Red light should be OFF). (2) The TSC Return Fan Stops and the Clean Up Unit Fan should start (Red "0N" Light should be lit). (3) Outside Air Isolation Damper (MD-3460?) sheuld close (Green "CLOSE" light should be lit). (4) Return Fan Isolation Damper (HD-34603) should close (Green "CLOSE" light should be lit). (5) Outside Air Volume Control Damper (MD-34604) should modulate open (Red " MODULATE" light should be lit). (6) Clean Up Unit Volume Control Damper (HD-34605) should modulate open (Red " MODULATE" light should be lit).._ ) (7) In the " EMERGENCY" mode, the TSC should be at a "/ positive pressure of approximately 0.125 inches W.G. as indicated by TSC Positive Pressure Gauge 82608. (d) Tae TSC air temperature may rise for a period of time following startup. Several hours are necessary-to cool the system down and subsequently again cool the TSC. 4.3.2 Trouble Alarm (a) The Filter Unit Red Trouble light will be lit if the following occurs: (1) TSC Cleanup Unit Fan Differential Pressure Lo (DPIS-82321). (2) Prefilter Differential Pressure Hi (DPIS-82331). (3) ist HEPA Filter Differential Pressure Hi (DPIS-82332). (4) Charcoal Filter Differential Pressure Hi (DPIS-82333). (5) 2nd HEPA Filter Differential Pressure Hi (DPIS-82334). IBM i

t r3-6 Rtv. 4 i Page 7 (B) If the above alarm should be lit, investigate C the local dp filter indications. The filters may k require changing. 4.3.3 System Shutdown (a) At the TSC Control Panel, turn ES-82601 from " EMERGENCY" to " NORMAL". (b) Check the following indications at the TSC Control Panel (refer to Figure 5, TSC Clean-up System): (1) Filter Unit Trouble Light (Red light should be OFF). (2) The TSC Return Fan Stops and the Clean Up Unit Fan should start (Green "0FF" light should be lit). [ (3) Outside Air Isolation Damper (MD-34602) i should open (Red "0 PEN" light should be lit). f I (4) Return Fan Isolation Damper (MD-34603) should a open (Red "0 PEN" light should be lit). J (5) Outside Air Volume Control Damper (MD-34604) f should close (Green "CLOSE" light should be lit). s:- (6) Clean up Unit Volume Control Damper (MD-34605) should close (Green "CLOSE" light should be lit). p! 1 l I c l ) (-

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c O. RECALL DISPLAY COMPUTER EMERGENCY TERMINAL / PRINTER LOCKER ECM NWS/ MET DATA DISP W ACQUISITION TELECOPIER PLUME HAP COMPUTER MODEM / PRINTER 1 FIELD SURVEY GDE ORER TEAM TERMINAL RADIO SYSTEM TAPE RECORDER C0KtUNICATIONS .1 X g TI T y i-f (XJ'l s e oo o o o g s NRC D OOO RAD PROT TECH C NSP ENGR AREA C SUPPORT D O O C gg ENGR'S CON ENCE / Q_ Q CONSOLE e 7' /_ / m / c4 / f t PLANT E ENT IN1ERceH,N AC A DE COM ROL CABINET DOSE PROJECTION RADIATION PROTECTION EQUIPMENT STATUS BOARD CHALKBOARD EMERGENCY ORGANIZATION PLANT SURVEY STATUS BOARD STATUS BOARD E El i 1.<, i TECHNICAL SUPPORT CENTER e W

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F3-6 Rt.v. 4 Page 10 PINGP 652, Rev. 0 ' s Page 1 of 1 I Retention: Lifetime ~ FIGURE 3 EMERGENCY CENTER ACTIVATION EXPOSURE RECORDS DATE: CENTER: l l l l l l NAME I TLD NO. I DOSIMETER READINGS I NET l .) IN OUT l t i I I I I I I I I I I I I I 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 4 I I I l l l AV l l l l l AJ LA l l l l 44M aW l l D l 7 T4P'1 l l lAd l l lW l l l l I l l I I I I I I I I-I i I I I l I e .~ l l I I I I l i I I I I l l I I I I l l I I i l i I l 1 I I I I I l l I I I I I i, I I I I I l l I I I I I I I I 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 ~j l i I I I i IBM m

n EVENT STAT. PINGP 653 Rev. 1 Page 1 Of 1 Retention: Life PRAIRIE ISLAND UNIT # TIME NOTE: Indicates Parameter Not Updated RCS PARAMETERS NSSS LOOP PARAMETERS LOOP A B 1. RCS Pressure psig 1. Wide Range Th ( F) 2. Trend UP/DOWN/ STABLE 2. Wide Range Tc ( F) 3. Pressurizer Level 3. Incore Thermocouples ( F) (Max / Avg) 4. Trend UP/DOWN/ STABLE 4. Subcooling Margin ( F/ psi) 5. Pressurizer Heaters ON/ RCP Status (ON/0FF) RCS MAKE UP FLOW STATUS S.G. Pressure (psig) 1. SI, Flowrate ON/0FF, end (UP/DOWN/ STABLE) } 2. RHR, Flowrate ON/0FF, .G. Level, Wide Range (%) j 3. RWST Level Level, Narrow Range (%) e 4. Normal Charging, Flowrate ON/0FF, gpm

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ISOLATED, gpm

1. MSIV

.atus (OPEN/ CLOSED) 6. Accumulators psig AUX Feedwater Flow (gpm) CONTAINMENT PARAMETERS ondensate Storage Tank Lvl (%) 1. Containment Press / Temp psig F M_ _ PARAMETERS 2. Containment Rad Level 1. Diesel Generators ON/0FF 3. Sump B Level 2. Offsite Power YES/NO 4. Hydrogen Concentration 3. CC Normal YES/NO 5. Containment Spray ON/0FF, gpm 4. CL Normal YES/NO mxm 6. FCU ON/0FF TRAIN A TRAIN B $@Y C

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Shield Building Vent ON/0FF ON/0FF 33 6. AUX Building Special ON/0FF ON/0FF 7. Control Room Special ON/0FF ON/0FF 8. Spent Fuel Special ON/0FF ON/0FF w

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PAGE 1 OF 9 l l EMERGENCY PLAN IMPLEMENTING g i l PRAIRIE ISLAND NUCLEAR I PROCEDURES l 7 i l GENERATING PLANT l I \\ l NORTHERN STATES POWER CO'4P/dY INumber: F3-10 Rev: 5 l l l History Copy l l f IRetention Time: Lifetime l l 0 TITLE: l l Sup a Prote tion l l l Approved By: j l PERSONNEL ACCOUNTABILITY l l // l l l P1' ant Managej ' l l l O.C. Date: Y-A b N I I l I I l l l 1 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 I l l I I l 2.0

SUMMARY

l 1 l l In the event of a plant evacuation, the personnel accountability l l check within the Protected Area should be completed within thirty l ~ l (30) minutes following the evacuation to allow an orderly search l l for missing personnel. The Emergency Director is responsible for l l the completion of this personnel accountability and may delegate l l this authority to the Guard Force and the respective Coordinators l l at each of the emergency operating centers. All personnel l l accountability results SHALL be forwarded to the Emergency l l Director. l l l l l 3.0 APPLICABILITY l i I T.;iIS INSTRUCTION SHALL APPLY TO ALL PLANT PERSONNEL. l l l l l l 4.0 PRECAUTIONS l l l l (1) All individuals remaining in the Protected area following l l a plant evacuation SHALL be verified by a direct contact l l (either in person or verbally) and their location, name l l and badge # recorded on the personnel accountability l l sheet. Figure 1 (PINGP #601). l l 1 l (2) The Emergency Director should ensure that this instruction l l is completed. l (. I I l l l l l l IBM e

w, i-F3-10 Rev. 5 Page 2 3 r (3) Wen the initial accountability is completed, access to -Y the Protected Area shall require coordination between the t Emergency Director, Radiation Protection Group, and the Supervisor Security and Services to ensure an ongoing personnel accountability exists throughout the duration of 1.he emergency i situation. (4) To ensure a continuous personnel accountability, an accountability check should be completed once per i shift (every 8 hours) or when requested by the Emergency Director (See Step 5.12). i~ 5.0 PROCEDURE 5.1 During an evacuation, all nonessential personnel SHALL-proceed to the designated assembly area. l l l NOTE: The designated assembly area may be either the l l Screenhouse or the Construction Office Building. l } l Listen for instructions over the public address l l address system prior to evacuating. l I l 4 5.2 As soon as the evacuation alarm sounds, the CAS operator SHALL type EEV (Emergency Evacuation) into the security computer to activate the OSC, TSC and the Screenhouse { accountability card readers. 5.3 As soon as the evacuation alarm sounds, all personnel in the TSC and OSC SHALL insert or ensure that their badges are inserted into the TSC or OSC card readers. 5.4 As soon as all OSC personnel have inserted their badges into the OSC card reader, the OSC Coordinator should inform the Supervisor Security and Services in the TSC. I 5.5 Wen it has been verified that all badges (OSC and TSC) have i. been inserted into the card readers, the Supervisor Security l' and Services shall then cause the accountability report to be run. 5.6 The OSC Coordinator should: 5.6.1 Designate an individual to perform a Control l Room Accountability, listing all Control Room i Personnel and out plant operators on Figure 1 (PINGP #601). ) l 5.6.2 Ensure that the Control Room Accountability sheet, d l-PINGP #601 is transferred to the Supervisor Security and Services in the TSC, as soon as it is completed. i; IBM I t L

F3-10 Rev. 5 Page 3 CE 5.7 Actions Of Personnel Evacuating The Plant Shall Be As Follows: m 5.7.1 _If the Construction Office Building is the designated assembly point: (1) All Personnel Shall evacuate via the Guard House or as designated by the Security Force. (2) All Personnel Shall give their badge to the Security Force member as they i exit the protected area. (3) All Personnel Shall proceed to the i Construction Office Building and 1 ' assemble in the designated areas, 4 as indicated (See Figure 2). 5.7.2 If The Screenhouse Is The Designated Assembly ) Point: .I e i I (1) All Personnel Shall evacuate the plant and enter the Screenhouse through the east door. CS (2) All Personnel Shall file through the Screenhouse, as indicated on Figure 3, and insert their badge into the Screenhouse Accountability Card Reader. I l l CAUTION: Do not insert badge into the card l l reader outside the Screenhouse east l I door. l l l (3) After each badge has been inserted into the Screenhouse Accountability Card Reader, all Personnel Shall follow the assembly route (See Figure 3) and proceed to the Accountability Holding Area. i I I l CAUTION: Do not exit the Screenhouse until instructed. I I I i; a o IBM

i 'i F3-10 Rev. 5 Page 4 s 5.8 The Security Force action SHALL be as follows: rI]) .a 5.8.1 If the_ Construction Office Building is the designated assembly point, the Security Force action SHALL be as follows: (a) The Security Force shall collect all badges from personnel as they leave the protected area via the Guard House. I I l NOTE: Evacuating personnel need not stop at l l the Portal Monitor in the Guard House I or at Access Control. l l 1 b. The Security Force SHALL insert all badges into the two (2) Guard House exit card readers as soon as possible. c. As soon as all badges (evacuated personnel, OSC personnel and TSC personnel) have been inserted into the card readers, the Security Shift Super-visor should obtain a list of unaccounted personnel from the security computer by , ts, c typing in EVACNT (Evacuation Accountability). )

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-I j l NOTE: This unaccounted personnel list l l l includes missing personnel and those l l who have not inserted their badges into thel l card readers, e.g.,' Control Room Operators l l l and out plant operators. I l l l l (d) As soon as the " Unaccounted Personnel List" is generated, the Security Force SHALL bring this list to the Supervisor Security and Services in the TSC. 5.8.2 If the Screenhouse is the designated assembly point, the Guard Force action SHALL be as follows: i (a) The Security Force SHALL proceed to the i Screenhouse to assist in the evacuation and accountability. l (b) The Security Force SHALL ensure.that all personnel evacuating insert their badges into the accountab lity card reader. t (c) The Security Force SHALL ensure all personnel -s proceed to the accountability holding area. 4 IBM

b- -i F3-10 f Rev. 5 Page 5 ( (d) As soon as all badges have been inserted into the screenhouse accountautlity card reader, the Security Officer posted at the screenhouse assembly point Shall notify the security shif t supervisor (Ext. 324). (e) As soon as all badges (evacuated personnel, OSC personnel and TSC personnel) have been inserted into the card readers, the security shift supervisor should obtain a list of unaccounted personnel from the security computer by typing in EVACNT (Evacuation Accountability). l l NOTE: This unaccounted personnel list l l includes missing personnel and those l l who have not inserted their badges into thel l card readers, e.g., Control Room Operators l l and out plant operators. l I l (f) As soon as the " Unaccounted Personnel List" is generated, the Security Force SHALL bring this list to the Supervisor Security and Services '? in the TSC. 5.9 The Supervisor Security and Services, or designee shall then compare the " Unaccounted Personnel List" with the " Emergency Operating Center Perscnnel Accountability Check", Figure 1 (PINGP Form #601), to determine if all personnel are accounted for. 5.10 If all personnel are not accounted for, re-check all Emergency Operating Centers, the Guard House and the applicable assembly point for missing personnel. I 5.11 If all personnel cannot be acccunted for, the Emergency Director SHALL initiate a search for missing personnel, in accordance with F3-11, " Search and Rescue". 1 5.12 Once each shift (every 8 hours) or when requested by the Emergency Director, a personnel accountability check onsite should be conducted as follows: 5.12.1 -The Supervisor Security and Services shall request I the CAS Operator (Ext. 318) to activate the OSC and TSC card readers. The CAS operator SHALL then type EEV (Emergency Evacuation) into the security computer. 5.12.2 All personnel in the TSC and OSC SHALL then insert ( their badges into the TSC and OSC card readers. IBM

F3-10 6 Rev. 5-Page 6 U%g ,r 5.12.3 As soon as.all OSC personnel have inserted their ) badges into the OSC card reader, the OSC Coordinator should inform the Supervisor Security and Services in the TSC. 5.12.4 When it has been verified that all badges (OSC & TSC) have been inserted into the card readers, the Supervisor Security and Services shall then cause the accountability report to be run. 5.12.5 The OSC Coordinator should: (a) Designate an individual to perform a Control Room Accountability, listing all Control Room. Personnel and out plant operators on Figure 1 (PINGP #601). (b) Ensure that the Control Room Accountability Sheet, PINGP #601, is transferred to the Supervisor Security and Services in the TSC, as soon as it is completed. 5.12.6 As soon as all OSC and TSC personnel have inserted their badges into the card readers, the Security Shift Supervisor should obtain a list of unaccounted personnel from the security computer by typing in g@ EVACNT (Evacuation Accountability). 'cv l l l NOTE: This unaccounted personnel list l l l includes missing personnel and those who I I have not inserted their badges into the l l card readers, e.g., Control Room operators l l and out plant operators. l l l 5.12.7 As soon as the " Unaccounted Personnel List" is i generated, the Security Force SHALL bring this list to the Supervisor Security and Services in the TSC. 5.12.8 The Supervisor Security and Services or designee shall then compare the " Unaccounted Personnel List" with the " Emergency Operating Center Personnel Accountability Check", Figure 1 (PINGP Form #601), to determine if all personnel are accounted for. 5.12.9 If all personnel are not accounted for, re-check all i Emergency Operating Centers and the applicable assembly point for missing personnel. ,w 5.12.10 If all personnel cannot be accounted for, the "j Emergency Director SHALL initiate a search for missing personnel, in accordance with F3-11, " Search l and Rescue". l IBM k 1

i .) ) F3-10 i Rev. 5 Page 7 PINGP #601, Rev. O FIGURE 1 EMERGENCY OPERATING CENTER PERSONNEL ACCOUNTABILITY CHECK LOCATION: Control Room I i Technical Support Center i l Operational Support Center l I Radiation Protection Group i i Date: Time: I NAME Badge # NAME Badge # 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 I I I l l l l Y*?#' 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 1 I I I I l l 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 l l I I I I I I I I I I I I l l I I I I ( l I l~ l I Completed by : IBM

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7 [, t i i PAGE 1 OF 3 I i l l EMERGENCY PLAN IMPLEMENTING l i l PRAIRIE ISLAND NUCLEAR l PROCEDURES l i l GENERATING PLANT l l l NORTHERN STATES POWER COMPANY INumber: F3-29 Rev: 2 l l l History Copy l i l Retention Time: Lifetime l l l TITLE: I Sup Rad /r.ection l l l Approved By:- l l 1 l l EMERGENCY SECURITY l l l Pldft 'Manapr PROCEDURES l l OC Date: 9. F-N l l l I I I l l 1.0 PURPOSE l l l l The purpose of this instruction is to delineate the responsibilities l r l of the Security Force during emergency conditions at Prairie Island. l l [ l I I I l 2.0 APPLICABILITY l ] I I l This instruction shall apply to all members of the plant Security Force. l l l l l l C.. l 3.0 DidCUSSION l j I I l All security requirements shall be in accordance with the Prairie l l Island Nuclear Generating Plant Security Plan and the Guard Force l l Section Work Instructions. l l l l l l 4.0 PRECAUTIONS l l l l 4.1 Prairie Island security officers shall not make any information l l l releases to members of the news media or the public. All l l Inquiries by the news media shall be directed to the NSP l l Communications Department at NSF Headquarters or at the Joint l l Public Information Center (JPIC) located at the Minnesota State l l Capitol in St. Paul. l l l l l 4.2 Various plant personnel are required to report to Onsite l l Emergency Operating Centers during plant emergencies. Due regard l l for plant conditions as well as maintaining security of the plant l l should be considered to expedite allowing these key personnel l 1 l entrance to the Protected Area and Vital areas during emergencies. l I I l 4.3 All Security Force members shall obtain and zero a 0-1R dosimeter l l at the beginning of each shift. During emergency conditions, l l l the Security Officers should periodically, or when requested, l j read their dosimeters. ~ l ( l I I i I l IBM

( F3-29 L Rev. 2 Page 2 i 5.0 PROCEDURE 5.1 During an emergency, all Security Officers shall continue with their normal dut.ies, unless directed otherwise. 5.2 When requested by the Shift Emergency Communicator (SEC), a Security Force member shall be designated to proceed to the Technical Support Center (TSC) to control the telephone switchboard. This Security Officer shall control the switchboard until relieved by a backup communicator or the emergency situation is terminated. 5.3 When the evacuation alarm sounds: 5.3.1 All Security Officers, with t.be exception of the SAS Operator i shall evacuate to the guardhouse for further instructions. I I l NOTE: The SAS Operator should evacuate when l l l directed by the Emergency Director. l l l 5.3.2 The Security Force shall assist in the evacuation of I pt.:sonnel to the designated assembly point, which will normally be the Construction Office Building. l l l NOTES: (1) To speed evacuation from the Protected l l Area, it may be beneficial to open the l l vehicle gates and allow personnel to l l exit there. l l l l (2) It will not be necessary to require l l personnel to stop at the portal l I monitors. Collect all ID badges and l I process badges so an early printout l l of persornel remaining within the l l Protected Area can be obtained. l l l } 5.3.3 If the evacuation of personnel is via some route other I than through the guardhcuse, instruct personnel of the designated evacuation point and control access via this exit as per the Guard Force Section Work Instructions. 5.3.4 Perform a check of all areas immediately surrounding the Protected Area so that all personnel are notified of the evacuation in progress by having the patrol guards: k ..J t I a 1 IBM j

i F3-29 Rev. 2 Page 3 I s (1) Make continuous inside rounds with the patrol vehicle, especially on the South and East side of the plant, using the loudspeaker in the patrol vehicle, if necessary, to ensure all people are following directions of the Emergency Director; and (2) Survey all trailers, warehouses and out buildings, to ascertain that all persons are aware of and follow the directions of the Emergency Director. t 5.4 The Security Force shall assist in the personnel accountability, as a per F3-10, " PERSONNEL ACCOUNTABILITY", and the Guard Force Section Work Instructions. 7 5.5 When the initial accountability is complete, access to the Protected Area shall require coordination between the Emergency Director, Radiation Protection Group and the Supervisor Security and Services or designee to ensure an ongoing personnel accountability exists throughout the duration of the emergency condition. 5.6 An accountability check should be completed once per shift (every C_. - 8 hours) to ensure a continuous personnel accountability, or when requested by the Emergency Director. 5.7 The Security Force shall make all attempts to expedite entrance to i the Protected Area by Emergency Organization personnel. I I l NOTE: The Security Force shall consider plant l I l conditions as well as plant security. l l l 5.8 When requested by the Emergency Director or the Radiation Protection Group, the Security Force should assist the Radiation l.i Protection Group in establishing and controlling a Secondary l Access Control Point, in accordance with F3-21, " Establishment of r a Secondary Access Control Point". 5.9 The Security Force should assist the Assembly Point Coordinator in -I i personnel accountability, crowd control, and traffic control. 5.10 During an Alert, Site Area, or General Emergency, the Security vehicle should be positioned at the plant entrance, if conditions j permit, or at an alternate location, to control access to the plant site. ?"G IBM

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