ML010300342
| ML010300342 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 01/23/2001 |
| From: | Entergy Nuclear Generation Co |
| To: | Office of Nuclear Security and Incident Response |
| References | |
| -RFPFR | |
| Download: ML010300342 (67) | |
Text
NUCLEAR ORGANIZATION CONTROLLED DOCUMENT TRANSMITTAL NOTICE DOCUMENTI TITLE:_ cEt-Tl- 1/21, ~ E10-T10- 'Yee TO: MAIL:
CONTROLLED COPY NO.: 1/TNMITTAL NO.: 6')r ) DATE:
FOR DOCUMENT CONTROL USE ONLY
/X 1. The attached controlled document(s) are transmitted fcr your use.
Please insert/remove as indicated on the attached Change Instruction Notice. Please check Block 6, sign this form and return upon receipt.
/7 2. The controlled document(s) listed on the attached Change Instruction Notice have been retired from use. Please check Block 7, sian this form and return upon receipt.
/7 3. This is your notice. The document(s) indicated above were transmitted to you on . Please check the status of your controlled copy, sign this document and return.
If you do not have these documents, check Block 5 and a new copy will be issued.
/_7 4. Your name has been removed from the Distribution List of the controlled document listed above. Please check Block 7, sign this form and return it with the document to the Document I Control SuDervisor.
COPY HOLDER CHECK ONE
/7 5. I am not currently in possession of the above documents. Please issue another set to me.
/7 6. i have received from the sender the material and attachmenzs as indicated above, and i have updated my controlled manual accordingly.
/7 7. i am returning the documents listed above.
PLEASE SIGN AND RETURN TO: Controlled Document Clerk, MAIL STOP #19 NO ENVELOPE REQUIRED FOR INTERNAL COMPANY MAIL Entergy, Controlled Document Clerk Pilgrim Nuclear Power Station 600 Rocky Hill Road, Support Building Plymouth, Massachusetts 02360 Date Signature of Holder Ac04 Controlled Copy No.
CHANGE INSTRUCTION NOTICE (CLN)
Transmittal No.:04- **3/ Date: 3 /
Pi._-. update your copy of with the attachments to this transmittal as instructed below.
REMOVE AND DISCARD {REV. NO. I L.NSERT REV. N'O. I I ___
c~C &31 I
/
11 1
_ _ _ _ _ _ _~ _ _ _ _ _ __
~3 /I ~ _ _
_ ~~I_
__ _ _ _ I _
1 _ ___ _ _
IPNPS I Emergency Plan Implementing Procedure Manual I Number:
N/A RType H8.24 TABLE OF CONTENTS Effective Number Title Revision Date EP-IP-100 Emergency Classification and Notification 13 01/23/01 EP-IP-200 On-Call Emergency Director 8 04/04/00 EP-IP-201 Emergency Plant Manager 1 05/14/99 EP-IP-202 Company Spokesperson 2 03/15/00 EP-IP-210 Control Room Augmentation 7 12/12/00 EP-IP-220 TSC Activation and Response 11 11/15/00 EP-IP-229 TSC/OSC Equipment Operation 5 07/25/00 EP-IP-230 OSC Activation and Response 3 11/15/00 EP-IP-231 Onsite Radiation Protection 5 07/25/00 EP-IP-240 Emergency Security Organization Activation and 8 03/15/00
Response
EP-IP-250 EOF Activation and Response 8 07/25/00 EP-IP-251 Offsite Radiation Protection 5 12/26/00 EP-IP-252 Facilities Support 6 09/28/99 EP-IP-253 Relocation of the EOF 3 07/13/00 EP-IP-254 Communications Support 2 12/06/00 EP-IP-259 EOF Equipment Operation 3 05/24/00 EP-IP-300 Offsite Radiological Dose Protection 3 01/19/00 EP-IP-310 Radiation Monitoring Team Activation and Response 4 11/15/00 EP-IP-315 Personnel Monitoring Team Activation and Response 4 05/24/00 EP-IP-330 Core Damage 2B 06/19/98 EP-IP-400 Protective Action Recommendations 8 01/23/01 EP-IP-410 Evacuation/Assembly 4 05/24/00 Page 1 of 2 Revision 64 01/23/2001 01/23/2001 Page 1 of 2 Revision 64
I PNPS I Procedure Emergency Manual Plan Implementing Number: N/A I I
RType H8.24 TABLE OF CONTENTS Effective Number Title Revision Date EP-IP-420 Search and Rescue 2 11/15/00 EP-IP-440 Emergency Exposure Controls 5A 04/08/98 EP-IP-501 Transport of Contaminated Injured Personnel 3 05/24/00 EP-IP-520 Transition and Recovery 4 12/31/99 Revision 64 01/23/2001 01/23/2001 Page 2 Page of 2 2 of 2 Revision 64
RTYPE H8.24 PILGRIM NUCLEAR POWER STATION Procedure No. EP-IP-100 EMERGENCY CLASSIFICATION AND NOTIFICATION Stop Think Act Review SAFETY REVIEW REQUIRED SAFETY RELATED EP-IP-100 Rev. 13
REVISION LOG REVISION 13 Date Originated 9/00 Paaes Affected Descriotion 5,6.27 Revise to include design basis core cooling requirements (2/3 core height with Core Spray) specified in EOP-01.
8 Add new definition for radiation monitor readings.
27 Revise EAL 1.4.1.4 and EAL 1.4.1.3 with new EAL values for Drywell and Torus High Range Radiation Monitors.
REVISION 12 Date Originated 1/00 Paaes Affected Description All All pages formatted to reflect the updated Procedures format.
Revision bars are not shown for reformatting.
8-10,14 Revise titles.
41 Revise titles, editorial changes, and changes for new CANS.
42 Revise titles and changes for new CANS.
EP-IP-100 Rev. 13 Page 2 of 47
TABLE OF CONTENTS Pace 1 .0 P UR P O S E ........................................................................... .......... .................... 5 2 .0 R E F E R E NC E S .................................................................................................. 5 3 .0 DE F INIT IO NS .................................................................. ................................ 5 4 .0 R E S P O NS IBILITIE S ......................................................................................... 9 5 .0 P R O C E D UR E. .................................................................................................. 9 5.1 RECO G NIZING AN EM ERG ENCY ....................................................... 9 5.2 INITIAL DECLARATION OF AN EMERGENCY FROM T HE C O NT R O L R O O M........................................................................ 10 5.3 WHILE IN A CLASSIFIED EMERGENCY ............................................. 11 5.4 T R A NS ITO R Y EV E NT S ........................................................................ 13 5.5 DOWNGRADING EMERGENCY CLASSIFICATIONS ........................... 14 5.6 TRA N SIT IO N TO R EC O VERY ............................................................... 14 5.7 INITIAL NOTIFICATION FORM DESCRIPTION ................................... 15 5.8 FOLLOW-UP INFORMATION FORM DESCRIPTION .......................... 17 0 .0 R E C O R D S ........................................................................................................ 18 7 .0 A T T A C HME NT S ............................................................................................... 19 ATTACHMENT 1 - UNUSUAL EVENT NOTIFICATIONS CHECKLIST ............ 20 ATTACHMENT 2 - ALERT NOTIFICATIONS CHECKLIST .............................. 21 ATTACHMENT 3 - SITE AREA EMERGENCY NOTIFICATIONS CHECKLIST 23 ATTACHMENT 4 - GENERAL EMERGENCY NOTIFICATIONS CHECKLIST. 25 ATTACHMENT 5 - EMERGENCY ACTION LEVELS ....................................... 27 EP-IP-100 Rev. 13 Page 3 of 47
TABLE OF CONTENTS (Continued)
Paae ATTACHMENT 6 - SAMPLE - INITIAL NOTIFICATION FORM ........................ 32 ATTACHMENT 7 - SAMPLE - FOLLOW-UP INFORMATION FORM ............... 35 ATTACHMENT 8 - SAMPLE - TERMINATION CHECKLIST ............................ 38 ATTACHMENT 9 - SAMPLE - ESSENTIAL INFORMATION CHECKLIST ....... 40 ATTACHMENT 10 - ACTIVATION OF THE EMERGENCY RESPONSE O R G A NIZAT IO N ........................................................... 42 ATTACHMENT 11 - DOCUMENT CROSS-REFERENCES .............................. 46 ATTACHMENT 12 - IDENTIFICATION OF COMMITMENTS ......................... 47 EP-IP-100 Rev. 13 Page 4 of 47
1.0 PURPOSE This Procedure provides instruction of the entry conditions at which specific emergency classifications must be declared, guidelines for the implementation of the Emergency Plan, and the process used to notify response personnel and organizations.
2.0 REFERENCES
(1] EP-AD-600, "EmergencyAction Level Technical Bases"
[2] EP-PP-01, "PNPSEmergency Plan"
[3] PNPS Technical Specifications 3.0 DEFINITIONS
[1] Adeauate Core Cooling - Heat removal from the Reactor sufficient to prevent rupturing the fuel clad. Three viable mechanisms for establishing adequate core cooling are defined: core submergence, spray cooling, and steam cooling.
(a) Submergence is the preferred method for cooling the core. The core is adequately cooled by submergence when it can be determined that RPV water level is at or above the top of the active fuel. All fuel nodes are then assumed to be covered with water and heat is removed by boiling heat transfer.
(b) Adequate SDray Cooling is provided, assuming a bounding axial power shape.
when at least one Core Spray subsystem is injecting into the RPV at the design flow rate (3,600 GPM) and RPV water level is at or above the elevation of the jet pump suctions (-175 in.). The covered portion of the core is then cooled by submergence while the uncovered portion is cooled by the spray flow. The required spray flow must be supplied by a single subsystem to ensure adequate spray distribution to all fuel bundles.
(c) Steam Coolina is relied upon only if RPV water level cannot be restored and maintained above the top of the active fue!, cannot be determined, or must be intentionally lowered below the top of the active fuel. The core is adequately cooled by steam if the steam flow across the uncovered length of each fuel bundle is sufficient to maintain the hottest peak clad temperature below the appropriate limiting value; 1500°F if makeup can be injected, 1800°F if makeup cannot be injected. The covered portion of the core remains cooled by boiling heat transfer and generates the steam which cools the uncovered portion.
EP-IP-100 Rev. 13 Page 5 of 47
Steam cooling with makeup capability is established by maintaining RPV water level above the Minimum Steam Cooling RPV Water Level (-150 in.) or RPV pressure above the Minimum Alternate RPV Flooding Pressure (a function of the number of open SRVs). In either case, the peak clad temperature is limited to 1500 0 F, the threshold for fuel rod perforation.
Steam cooling without makeup capability is established as long as RPV water level remains above the Minimum Zero-Injection RPV Water Level (-160 in.).
The peak clad temperature is permitted to rise to 1800'F, the threshold for significant metal-water reaction, to maximize the heat transfer to steam and to delay the need for RPV depressurization as long as possible. The minimum RPV water level at which adequate steam flow exists is higher when makeup capability exists because:
0
- The limiting fuel temperature is lower (1500 F). The higher limit of 1800'F is used only when cladding perforation cannot be avoided.
0 With injection, water at the core inlet is subcooled. Some of the energy produced by the core must then be expended in raising the temperature of the liquid to saturation and less steam will be produced to cool the uncovered portions of the core.
[2] Alert - Events are in progress or have occurred which involve an actual or potential substantial degradation of the level of safety at PNPS. Any releases are expected to be limited to small fractions of EPA Protective Action Guideline exposure levels.
"[3] BECONS - The PNPS community offsite notification system.
[4] Computerized Automated Notification System (CANS) - A computer-assisted system that, when activated, has the following capabilities:
(a) Activating the emergency pager system.
(b) Accepting calls from authorized responders to inform them of an abnormal or emergency condition at PNPS.
(c) Calling response personnel at their home or work phone to inform them of an abnormal or emergency condition at PNPS.
(d) Maintaining an updated list of personnel responding and their estimated time of arrival at their facility.
[5] Cannot Be Determined - The current value or status of an identified parameter relative to that specified in the Emergency Action Level (EAL) cannot be ascertained using all available indications (direct and indirect, singly or in combination).
EP-IP-100 Rev. 13 Page 6 of 47
is not
[6] Cannot Be Maintained Above/Below - The value of the identified parameter(s) making an able to be kept above/below specified limits. This determination includes in relation to the evaluation that considers both current and future system performance that the actual value of current value and trend of the parameter(s). It does not imply the parameter must first pass the specified limit.
parameter(s) is not able
[7] Cannot Be Restored Above/Below - The value of the identified those limits. This to be returned to above/below specified limits after having passed both current and future determination includes making an evaluation that considers of the parameter(s). It system performance in relation to the current value and trend operation does not imply any specific time interval, but does not permit prolonged (May be used beyond the limit without declaring the specified emergency classification.
in combination with Definition 3.0[6].)
specified in an EAL
[8] Controlled Process - A preplanned activity for which the conditions approved Procedure.
are anticipated to be or are intentionally exceeded as part of an (9] DNN - Digital Notification Network.
notification, any
[101 Emeroency Release is/is not in Proaress - For purposes of offsite progress' which:
release of radioactivity is considered 'an emergency release in
- Involves an actual or suspected Turbine Building or unmonitored release associated with the emergency event.
[11] ENS - NRC Emergency Notification System.
Director when
[12] Essential Information Checklist - The form used by oncoming Emergency in this Procedure.
relieving present Emergency Director of the responsibilities outlined Center and Corporate This form may also be used to provide information to Media personnel.
response duties
[13] Essential Personnel - Those individuals assigned specific emergency Procedures.
as identified in the PNPS Emergency Plan and Implementing periodic
[14] Follow-Uo Information Form - The form used to initiate and document emergency classification updates to offsite agencies.
which involve actual or
[15] General Emeraencv - Events are in progress or have occurred for loss of imminent substantial core degradation or melting with the potential Protective Action containment integrity. Releases can be expected to exceed EPA Guideline exposure levels for more than the area near the site boundary.
initial emergency
[16] Initial Notification Form - The form used to initiate and document classification notifications to offsite agencies.
EP-IP-100 Rev. 13 Page 7 of 47
[17] Non-Essential Personnel - Personnel who are not assigned specific emergency response duties.
[18] Primary System - The pipes, valves, and other equipment which connect directly to the Reactor Pressure Vessel (RPV) such that a reduction in RPV pressure will effect a decrease in the steam or water being discharged through an unisolated break in the system.
[19] Radiation Monitor Channel A and B Above/Below EAL Threshold Readinas - The value of both channels statements above or below a threshold reading may not apply when one channel is known to be inoperable or out of service. The determination of a valid reading on either channel that exceeds the EAL threshold constitutes that the intent of the EAL has been met and the associated classification should be declared.
[201 Release is above/below Protective Action Guides (PAGs) - PAGs are defined by the EPA as dose in excess of 1 rem TEDE or 5 rem CDE Thyroid. For purposes of offsite notification and in the absence of dose assessment data, an emergency release is considered above PAGs when the General Emergency criteria for EAL category 5.0, Radioactivity Release, Classification Sections 5.1, Effluent Monitors, and 5.2, Dose Projection & Environmental Measurements (EALs 5.1.1.4, 5.2.1.4, and 5.2.2.4) are met.
[21] Shutdown - As regards Reactor status, the Reactor is shutdown if the Reactor is subcritical (power decreasing) and below the heating range (IRM range 7).
[22] Site Area Emergency - Events are in progress or have occurred which involve actual or likely major failures of PNPS functions needed for the protection of the public. Any releases are not expected to exceed EPA Protective Action Guidelines exposure levels except near the site boundary.
[23] Sustained Loss - Loss of power supply, system or component operability for which the return to service has not been determined to be imminent. It does not imply any specific time interval, but prolonged operation is not permitted without declaring the specified emergency condition based on the potential for degraded plant safety.
[24] Termination - The point at which the event is no longer considered to be an emergency.
Termination of the emergency is formally identified by an Initial Notification message transmission and entry into Recovery.
[25] Transitory Event - An event in which PNPS exceeded an Emergency Action Level (EAL) but conditions improved prior to classification.
[26] Unusual Event - Events are in progress or have occurred that indicate a potential degradation of the level of safety at PNPS. No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs.
EP-IP-100 Rev. 13 Page 8 of 47
4.0 RESPONSIBILITIES
[1] The Operations Shift Superintendent, or the Control Room Supervisor if the Operations Shift Superintendent is incapacitated or away from the Control Room, shall be of responsible for the initial emergency classification declaration and implementation this Procedure.
[2] The Operations Shift Superintendent, or Control Room Supervisor if the Operations Director upon Shift Superintendent is unavailable, shall assume the role of Emergency as the initial declaration of any emergency classification and shall continue to function or Emergency Director until relieved of those duties by the on-call Emergency Director other qualified individual (i.e., Emergency Plant Operations Supervisor or off-shift Operations Shift Superintendent).
[3] The Emergency Director is the final authority for determining the emergency This classification level (initial classification, downgrading, or terminating to recovery).
authority may not be delegated.
[4] The Emergency Director is responsible for directing and overseeing notification of the on-call PNPS Emergency Response Organization.
for the
[5] The Control Room Operations Assistant or a designated alternate is responsible following:
(a) When directed, notifying the on-call PNPS Emergency Response Organization.
(b) Periodically checking on the status of personnel responding to the notification process.
(c) If CANS and BEEPS fail, Security is responsible for notifying on-call personnel using commercial telephone lines.
5.0 PROCEDURE 5.1 RECOGNIZING AN EMERGENCY
[1] When indications of abnormal conditions are received, personnel will verify the symptoms/indications and then compare them with the Emergency Action Leve!s (Attachment 5).
EP-IP-100 Rev. 13 Page 9 of 47
for
[2] Identify the highest emergency classification level (if multiple EALs are exceeded) which an EAL has been met or exceeded considering the following:
(a) If conditions warrant the issuance of Protective Action Recommendations (PARs), the classification of General Emergency will be made.
(b) If plant conditions indicate a possible radiological release or a release is in EALs progress or suspected, evaluate the applicability of offsite dose-based (category 5.2).
no (c) If a classification level was met or exceeded but the classifiable condition longer exists (a lesser classification level may or may not still be appropriate),
refer to Section 5.4, Transitory Events.
ROOM 5.2 INITIAL DECLARATION OF AN EMERGENCY FROM THE CONTROL Operations
[1] The Operations Shift Superintendent, or Control Room Supervisor if the Room operating staff:
Shift Superintendent is unavailable, shall announce to the Control (a) That an emergency has been declared.
(b) The emergency classification level.
has (c) That the Operations Shift Superintendent (Control Room Supervisor) assumed the role of Emergency Director.
[23 Conduct initial emergency notifications as follows:
NOTE Station personnel In the event the public address system is inoperative during notifications to plant personnel.
- at any time, determine alternate means to disseminate information to (a) For events which are classified as a General Emergency, complete the General Emergency Notifications Checklist (Attachment 4).
NOTE emergency If during the declaration process it becomes necessary to uoarade the simultaneous classification level before the actual initial notification transmittal, do not send classification notifications. Generate and send a new notification form with the appropriate level.
the Site (b) For events which are classified as a Site Area Emergency, complete Area Emergency Notifications Checklist (Attachment 3).
EP-IP-100 Rev. 13 Page 10 of 47
(c) For events which are classified as an Alert complete the Alert Notifications Checklist (Attachment 2).
(d) For events which are classified as an Unusual Event. complete the Unusual Event Notifications Checklist (Attachment 1).
[3] Contact (or direct an assistant to contact) the on-shift Radiation Protection Supervisor/Technician and direct them to review EP-IP-231 and assume the responsibilities of the Onsite Radiological Supervisor for emergency exposure controls until relieved by the on-call Onsite Radiological Supervisor.
[4] Contact (or direct an assistant to contact) on-shift Production Maintenance personnel not already involved in the emergency and inform them to report to the Control Room or the OSC to stand by for repair and corrective action activities if necessary.
[5] The Emergency Plant Operations Supervisor (EPOS) may relieve the Operations Shift Superintendent as Emergency Director until the on-call Emergency Director assumes responsibility for the position in the EOF.
[6] The on-shift Emergency Director will remain in the Control Room until relieved by the on-call Emergency Director.
5.3 WHILE IN A CLASSIFIED EMERGENCY (1] As soon as possible, but no later than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after event classification, ensure that the ENS or a commercial telephone line is continuously staffed with a knowledgeable individual to provide additional event notification and plant information to the NRC.
[2] Emergency response personnel will continuously review the Emergency Action Levels (Attachment 5) to ensure proper and appropriate event classification.
(a) If the declaration of a higher classification is warranted, conduct initial emergency notifications as follows:
(1) For events which are classified as a General Emergency complete the General Emergency Notifications Checklist (Attachment 4).
NOTE If during the declaration process it becomes necessary to uporade the emergency classification level before the actual initial notification transmittal, do not send simultaneous notifications. Generate and send a new notification form with the appropriate classification level.
(2) For events which are classified as a Site Area Emergency, complete the Site Area Emergency Notifications Checklist (Attachment 3).
EP-IP-100 Rev. 13 Page 11 of 47
(3) For events which are classified as an Alert, complete the Alert Notifications Checklist (Attachment 2).
(b) If a higher classification level was met but that classifiable condition no longer exists (a lesser classification level may or may not still be appropriate), refer to Section 5.4, Transitory Events.
(c) If the emergency conditions support downgrading the classification level, refer to Section 5.5, Downgrading Emergency Classifications.
(d) If the situation has been controlled and a state of emergency is no longer necessary, refer to Section 5.6, Transition to Recovery.
[3] Provide periodic updates (hourly or whenever conditions change) to the Commonwealth and local communities using Follow-Up Information Forms (Attachment 7). The upoate periodicity may be adjusted by mutual agreement with the Commonwealth.
[4] As conditions improve and additional personnel and resources become available, certain recovery activities (described in EP-IP-520) may be initiated prior to termination of the emergency.
[5] Turnover of the Emergency Director Position (a) The offgoing Emergency Director will provide the oncoming Emergency Director with a briefing of the emergency conditions and the status of offsite notifications.
(b) Items contained on the Essential Information Checklist (Attachment 9) will be used to facilitate the turnover briefing as follows:
(1) The offgoing Emergency Director may complete an essential Information Checklist and provide a copy to the oncoming Emergency Director to be used for the turnover briefing.
(2) The oncoming Emergency Director may complete an Essential Information Checklist while covering each item during conduct of the turnover briefing.
(c) Discuss any Protective Action Recommendations issued to offsite agencies as applicable.
EP-IP-100 Rev. 13 Page 12of47
5.4 TRANSITORY EVENTS
[1] For situations which begin under non-emergency conditions then experience events which ultimately result in a classifiable emergency, enter and execute the following Attachment which corresponds to the appropriate current classification level:
(a) Attachment 1, Unusual Event Notifications Checklist.
(b) Attachment 2, Alert Notifications Checklist.
(c) Attachment 3, Site Area Emergency Notifications Checklist.
[2] For situations which begin under non-emergency conditions, experience events which qualify as a classifiable emergency, and result in conditions which no longer meet a classification level:
(a) Consider the following items prior to entering Recovery:
(1) Conditions no longer meet an Emergency Action Level and it appears unlikely that conditions will deteriorate.
(2) Plant releases of radioactive materials to the environment are under control (within Technical Specifications) or have ceased and the potential for an uncontrolled radioactive release is acceptably low.
(3) The Reactor is in a stable condition and long-term core cooling is available.
(4) Offsite conditions do not unreasonably limit access of outside support to the Station and qualified personnel and support services are available.
(b) Complete and distribute an Initial Notification Form to specify the transitory event classification level and signify entry into Recovery (EAL number 0.0.0.0 is used to signify entry into Recovery).
(c) Exit this Procedure and enter EP-IP-520, "Transition and Recovery."
EP-IP-100 Rev. 13 Page 13of47
[3] For situations which begin in a classified emergency then experience events which ultimately result in:
(a) A return to the current classification level transitory event Complete and distribute an Initial Notification Form to specify the level.
classification level and signify return to the current classification NOTE result in a downgraded Transitory events which occur during an emergency cannot directly be performed separately.
,classification level or entry into Recovery. These actions must (b) A lower classification level or no lonoer meet a classification level event Complete and distribute an Initial Notification Form to specify the transitory classification level.
classification level and signify return to the current
[4] Return to Section 5.3.
5.5 DOWNGRADING EMERGENCY CLASSIFICATIONS below the Alert
[1] Once in an Alert or higher classification level, the decision to downgrade activated.
level shall only be made after the TSC, OSC, and EOF have been public address
[2] Have the Control Room make the following announcement over the system, TWICE:
level has "Attention all personnel, attention all personnel: The emergency classification been downgraded to a/an (applicable classification level)."
the lower
[3] Complete and distribute an Initial Notification Form to signify entry into emergency classification level.
[4] Return to Section 5.3.
5.6 TRANSITION TO RECOVERY Plan
[1] If entering Recovery from an Unusual Event, determine the need for a Recovery Event will not and support organization. Generally, the activities following an Unusual prior to event require the formation of a Recovery Organization or a transition period if recovery efforts termination and entry into Recovery. Refer to EP-IP-520 for guidance generation of following an Unusual Event extend beyond offsite notification and the required reports.
EP-IP-100 Rev. 13 Page 14 of 47
[2] Complete the Termination Checklist (Attachment 8).
(a) If conditions will allow for the termination of the emergency and entry into Recovery, exit this Procedure and enter EP-IP-520, "Recovery."
(b) If conditions do no support termination of the emergency and entry into Recovery, continue following the guidance provided in Section 5.3 of this procedure.
5.7 INITIAL NOTIFICATION FORM DESCRIPTION Upon activation of the EOF, the Control Room and EOF must coordinate the numbering
/sequence of notifications to ensure consecutive numbers are assigned to notification forms.
[1] Form Number: Notification form numbers are assigned sequentially from the start of the emergency. The sequence includes the Initial Notification Form as well as the Follow-Up Information Form.
[21 Block 1: Designation for notifications conducted as part of a drill or exercise versus an actual event.
[3] Block 2: Specifies the time, circumstance, and classification level applicable to the notification form as follows:
(a) The time and date denote the point at which the Emergency Director (or Operations Shift Superintendent) recognized and formally declared the new event classification level.
(b) The "entered" check box is used when the first Initial Notification Form is completed for an emergency.
(c) The "transitory" check box is used to provide a location to enter the highest classification level which was met during a transitory event.
(d) The "upgraded to" check box is used to provide initial notification of emergencies which require the declaration of a higher classification.
(e) The "downgraded to" check box is used to provide initial notification of emergencies which warrant lowering the classification level.
(f) The classification level boxes are used to indicate the classification applicable to the notification.
EP-IP-100 Rev. 13 Page 15 of 47
[4] Block 3: Provides the applicable EAL number and description for the specified classification level as follows:
the (a) For events with more than one EAL in the highest classification level, provide may EAL number for which the event was classified on. Additional EAL numbers be provided in the description section if desired.
(b) EAL number 0.0.0.0 is used to signify entry into Recovery.
is (c) A brief non-technical description (avoiding abbreviations and acronyms) of the EAL provided in enough detail to allow an understanding of the nature number (and the transitory event if applicable).
the relative
[5] Block 4: Provides indication of an emergency radioactive release and whether magnitude. If necessary, refer to EP-IP-400, "ProtectiveActions", to determine is above an emergency release is in progress, whether an emergency release necessary.
protective action guides, and what protective action recommendations are of the
[63 Block 5: Provides the most recent meteorological data obtained from any available sources.
by PNPS
[7] Block 6: Provides any applicable protective action recommendations made ERO personnel as follows (a) Protective Action Recommendations are only issued by PNPS in a General Emergency. If the classification level is not a General Emergency, the "No Protective Actions Necessary" check box shall be selected.
(b) If MEMA or MDPH representatives are present in the EOF and the classification is level is General Emergency, the "Provided to MEMA/MDPH" check box selected.
(c) If MEMA or MDPH representatives are not present in the EOF and the classification level is General Emergency, the appropriate protective action recommendations check boxes and affected subareas are selected.
and the
[8] Block 7: Indicates the time and date when transmission of the form was begun name of the individual performing the transmission.
and
[9] Block 8: Indicated the time and date when transmission of the form was received the name of the individual receiving the transmission.
[10] Block 9: Provides the protective action recommendations made by personnel when MEMA or MDPH representatives are present in the EOF (only applicable for General Emergency classifications).
[11] Block 10: Emergency Director approval signature.
EP-IP-100 Rev. 13 Page 16 of 47
5.8 FOLLOW-UP INFORMATION FORM DESCRIPTION
[1] Form Number: Notification form numbers are assigned sequentially from the start of the emergency. The sequence includes the Initial Notification Form as well as the Follow-Up Information Form.
[2] Block 1: Designation for notifications conducted as part of a drill or exercise versus an actual event.
[3] Block 2: Specifies the time and classification level applicable to the Follow-Up Information Form.
[4] Block 3: Indicates the prevailing trend for conditions at the Station.
[5] Block 4- Provides the applicable EAL number and description for the specified classification level as follows:
(a) For events with more than one EAL in the highest classification level, provide the EAL number for which the event was classified on. Additional EAL numbers may be provided in the description section if desired.
(b) A brief non-technical description (avoiding abbreviations and acronyms) is provided in enough detail to allow an understanding of the nature of the EAL number.
[6] Block 5: Indicates whether offsite assistance has been requested, the type of assistance, and the reason for the request.
[7] Block 6: Provides indication of an emergency radioactive release and the relative magnitude. If necessary, refer to EP-IP-400, "ProtectiveActions", to determine whether an emergency release is in progress, whether an emergency release is above protective action guides, and what protective action recommendations are necessary.
[8] Block 7: Provides the most recent meteorological data obtained from any of the available sources.
[9] Block 8: Provides any applicable protective action recommendations made by PNPS ERO personnel as follows:
(a) Protective Action Recommendations are only issued by PNPS in a General Emergency. If the classification level is not a General Emergency, the "No Protective Actions Required" check box shall be selected.
(b) If MEMA or MDPH representatives are present in the EOF and the classification level is General Emergency, the "Provided to MEMA/MDPH" check box is selected.
EP-IP-100 Rev. 13 Page 17 of 47
(c) If MEMA or MDPH representatives are not present in the EOF and the classification level is General Emergency, the appropriate Protective Action Recommendations check boxes and affected subareas are selected.
[10] Block 9: Indicates the time and date when transmission of the form was begun and the name of the individual performing the transmission.
and
[11] Block 10- Indicates the time and date when transmission of the form was received the name of the individual receiving the transmission.
made by
[12] Block 11 : Provides the protective action recommendations and their bases are present in the EOF PNPS ERO personnel when MEMA or MDPH representatives (only applicable for General Emergency classifications).
[13] Block 12: Emergency Director approval signature.
6.0 RECORDS
[1] The following documents are generated as a result of the implementation of this Procedure:
(a) Unusual Event Notifications Checklist (b) Alert Notifications Checklist (c) Site Area Emergency Notifications Checklist (d) General Emergency Notifications Checklist (e) Essential Information Checklist (f) Initial Notification Form (g) Follow-Up Information Form (h) Termination Checklist
[2] All records shall be forwarded to Emergency Preparedness for final disposition following the termination of the emergency.
EP-IP-100 Rev. 13 Page 18 of 47
7.0 ATTACHMENTS ATTACHMENT 1 - UNUSUAL EVENT NOTIFICATIONS CHECKLIST ATTACHMENT 2 - ALERT NOTIFICATIONS CHECKLIST ATTACHMENT 3 - SITE AREA EMERGENCY NOTIFICATIONS CHECKLIST CHECKLIST ATTACHMENT 4 - GENERAL EMERGENCY NOTIFICATIONS ATTACHMENT 5 - EMERGENCY ACTION LEVELS ATTACHMENT 6 - SAMPLE - INITIAL NOTIFICATION FORM FORM ATTACHMENT 7 - SAMPLE - FOLLOW-UP INFORMATION ATTACHMENT 8 - SAMPLE - TERMINATION CHECKLIST ATTACHMENT 9 - SAMPLE - ESSENTIAL INFORMATION CHECKLIST ATTACHMENT 10 - ACTIVATION OF THE EMERGENCY RESPONSE ORGANIZATION ATTACHMENT 11 - DOCUMENT CROSS-REFERENCES ATTACHMENT 12 - IDENTIFICATION OF COMMITMENTS EP-IP-100 Rev. 13 Page 19of47
ATTACHMENT 1 Sheet 1 of 1 UNUSUAL EVENT NOTIFICATION OF STATION PERSONNEL - STANDBY STATUS CAUTION During a security threat it may be advisable NOT to sound an alarm.
Sound/have the Control Room sound the Operator Recall Alarm and make the following announcement over the public-address system, TWICE:
A. "Attention all personnel, attention all personnel: An Unusual Event has been declared due to (brief description of-initiatina event). All on-call members of the Emergency Response Organization stand by for further instructions. All other personnel continue with your present duties until additional instruction is given."
B. If there is a localized emergency (for example, high radiation, fire), announce its type and location and instruct personnel to stand clear of this area.
Time Completed:
NOTIFICATION OF THE ERO - STANDBY STATUS Notify or direct notification of the ERO in accordance with Attachment 10, Activation of the Emergency Response Organization.
Time Completed:
NOTIFICATION OF STATE AND LOCAL AGENCIES Within 15 minutes of the event classification transmit an Initial Notification Form (Attachment 6) to the Commonwealth and local authorities.
Time Completed:
NOTIFICATION OF THE NRC Inform the NRC of the event classification using the ENS or a commercial telephone (Attachment 6 Step 4).
Time Completed:
RETURN TO THE PROCEDURE (EITHER STEP 5.2[2] OR 5.411])
EP-IP-100 Rev. 13 Page 20 of 47
ATTACHMENT 2 Sheet 1 of 2 ALERT SITE & PUBLIC AREA NOTIFICATION - RELEASE OF NONESSENTIAL PERSONNEL CAUTION During a security threat it may be advisable NOT to sound an alarm.
Sound/have the Control Room sound the Operator Recall Alarm and make the following announcement over the public-address system, TWICE:
A. "Attention all personnel, attention all personnel: An Alert has been declared due to (brief descriDtion of initiating event). All on-call members of the Emergency Response Organization report to your designated emergency response facility. All Pilgrim Station personnel assemble in your normal office or shop area, report to your supervisor, and await instructions. All visitors, all nonessential contractor personnel, all declared pregnant females, and all handicapped personnel please leave the site at this time."
B. If there is a localized emergency (for example, high radiation, fire), announce its type and location and instruct personnel to stand clear of this area.
C. If there is a potential for an airborne radiological release, consider announcing that there will be no eating, drinking, or smoking until further notice.
D. (Turn on the outside speakers) "Attention please! Attention please! This is Pilgrim Station.
Please leave the recreation areas without delay." (Turn off the outside speakers)
Time Completed:
NOTIFICATION OF THE ERO - EMERGENCY FACILITY ACTIVATION Notify or direct notification of the ERO in accordance with Attachment 10, Activation of the Emergency Response Organization.
Time Completed:
NOTIFICATION OF STATE AND LOCAL AGENCIES Within 15 minutes of the event classification transmit an Initial Notification Form (Attachment 6) to the Commonwealth and local authorities.
Time Completed:
EP-IP-100 Rev. 13 Page 21 of 47
ATTACHMENT 2 Sheet 2 of 2 ALERT (Continued)
NOTIFICATION OF THE NRC Inform the NRC of the event classification using the ENS or a commercial telephone (Attachment 6 Step 4).
Time Completed:
ACTION VERIFICATION Have Security verify public access areas have been evacuated.
Time Completed:
RETURN TO THE PROCEDURE (EITHER STEP 5.2[2], 5.3[2](a), OR 5.411])
EP-IP-100 Rev. 13 Page 22 of 47
ATTACHMENT 3 Sheet 1 of 2 SITE AREA EMERGENCY ASSEMBLY AREA DESIGNATION Determine the Assembly Area based on meteorological conditions as follows:
Assembly Area Wind Direction (0 from)
I-] Support Building Cafeteria 000-289' or 324°-360° Chiltonville Training Center 2900-3233 NOTIFICATION OF SECURITY (IF NOT PREVIOUSLY DONE)
- 1. Inform Security of the location of the designated Assembly Area and the official declaration time of the Site Area Emergency.
- 2. Direct Security to ensure that personnel in the Support Building are sent to their assembly area.
- 3. Direct Security to initiate personnel accountability procedures.
- 4. Direct Security to verify public access areas are being/have been evacuated.
Time Notified:
SITE & PUBLIC AREA NOTIFICATION - PROTECTED AREA EVACUATION CAUTION During a security threat it may be advisable NOT to sound an alarm.
Consider radiological conditions when preparing to evacuate personnel. If high dose rates will be encountered, it may be better to shelter non-essential personnel on-site.
Sound/have the Control Room sound the Emergency Site Evacuation Alarm and make the following announcement over the public-address system, TWICE:
A. If enterino from no event or an Unusual Event:
"Attention all personnel, attention all personnel: A Site Area Emergency has been declared due to (brief description of event). All on-call Emergency Response Organization members report to your designated emergency response facility. All other personnel evacuate to (Assembly Area)."
If uoaradina from an Alert:
"Attention all personnel, attention all personnel: A Site Area Emergency has been declared due to (brief descriotion of event). All personnel who are not part of the on-call Emergency Response Organization evacuate to (Assembly Area)."
Continued on next page.
EP-IP-100 Rev. 13 Page 23 of 47
ATTACHMENT 3 Sheet 2 of 2 SITE AREA EMERGENCY (Continued)
SITE & PUBLIC AREA NOTIFICATION - PROTECTED AREA EVACUATION (CONTINUED)
B. If there is a localized emergency (for example, high radiation, fire), announce its type and location and instruct personnel to stand clear of this area.
C. If there is a potential for an airborne radiological release, consider announcing that there will be no eating, drinking, or smoking until further notice.
D. If not previously done: (Turn on the outside speakers) "Attention please! Attention please!
This is Pilgrim Station. Please leave the recreation areas without delay". (Turn off the outside speakers.)
Time Completed:
NOTIFICATION OF THE ERO - EMERGENCY FACILITY ACTIVATION If not already notified, notify or direct notification of the ERO in accordance with Attachment 10, Activation of the Emergency Response Organization.
Time Completed:
NOTIFICATION OF STATE AND LOCAL AGENCIES Within 15 minutes of the event classification transmit an Initial Notification Form (Attachment 6) to the Commonwealth and local authorities.
Time Completed:
NOTIFICATION OF THE NRC Inform the NRC of the event classification using the ENS or a commercial telephone (Attachment 6 Step 4).
Time Completed:.
VERIFY ACCOUNTABILITY Security should report within 30 minutes of declaration of a Site Area Emergency that accountability is complete and provide the names of missing persons, if any. Log the time that accountability was completed.
Time Completed:
ýRETURN TO THE PROCEDURE (EITHER STEP 5.2[2], 5.3[2](a), OR 5.4[1]) I EP-IP-100 Rev. 13 Page 24 of 47
ATTACHMENT 4 Sheet 1 of 2 GENERAL EMERGENCY ASSEMBLY AREA DESIGNATION Determine the Assembly Area based on meteorological conditions as follows:
Assembly Area Wind Direction (0 from)
Ui Support Building Cafeteria 000-289' or 324°-36-0 Ll Chiltonville Training Center 290°-3230 NOTIFICATION OF SECURITY (IF NOT PREVIOUSLY DONE)
- 1. Inform Security of the location of the designated Assembly Area and the official declaration time of the General Emergency
- 2. Direct Security to ensure that personnel in the Support Building are sent to their assembly area.
- 3. Direct Security to initiate personnel accountability procedures.
- 4. Direct Security to verify public access areas are being/have been evacuated.
Time Notified:
SITE & PUBLIC AREA NOTIFICATION - PROTECTED AREA EVACUATION CAUTION During a security threat it may be advisable NOT to sound an alarm.
Consider radiological conditions when preparing to evacuate personnel. If high dose rates will be encountered, it may be better to shelter nonessential personnel on-site.
Sound/have the Control Room sound the Emergency Site Evacuation Alarm and make the following announcement over the public-address system, TWICE:
A. If enterina into a General Emeraency from an Alert or lower: "Attention all personnel, attention all personnel: A General Emergency has been declared due to (briefdescriotion of event). All on-call members of the Emergency Response Organization report to your designated emergency response facility. All other personnel evacuate to (Assembly Area).
There will be no eating, drinking, or smoking until further notice."
If uooradina from an Site Area Emeraencv: "Attention all personnel, attention all personnel:
A General Emergency has been declared due to (brief descriotion of event). There will be no eating, drinking, or smoking until further notice."
Continued on next page.
EP-IP-100 Rev. 13 Page 25 of 47
ATTACHMENT 4 Sheet 2 of 2 GENERAL EMERGENCY (CONTINUED),
SITE & PUBLIC AREA NOTIFICATION - PROTECTED AREA EVACUATION (CONTINUED)
B. If there is a localized emergency (for example, high radiation, fire), announce its type and location and instruct personnel to stand clear of this area.
C. If not previously done: (Turn on the outside speakers) "Attention please! Attention please!
This is Pilgrim Station. Please leave the recreation areas without delay." (Turn off the outside speakers.)
Time Completed:
NOTIFICATION OF THE ERO - EMERGENCY FACILITY ACTIVATION If not already notified, notify or direct notification of the ERO in accordance with Attachment 10, Activation of the Emergency Response Organization.
Time Completed:
NOTIFICATION OF STATE AND LOCAL AGENCIES Within 15 minutes of the event classification transmit an Initial Notification Form (Attachment 6) to the Commonwealth and local authorities. Protective Action Recommendations issued in accordance with EP-IP-400 are mandatory for a General Emergency classification.
Time Completed:
NOTIFICATION OF THE NRC Inform the NRC of the event classification using the ENS or a commercial telephone (Attachment 6 Step 4).
Time Completed:
VERIFY ACCOUNTABILITY If not previously done, Security should report within 30 minutes of declaration of a General Emergency that accountability is complete and provide the names of missing persons, if any.
Log the time that accountability was completed.
Time Completed:
RETURN TO THE PROCEDURE (EITHER STEP 5.2[2] OR 5.3[2](a))
EP-IP-100 Rev. 13 Page 26 of 47
, (
ATTACHMENT 5 Sheet 1 of 5 1.0 REACTOR FUEL SITE AREA EMERGENCY ALERT UNUSUAL EVENT GENERAL EMERGENCY 1.1.1.2 1.1.11 1.1 Coolant 1.1.1.4 Reactor coolant system sample activity Reactor coolant system sarriple activity Activity Reactor coolant system sample activity which indicates a > 20 nhrcrocuuies/nd total iodine.
> 200 ricrocurieshld total iodine
=
core condition as determined by EP-tP-330, "Cora
.el 1.mOg-as1.2.1.2 1.2.1.1 1.2 Off-gas Air ejector ott-gas radiatlio rijonitors 1705-3A and B 00 Air eleclor oil-gas radiation levels approaching Techrnical Activity Panel 910 reading 20.0 infi/hr Specification release tinrtts as indicated by Air Ejector Otl-gas Radiation Monitors 1705-3A and B Panel 910 I ligh-Itligh alarr* whicti does not clear within 13 mirrrutes 1.3.1.1 1.3 Thernial Limits MCPR < Techinical Spectfication hiel cladding inlegity sately hinit.
1,4,1.3 1.4.1.2 1,4 nadiation 1.4.1.4 Valid Orywell Higt Range Area Radiation Monitor reading Refuel Floor Ventilation Exhaust Radiation (RFVE)
Monitors Valid trywall htigh Rngse Area Radiation Monitor reading Monlior 1705.8 Channel A(NC) and Channel B(BID) Higth
. 10.000 R/hir (RIT- 1001-606A arid B) or Valid I orus Itigh > 200 flihr (RIT. 10t 1-606A and B) or Valid Torus Ittgh Range Area Radiation Monitor reading , 200 fl/ir Range Area Radiation Monitor reading a 3 Ruir trip Panel 910.
(lIlt -lltt.l607A aid B) due to degraded reactor fuel (Flt.tI1001-617A and B) due to degraded reactor luel "N Integrity coiidtutions rteegirty conditioins. Upscale alarm on two or more of ti0e following Area Radiation Monitors Panel 911 which cannot be attrilb.ted to a controiled process:
"* New fuel storage area (t11)
"* Refuuling Iloor spent luel pool room (1112)
"* Refueal floor reactor basin separator (I13)
J
- Refuel floor reactor basin speoit tuelarea (1141 2.0 REACTOR PRESSURE VESSEL 2.1.1.3 2.1.1.2 2.1.1.1 2.1 Reactor Water 2.1.1.4 RPV water level cannot be determiined (RPV Flooding is RPV water level cannot be restored and nmirtainted RPV water level cannot be maintained above -125 inches Level Sustaiied RPV water level < -160 incies.
A.NQ No sources oa RP'V injection available (AF).
_N0 required). above 112 inches I
Ho sources (EOP 1 Tettle C Injection Sulbsysteins) 01 2A1.2.4 adequale capacity are available to restore water level.
ttl'V is depiessurizet aind ino inecliattisnr of adequate coio cooling can be established try iitjection into ilia RPV troiu ary souice (Purirnluy Conitaliliriert Flooding is 2.2.1.2 2.2.1.1 2.2 Reactor Reactor vessel doi*e pressure coainot ire irrailrrisled Sustained reactor vessel doite pressure a 1325 psig Pressutre < 1115 psir (except during ltPV hydrostalic testinr) 2.3.1.3 2.3.1.2 2.3 Reactor Power 2,3.1.4 Reactor power . 3% and torus leilipallture above tire Boron injection into tile RPV inlentionally initiated (bororn A reactor Scram lies been initiated
- Boron Injection Initiation Temperalure" (311T) FOP injection required) with either &WNQ Figure 4.
- Standby Liquid Control System (SBLC) 1he reactor is not shuldowin AN*PIt"E 3 13
. An SRV is open.
- One or more of the methods detailed in PNPS OF Procedure 5,3,20. "Altenate Borate Injection*
- Drywall pressure , 2 2 psig.
EP-IP-100 Rev. 13 Page 27 of 47
( (
ATTACHMENT 5 Sheet 2 of 5 3.0 PRIMARY CONTAINMENT 3.1 Drywell 3.1.1.3 3.1.1.1 Bulk diywell temperature cannot be maintained < 150"F Telnperature Bulk drywell temperature cannot be maintained < 280"F as determined by PNPS Procedure 2 1 27. "D(ywell as determined by PNPS Procedure 2 1 27. "Drywell lenipeialure Indication Temperature Indication" AND Primary containment integrity is required 3.2.1.3 3.2.1.1 3.2 Torus water Torus water temperature I 10F Temperature Torus water temperature cannot be nmaintained below the "Heat Capacity Temperature Limit" ItHC FL) Figure 3. 3.3.1.1 3.3 Contahmiettt 3.3.1.4 3.3.1.3 3.3.1.2 3.3.1.1 cannot be maintained Both torus water level and RPV pressure cannot be Torus water level cannot be mairtained < 180 inches Reactor coolant system to drlywell unidentified leakage Water Level PPrimary
< 77 leetcontainmnent water level maintained below the"SRV Tait Pipe Level Lint" > 5 gprn with reactor coolant temperature > 212"F (SRVTPLL) EOP Figure 2 OR Reactor coolant system to drywett total leakage > 25 gpir 3.3.2.3 with reactor coolant tenupuratue > 212'F Torus water level cannot be maintained ' 90 inches 3.3.2.1 Torus water level cannot be nairtained:
. < 132 (A1inches narrow range) hinctes.
. > 127 inches (-6 inches narrow range).
6VQ Primnary containment integrity is required.
3.4.1.4 3.4,1.3 3.4.1.2 3.4 Primary Torus bottom pressure cannot be maintained below the Primary containment pressure cannot be maintained Containment Torus pressure approaching "The Primary Containment "Pressure Suppression Pressure" (PSP) EOP Figure a < 2.2 psig (except during testing such as ILRI. etc)
Pressure Pressure Lisi" (PCPL) EOP Figure 7 (prior to initiation of (except during testng such as ILRT. etc.).
containment venlinC)L 3.5.1.4 3.5.1.3 3.5.1.2 3.5 Containment 1%
Orywell or torus thydrogen concentration ' 1% Drywell or torus hydrogen concentration '
H1&
80 Drywall or torus hydrogen concentration 86%
AND AND Concentration Drywall or torus oxygen concentration 2 5% (Prior to Diywell or torus oxygen concentration > 4%
initiation of containment venting),
3.5.2.4 Diywell or lorus hydrogen concentration cannot tie delernined to be < 6%.
AND Drywelt or tnrus oxygen conc~entratinn cannot he deternmried to be < 5% (Prior to initiation ot containment venting).
EP-IP-100 Rev. 13 Page 28 of 47
! ( (
ATTACHMENT 5 Sheet 3 of 5 A fl a------ fl..
'i.U ZECONDARY UUNIAINMI-N I 4.1.1.3I 4111 4.1 Secondary 4.1.1.3 4111 Secondary containment area water levels exceed Ilie Secondary "Maximum Sale corntaminanlt Operating area more areas two orexceed waterinlevels Value" Ilia Containment "Maxir*urii Sale Operating Value" in two or more areas EOP Table L Area Water EOP table L AND Levels AND Reactor coolanl lemperature > 212'F with irradiated fuel A prioriary system is discharging into lIhe area in Ilie vessel AND Reactor coolanl lemperaurre > 212'F with irradiated luel in lthe vessel.
I I 4.2.1.1
_________________________________________________I- in lia vese Secondary containment area temperatures exceed Ilie 4.2.1.3 4.2 Secondary Secondary containmenl area temperatures exceed Ihe "Maximuni Safe Operating Value- in two or more areas Containment "Maximum Sale Operating Value" in two or more areas EOP Table L Area EOP Table I AND Temperatures AND Reactor coolant temperalure > 212"F with irradialed luel A pirirary system is discharging into tire area i the vessel AND Reactor coolant temperature > 212"F with irradiated fuel in the vessel I___________________________________ I.
_1__11 I_ 4.3.1.2 4.3 Secondary General area radiation levels measured in-planl which Seconrdary containnment radiation levels exceed the increase by a lactor of 1000 times nornmal as a resull of Containinent "Maxinium Sale Operating Value" in two or miore areas airborne radioactivity which cannot be atlribuled to a Area Radiation EOP Table L. controlled process.
Levels IwQ I JA uiary system isdischarging intolire area. I__________________.________
- ).U I*AUIUAU I IVl I Y I'*I"Lt:::A*P-..
I 5.1.1.1 0.111 T¶AUIUATIiVITT LMUZMi 5.1.1.2 6.1.1.2 Valid Reactor Building Ventilalion Exhaust (RBVE) 5.1.1.1 5.1 Effluent 6.1.1,4 5.1.1.3 Valid Reactor Building Ventilation Exhaust (RBVE)
Valid Main Stack Process Radiation Monitor 1705.18 A monifor 1705-32A and B Panel 910 high alarm which Valid Main Stack Process Radiation Monitor 1705-18 A monitor 1705-32A and B Panel 910 high-high alarm which Monitors > 2 4E5 cps and B Panel 910 reading > 2 4E4 cps. does not clear within 15 minutes from lhe tine action is aandB Panel 910 reading does not clear within 15 minutes Item the time acion is taken to isolate the source taken to isolate the source.
5.1.2.2 6.1.2.1 Maxi stack radioactivity effluents in excess of the Valid Main Slack Process Radiation Monitor 1705-18A high-high alarm selpoint for giealer than 15 imnutes as aandB Panel 9 10 reading s 10.000 cps lot greater than indicated by the Main Stack Process Radiation Monitors 15 minutes 1705-18A and B Panel 910 5.1.3.1 Radwasle Effluent Radiation Moiior (1705 30) high alarm Panel 910 AND)
Radwaste discharge is not isolated FV-7214-A and B) 5.2 Dose 6.2.1.4 5.2.1.3 Projection & Dose projection based on effluent monilors or actual Dose projection based on effluent monitors or aclual environmenial measuiremets which indicale doses in environmental measurements which indicate doses in Environtmental exicess of 100 tirem whole body or 500 nireii thyroid at excess of 1000 mirem whole body or 6000 irern thyroid at the site boundary or beyond Measurnlemnts therIsite boundary or beyond 5.2.2.4 Dose projeclion based on effluent monitors or actual envnronnr*inlal rmeasuremenls which indicate dose rates in excess of 1000 rireri/hr whole body or 5000 nrenihlir 5.3.1.1 thyroid atthe site boundary or beyond Transportation of a conlairriated injured person to an 5.3 Cortiamirtaled Inflsite medical facility tnnlrrvi EP-IP-100 Rev. 13 Page 29 of 47
( (
ATTACHMENT 5 Sheet 4 of 5 6.0 INTERNAL EVENTS SITE AREA EMERGENCY ALERT UNUSUAL EVENT GENERAL EMERGENCY 6.1 Te'nical6.1.1.1 6.1 Technical TilTe plant is not brought to the required operating mode Specifications within Iechnical Specifications LCO Action Statement time 6.2.1.3 6.2.1.2 6.2.1.1 6.2 Safely Loss of Control Room habitability (eg . fire. smoke, Failure ota reactor Satety Relief Valve (RV.203-3A thru Systems Evacuation of Control Room without establishtnent of D) to close following reduction of appticable piessure as plant control fiom remote shutdown stations within radiological hazards, etc).
15 minutes. indicated by either 6.2.2.2 . Accoustic monitor ZI-203 Panel C171.
Inability to establish and maintain cold shuldown OR 6.2.2.3 conditions as indicated by: SRV tailpipe tenperalure recorder TR.260-20 Steam line break outside primary contaiinent without isolation. Reactor Mode Switch in "Shuldown." Panel 921.
AND AND AND" Reactor coolant lemperature > 212'F Reactor coolant temnperature cannot be maintained Reactor coolant temperature > 212F witt irradiated tuet
! 212'F. iii the vessel.
6.2.3.3 Inability to imnnediately isolate any Main Steam Line tollowirng a valid PCIS signal (Group t)
AND Reactor coolant temperature >
212*F.
6.3.1.2 6.3.1.1 6.3 Electrical System 6.3.1.3 Sustained loss of atl AC power capability as indicated by Loss of all AC power capability as indicaleo by the Loss of all vital onsile AC power capability as indicated Sstem the inability to power any 4kV bus (Al thru A6) from any inability to power any 4kV bus (A Ithru A6) from any by:
Insbility to power Bus A5 from any onsito gemritor.
Failures source (all 4kV buses de-energized). source (all 4kV buses do-energized).
6.3.2.2 Inability to power Bus AG from any onsita generstor 6.3.2.3 Loss of all 125 VDC power capability as indicated by: Onflte aenerators are; Sustained loss of all 125 VDC power capability as Voltage < 105 VCD Panel D-16. Main Generator via Unit Auxiliary Transformer indicated by:
Voltage < 105 VDC Panel 0-16. AND Emergency Diesel Generator A Voltage < 105 VDC Panel D-17 Emergency Diesel Generator B AND Voltage < 105 VDC Panel 0.17 , Station Blackout Diesel Generator 6.3.2.1 Loss of all vital otfsite AC power capabitity as indicated by Inability to immediately supply AC power to Bus A5 from any ottsite power supply translotrmer" AND inabiltity to to immediately supply AC power to Bus A6 tioim any ollsite power supply tuanslotorini Otlsile oowersnIpil tratrsfoliers are
- Startup Transtoruer (X4)
- Shutdown Transtormer (X13)
- Main Transtormer with Main Generator phase bus links removed (backscuttle) 6.4.1.2 6.4.1.1 6.4 Loss of 6n4LossofComplete loss of plant process compuiter alarm and Loss of indications and/or alarnis which cause a Indlcarmon, indications signiticant loss of assessment capabilities such as*
Alarm, or AND Loss of indication or arnilricialion on safety-related tFoss ot most or all Control Rooin annunciators. equlpmnenl to an extent requiring shutdownt by Technical Comnrmt AND Specifications Capability AND Reactor coolant temperature is > 212'F Reactor coolant feiipeiature is > 212'F 6.4.2,1 Loss ot all ability to commrunicate with or adequately activate the Emergency Response Organization as indicated by the complete loss of ttie onsile telephone systems EP-IP-100 Rev. 13 Page 30 of 47
(
ATTACHMENT 5 Sheet 5 of 5 7.0 EXTERNAL EVENTS 7.1 Security 7.1.1.4 7.1.1.3 7.1.1.2 7.1.1.1 Threats An ongoing security comripromise which in the iudgrient of An ongoing security compromise which in the judgmenl of Any ongoing secitily compromise (> 10 irerules) as Arty atlend'il uiaurithoied entry into the Protected Area the Operalions Shill Stupeinletndent has led to the loss of tire Operations Shill Superintendenl may lead Io lite loss delernriied by the Stalioni Secisily Force. as deteinrineil by the Station Seciuliy Force physical control of the plant. of physical cordlol of the plant.
7.1.2.1 Any indication of attenmpted sabolage 7.1.3.1 Receipt of a credible bomb Ihreat as delermined by the Slation Security Force 7.2 Fire 7.2.1.3 7.2.1.2 7.2.1.1 Any lire which has affected Ihe abifify of two or more Fire burning out of control in a plant vital area Fire within [lie Protected Area lasting > 10 minutes from the lime firefighting elforts begin (Fire Brigade fire lighting Table 7-1 Safety Systems safely syslems (I able 7- 1) to perfoirr ll(heir intended lunclion and poses a significant polential for release of efforts have begun when tIre Fire Brigade first applies fire radioactivity. fighting agents on tre fre.).
ResidualReacor coolant temperature 212. Any fire orsile for which oflsrie fire fighting assistance is requested (the required notification ol the Plymotlh Fire Core Spray Depailineni for any onsile lire does nul constrtute a requesl for olfsrle fire Ifglrhrtigassistance.)
7.3 Man-made Emergency Diesel Generators 7.3.1.3 7.3.1.2 7,3.1.1 Events Any of tire following which has affecled lhe abilily of two Any of the following evenrs occurring which aflect plant Any of tire following events occurring onsite or more safely systems (Table 7-1) to perform their operation:
- Aircraft crash.
High Pressure Coolant Injection inlended function and poses a significant polential for
- Aircraft crash on facility. Explosion (unplanned) release ol radioactivity:
- Missile impact from any source on facirily. Toxic or flammable gas release.
Automatic Depressurization System *Aircilit crash on facility.
- Entry of toxic or flammable gas into a planl process Missile ilrpact from any source on facility. building atmospheie (includes significant Main Reactor Protection System
- Entry of toxic or flammable gas into a plant process Generalor hydrogen leaks),
building atmosphere J*Explosion (Unplanned).
- Explosion (unplanned)
ATWS/ARI IANo
- Reaclor coolant temperature v 212'F ,
7.4 Natural Events Primary Containment Isolation 7.4.1.3 7.4.1.2 7.4.1.1 System Any of the following which has affecled Ihe ability of two Any of the following which causes damage to permanent Sustained winds (- 5 minutes) in excess of 75 mph as or more safety systems (Table 7-1) to perform their plant struictures or equipment which allect plant operalion: indicated oi wind speed recorder Panel MT1 rintended funclion and poses a significant polential for
- Earthquake Standby Gas Treatment release of radioactivity. Tornado 7.4.2.1 l Eailrhqiake Hurricane H Report of a tornado onsile Standby Liquid Control Tornado
- Olher Natural Phenomena Hu-rricane 7.4.3.1 Nalural Phenomena 7.4.2.2 Airy earthqiiake dotected by seismic irstlitirenlalion as Reactor Building Closed Cooling
- Other W eAND Any earthquake onsile which has been determined to be indicated by.
Water Reactor coolant tenmperalure is v 212*F greater than Operating Basis Earthquake levels (008 g)
- Seismic monitor event alarm Panel 9 11 Service Water 7.4.2.3 o 'Seisiric Recoirler Operaling" anvirciator Panel C1 Any earthquake oisite which has beern determined to lie Right A-7 greater than Sale Shutdown Earthquake levels (0. 15 g) AND Grouind motion is fell by one or riore plain operations personnel.
8.0 OTHER 8.1 Other 8.1.1 4 8.1.1.3 8.1.1.2 8.1.1.1 In the opinion of the Operations Shift Superintendent or lit the opinion of the Operations Shift Superinlendent or Any evenl which in [lie opinion of lhe Operations Shill Any evenl which in lite opinion of lhe Operations Shifl Errergency Direclor events are in progress which indicate Emergency Director events are in progiess which indicate Superiilendenl or Energency Director could or has Superintlendenl or Ermrergency Director could or has led to acliral or imminent core damage and Ihe polential for a actual or likely failures of plant systems needed to protect caused actual substantial degradalion of the level of plant a potential degradation of Ihe level of safety of the plant large release of radioaclive malerial outside the site flie public and pose a significanl radioactivity release safety.
boundary polential. 8.1.2.1 Any evenl which in the opinion of the Operations Shift Superinlendent or Emergency Director warranls lhe prompt notification of Coimnionwealth and local aulhorities and precaulionary notificalion of Emergency Response I I Organization personnel EP-IP-100 Rev. 13 Page 31 of 47
ATTACHMENT 6 Sheet 1 of 3 1 THIS IS: UL A DRILL LU AN ACTUAL E"VENT I 2~ AS OF: I I PILGRIM NUCLEAR POWER STATION HAS:
VENT I time date J ENTERED: -AN UNUSUAL E' VENT U HAD A TRANSITORY R_ _AN ALERT THEN ENTERED: Ul A SITE AREA EI
/ERGENCY IUPGRADED TO:
I A GENERAL EM ERGENCY U DOWNGRADED TO: LJ RECOVERY 1J EAL No. BRIEF DESCRIPTION OF EVENT:
A I A, --. ,.* *. .- "-, . . .
UAUIs-U
[J1IS I IVNI J-IiS NOT ................................................................... PRGLEASE:
IN PROGRESS UtIS ABOVE Ul IS BELOW .................................. PROTECTIVE ACTION GUIDES 5I METEOROLOGICAL DATA AS OF WIND DIRECTION FROM 0 TO
° AT mph L6] PNPS's PROTECTIVE ACTION RECOMMENDATIONS (PARs):
U NO PROTECTIVE ACTIONS NECESSARY GENERAL EMERGENCY AND MEMAJMD.HkAEPRESENT IN THE EOF:
IU PROVIDED TO MEMA/MDPH GENERAL, EME.RGENCY AND MEMA/MDPH'AE NOT PRESENT IN THE- EF:
UlSHELTERSUBAREA(s) 1 2 3 4 5 6 7 8 9 10 11 Ul EVACUATE SUBAREA(s) 1 2 3 4 5 6 7 8 9 10 11 12 (circle the affected subareas)
E71NOTIFICATION INITIATED I time I date IBYi name 8_1 NOTIFICATION RECEIVED I 7m BY time date name EP-IP-100 Rev. 13 Page 32 of 47
ATTACHMENT 6 Sheet 2 of 3 IINITIAL NOTIFICATION FORM No.W NOTE DO NOT TRANSMIT THIS SHEET OVER DNN M APPLICABLE ONLY IN A GENERAL EMERGENCY PILGRIM STATION'S PROTECTIVE ACTION RECOMMENDATIONS GIVEN TO MEMA/MDPH REPRESENTATIVES IN THE EMERGENCY OPERATIONS FACILITY (circle the affected subareas):
[SHELTERSUBAREA(s) 1 2 3 4 5 6 7 8 9 10 11
[EVACUATESUBAREA(s) 1 2 3 4 5 6 7 8 9 10 11 12 EMERGENCY DIRECTOR REVIEW AND APPROVAL, THE EMERGENCY DIRECTOR SHALL REVIEW AND SIGN THESE FORMS INDICATING VERIFICATION OF AND APPROVAL FOR INFORMATION RELEASE AND PROTECTIVE ACTION RECOMMENDATION (if given).
APPROVED FOR RELEASE: [ Emergency Director's Signature I
EP-IP-IO0 Rev. 13 Page 33 of 47
ATTACHMENT 6 Sheet 3 of 3 INITIAL NOTIFICATION FORM TRANSMISSION INSTRUCTIONS NO:
(Check off the boxes as steps are completed.)
SteD 1: TRANSMIT THE FORM J Verify Blocks 1 - 6 are complete, release is approved by signature, and then fill out Block 7 of the form. Forguidance on individual Block descriptions refer to EP-IP-100.
II Place only the first page of the completed form face down in the DNN fax machine.
L-I Follow the posted instructions at the DNN fax machine. Proceedimmediately to Step 2.
SteD 2: CONTACT THE COMMONWEALTH AND LOCAL OFFICIALS If notification is made on anything other than dedicated communication links (DNN or BECONS), request a verification callback.
SPick up the DNN ring-down phone and read the following message twice:
"Attention, attention. Please standby for a roll call."
L-- Perform a roll call and check off the responding locations as they are identified.
LJ Middleboro State Police LI Carver LJ Marshfield J1 Framingham MEMA L1 Duxbury J Plymouth LI Bridgewater L3 Kingston Ll Taunton JI Read the following message twice:
"This is the Pilgrim Nuclear Power Station. An Initial Notification Form is being transmitted. Obtain the transmitted form from your telecopy machine or obtain a blank form and standby for initial notification data."
Step 3: TRANSMIT THE DATA Ll Read the information in Block 1 through Block 6.
JI Tell those parties who have complete information to hang up, then provide missing information to remaining parties.
F- Contact locations not answering roll call via BECONS or commercial telephone (auto-dialer) and read the information in Block 1 through Block 6.
Step 4: NOTIFY THE NRC LJ Using the ENS or commercial phone read the information in Block 1 through 6.
Name of
Contact:
Time:
Step 5: ORGANIZE THE REPORT LJ Obtain the printed report from the DNN fax machine and staple it to this form.
LJ Inform the Emergency Director that transmission was completed at time:
Time:
COMPLETED BY:
Signature of person making notifications EP-IP-100 Rev. 13 Page 34 of 47
ATTACHMENT 7 Sheet 1 of 3 1 I THIS IS: 1: A DRILL LI AN ACTUAL EVENT 2 AS OF: PILGRIM NUCLEAR POWER STATION IS STILL AT A:
time date I[]UNUSUAL EVENT LJ ALERT [* SITE AREA EMERGENCY [* GENERAL EMERGENCY El STATION CONDITIONS ARE: D~lIMPROVING i-ISTABLE LI*DEGRADING 14 1 EAL No. BRIEF DESCRIPTION OF EVENT: I 5 OUTSIDE ASSISTANCE: L3 HAS F1 HAS NOT BEEN REQUESTED 0II AMBULANCE REASON FOR OUTSIDE ASSISTANCE:
LI FIRE DEPARTMENT LIJ POLICE L-J OTHER (Specify) 6 RADIOACTIVE RELEASE:
L-I is LII IS N O T ................................................................... IN PRO G R ESS LI IS ABOVE [J IS BELOW .................................. PROTECTIVE ACTION GUIDES SMETEOROLOGICAL DATA AS OF 0
STABILITY CLASS WIND DIRECTION FROM TO AT mph 8 PNPS's PROTECTIVE ACTION RECOMMENDATIONS (PARs):
JI NO PROTECTIVE ACTIONS REQUIRED GENEtR*_L '.EMERGENCY AND MEMA/MDPH-AREPRESENT IN THE EOF:
PROVIDED TO MEMA/MDPH GEN*ERAL E-MERGEN~CY ANDME*MAiIDPH- ARdE-NOT PRESENT IN THE=EOF:....
'- SHELTER SUBAREA(s) 1 2 3 4 5 6 7 8 9 10 11 LI EVACUATE SUBAREA(s) 1 2 3 4 5 6 7 8 9 10 11 12 (circletheaffec*edsubareas) 9 NOTIFICATION INITIATED I IBY time date name n
I BY I 10 NOTIFICATION RECEIVEDi time date name EP-IP-100 Rev. 13 Page 35 of 47
ATTACHMENT 7 Sheet 2 of 3 IFOLLOW-UP INFORMATION FORM (Cont.)I No.W NOTE DO NOT TRANSMIT THIS SHEET OVER DNN j APPLICABLE ONLY IN A GENERAL EMERGENCY PILGRIM STATION'S PROTECTIVE ACTION RECOMMENDATION GIVEN TO MEMA/MDPH REPRESENTATIVES IN THE EMERGENCY OPERATIONS FACILITY (circle the affected subareas):
I*SHELTERSUBAREA(s) 1 2 3 4 5 6 7 8 9 10 11
[EVACUATESUBAREA(s) 1 2 3 4 5 6 7 8 9 10 11 12 SINCE PREVIOUS NOTIFICATION, THIS RECOMMENDATION HAS:
LICHANGED UI REMAINED THE SAME THIS RECOMMENDATION IS BASED ON:
Ll PLANT CONDITIONS UI PROJECTED RELEASE [lACTUAL RELEASE EMERGENCY DIRECTOR REVIEW AND APPROVAL:
THE EMERGENCY DIRECTOR SHALL REVIEW AND SIGN THIS FORM INDICATING VERIFICATION OF AND APPROVAL FOR INFORMATION RELEASE AND PROTECTIVE ACTION RECOMMENDATION (if given).
APPROVED FOR RELEASE:
Emergency Director's Signature EP-IP-100 Rev. 13 Page 36 of 47
ATTACHMENT 7 Sheet 3 of 3 FOLLOW-UP INFORMATION FORM TRANSMISSION INSTRUCTIONS No:
(Check off the boxes as steps are completed.)
Step 1: TRANSMIT THE FORM
[i Verify Blocks 1 - 8 are complete, release is approved by signature, and then fill out Block 9 of the form. Forguidance on individual Block descriptions refer to EP-IP-100..
UJ Place only the first page of the completed form face down in the DNN fax machine.
Ji Follow the posted instructions at the DNN fax machine. Proceedimmediately to Step 2.
Step 2: CONTACT THE COMMONWEALTH AND LOCAL OFFICIALS If notification is made on anything other than dedicated communication links (DNN or BECONS), request a verification callback.
Li Pick up the DNN ring-down phone, and read the following message twice:
"Attention, attention. Please standby for a roll call."
Li Perform a roll call and check off the responding locations as they are identified.
i- Middleboro State Police Ui Carver Li Marshfield Li Framingham MEMA Li Duxbury Li Plymouth Ll Bridgewater L3 Kingston Li Taunton Li Read the following message twice:
"This is the Pilgrim Nuclear Power Station. A Follow-Up Information Form is being transmitted. Obtain the transmitted form from your telecopy machine or obtain a blank form and standby for follow-up information data."
Step 3: TRANSMIT THE DATA Li Read the information in Block 1 through Block 8.
Li Tell those parties who have complete information to hang up, then provide missing information to remaining parties.
Ll Contact locations not answering roll call via BECONS or commercial telephone (auto-dialer) and read the information in Block 1 through Block 8.
Step 4: NOTIFY THE NRC Li Using the ENS or commercial phone read the information in Block 1 through 8.
Name of
Contact:
Time:
Step 5: ORGANIZE THE REPORT LJ Obtain the printed report from the DNN fax machine and staple it to this form.
LJ Inform the Emergency Director that transmission was completed at time:
COMPLETED BY: Time:
Signature of person making notifications EP-IP-100 Rev. 13 Page 37 of 47
ATTACHMENT 8 Sheet 1 of 2 TERMINATION CHECKLIST True False
- 1. Conditions no longer meet an Emergency Action Level and it l F appears unlikely that conditions will deteriorate.
List any EAL(s) which is/are still exceeded and a justification as to why a state of emergency is no longer applicable:
EAL Justification Plant releases of radioactive materials to the environment are 2.
under control (within Technical Specifications) or have ceased Li F!1 and the potential for an uncontrolled radioactive release is acceptably low.
- 3. The radioactive plume has dissipated and plume tracking is no longer required. The only environmental assessment activities in progress are those necessary to determine the extent of deposition resulting from passage of the plume.
- 4. In-plant radiation levels are stable or decreasing, and acceptable given the plant conditions.
- 5. The reactor is in a stable shutdown condition and long-term core cooling is available.
- 6. The integrity of the Reactor Containment Building is within Technical Specifications limits.
L DL
- 7. The operability and integrity of radioactive waste systems, decontamination facilities, power supplies, electrical equipment, and plant instrumentation including radiation monitoring equipment are acceptable.
- 8. Any fire, flood, earthquake, or similar emergency condition or threat to security no longer exists.
- 9. Any contaminated, injured person has been treated and/or transported to a medical care facility.
EP-IP-100 Rev. 13 Page 38 of 47
ATTACHMENT 8 Sheet 2 of 2 TERMINATION CHECKLIST (CONTINUED)
True False
- 10. All notifications required by the event procedures have been made.
- 11. Offsite conditions do not unreasonably limit access of outside J J support to the Station and qualified personnel and support services are available.
- 12. Discussions have been held with Federal, Commonwealth, and U 0 local agencies and agreement has been reached and coordination established to terminate the emergency.
It is not necessary that all responses listed above be "TRUE"; however, all items must be considered prior to event termination and entry into Recovery. For example, it is possible that some conditions remain which exceed an Emergency Action Level following a severe accident but entry into Recovery is appropriate. Additionally, other significant items not included on this list may warrant consideration such as severe weather.
Comments:
Approved: Date/Time:
Emergency Director EP-IP-100 Rev. 13 Page 39 of 47
ATTACHMENT 9 Sheet 1 of 2 Jill II 1W I *flI L FU EIJ f1,YLI 3T Uli*I IlIN b~lr~l'*, h..I ESSENTIAL INIOKI'
[] Initial Message Li Update 4Radiolgica Condtion Date: Time: am/pm Release Status:
Person Providina Information: o None L[ Imminent LI In Progress EI Uncontrolled El Controlled Name: Ll Above PAGs O- Below PAGs Location: hr(s)
Projected Release Duration:
I F I aI.sII c i or Status Offsite Protective Actions:
El None Issued Time Declared: am/pm ol Provided to Commonwealth
-I Off-Normal Event Onsite Protective Actions:
LI Unusual Event Q None LI Alert LI Potassium Iodide LI Site Area Emergency -I Evacuation of Nonessential Personnel LI General Emergency [] Other:
LIRecove - -I -
LI No LIYes rogessInjuries:
Actonsin How Many__
72)Briefu mmaryInjuries Evet a ititing[ - PersoHow Cinn+. F1 NJ~ [n ypc
%. W lIlLG"AIII -.I -:I II 1 m ,
Overexposure: C3 No [] Yes LI Minor LI Major Nature of injuries or contamination:
.6 o fs i A g n c N o ti fi a ti o n NRC Time: am/pm MEMA Time: am/pm P"N C ot MDPH Time: am/pm On-Line LI Off-Line LI Unstable Local (last town) Time: am/prm Stable LI At Power Cooling Down LI Cold Shutdown
- 7) *
- r, -A - M1 Time of Reactor Shutdown: am/pm EL LI None LI Fire Department El Ambulance LI Police LI Improving El Same LI Deteriorating Other:
Describe equipment, instrument, or other 1 8 N M N problems-ElI LI None ElI Draft News Release LI News Release Approved Press Conference
- 9) Sintr *. an S -
EP-IP-100 Rev. 13 Page 40 of 47
ATTACHMENT 9 Sheet 2 of 2 ESSENTIAL INFORMATION CHECKLIST N
i Additional Information:-
EP-IP-100 Rev. 13 Page 41 of 47
ATTACHMENT 10 Sheet 1 of 4 ACTIVATION OF THE EMERGENCY RESPONSE ORGANIZATION Emeroencv Resoonse Organization Notification Using CANS NOTE If at any time CANS cannot be contacted or does not respond as indicated, go to Section II (Notification Using Group Pages if CANS Fails) in this Attachment.
If the individual activating CANS is not the Operations Shift Superintendent, Control Room Supervisor, Shift Control Room Engineer, or the Operations Assistant, it is necessary for the individual to obtain a security code (Social Security number) from one of these individuals.
[1] Ascertain the current emergency classification from the Emergency Director.
[2] Obtain the phone number for CANS from the Immediate Notification section of the PNPS Emergency Telephone Directory.
[3] Attempt to contact CANS using any touch-tone phone line.
[4] Listen for the introductory message and enter your security code (Social Security number) upon request followed by the # sign.
NOTE For activation of the ERO for drills and exercise, precede the following classification codes with DRILL (37455 on telephone keypad). For example, for a drill classification of Alert, enter DRILL 2222 (374552222) as the emergency classification code.
[5] Listen for verbal prompt and enter the proper code for present emergency classification.
The codes are:
2 1111 UnusualEvent 2222 Alert 0 3333 Site Area Emergency a 4444 General Emergency a 0000 Termination of classifiable event/Recovery EP-IP-100 Rev. 13 Page 42 of 47
L ATTACHMENT 10 Sheet 2 of 4
[6] If you are NOT satisfied with the emergency classification, press the # sign to re-enter classification.
OR If you are satisfied, hang up the phone to start the notification process.
[7] Verify CANS operability by checking the emergency pager located in the locker in the Operations Shift Superintendent's office. Ensure that the pager is activated and indicates the proper emergency classification. Allow approximately 5 minutes for CANS to activate the pager.
NOTE If communication is established with the EOF prior to initiation of Step [8], Step [8] may be omitted.
[8] If the Emergency Operations Facility has not contacted the Control Room after approximately 35 to 40 minutes from the time the Control Room pager has activated, check on-call personnel response in the following manner:
(a) Obtain the CANS phone number from the Immediate Notification section of the PNPS Emergency Telephone Directory.
(b) Contact CANS using any available touch-tone phone. If no contact is made, pause and try again.
(c) Listen for the introductory message and enter your security code (Social Security number) when requested followed by the # sign.
(d) When prompted, enter '3' for the status of the classification scenario.
(e) Retrieve the CANS report from the DNN facsimile machine ard review the list for unfilled positions.
(f) Repeat Steps (a) through (e) above as often as necessary to keep apprised of the notification process.
EP-IP-100 Rev. 13 Page 43 of 47
ATTACHMENT 10 Sheet 3 of 4 II. Notification Usina Group Paces if CANS Fails NOTE If contact with the paging system cannot be made or the paging system does not respond as indicated, go to Section III (Notification Using Telephones if Both CANS and the Paging System Fail) of this Attachment.
[1] Obtain the ERO pager PIN and the access telephone number from the Immediate Notification section of the PNPS Emergency Telephone Directory.
[2] Contact the paging system by dialing the access telephone number.
[3] Upon contact, listen for the verbal prompt to enter the PIN number. When prompted, enter the ERO pager PIN followed by the # sign. If the verbal prompt is not heard, repeat Step [2].
[4] Listen for the verbal prompt to enter display message. When prompted, enter the proper code for present emergency classification. The codes are:
- 1111 Unusual Event 0 2222 Alert
- 3333 Site Area Emergency
- 4444 General Emergency
- 0000 Termination of classifiable event / Recovery
[5] Press the # sign to complete the entry.
EP-IP-100 Rev. 13 Page 44 of 47
ATTACHMENT 10 Sheet 4 of 4 Ill. Notification using Teleohones if Both CANS and the Paaina System Fail (1] Request the Emergency Director to inform Security at the Primary Access Control Point to notify the Emergency Response Organization using the PNPS Emergency Telephone Directory and commercial telephone lines in accordance with EP-IP-240.
[2] Call out one individual for each of the following emergency positions using the PNPS Emergency Telephone Directory. When contact is made, ask if any alcoholic beverage them has been consumed within the last 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. If the individual answers YES, inform the that an alternate shall be contacted. If the individual answers NO, inform them of event and that CANS and the pager system have failed. Record the name and response time below.
Emergencv Director (EOF)
Name Response Time (min.)
Emeraencv Plant Manaaer (TSC/OSC)
Name Response Time (min.)
Emeraency Offsite Manacer (EOF)
Name Response Time (min.)
EP-IP-100 Rev. 13 Page 45 of 47
ATTACHMENT 11 Sheet 1 of 1 DOCUMENT CROSS-REFERENCES This Attachment lists those documents, other than source documents, which may be affected by changes to this Procedure.
Document Number Document Title EP-IP-400 Protective Action Recommendations EP-IP-520 Transition and Recovery EP-AD-600* PNPS EAL Technical Bases Document PNPS 2.1.27 Drywell Temperature Indication PNPS 5.3.20 Alternate Borate Injection
_ _...._ EAL Wall Chart
EP-IP-100 Rev. 13 Page 46 of 47
ATTACHMENT 12 Sheet 1 of 1 IDENTIFICATION OF COMMITMENTS This Attachment lists those external commitments (i.e., NRC commitments, QAA audit findings, and INPO inspection items) implemented in this Procedure.
Reference Document Commitment Affected Section(s)
NRC Inspection Finding Develop and implement a system for use by Att. 5, EAL 81-15-34 the Control Room staff to aid in promptly Chart classifying events.
NRC Inspection Finding Provide EALs which include specific and Att. 5 81-15-35 observable Control Room instrument readings for each EAL corresponding to the respective initiating condition.
NRC Inspection Finding Provide EALs which address and conform to Att. 5 81-15-35, 84-41-02, all pertinent initiating conditions contained in 86-33-01 Appendix 1 of NUREG-0654.
NRC Inspecting Finding Revise the offsite notification procedures to Att. 6 81-1 5-36 specify protective action recommendations in the notification messages.
NRC Inspecting Finding Revise the communication procedures to Att. 6 & 7 81-15-41 ensure (verify) correct transmission. I NRC Inspection Finding Provide EALs based on field monitoring Att. 5 84-05-04 results and on the methods used if the (Category 5.2) effluent and containment monitors are inoperable or off-scale.
NRC Inspection Finding Revise the EAL on hurricane wind speed to Att. 5 84-41-01 reflect the National Weather Service (EAL 7.4.1.1) definition for hurricanes.
NRC Inspecting Finding Review the offsite notification procedure and Att 6 & 7 84-41-06 make appropriate changes to provide a high probability of completing offsite notification.
QAA Audit Report 87-48 Include in the EALs all initiating conditions in Att. 5 DR 1723, Issue 1 Appendix 1 of NUREG-0654.
QAA Audit Report 87-48 Ensure public access areas are closed at an Att. 2, 3, 4 DR 1723, Item 4 Alert or above.
NRC Inspection Report Provide further clarification and Att. 5 50-293/88-28 Item 2.4 and quantification for earthquake EALs. (EAL 7.4.2.2 7.4.2.3 Modifications to transmitted portions of Initial Notification and Follow-Up Information Form shall be reviewed with the Commonwealth.
EP-IP-100 Rev. 13 Page 47 of 47
RTYPE H8.24 PILGRIM NUCLEAR POWER STATION Procedure No. EP-IP-400 PROTECTIVE ACTION RECOMMENDATIONS Stop Think STAR Act Review SAFETY REVIEW REQUIRED SAFETY RELATED EP-IP-400 Rev. 8
REVISION LOG REVISION 8 Date Originated 9100 Paaes Affected Descriotion All Reformat all pages lAW PNPS 1.3.4-1. Revison bars are not shown for reformat changes.
4 Add EOP-01 to References.
7,8,12 Incorporate revised EAL 1.4.1.4 General Emergency threshold values and include design basis core cooling requirements (2/3 core height with Core Spray) specified in EOP-01 for indication of substantial core damage.
EP-IP-400 Rev. 8 Page 2 of 16
TABLE OF CONTENTS Paae
. . . ................... . 4 1.0 P UR P O S E ..........................................................................
2.0 REFERENCES
4 3 .0 D E F INIT IO N S ...............................................................................................................
5 4 .0 DIS C US S IO N ................................................................................................................
5 5 .0 R E S P O NS IB ILIT IE S .....................................................................................................
6 6 .0 P R O C E D UR E ...............................................................................................................
6 6 .1 B A C KG R O UND ..............................................................................................
7 6.2 PLANT-BASED PROTECTIVE ACTION RECOMMENDATIONS .................
6.3 DOSE ASSESSMENT-BASED PROTECTIVE ACTION R E C O MME ND AT IO NS ...................................................................................... 9 10 7.0 RECORDS .................................................................................
8 .0 A TT A C H ME NT S ................................................................................. ........................ 10 11 ATTACHMENT 1 - PROTECTIVE ACTION RECOMMENDATION PROCESS .................
13 ATTACHMENT 2 - ACCIDENT PHASE AND EXPOSURE PATHWAYS ..........................
ATTACHMENT 3 - PROTECTIVE ACTION RECOMMENDATION BOUNDING C A LC ULA T IO NS ................................................................................ 14 15 ATTACHMENT 4 - DOCUMENT CROSS-REFERENCES ...............................................
16 ATTACHMENT 5 - IDENTIFICATION OF COMMITMENTS .............................................
EP-IP-400 Rev. 8 Page 3 of 16
1.0 PURPOSE This Procedure provides instruction and guidance in determining offsite Protective Action Recommendations (PARs) in the event of a radiological emergency at the Pilgrim Nuclear Power Station (PNPS).
2.0 REFERENCES
[2] EP-PP-01, "PNPS Emergency Plan"
[3] EPA 400-R-92-001, "Manual of Protective Action Guides and Protective Actions for Nuclear Incidents", October, 1991
[4] IE Information Notice No. 83-28, "Criteria for Protective Action Recommendations for General Emergencies", dated May 4, 1983
[5] NUREG-0654 FEMA REP-1, Rev. 1, Supplement 3; "Criteria for Protective Action Recommendations for Severe Accidents" 3.0 DEFINITIONS
[1] Core Melt Sequence - A situation in which the core is uncovered and there is no means for restoring coolant to the core. Without coolant, overheating and melting of the fuel will occur.
[2] Dose Assessment - The dose calculated to occur at a downwind receptor based on actual release rates and meteorological data. Dose assessments are primarily used to ensure plant-based Protective Action Recommendations are adequate.
[3] Dose Commitment - The dose that will be accumulated by a specific organ over a specified period following uptake.
[4] Dose Projection - The dose calculated to occur at a downwind receptor based on projected release rates or meteorological data. Dose projections are primarily used to conduct bounding calculations prior to a release occurring.
[5] Emergency Planninq Zones (EPZs) - Areas established around a nuclear power station in which predetermined protective action plans are needed.
The first EPZ has an approximate radius of 10 miles for the plume exposure pathway.
The second EPZ has an approximate radius of 50 miles for the food and water ingestion exposure pathway.
EP-IP-400 Rev. 8 Page 4 of 16
[6] Evacuation Exposure Period - The period during which those being evacuated are exposed to the radioactive plume.
[7] Gao Release Seauence - A situation in which the core is overheated and/or uncovered and there is no rapid means for restoring coolant to the core. Without cooling, overheating and failure of the fuel cladding will occur.
[8] MEMA/OEP - Massachusetts Emergency Management Agency/Office of Emergency Preparedness.
[9] MDPH - Massachusetts Department of Public Health.
[10] Offsite - The area outside the owner controlled area.
[11] Proiected Exposure Time - That period of time in which the offsite population will be exposed to radiation as a result of an airborne radioactive release.
4.0 DISCUSSION None 5.0 RESPONSIBILITIES
[1] The Emergency Director is responsible for recommending protective actions to offsite agencies (MEMA/OEP, State Police, EPZ and host communities) to protect the health and safety of the general public.
[2] The Emergency Offsite Manager is responsible for recommending offsite protective actions to the Emergency Director following discussions with the Offsite Radiological Supervisor and the Operations Advisor.
[3] The Offsite Radiological Supervisor is responsible for determining the need for offsite protective actions, based on radiological considerations, and for providing these recommendations to the Emergency Offsite Manager.
[4] The Operations Advisor is responsible for determining the need for offsite protective actions, based on plant conditions, and for providing these recommendations to the Emergency Offsite Manager.
EP-IP-400 Rev. 8 Page 5 of 16
6.0 PROCEDURE
6.1 BACKGROUND
[1] Protective Action Recommendations (PARs) are made by PNPS personnel whenever a General Emergency is declared. Additionally, if in the opinion of the Emergency Director conditions warrant the issuance of PARs, a General Emergency will be declared (PNPS will not issue PARs for any accident classified below a General Emergency).
[2] PARs provided in response to a radioactive release include evacuation and taking shelter.
(a) Dose assessment results which indicate exposure > 1 rem whole body (EPA TEDE) or > 5 rem thyroid (EPA CDE thyroid) should be used as the threshold for dose-based evacuation PARs.
(b) Evacuation is the preferred action unless external conditions impose a greater risk from the evacuation than from the dose received.
(c) PNPS personnel do not have the necessary information to determine whether offsite conditions would require sheltering instead of an evacuation. Therefore, an effort to base PARs on external factors (such as road conditions, traffic/traffic control, weather, or offsite emergency worker response) should not be attempted.
[3] At a minimum, a plant condition-driven PAR to evacuate the 2 mile ring and 5 miles downwind, and shelter all other subareas, is given at the declaration of a General Emergency. Depending on the plant conditions, evacuation of a 5 mile radius and 10 miles downwind, and shelter all other subareas, may be issued instead of the minimum PAR.
(a) PARs are included with the initial and follow-up notifications issued at a General Emergency.
(b) The PAR must be provided to the Commonwealth within 15 minutes, and to the NRC within 60 minutes of:
(1) The General Emergency classification.
(2) Any change in recommended actions.
EP-IP-400 Rev. 8 Page 6 of 16
[4] The Emergency Director may elect to specify the PARs for any combination of subareas or the entire EPZ (or beyond) regardless of plant and dose-based guidance. However, dose-based PARs should not normally be extended based on the results of hypothetical dose projections. Plant-based PARs are inherently conservative such that expanding the evacuation zone as an added precaution could result in a greater risk from the evacuation than from the radiological consequences of a release. It also would dilute the effectiveness of the offsite resources used to accommodate the evacuation.
Plant-based PARs should only be extended as provided for in Steps 6.2[5] and 6.2[6]
and Section 6.3.
[5] Protective actions taken in areas affected by plume deposition following the release are determined and controlled by offsite governmental agencies.
(a) PNPS is not expected to develop offsite recommendations involving ingestion or relocation issues following plume passage.
(b) PNPS may be requested to provide resources to support the determination of postplume protective actions.
[6] Throughout the duration of a General Emergency, assess plant conditions and effluent release status to ensure the established PARs are adequate.
[7] Additional protective action guidance is provided in Attachment 2 (Accident Phases and Exposure Pathways).
6.2 PLANT-BASED PROTECTIVE ACTION RECOMMENDATIONS
'- [1] Use Attachment 1 (Protective Action Recommendation Process) as an aid in determining the proper PAR.
[2] At a minimum, evacuation of the 2 mile ring and 5 miles downwind (with sheltering of all other subareas) will be recommended for a declaration of General Emergency.
[3] For plant conditions in which substantial core damage is imminent or has occurred AND a significant release of Reactor coolant into the containment is imminent or has occurred AND containment failure is imminent or has occurred, evacuation of the 5 mile ring and 10 miles downwind (with sheltering of all other subareas) will be recommended.
(a) Indications that substantial core damage is imminent or has occurred include:
(1) Core damage > 1% melt.
(2) CHRMs reading > General Emergency EAL 1.4.1.4 threshold values.
(3) Containment hydrogen reading > 18%.
(4) Core temperatures > 2400'F.
EP-IP-400 Rev. 8 Page 7 of 16
(5) RPV water level cannot be restored and maintained above -150 inches (Minimum Steam Cooling RPV Water Level) for an extended period of time AND no Core Spray subsystem flow can be restored and maintained above 3,600 GPM (design Core Spray flow).
(6) RPV water level cannot be restored and maintained above -175 inches (elevation of jet pump suction) for an extended period of time.
(b) Indications that a significant release of Reactor coolant is imminent or has occurred include:
(1) A large break (> approximately 6") loss of coolant accident.
(2) The presence of hydrogen gas in containment not attributable to chemistry processes.
(3) Excessive leakage or makeup not attributable to operating conditions or transients.
(4) Rapid vessel depressurization.
(c) Indications that containment failure is imminent or has occurred include:
(1) A release of radioactivity that cannot be maintained below the General Emergency criteria of EAL 5.0 classifications.
(2) Primary Containment pressure cannot be maintained below the PCPL curve (EOP Figure 7).
(3) Primary Containment H2 and 02 gas concentrations cannot be maintained below combustible limits (_>6% hydrogen and Ž 5% oxygen).
(4) EOPs are entered and actions have begun which will lead to the emergency venting of containment.
[4] Containment monitors can provide indication of both core damage and RCS leakage.
Monitor values used to determine a specific amount of core damage are dependent on plant conditions, power history, and time after shutdown. Monitor readings used to quantify an amount of damage or coolant leakage should be complimented by other indications and engineering judgment.
[5] If no release is in progress, then:
(a) Perform dose projections on possible conditions as time permits to determine whether Protective Action Guides (PAGs) could be exceeded.
(b) Consider adding any subareas requiring evacuation as determined by dose projection to the plant-based PARs.
EP-IP-400 Rev. 8 Page 8 of 16
6.3 DOSE ASSESSMENT-BASED PROTECTIVE ACTION RECOMMENDATIONS NOTE Dose projections are not required to support the decision process in Attachment 1 (Protective Action Recommendation Process).
[1] In the event dose assessment results indicate the need to recommend actions beyond the outer EPZ boundaries, that is past 10 miles:
(a) Dispatch Radiation Monitoring Teams to downwind areas to verify the calculated exposure rates prior to issuing PARs outside the EPZ.
(b) Many assumptions exist in dose assessment calculations, involving both source term and meteorological factors, which make predictions over long distances highly questionable.
[2] From the Control Room: If a release is in progress and time permits, direct the SCRE or other qualified SRO to perform offsite dose assessment in accordance with EP-IP-300 to determine whether the plant-based PARs of Attachment 1 are adequate.
[3] From the Emerqency Operations Facility: Conduct offsite dose assessment in accordance with EP-IP-300 to determine whether the plant-based PARs of Attachment 1 are adequate using the following methods as applicable:
(a) Monitored Release:
(1) If a release is in progress, assess the calculated impact to determine whether the plant-based PARs of Attachment 1 are adequate.
(2) If a release is not in progress, use current meteorological and core damage data to project effluent monitor threshold values which would require 2, 5, and 10 mile evacuations (Attachment 3). Reestablish threshold values whenever meteorological conditions or core damage assessment values change.
(b) Containment Leakace/Failure:
(1) If a release is in progress, assess the calculated impact to determine whether the plant-based PARs of Attachment 1 are adequate.
(2) If a release is not in progress, use current meteorological and core damage data on various scenarios (design leakage, failure to isolate, catastrophic failure) to project the dose consequences to determine whether the plant-based PARs of Attachment I are adequate.
Reestablish scenario values whenever meteorological conditions or core damage assessment values change.
EP-IP-400 Rev. 8 Page 9 of 16
(c) Field Team Analysis: Actual field readings from Radiation Monitoring Teams should be compared to dose assessment results and used as a dose projection method to validate calculated PARs and to determine whether the plant or release-based protective actions of Attachment 1 are adequate.
(d) Release Point Analysis: Actual sample data from monitored or unmonitored release points should be utilized in conjunction with other dose assessment and projection methods to validate calculated PARs and to determine whether the plant-based protective actions of Attachment 1 are adequate.
[4] The Emergency Director, the Emergency Offsite Manager, and the Offsite Radiological Supervisor shall discuss dose assessment and projection analysis results and evaluate their applicability prior to issuing PARs to the Commonwealth.
7.0 RECORDS All forms and other documentation shall be reviewed for completeness and forwarded to the Emergency Preparedness Manager.
8.0 ATTACHMENTS ATTACHMENT 1 - PROTECTIVE ACTION RECOMMENDATION PROCESS ATTACHMENT 2 - ACCIDENT PHASE AND EXPOSURE PATHWAYS ATTACHMENT 3 - PROTECTIVE ACTION RECOMMENDATION BOUNDING CALCULATIONS ATTACHMENT 4 - DOCUMENT CROSS-REFERENCES ATTACHMENT 5 - IDENTIFICATION OF COMMITMENTS EP-IP-400 Rev. 8 Page 10 of 16
ATTACHMENT 1I Sheet 1 of 2 PROTECTIVE ACTION RECOMMENDATION PROCESS I-e 1: Deemn Emrec elaeSau Go to PARs A
Go to PARs A
IStep, 2: Determine the Appropriate PARS PARs General No No PARS Required Emergency NoN A R A Declared?
PARs Yes B Substantial core damage is imminent or has occurred.
AND r 1
A significant release of reactor Evacuate 2 Mile Ring & 5 Miles coolant is imminent or has occurred. Downwind. Shelter all other subareas.
AND . m Containment failure is imminent or has occurred.
4Yes Evacuate S Mile Ring & 10 Miles Downwind. Shelter all other subareas.
EP-IP-400 Rev. 8 Page 11 of 16
Sheet 2 of 2 1 SATTACHMENT PROTECTIVE ACTION RECOMMENDATION PROCESS (CONT.)
- 1) CONTROL ROOM ONLY: Qualified individual is immediately available to perform dose assessment.
- 2) Perform dose assessment as soon as possible to verify that the release is below/above PAGs and to determine whether additional subareas require evacuation.
- 3) Indications that substantial core damage is imminent or has occurred include:
"* Core damage > 1% melt.
"* CHRMs reading > General Emergency EAL 1.4.1.4 threshold values.
"* Containment hydrogen reading > 18%.
"* Core temperatures > 2400'F.
"* RPV water level cannot be restored and maintained above -150 inches (Minimum Steam Cooling RPV Water Level) for an extended period of time AND no Core Spray subsystem flow can be restored and maintained above 3,600 GPM (design Core Spray flow).
- RPV water level cannot be restored and maintained above -175 inches (elevation of jet pump suction) for an extended period of time.
- 4) Indications that a significant release of Reactor coolant is imminent or has occurred include:
"* A large break (> 6") loss of coolant accident.
"* Presence of hydrogen gas in containment not attributable to chemistry processes.
"* Excessive leakage or makeup not attributable to operating conditions or transients.
"* Rapid vessel depressurization.
- 5) Indications that containment failure is imminent or has occurred include:
"* A release of radioactivity that cannot be maintained below the General Emergency criteria of EAL 5.0 classifications.
"* Primary Containment pressure cannot be maintained below the PCPL curve (EOP Figure 7).
"* Primary Containment H2 and 02 gas concentrations cannot be maintained below combustible limits
(> 6% hydrogen and 2 5% oxygen).
"* EOPs are entered and actions have begun which will lead to the emergency venting of containment.
2 Mile Ring, 5 Miles Downwind 5 Mile Ring, 10 Miles Downwind Wind Direction Affected Wind Direction Affected Subareas (0 From) Subareas (0 From) 0200-0690 1,12,2,3 0200-0210 [1,12, 2, 3, 4, 5, 6 0700-1220 1, 12,3 0220-0560 1, 12, 2, 3, 4, 5, 6,11 1230 - 1400 1,12,3,4 0570-0660 1, 12, 2, 3, 4, 6, 11 1410- 1830 1, 12,4 0670.0690 1, 12, 2, 3, 4, 6, 7, 11 1840-3050 1,12 0700-1030 1,12,2,3,4,6,7,8, 11 3060-0190 1,12,2 1040.1090 1,12,2,3,4,6,7,8,9,11 Any Subareas requiring evacuation 1100. 1150 11,12,2,3,4,6,7,8,9 as determined by Dose Assessment 116°-1290 11, 12, 2, 3, 4, 7, 8, 9 are added to the plant-based PARs. 1300-1320 1, 12, 2, 3, 4, 7, 8, 9, 10 Shelter All Other Subareas 1330.1400 1,12,2,3,4,8,9,10 1410.1750 1, 12, 2, 3, 4, 9, 10 1760-1790 1, 12, 2, 3, 4, 10 1800.3180 1,12,2,3,4 3190-0190 1, 12, 2, 3, 4, 5 Shelter All Other Subareas EP-IP-400 Rev. 8 Page 12 of 16
ATTACHMENT 2 Sheet 1 of 1 ACCIDENT PHASE AND EXPOSURE PATHWAYS Potential Exposure Pathways Protective And Incident Phases Actions
- 1. External radiation from Shelter the facility. Evacuation Access Control
- 2. External radiation from Shelter the plume. Evacuation Access Control
- 3. Inhalation of activity in I Shelter Early Administration of KI the plume.
Evacuation Access Control
- 4. Contamination of skin Shelter and clothes. Evacuation Decontamination of Persons
- 5. External radiation from Evacuation ground deposition. Relocation Decontamination of Land Decontamination of Property
- 6. Ingestion of contaminated Food and Water Controls food and water.
- 7. Inhalation of resuspended Relocation activity. Decontamination of Land Decontamination of Property Note: The use of stored animal feed and uncontaminated water to limit the uptake of radionuclides by domestic animals in the food chain can be applicable in any of the phases.
EP-IP-400 Rev. 8 Page 13 of 16
ATTACHMENT 3 Sheet 1 of 1 PROTECTIVE ACTION RECOMMENDATION BOUNDING CALCULATIONS Name: Date: Time:
Basis Monitor Reading Monitor SB-2 Mile 2-5 Mile 5-10 Mile Wind Speed: Evacuation Evacuation Evacuation Wind Direction: Main Stack Reactor Stability Class: Building Turbine Release Duration: Building Notes:
- 1. Insert "N/A" in monitor reading boxes where threshold values will not provide a dose necessary to drive the evacuation.
- 2. Site Boundary to 2 mile evacuations require an indicated dose:
> 1 rem Whole Body > 5 rem Thyroid at the Site Boundary and
< 1 rem Whole Body and < 5 rem Thyroid at 2 miles.
- 3. 2 to 5 mile evacuations require an indicated dose:
> 1 rem Whole Body or > 5 rem Thyroid at 2 miles and
< 1 rem Whole Body and < 5 rem Thyroid at 5 miles.
- 4. 5 to 10 mile evacuations require an indicated dose > to 1 rem Whole Body or Ž5 rem Thyroid at 5 miles.
EP-IP-400 Rev. 8 Page 14 of 16
ATTACHMENT 4 Sheet 1 of 1 DOCUMENT CROSS-REFERENCES This Attachment lists those documents, other than source documents, which may be affected by changes to this Procedure.
Document Number Document Title EP-IP-100 Emergency Classifications EP-IP-300 Offsite Dose Assessment EP-IP-330 Core Damage EP-IP-400 Rev. 8 Page 15 of 16
ATTACHMENT 5 Sheet 1 of 1 IDENTIFICATION OF COMMITMENTS This Attachment lists those external commitments (i.e., NRC commitments, QA audit findings, and INPO inspection items) implemented in this Procedure.
Reference Document Commitment Affected Section(s)/Step(s)
NRC Inspections Finding Provide recommended protective actions 6.2, 5.3, Att. 1 81-15-38 based on actual and projected core/containment conditions and offsite factors which may impact on the effectiveness of the recommendations and consider the near-site population.
NRC Inspection Finding Include discussion of radiological data 6.3.5 84-35-06 analysis and evaluation by key EOF staff members prior to making protective action recommendations to the state.
QA Audit Report 86-74 As part of the protective actions 6.2, Att. 1 Recommendation recommendation procedure, include offsite 86-74-08 protective action decision making based on plant conditions as suggested in NUREG 0654, Appendix 1, and NRC IE Information I Notice 83-28.
EP-IP-400 Rev. 8 Page 16 of 16