ML020600093
| ML020600093 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 02/15/2002 |
| From: | Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Security and Incident Response |
| References | |
| Download: ML020600093 (68) | |
Text
PILGRIM NUCLEAR POWER STATION CONTROLLED DOCUMENT TRANSMITTAL NOTICE VOCUMENT TITLE: 2dp-K /ldý )(ev. /7 4Ael- 0o'
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TO: MAIL:
CONTROLLED COPY NO.: 1/ TRANSMITTAL NO.: 0.2 -6* 1 DATE: 0A FOR DOCUMENT CONTROL USE ONLY
_ 1. The attached controlled document(s) are transmitted for 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, sign 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.
7f you do not have these documents, check Block 5 and a new copy will be issued.
/-74. 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 Supervisor.
COPY HOLDER CHECK ONE
// 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 attachments 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 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 Controlled Copy No.
P Transmittal No. :02 - 06 Y Date.,
Please update your copy of &P - /,., /'
with the attachments to this transmittal as instru ted below.
REV. REV.
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Emergency Plan Implementing I PNPSI Number:
Procedure Manual N/A RType H8.24 TABLE OF CONTENTS Effective Number Title Revision Date EP-IP-100 Emergency Classification and Notification 17 02/15/02 EP-IP-200 On-Call Emergency Director 9 02/07/01 EP-IP-201 Emergency Plant Manager 2 08/08/01 EP-IP-202 Company Spokesperson 3 02/07/01 EP-IP-210 Control Room Augmentation 7 12/12/00 EP-IP-225 Severe accident Management Support 0 02/15/02 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 4 08/08/01 EP-IP-231 Onsite Radiation Protection 6 08/29/01 EP-IP-240 Emergency Security Organization Activation and 9 09/17/01
Response
EP-IP-250 EOF Activation and Response 9 02/07/01 EP-IP-251 Offsite Radiation Protection 5 12/26/00 EP-IP-252 Facilities Support 7 02/01/01 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 4 09/17/01 EP-IP-300 Offsite Radiological Dose Assessment 4 05/01/01 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 4 12/10/01 EP-IP-400 Protective Action Recommendations 9 10/03/01 Page 1 of 2 Revision 75 02/15/02 Page 1 of 2 Revision 75
Emergency Plan Implementing Number: NI PNPS jProcedure Manual N/A RType H8.24 TABLE OF CONTENTS Effective Number Title Revision Date EP-IP-410 Evacuation/Assembly 5 09/17/01 EP-IP-420 Search and Rescue 3 02/12/01 EP-IP-440 Emergency Exposure Controls 6 08/08/02 EP-IP-501 Transport of Contaminated Injured Personnel 3 05/24/00 EP-IP-520 Transition and Recovery 5 02/07/01 2 of 2 Revision 75 02/15/02 Page Page 2 of 2 Revision 75
RTYPE H8.24 PILGRIM NUCLEAR POWER STATION Procedure No. EP-IP-100 EMERGENCY CLASSIFICATION AND NOTIFICATION Stop Think STA R Act Review SAFETY RELATED EP-IP-100 Rev. 17
REVISION LOG REVISION 17 Date Originated 1/02 Pages Affected Description 9-11,15,31,42,43 Replace OSS with Shift Manager to reflect organizational title change.
27 Revise the sustained RPV water level from < -160 inches to
< -165 inches for EAL 2.1.1.4.
27 Revise EAL wording to add "Reactor power > 3%" as one of the entry conditions for EAL 2.3.1.3.
28 Revise EAL wording to "Bulk drywell temperature cannot be restored and maintained < -280°F" and change figure reference for the HCTL curve from "Figure 3" to "Figure 2" for EAL 3.2.1.3.
28 Delete EAL 3.3.1.4, Primary Containment water level cannot be maintained < 77 feet.
28 Revise wording in EAL 3.3.1.3 to "Torus water level cannot be maintained below 175 inches (SRV Tail Pipe Level Limit (STPLL))".
28 Revise EAL wording from "Torus pressure" to "Torus Bottom pressure" and change figure reference from "EOP Figure 7" to "EOP Figure 4" for EAL 3.4.1.4.
REVISION 16 Date Originated 11/01 Pages Affected Description 27 Revise EAL 1.4.1.4 and EAL 1.4.1.3 for Torus High Range Area Radiation Monitors due to relocation of detectors.
REVISION 15 Date Originated 5/01 Pa.qes Affected Description 14 Change the term from "current" to "prior" classification level for instructions when lowering a classification.
27 Revise EAL 1.4.1.4 and EAL 1.4.1.3 for Drywell and Torus High Range Area Radiation Monitors.
31 Correct Seismic Recorder Operating annunciator panel location for EAL 7.4.3.1.
EP-IP-100 Rev. 17 Page 2 of 47
TABLE OF CONTENTS Page 1.0 P UR P O S E ........................................................................................................ 5 2 .0 R E F E R E NC E S ........................................................................................... ...... 5 3 .0 D E F INIT IO NS ................................................................................................... 5 4 .0 R E S P O NS IB ILIT IE S ........................................................................................ 9 5 .0 P RO C E D UR E ............................................................................................... .. 10 5.1 RECOGNIZING AN EMERGENCY ...................................................... 10 5.2 INITIAL DECLARATION OF AN EMERGENCY FROM TH E C O NTRO L RO O M....................................................................... 10 5.3 WHILE IN A CLASSIFIED EMERGENCY ............................................. 12 5.4 TRA N SITO RY EV ENTS ....................................................................... 13 5.5 DOWNGRADING EMERGENCY CLASSIFICATIONS ......................... 14 5.6 TRANSITION TO RECOVERY ............................................................. 15 5.7 INITIAL NOTIFICATION FORM DESCRIPTION .................................. 15 5.8 FOLLOW-UP INFORMATION FORM DESCRIPTION ......................... 17 6 .0 R E C O R D S ................................................................................................... . . 18 7.0 ATT 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. 17 Page 3 of 47
TABLE OF CONTENTS (Continued)
Pa~ae 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 RG A NIZATIO N ............................................................ 42 ATTACHMENT 11 - DOCUMENT CROSS-REFERENCES ............................ 46 ATTACHMENT 12 - IDENTIFICATION OF COMMITMENTS ......................... 47 EP-IP-100 Rev. 17 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, "PNPS Emergency Plan"
[3] PNPS Technical Specifications 3.0 DEFINITIONS
[1] Adequate 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 Spray 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 Cooling is relied upon only if RPV water level cannot be restored and maintained above the top of the active fuel, 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. 17 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°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 0 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:
The limiting fuel temperature is lower (1500°F). The higher limit of 1800°F is used only when cladding perforation cannot be avoided.
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] 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).
[5] Cannot Be Maintained Above/Below - The value of the identified parameter(s) is not able to be kept above/below specified limits. This determination includes making an evaluation that considers both current and future system performance in relation to the current value and trend of the parameter(s). It does not imply that the actual value of the parameter must first pass the specified limit.
[6] Cannot Be Restored Above/Below - The value of the identified parameter(s) is not able to be returned to above/below specified limits after having passed those limits. This determination includes making an evaluation that considers both current and future system performance in relation to the current value and trend of the parameter(s). It does not imply any specific time interval, but does not permit prolonged operation beyond the limit without declaring the specified emergency classification. (May be used in combination with Definition 3.0[5].)
EP-IP-100 Rev. 17 Page 6 of 47
[7] 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.
[8] Controlled Process - A preplanned activity for which the conditions specified in an EAL are anticipated to be or are intentionally exceeded as part of an approved Procedure.
[9] DNN - Digital Notification Network.
[10] Emergency Radioactive Release is/is not in Progress - For purposes of offsite notification, any release of radioactivity is considered 'an emergency radioactive release in progress which:
Meets any EAL of Classification Subsection 5.1, Effluent Monitors OR Involves an actual or suspected Turbine Building or unmonitored release which is associated with the emergency event.
[11] Emergency Radioactive 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, an emergency radioactive release is considered above PAGs when:
General Emergency EAL 5.2.1.4 or EAL 5.2.2.4 is exceeded based on having dose projections or offsite measurements.
OR In the absence of having dose projections or offsite measurements. General Emergency EAL 5.1.1.4 is exceeded.
[12] ENS - NRC Emergency Notification System.
[13] Essential Information Checklist - The form used by oncoming Emergency Director when relieving present Emergency Director of the responsibilities outlined in this Procedure.
This form may also be used to provide information to Media Center and Corporate personnel.
EP-IP-100 Rev. 17 Page 7 of 47
[14] Essential Personnel - Those individuals assigned specific emergency response duties as identified in the PNPS Emergency Plan and Implementing Procedures.
[15] Follow-Up Information Form - The form used to initiate and document periodic emergency classification updates to offsite agencies.
[16] General Emergency - Events are in progress or have occurred which involve actual or imminent substantial core degradation or melting with the potential for loss of containment integrity. Releases can be expected to exceed EPA Protective Action Guideline exposure levels for more than the area near the site boundary.
[17] Initial Notification Form - The form used to initiate and document initial emergency classification notifications to offsite agencies.
[18] Non-Essential Personnel - Personnel who are not assigned specific emergency response duties.
[19] 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.
[20] Radiation Monitor Channel A and BAbove/Below EAL Threshold Readings - 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.
[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 EmerQency - 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.
EP-IP-100 Rev. 17 Page 8 of 47
[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.
4.0 RESPONSIBILITIES
[1] The Shift Manager, or the Control Room Supervisor if the Shift Manager is incapacitated or away from the Control Room, shall be responsible for the initial emergency classification declaration and implementation of this Procedure.
[2] The Shift Manager, or Control Room Supervisor if the Shift Manager is unavailable, shall assume the role of Emergency Director upon initial declaration of any emergency classification and shall continue to function as the Emergency Director until relieved of those duties by the on-call Emergency Director or other qualified individual (i.e.,
Emergency Plant Operations Supervisor or off-shift Shift Manager).
[3] The Emergency Director is the final authority for determining the emergency classification level (initial classification, downgrading, or terminating to recovery). This authority may not be delegated.
[4] The Emergency Director is responsible for directing and overseeing notification of the on-call PNPS Emergency Response Organization.
"- [5] The Control Room Operations Assistant or a designated alternate is responsible for the 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.
EP-IP-100 Rev. 17 Page 9 of 47
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 Levels (Attachment 5).
[2] Identify the highest emergency classification level (if multiple EALs are exceeded) for 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 progress or suspected, evaluate the applicability of offsite dose-based EALs (category 5.2).
(c) If a classification level was met or exceeded but the classifiable condition no longer exists (a lesser classification level may or may not still be appropriate),
refer to Section 5.4, Transitory Events.
5.2 INITIAL DECLARATION OF AN EMERGENCY FROM THE CONTROL ROOM
[1] The Shift Manager, or Control Room Supervisor if the Shift Manager is unavailable, shall announce to the Control Room operating staff:
(a) That an emergency has been declared.
(b) The emergency classification level.
(c) That the Shift Manager (Control Room Supervisor) has assumed the role of Emergency Director.
[2] Conduct initial emergency notifications as follows:
NOTE In the event the public address system is inoperative during notifications to Station personnel at any time, determine alternate means to disseminate information to plant personnel.
(a) For events which are classified as a General Emergency, complete the General Emergency Notifications Checklist (Attachment 4).
EP-IP-100 Rev. 17 Page 10 of 47
NOTE If during the declaration process it becomes necessary to upgrade 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.
(b) For events which are classified as a Site Area Emergency, complete the Site Area Emergency Notifications Checklist (Attachment 3).
(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 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 Shift Manager 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.
EP-IP-100 Rev. 17 Page 11 of 47
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 upgqrade 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).
(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).
[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.
EP-IP-100 Rev. 17 Page 12 of 47
[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.
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.
EP-IP-100 Rev. 17 Page 13 of 47
(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, "Transitionand Recovery."
[3] For situations which begin in a classified emergency then experience events which ultimately result in:
(a) A return to the current classification level Complete and distribute an Initial Notification Form to specify the transitory event classification level and signify return to the current classification level.
NOTE Transitory events which occur during an emergency cannot directly result in a downgraded classification level or entry into Recovery. These actions must be performed separately.
(b) A lower classification level or no longer meet a classification level Complete and distribute an Initial Notification Form to specify the transitory event classification level and signify return to the prior classification level.
[4] Return to Section 5.3.
5.5 DOWNGRADING EMERGENCY CLASSIFICATIONS
[1] Once in an Alert or higher classification level, the decision to downgrade below the Alert level shall only be made after the TSC, OSC, and EOF have been activated.
[2] Have the Control Room make the following announcement over the public address system, TWICE:
"Attention all personnel, attention all personnel: The emergency classification level has been downgraded to a/an (applicable classification level)."
[3] Complete and distribute an Initial Notification Form to signify entry into the lower emergency classification level.
[4] Return to Section 5.3.
EP-IP-100 Rev. 17 Page 14 of 47
5.6 TRANSITION TO RECOVERY
[1] If a state of emergency is no longer necessary based on plant status conditions, complete the Termination Checklist (Attachment 8) to determine whether conditions allow termination of the event and entry into Recovery.
[2] If conditions allow for termination of the emergency and entry into Recovery, exit this Procedure and enter EP-IP-520, "Transitionand Recovery".
[3] If conditions do not 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 NOTE 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.
[2] 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 Shift Manager) 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. 17 Page 15 of 47
[4] Block 3: 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) EAL number 0.0.0.0 is used to signify entry into Recovery.
(c) 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 (and the transitory event if applicable).
[5] Block 4: 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.
[6] Block 5: Provides the most recent meteorological data obtained from any of the available sources.
[7] Block 6: 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 Necessary" 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.
(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.
[8] Block 7: Indicates the time and date when transmission of the form was begun and the name of the individual performing the transmission.
[9] Block 8: Indicated the time and date when transmission of the form was received and the name of the individual receiving the transmission.
[10] Block 9: Provides the protective action recommendations made by PNPS ERO 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. 17 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. 17 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.
[11] Block 10: Indicates the time and date when transmission of the form was received and the name of the individual receiving the transmission.
[12] Block 11: Provides the protective action recommendations and their bases made by PNPS ERO personnel when MEMA or MDPH representatives are present in the EOF (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. 17 Page 18 of 47
7.0 ATTACHMENTS
'v ATTACHMENT 1 - UNUSUAL EVENT NOTIFICATIONS CHECKLIST ATTACHMENT 2 - ALERT NOTIFICATIONS CHECKLIST ATTACHMENT 3 - SITE AREA EMERGENCY NOTIFICATIONS CHECKLIST ATTACHMENT 4 - GENERAL EMERGENCY NOTIFICATIONS CHECKLIST ATTACHMENT 5 - EMERGENCY ACTION LEVELS ATTACHMENT 6 - SAMPLE - INITIAL NOTIFICATION FORM ATTACHMENT 7 - SAMPLE - FOLLOW-UP INFORMATION FORM 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. 17 Page 19 of 47
ATTACHMENT 1 Sheet I 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 (briefdescription of initiatingevent). 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 5.4[1])
EP-IP-100 Rev. 17 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 (brif description of initiatinq 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 persons with disabilities 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.
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. 17 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 Ensure Security has evacuated and closed public access areas.
Time Completed:
RETURN TO THE PROCEDURE (EITHER STEP 5.2[2], 5.3[2](a), OR 5.4[1])
EP-IP-100 Rev. 17 Page 22 of 47
ATTACHMENT 3 Sheet I of 2 SITE AREA EMERGENCY ASSEMBLY AREA DESIGNATION Determine the Assembly Area based on meteorological conditions as follows:
Assembly Area Wind Direction (0 from)
LJ Support Building Cafeteria 0000-2890 or 3240-3600 L- Chiltonville Training Center 2900-3230 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 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 entering from no event or an Unusual Event:
"Attention all personnel, attention all personnel: A Site Area Emergency has been declared due to (briefdescription of event). All on-call Emergency Response Organization members report to your designated emergency response facility. All other personnel evacuate to (Assembly Area)."
If upgrading from an Alert:
"Attention all personnel, attention all personnel: A Site Area Emergency has been declared due to (brief description 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. 17 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. Ifthere is a potential for an airborne radiological release, consider announcing that there will be no eating, drinking, or smoking until further notice.
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:
ACTION VERIFICATION Ensure Security has evacuated and closed public access areas.
Tirne Completed:
I RETURN TO THE PROCEDURE (EITHER STEP 5.2[2], 5.3[2](a), OR 5.4[1])
EP-IP-100 Rev. 17 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 (I from)
Ll Support Building Cafeteria 0000-2890 or 3240-3600 UI- Chiltonville Training Center 2900-323° 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 enterinq into a General Emergency from an Alert or lower: "Attention all personnel, attention all personnel: A General Emergency has been declared due to (briefdescription 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 upgqrading from an Site Area Emergqency: "Attention all personnel, attention all personnel:
A General Emergency has been declared due to (brief description of event). There will be no eating, drinking, or smoking until further notice."
Continued on next page.
EP-IP-100 Rev. 17 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.
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:
ACTION VERIFICATION Ensure Security has evacuated and closed public access areas.
Time Completed:
RETURN TO THE PROCEDURE (EITHER STEP 5.2[2] OR 5.3[2](a))
EP-IP-100 Rev. 17 Page 26 of 47
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ATTACHMENT 5 Sheet 1 of 5 1.0 REACTOR FUEL 9* T GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT 1.1 Coolant 1.1.1.4 1.1.1.2 1.1.1.1 Activity Reactor coolant system sample activity which indicates a Reactor coolant system sample activity Reactor coolant system sample activity core melt condition as determined by EP-IP-330, "Core > 200 microcuries/ml total iodine. > 20 microcuries/ml total iodine.
Damage." asdeterminedbyEP 1.2 Off-gas 1.2.1.2 1.2.1.1 Activity Air ejector off-gas radiation monitors 1705-3A and B Air ejector off-gas radiation levels approaching Technical Panel 910 reading > 20,000 mR/hr. Specification release limits as indicated by Air Ejector Off-gas Radiation Monitors 1705-3A and B Panel 910 High-High alarm which does not clear within 13 minutes.
1.3 Thermal Limits 1.3.1.1 MCPR < Technical Specification fuel cladding integnty safety limit.
1.4 Radiation 1.4.1.4 1.4.1.3 1.4.1.2 Monitors Valid Drywell High Range Area Radiation Monitor reading Valid Drywell High Range Area Radiation Monitor reading Refuel Floor Ventilation Exhaust Radiation (RFVE)
> 3400 R/hr (RIT-1001-606A and B) or Valid Torus High > 650 R/hr (RIT-1001-606A and B) or Valid Torus High Monitor 1705-8 Channel A(A/C) and Channel B(B/D) High Range Area Radiation Monitor reading > 100 RPhr Range Area Radiation Monitor reading > 4 RJhr trip Panel 910.
(RIT-1001-607A and B) due to degraded reactor fuel (RIT-1001-607A and B) due to degraded reactor fuel AND integrity conditions. integrity conditions. Upscale alarm on two or more of the following Area Radiation Monitors Panel 911 which cannot be attributed to a controlled process:
- New fuel storage area (#11)
- Refueling floor spent fuel pool room (#12)
- Refuel floor reactor basin separator (#13)
- Refuel floor reactor basin spent fuel area (#14) 2.0 REACTOR PRESSURE VESSEL 2.1 Reactor Water 2.1.1.4 2.1.1.3 2.1.1.2 2.1.1.1 Level Sustained RPV water level < -165 inches. RPV water level cannot be maintained above -125 inches RPV water level cannot be determined (RPV Flooding is RPV water level cannot be restored and maintained AND (TAF). required). above -12 inches.
No sources of RPV injection available. AND No sources (EOP 1 Table C Injection Subsystems) of 2.1.2.4 adequate capacity are available to restore water level.
RPV is depressurized and no mechanism of adequate core cooling can be established by injection into the RPV from any source (Primary Containment Flooding is required) 2.2 Reactor 2.2.1.2 2.2.1.1 Pressure Sustained reactor vessel dome pressure > 1325 psig. Reactor vessel dome pressure cannot be maintained
< 1115 psig (except during RPV hydrostatic testing).
2.3 Reactor Power 2.3.1.4 2.3.1.3 2.3.1.2 Reactor power > 3% and torus temperature above the Reactor power > 3% and boron injection into the RPV A reactor Scram has been initiated.
"Boron Injection Initiation Temperature (BIIT) EOP intentionally initiated (boron injection required) with either: AND Figure 4. . Standby Liquid Control System (SBLC). The reactor is not shutdown.
AND EITHER OR
- An SRV is open.
- Drywell pressure > 2.2 psig.
EP-IP-100 Rev. 17 Page 27 of 47
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ATTACHMENT 5 Sheet 2 of 5 3.0 PRIMARY CONTAINMENT 3.1 Drywell 3.1.1.3 3.1.1.1 Temperature Bulk drywell temperature cannot be restored and Bulk drywell temperature cannot be maintained < 150°F maintained < 280'F as determined by PNPS Procedure as determined by PNPS Procedure 2.1.27, "Drywell 2.1.27, "Drywell Temperature Indication." Temperature Indication."
AND Primary containment integrty is required.
3.2 Torus water 3.2.1.3 3.2.1.1 Temperature Torus water temperature cannot be maintained below the Torus water temperature > 110F.
"Heat Capacity Temperature Limit" (HCTL) Figure 2.
3.3 Containment 3.3.1.3 3.3.1.2 3.3.1.1 Water Level Torus water level cannot be maintained below 175 inches Torus water level cannot be maintained < 180 inches. Reactor coolant system to drywell unidentified leakage (SRV Tail Pipe Level Limit (STPLL)). > 5 gpm with reactor coolant temperature > 212TF.
OR 3.3.2.3 Reactor coolant system to drywell total leakage > 25 gpm Torus water level cannot be maintained > 90 inches. with reactor coolant temperature > 212°F.
3.3.2.1 Torus water level cannot be maintained:
- < 132 inches. (-1 inches. narrow range).
- > 127 inches (-6 inches. narrow range).
AND Primary containment integrity is required.
3.4 Primary 3.4.1.4 3.4.1.3 3.4.1.2 Containment Torus bottom pressure approaching 'The Primary Torus bottom pressure cannot be maintained below the Primary containment pressure cannot be maintained Pressure Containment Pressure Limit" (PCPL) EOP Figure 4 (prior "Pressure Suppression Pressure" (PSP) EOP Figure 6 < 2.2 psig (except during testing such as ILRT. etc.)
to initiation of containment venting). (except during testng such as ILRT. etc.).
3.5 Containment 3.5.1.4 3.5.1.3 3.5.1.2 H2 & 02 Drywell or torus hydrogen concentration -Ž 6%. Drywell or torus hydrogen concentration > 1%. Drywell or torus hydrogen concentration > 1%.
AND AND Concentration Drywell or torus oxygen concentration >5% (Prior to Drywell or torus oxygen concentration > 4%.
initiation of containment venting).
3.5.2.4 Drywell or torus hydrogen concentration cannot be determined to be < 6%.
AND Drywell or torus oxygen concentration cannot be determined to be < 5% (Prior to initiation of containment venting).
EP-IP-100 Rev. 17 Page 28 of 47
ATTACHMENT 5 Sheet 3 of 5 4.0 SECONDARY CONTAINMENT 4.1 Secondary 4.1.1.3 4.1.1.1 Containment Secondary containment area water levels exceed the Secondary containment area water levels exceed the Area Water "Maximum Safe Operating Value" in two or more areas "Maximum Safe Operating Value" in two or more areas EOP Table L. EOP Table L Levels AND AND A primary system is discharging into the area. Reactor coolant temperature > 212°F with irradiated fuel AND in the vessel.
Reactor coolant temperature > 212°F with irradiated fuel in the vessel.
4.2 Secondary 4.2.1.3 4.2.1,1 Containment Secondary containment area temperatures exceed the Secondary containment area temperatures exceed the Area "Maximum Safe Operating Value" in two or more areas "Maximum Safe Operating Value" in two or more areas EOP Table L. EOP Table L.
Temperatures AND AND A primary system is discharging into the area. Reactor coolant temperature> 212°F with irradiated fuel AND in the vessel.
Reactor coolant temperature > 212=F with irradiated fuel in the vessel 4.3 Secondary 4.3.1.3 4.3.1.2 Containment Secondary containment radiation levels exceed the General area radiation levels measured in-plant which Area Radiation "Maximum Safe Operating Value" in two or more areas increase by a factor of 1000 times normal as a result of Levels EOP Table L. airborne radioactivity which cannot be attributed to a AND controlled process.
A primary system is discharging into the area.
5.0 RADIOACTIVITY RELEASE 5.1 Effluent 5.1.1.4 5.1.1.3 5.1.1.2 5.1.1.1 Monitors Valid Main Stack Process Radiation Monitor 1705-18 A Valid Main Stack Process Radiation Monitor 1705-18 A Valid Reactor Building Ventilation Exhaust (RBVE) Valid Reactor Building Ventilation Exhaust (RBVE) and B Panel 910 reading > 24E5 cps. and B Panel 910 reading > 2.4E4 cps. monitor 1705-32A and B Panel 910 high-high alarm which monitor 1705-32A and B Panel 910 high alarm which does not clear within 15 minutes from the time action is does not clear within 15 minutes from the time action is taken to isolate the source, taken to isolate the source.
5.1.2.2 5.1.2.1 Valid Main Stack Process Radiation Monitor 1705-18A Main stack radioactivity effluents in excess of the and B Panel 910 reading > 10,000 cps for greater than high-high alarm setpoint for greater than 15 minutes as 15 minutes. indicated by the Main Stack Process Radiation Monitors 1705-18A and B Panel 910.
5.1.3.1 Radwaste Effluent Radiation Monitor (1705-30) high alarm Panel 910.
AND Radwaste discharge is not isolated (FV-7214-A and B).
5.2 Dose 5.2.1.4 5.2.1.3 Projection & Dose projection based on effluent monitors or actual Dose projection based on effluent monitors or actual Environmental environmental measurements which indicate doses in environmental measurements which indicate doses in excess of 1000 mrem whole body or 5000 mrem thyroid at excess of 100 mrem whole body or 500 mrem thyroid at Measurements the site boundary or beyond. the site boundary or beyond.
5.2.2.4 Dose projection based on effluent monitors or actual environmental measurements which indicate dose rates in excess of 1000 mrem/hr whole body or 5000 mrem/hr thyroid at the site boundary or beyond.
5.3 Contaminated 5.3.1.1 Injury Transportation of a contaminated injured person to an offsite medical facility.
EP-IP-100 Rev. 17 Page 29 of 47
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ATTACHMENT 5 Sheet 4 of 5 6.0 INTERNAL EVENTS I. T GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT 6.1 Technical 6.1.1.1 Specifications The plant is not brought to the required operating mode within Technical Specifications LCO Action Statement time.
6.2 Safety 6.2.1.3 6.2.1.2 6.2.1.1 Systems Evacuation of Control Room without establishment of Loss of Control Room habitability (e.g., fire, smoke, Failure of a reactor Safety Relief Valve (RV-203-3A thru plant control from remote shutdown stations within radiological hazards, etc.). D) to close following reduction of applicable pressure as 15 minutes indicated by either:
6.2.2.2 - Accoustic monitor ZI-203 Panel C171.
6.2.2.3 Inability to establish and maintain cold shutdown OR Steam line break outside primary containment without conditions as indicated by:
- SRV tailpipe temperature recorder TR-260-20 isolation. - Reactor Mode Switch in "Shutdown." Panel 921.
AND AND AND Reactor coolant temperature > 212F.
- Reactor coolant temperature cannot be maintained Reactor coolant temperature > 212°F with irradiated fuel
! 212 °F. in the vessel.
6.2.3.3 Inability to immediately isolate any Main Steam Line following a valid PCIS signal (Group I).
AND Reactor coolant temperature > 212'F.
6.3 Electrical 6.3.1.3 6.3.1.2 6.3.1.1 System Sustained loss of all AC power capability as indicated by Loss of all AC power capability as indicated by the Loss of all vital onsite AC power capability as indicated the inability to power any 4kV bus (Al thru A6) from any inability to power any 4kV bus (Al thru A6) from any by:
Failures source (all 4kV buses de-energized). Inability to power Bus A5 from any onsite generator*.
source (all 4kV buses de-energized).
AND 6.3.2.3 6.3.2.2 Inability to power Bus AS from any onsite generator*
Sustained loss of all 125 VDC power capability as Loss of all 125 VDC power capability as indicated by:
- Onsite generators are:
indicated by, Voltage < 105 VCD Panel D-16.
- Main Generator via Unit Auxiliary Transformer Voltage < 105 VDC Panel D-16. AND
- Emergency Diesel Generator A AND Voltage < 105 VDC Panel D-17. Emergency Diesel Generator B Voltage < 105 VDC Panel D-17.
- Station Blackout Diesel Generator 6.3.2.1 Loss of all vital offsite AC power capability as indicated by:
Inability to immediately supply AC power to Bus ASfrom any offsite power supply transformer*.
AND Inability to to immediately supply AC power to Bus A6 from any offsite power supply transformer*.
Offsite power supply transformers are:
- Startup Transformer (X4)
- Shutdown Transformer (X13)
° Main Transformer with Main Generator phase bus links removed (backscuttle) 6.4 Loss of 6.4.1.2 6.4.1.1 Indication, Complete loss of plant process computer alarm and Loss of indications and/or alarms which cause a indications. significant loss of assessment capabilities such as:
Alarm, or AND Loss of indication or annunciation on safety-related Comm Loss of most or all Control Room annunciators. equipment to an extent requiring shutdown by Technical Capability AND Specifications.
Reactor coolant temperature is > 212'F. AND Reactor coolant temperature is > 212F.
6.4.2.1 Loss of all ability to communicate with or adequately activate the Emergency Response Organization as indicated by the complete loss of the onsite telephone systems.
EP-IP-100 Rev. 17 Page 30 of 47
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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 compromise which in the judgment of An ongoing security compromise which in the judgment of Any ongoing security compromise (> 10 minutes) as Any attempted unauthorized entry into the Protected Area the Shift Manager has led to the loss of physical control of the Shift Manager may lead to the loss of physical control determined by the Station Security Force. as determined by the Station Security Force.
the plant. of the plant.
7.1.2.1 Any indication of attempted sabotage.
7.1.3.1 Receipt of a credible bomb threat as determined by the Station Security Force.
7.2 Fire 7.2.1.3 7.2.1.2 7.2.1.1 Any fire which has affected the ability of two or more Fire burning out of control in a plant vital area. Fire within the Protected Area lasting > 10 minutes from Table 7-1 Safety Systems safety systems (Table 7-1) to perform their intended the time firefighting efforts begin (Fire Brigade fire fighting function and poses a significant potential for release of efforts have begun when the Fire Brigade first applies fire radioactivity. fighting agents on the fire.).
Residual Heat Removal AND OR Reactor coolant temperature s 212°F. Any fire onsite for which offsite fire fighting assistance is requested (the required notification of the Plymouth Fire Core Spray Department for any onsite fire does not constitute a request for offsite fire fighting assistance.).
7.3 Man-made Emergency Diesel Generators 7.3.1.3 7.3.1.2 7.3.1.1 Events Any of the following which has affected the ability of two Any of the following events occurring which affect plant Any of the following events occurring onsite:
or more safety systems (Table 7-1) to perform their operation: - Aircraft crash.
High Pressure Coolant Injection intended function and poses a significant potential for
- Aircraft crash on facility. - Explosion (unplanned).
release of radioactivity:
- Missile impact from any source on facility.
- Toxic or flammable gas release.
Automatic Depressurization System . Aircraft crash on facility.
- Entry of toxic or flammable gas into a plant process
- Missile impact from any source on facility, building atmosphere (includes significant Main Reactor Protection System . Entry of toxic or flammable gas into a plant process Generator hydrogen leaks).
building atmosphere. . Explosion (unplanned).
ATVVS/ARI Explosion (Unplanned).
AND Reactor coolant temperature > 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 affected the 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 structures or equipment which affect plant operation: indicated on wind speed recorder Panel MT1.
intended function and poses a significant potential for
- Earthquake Standby Gas Treatment release of radioactivity:
- Tornado 7.4.2.1
- Hurricane Report of a tornado onsite.
Standby Liquid Control . Tornado
- Other Natural Phenomena
. Hurricane 7.4.3.1 Reactor Building Closed Cooling . Other Natural Phenomena 7.4.2.2 Any earthquake detected by seismic instrumentation as AND Any earthquake onsite which has been determined to be indicated by:
Reactor coolant temperature is > 212'F. greater than Operating Basis Earthquake levels (0.08 g). - Seismic monitor event alarm Panel C911.
OR Service Water 7.4.2.3 . "SEISMIC RECORDER OPERATING" annunciator Any earthquake onsite which has been determined to be Panel C903 Right B1.
greater than Safe Shutdown Earthquake levels (0.15 g). AND Ground motion is felt by one or more plant 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 Shift Manager or Emergency Director In the opinion of the Shift Manager or Emergency Director Any event which in the opinion of the Shift Manager or Any event which in the opinion of the Shift Manager or events are in progress which indicate actual or imminent events are in progress which indicate actual or likely Emergency Director could or has caused actual Emergency Director could or has led to a potential core damage and the potential for a large release of failures of plant systems needed to protect the public and substantial degradation of the level of plant safety degradation of the level of safety of the plant.
radioactive material outside the site boundary. pose a significant radioactivity release potential.
8.1.2.1 Any event which in the opinion of the Shift Manager or Emergency Director warrants the prompt notification of Commonwealth and local authorities and precautionary notification of Emergency Response Organization personnel.
EP-IP-100 Rev. 17 Page 31 of 47
ATTACHMENT 6 Sheet 1 of 3 time date Ll ENTERED: I* AN UNUSUAL EVENT L[ HAD A TRANSITORY _J AN ALERT THEN ENTERED: LI A SITE AREA EMERGENCY L[ UPGRADED TO: I] A GENERAL EMERGENCY J DOWNGRADED TO: LII RECOVERY
.J EAL No. BRIEF DESCRIPTION OF EVENT:
4 EMERGENCY RADIOACTIVE RELEASE:
L IIris LI IS NO T ................................................................... IN PRO G R ESS L1 IS ABOVE III IS BELOW .................................. PROTECTIVE ACTION GUIDES
ýJ METEOROLOGICAL DATA AS OF WIND DIRECTION FROM o0TO 0AT mph 6J PNPS's PROTECTIVE ACTION RECOMMENDATIONS (PARS):
III NO PROTECTIVE ACTIONS NECESSARY L- PROVIDED TO MEMA/MDPH GEA1EMRG~YAND EMjPý ISHELTERSUBAREA(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 (circle the affected subareas)
.71NOTIFICATIONINITIATED I ]i date time date name 81 NOTIFICATION RECEIVED I I By F 2time date name EP-IP-100 Rev. 17 Page 32 of 47
ATTACHMENT 6 Sheet 2 of 3 IINITIAL NOTIFICATION FORM (Cont.) I 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):
LJSHELTERSUBAREA(s) 1 2 3 4 5 6 7 8 9 10 11 J-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: I Emergency Director's Signature EP-IP-100 Rev. 17 Page 33 of 47
ATTACHMENT 6 Sheet 3 of 3 INITIAL NOTIFICATION FORM TRANSMISSION INSTRUCTIONS NO:
"(Checkoff the boxes as steps are completed.)
Step 1: TRANSMIT THE FORM Li 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-IO0.
LI Place only the first page of the completed form face down in the DNN fax machine.
Ll 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.
-i 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.
Li Middleboro State Police Li Carver Li Marshfield Li Framingham MEMA Li Duxbury Li Plymouth iJ Bridgewater Li Kingston Li Taunton Li 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 i- Read the information in Block 1 through Block 6.
Li Tell those parties who have complete information to hang up, then provide missing information to remaining parties.
i- Contact locations not answering roll call via BECONS or commercial telephone (speed-dialer) and read the information in Block 1 through Block 6.
Step 4: NOTIFY THE NRC Li Using the ENS or commercial phone, read the information in Blocks 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.
L. Inform the Emergency Director that transmission was completed at time:
COMPLETED BY: Time:
Signature of person making notifications EP-IP-100 Rev. 17 Page 34 of 47
ATTACHMENT 7 Sheet 1 of 3 No.=1 THIS IS: L3A DRILL LJAN ACTUAL EVENT 2 IASOF: ~j j J PILGRIM NUCLEAR POWER STATION IS STILL AT A:
time date JII UNUSUAL EVENT JI ALERT 11 SITE AREA EMERGENCY LJ GENERAL EMERGENCY 3STATION CONDITIONS-ARE: -I IMPROVING III STABLE JLI DEGRADING 4 EAL No. BRIEF DESCRIPTION OF EVENT:
51 OUTSIDE ASSISTANCE: JI HAS [I HAS NOT BEEN REQUESTED
[l AMBULANCE REASON FOR OUTSIDE ASSISTANCE:
LIJ FIRE DEPARTMENT' JI POLICE
_ OTHER (Specify) 6 EMERGENCY RADIOACTIVE RELEASE:
is LISI IS N O T ................................................................... IN PR O G R ESS J IS ABOVE Ll IS BELOW .................................. PROTECTIVE ACTION GUIDES METEOROLOGICAL DATA AS OF STABILITY CLASS WIND DIRECTION FROM 0 TOAT ___A mph 8 PNPS's PROTECTIVE ACTION RECOMMENDATIONS (PARs):
LINO PROTECTIVE ACTIONS REQUIRED
-Wfdlc AiNbff T T G~
L- PROVIDED TO MEMA/MDPH GOROAL 5-MJE-G5_-NCY k b [ U T 0,REsENT INTHit E9F.
J-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 (circle the affected subareas) 9 NOTIFICATION INITIATED I I BYI time date name 10i NOTIFICATION RECEIVEDI I I BY I time date name EP-IP-100 Rev. 17 Page 35 of 47
ATTACHMENT 7 Sheet 2 of 3 FOLLOW-UP INFORMATION FORM (Cont.)i No.- -
NOTE DO NOT TRANSMIT THIS SHEET OVER DNN 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):
[*SHELTERSUBAREA(s) 1 2 3 4 5 6 7 8 9 10 11 LJEVACUATESUBAREA(s) 1 2 3 4 5 6 7 8 9 10 11 12 SINCE PREVIOUS NOTIFICATION, THIS RECOMMENDATION HAS:
1ICHANGED L3 REMAINED THE SAME THIS RECOMMENDATION IS BASED ON:
J PLANT CONDITIONS L[ PROJECTED RELEASE J-ACTUAL RELEASE r721 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: I Emergency Director's Signature EP-IP-100 Rev. 17 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 JI Verify Blocks 1 - 8 are complete, release is approved by signature, and then fill out Block 9 of the form. For guidance on individualBlock descriptions, refer to EP-IP-100.
[J Place only the first page of the completed form face down in the DNN fax machine.
[I 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.
SPick up the DNN ring-down phone and read the following message twice:
"Attention, attention. Please standby for a roll call."
Ll Perform a roll call and check off the responding locations as they are identified.
LI Middleboro State Police LI Carver J Marshfield JI Framingham MEMA LI Duxbury J Plymouth L-1 Bridgewater LI Kingston [1 Taunton
[7 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 LJ 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.
LJ Contact locations not answering roll call via BECONS or commercial telephone (speed-dialer) and read the information in Block 1 through Block 8.
Step 4: NOTIFY THE NRC
-- Using the ENS or commercial phone, read the information in Blocks 1 through 8.
Name of
Contact:
Time:
Step 5: ORGANIZE THE REPORT L Obtain the printed report from the DNN fax machine and staple it to this form.
r- Inform the Emergency Director that transmission was completed at time:
COMPLETED BY: ________________ Time:_____
L Signature of person making notifications EP-IP-100 Rev. 17 Page 37 of 47
ATTACHMENT 8 Sheet 1 of 2 TERMINATION CHECKLIST True False Conditions no longer meet an Emergency Action Level and it [l Li 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
- 2. Plant releases of radioactive materials to the environment are under control (within Technical Specifications) or have ceased L) U 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. !l 13
- 5. The reactor is in a stable shutdown condition and long-term core LJ L cooling is available.
- 6. The integrity of the Reactor Containment Building is within Technical Specifications limits.
- 7. The operability and integrity of radioactive waste systems, decontamination facilities, power supplies, electrical equipment, 1l !3 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. 17 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 support to the Station and qualified personnel and support services are available.
- 12. Discussions have been held with Federal, Commonwealth, and J L) 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. 17 Page 39 of 47
ATTACHMENT 9 Sheet 1 of 2 ESSENTIAL INFORMATION CHECKLIST I Li Initial Message Ll Update 1 4R io0 OO gia 0o Date: Time: am/pm Emergqency Radioactive Release Status:
Person Providing Information: LI None Li Imminent Li In Progress Name: Li Controlled Li Uncontrolled Location: LI Below PAGs Li Above PAGs Phone: Projected Release Duration: hr(s) 1......
) Ci .
- o S Offsite Protective Actions:
Li None Issued Time Declared: am/pm 0i Provided to Commonwealth L] Off-Normal Event Onsite Protective Actions:
Li Unusual Event Li None Li Alert L1 Potassium Iodide Li Site Area Emergency Li Evacuation of Nonessential Personnel Li General Emergency Li Other:
ricuV4
- 2) Bre Sumr fEetadMtgtn-)St esne Acinsi Prges Injuries: How Many_ LiNo Li Yes
'vUI I.[c ff n Ii l~~ .
Overexposure: LJ No L Yes Li Minor L] Major Nature of injuries or contamination:
6* " Agn Nt f t NRC Time: am/pm o II MEMA Time: am/prm L[ On-Line Li Off-Line MDPH Time: am/pm Li Stable Li I IHntchI* Local (last town) Time: am/pm Li At Power Li Coolin g Down
[] Cold S hutdown )Of
- t -Asssac Reuete I
Time of Reactor Shutdown: am/prm L3None L] Fire Department L3 Improving Li Same L3 Deteriorating L3Police Li Ambulance L3 Other:
Describe equipment, instrument, or other problems: 8) New Mei Noifcaio Li None El Draft News Release Eli News Release Approved J Press Conference 1)Sig tr and Tile I
EP-IP-IO Rev. 17 Page 40 of 47
ATTACHMENT 9 Sheet 2 of 2 ESSENTIAL INFORMATION CHECKLIST N
/
!'t Additional Information:
EP-IP-100 Rev. 17 Page 41 of 47
ATTACHMENT 10 Sheet 1 of 4 ACTIVATION OF THE EMERGENCY RESPONSE ORGANIZATION I. Emergency Response 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 Shift Manager, Control Room Supervisor, Shift I 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:
1111 Unusual Event 2222 Alert
- 3333 Site Area Emergency 4444 General Emergency
- 0000 Termination of classifiable event/Recovery EP-IP-100 Rev. 17 Page 42 of 47
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 Shift Manager'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 and 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. 17 Page 43 of 47
ATTACHMENT 10 Sheet 3 of 4 II. Notification Using Group Pages 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
- 2222 Alert
- 3333 Site Area Emergency 0 4444 General Emergency
- 0000 Termination of classifiable event/Recovery
[5] Press the # sign to complete the entry.
EP-IP-100 Rev. 17 Page 44 of 47
ATTACHMENT 10 Sheet 4 of 4 III. Notification Using Telephones if Both CANS and the Paging 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 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 them that an alternate shall be contacted. If the individual answers NO, inform them of the event and that CANS and the pager system have failed. Record the name and response time below.
Emergency Director (EOF)
Name Response Time (min.)
Emergency Plant Manager (TSC/OSC)
Name Response Time (min.)
N-- Emergency Offsite Manager (EOF)
Name Response Time (min.)
EP-IP-100 Rev. 17 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. 17 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)/Step(s)
NRC Inspection Finding Develop and implement a system for use by Att. 5, EAL Chart 81-15-34 the Control Room staff to aid in promptly 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 81-15-36 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.
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 50-293188-28 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. 17 Page 47 of 47
RTYPE H8.24 PILGRIM NUCLEAR POWER STATION Procedure No. EP-IP-225 SEVERE ACCIDENT MANAGEMENT SUPPORT Stop Think Act Review SAFETY RELATED EP-IP-225 Rev. 0
REVISION LOG "REVISION 0 Date Originated 10/01 Pacqes Affected Description All New Procedure that describes key functional responsibilities for assessing plant conditions following entry into Emergency Operations Procedures (EOPs) and provides instructions to ensure a timely transition from EOPs into Severe Accident Guidelines (SAGs) when needed.
EP-IP-225 Rev. 0 Page 2 of 12
TABLE OF CONTENTS Page 1.0 PURPOSE AND SCOPE .......................................................................................... 4
2.0 REFERENCES
.............................................................................................................. 4 3.0 DEFINITIONS ...................................................................................................... 5 4 .0 D IS C US S IO N ................................................................................................................ 5 5.0 RESPONSIBILITIES ................................................................................................. 6 6.0 PROCEDURE ....................................................................................................... 7 7 .0 R E C O R D S .................................................................................................................... 9 8.0 ATTACHM ENTS .................................................................................................. 9 ATTACHMENT 1 - EOP-TO-SAG TRANSFER CHECKLIST ............................................ 10 ATTACHMENT 2 - DOCUM ENT CROSS-REFERENCES ............................................... 11 ATTACHMENT 3 - IDENTIFICATION OF COM MITM ENTS ............................................. 12 EP-IP-225 Rev. 0 Page 3 of 12
1.0 PURPOSE AND SCOPE This Procedure provides instructions to the Emergency Plant Operations Supervisor, the TSC Supervisor, the Engineering Coordinator/Operations, and the TSC Staff Engineers for assessing plant conditions following entry into Emergency Operations Procedures (EOPs) or possible entry into Severe Accident Guidelines (SAGs). If entry into SAGs becomes necessary, the Procedure will also provide for a timely transition from the EOPs into the SAGs.
2.0 REFERENCES
[1] BWR Owners Group Accident Management Guidelines Overview Document, Revision 0, May 1996
[2] BWR Owners Group Emergency Procedure and Severe Accident Guidelines, Revision 2, March 2001
[3] Emergency Response Organization Evaluation & Plant Specific Technical Support Guideline Recommendations, prepared by AMIT, May 28, 1996
[4] EP-PP-01, PNPS Emergency Plan
[51 EPRI Severe Accident Management Guidance Technical Basis Report, Vol. 1 and 2, EPRI TR-1 01869, Final Report, 12/92
[6] PNPS Plant Specific Technical Guidelines and Severe Accident Technical Guidelines
[7] PNPS Severe Accident Guidelines, SAG-01 and SAG-02
[8] Procedures (a) EP-SAG-100, "Severe Accident Management Organization Guidelines" EP-IP-225 Rev. 0 Page 4 of 12
3.0 DEFINITIONS
[1] Emergency Operating Procedure (EOP) - Plant procedure flow chart (symptomatic in nature) that provides comprehensive directions and instructions used by the plant staff to mitigate or prevent off-normal plant transients from progressing to severe accident conditions.
[2] Severe Accident Guideline (SAG) - Plant guideline that is used by the plant staff during a severe accident to assist in determining necessary mitigating actions to be taken.
They consist of:
- SAG-01, "RPV and Primary Containment Flooding"
- SAG-02, "Containmentand Radioactivity Release Control'
[3] Technical Support Guidelines (TSGs) - Plant guidelines to assist the ERO staff in decision-making process related to EOP and SAG implementation to prevent or mitigate off-normal events and to mitigate events that degrade to severe accident status. They contain listings of plant parameter information that can be used to obtain the status of current plant conditions, system and equipment availability, and plant critical control parameters. Three assessment aids comprise the TSGs, which consist of the following:
- Plant Condition Assessment (PCA)
"* Function Status Assessment (FSA)
"* Control Parameter Assessment (CPA) 4.0 DISCUSSION None EP-IP-225 Rev. 0 Page 5 of 12
5.0 RESPONSIBILITIES
[1] The Emergency Plant Operations Supervisor (EPOS) is responsible for:
(a) Implementing this Procedure for the Control Room staff.
(b) Assisting Control Room operating staff with actions to support EOP implementation and accident mitigation strategies.
(c) Assessing current plant status and conditions in relation to accident mitigation strategies and providing status update to the Emergency Plant Manager and the Emergency Director regarding necessary mitigating actions.
(d) Making the decision to enter into Severe Accident Guidelines.
[2] The TSC Supervisor is responsible for:
(a) Implementing this Procedure for the TSC staff.
(b) Overseeing technical assessment in the TSC to support the Control Room operating staff with accident mitigation strategies as needed.
(c) Assessing current plant status and conditions and providing recommendations to the Emergency Plant Manager and the EPOS regarding recommended mitigating actions.
[3] The Engineering Coordinator/Operations is responsible for:
(a) Assigning appropriate TSC Engineering staff (Operations, Systems, and ES/TAG) to initiate Technical Support Guidelines (Plant Condition Assessment, Control Parameter Assessment, and Function Status Assessment) in support of EOP accident mitigation strategies and actions.
(b) Providing plant operational technical assessment to support EOP accident mitigation strategies as needed.
[4] Designated TSC Engineering staff (Operations, Systems, and ES/TAG) is responsible for:
(a) Initiating Technical Support Guidelines (Plant Condition Assessment, Control Parameter Assessment, and Function Status Assessment) in support of EOP accident mitigation strategies and actions.
(b) Making recommendations for necessary action to be taken to mitigate or prevent off-normal events from degrading to severe accident status.
EP-IP-225 Rev. 0 Page 6 of 12
6.0 PROCEDURE
[1] The EPOS shall:
(a) Upon entry into EOPs OR upon recommendation of the TSC Supervisor, (whichever comes first), implement this Procedure in the Control Room.
(b) Assist Control Room staff with assessing current plant status conditions to support recommended accident mitigating actions (EOP and EOP Satellite Procedure implementation).
(c) If TSC is activated, ensure TSC staff is assessing and monitoring plant status conditions using appropriate EOPs and TSGs.
(d) Coordinate necessary accident mitigating actions with the Control Room, the TSC, and the EOF in support of EOP implementation.
(e) Monitor overall plant status conditions to determine when entry into the Severe Accident Guidelines is necessary using the guidance contained in Attachment 1 (EOP-to-SAG Transfer Checklist).
(f) If it is determined that accident conditions warrant implementation of Severe Accident Guidelines, then inform the TSC, EOF, and Control Room staffs of the decision to exit this Procedure and implement functional responsibilities in accordance with EP-SAG-1 00, "Severe Accident Management Organization Guidelines".
[2] The TSC Supervisor shall:
(a) Based on recommendations from the Engineering Coordinators (Operations/Systems) OR upon entry into EOPs (whichever comes first),
implement this Procedure in the TSC.
(b) Recommend the implementation of this Procedure in the Control Room to the EPOS.
(c) Notify the EPOS when this Procedure has been implemented in the TSC.
(d) Direct the Engineering Coordinator/Operations to assign appropriate TSC Engineering staff to initiate evaluation of plant status conditions using the TSGs in support of EOP accident mitigation strategies and functions (Plant Condition Assessment, Control Parameter Assessment, and Function Status Assessment).
(e) Inform the Emergency Plant Manager of accident mitigation information as necessary.
EP-IP-225 Rev. 0 Page 7 of 12
(f) If SAG implementation is directed by the EPOS, ensure that the TSC staff exits this Procedure and implements the functional responsibilities in accordance with EP-SAG-1 00, "Severe Accident Management Organization Guidelines",as necessary.
[3] The Engineering Coordinator/Operations shall:
(a) Coordinate with the Engineering Coordinator/Systems and ES/TAG Coordinator for assigning appropriate TSC Engineering staff (Systems and ES/TAG) to initiate Function Status Assessment in accordance TSG-100, "Function Status Assessment Guideline", to support EOP mitigation actions and functions.
(b) Assign appropriate TSC Operations Engineer support staff to initiate Plant Condition Assessment and Control Parameter Assessment in accordance with TSG-200, "PlantCondition Assessment Guideline", and TSG-300, "Control ParameterAssessment Guideline", to support EOP accident mitigation actions and functions.
(c) Direct the technical assessment of the Technical Support Guidelines in support of EOP implementation, including potential courses of action should entry into Severe Accident Guidelines be necessary.
(d) Make recommendations to the EPOS and the TSC Supervisor as to when entry into Severe Accident Guidelines is necessary.
(e) If SAG implementation is directed, exit this Procedure and implement and redirect TSC Operations Engineering support in accordance with EP-SAG-1 00, "Severe Accident Management Organization Guidelines", as necessary.
[41 Designated TSC Engineers (Systems and ES/TAG) shall:
(a) As directed by Engineering Coordinator/Operations, initiate Function Status Assessment in accordance with TSG-100, "FunctionStatus Assessment Gudeline", to support EOP accident mitigation strategies and functions.
(b) Recommend mitigating actions to the Engineering Coordinator/Operations.
(c) Evaluate and inform the ERO of actions that may be necessary.
EP-IP-225 Rev. 0 Page 8 of 12
[5] The TSC Operations Engineer support staff shall:
(a) As directed by Engineering Coordinator/Operations, initiate Plant Condition Assessment and Control Parameter Assessment in accordance with TSG-200, "PlantCondition Assessment Guideline", and TSG-300, "Control ParameterAssessment Guideline", to support EOP accident mitigation strategies.
(b) Recommend mitigating actions to the Engineering Coordinator/Operations and the TSC Supervisor.
(c) Evaluate and inform the ERO of actions that may be necessary.
7.0 RECORDS None 8.0 ATTACHMENTS ATTACHMENT 1 - EOP-TO-SAG TRANSFER CHECKLIST ATTACHMENT 2 - DOCUMENT CROSS-REFERENCES ATTACHMENT 3 - IDENTIFICATION OF COMMITMENTS EP-IP-225 Rev. 0 Page 9 of 12
ATTACHMENT 1 Sheet 1 of 1 EOP-TO-SAG TRANSFER CHECKLIST
"* Is the TSC activated?
"* Are the TSC Supervisor and Engineering Coordinator/Operations aware to exit this Procedure and implement the functional responsibilities in accordance with EP-SAG-1 00, "Severe Accident Management OrganizationGuidelines", as needed?
"* Reason for SAG entry:
"* Have the SAGs been reviewed and are TSGs in use in the TSC to support SAGs?
"* Have RPV and Primary Containment flooding strategy recommendations been received?
SM A B C D E F G Engineering Coordinator/Operations A B C D E F G
"* Has a candidate RPV and Primary Containment flooding strategy been selected?
"* Have the six functions performed in the candidate flooding strategy functions been reviewed?
", RPV injection
"" Primary Containment injection V Primary Containment venting V RPV venting V Torus spray V Drywell spray
"* Have SAG-02 Hydrogen and Oxygen Concentration strategies been identified?
Torus _ Drywell _ N/A
"* Does the SM concur with plant status and plans for SAG use?
"* Has the Emergency Director, EOM, and EPM been notified that decision-making responsibility has been assumed by the EPOS?
"* Has a plant announcement been made indicating that SAGs are in use and decision-making responsibility transferred to the EPOS?
EP-IP-225 Rev. 0 Page 10 of 12
ATTACHMENT 2 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-AD-1 10 Emergency Preparedness Organization and Responsibilities EP-AD-145 Severe Accident Management Program Maintenance EP-AD-210 Evaluating Changes for Impact on Training EP-AD-301 Emergency Preparedness Facilities and Equipment Surveillances EP-IP-201 Emergency Plant Manager EP-IP-210 Control Room Augmentation EP-IP-220 TSC Activation and Response EP-IP-225 Rev. 0 Page 11 of 12
ATTACHMENT 3 Sheet 1 of 1 IDENTIFICATION OF COMMITMENTS This Attachment lists those external commitments (NRC commitments, QA audit findings, and INPO inspection items) implemented in this Procedure.
Reference Document Commitment Affected Section (s)/Step(s)
BECo 2.98.117 LTP #489 Severe Accident Management All Initiating Document II EP-IP-225 Rev. 0 Page 12 of 12
PLEASE NOTE:
YOU HAVE 4 NEW TABS: EP-IP-220, 229 AND 230 PLEASE REMOVE OLD AND REPLACE WITH NEW EP-IP-225 IS NEW THANK YOU
EP-IP-220 TSC Activation and Response
EP-IP-225 Severe Accident Management Support
EP-IP 229 TSC/OSC Equipment Operation