ML010930249

Rev 14 to EP-IP-100, Emergency Classification and Notification

ML010930249
Person / Time
Site:	Pilgrim
Issue date:	03/30/2001
From:	Entergy Nuclear Generation Co
To:	Office of Nuclear Security and Incident Response
References
-RFPFR EP-IP-100, Rev 14
Download: ML010930249 (51)

Text

NUCLEAR ORGANI ZATION J -

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PLEASE SIGN AND RETURN TO: Controlled Document Clerk, MAIL STOP #19 NO ENVELOPE REQUIRED FOR INTERNAL COMPANY MAIL Entergy, Controlled Document Clerk Pilgrim Nuclear Power Station 600 Rocky Hill Road, Support Building Plymouth, Massachusetts 02360 Date Signature of Holder Controlled Copy No.

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CHANGE INSTRUCTION NOTICE (CIN) rransmittal No.1LJLA Plae update your copy of -(P with the attachments to this transmittal as instructed below.

REMOVE AND DISCARD REY.. No.

INSERT REV. NO.

1.

AK Date:

Emergency Plan Implementing Number:

i PNPS Procedure Manual N/A RType H8.24 TABLE OF CONTENTS Number EP-IP-100 EP-IP-200 EP-IP-201 EP-IP-202 EP-IP-210 EP-IP-220 EP-IP-229 EP-IP-230 EP-IP-231 EP-IP-240 EP-IP-250 EP-IP-251 EP-IP-252 EP-IP-253 EP-IP-254 EP-IP-259 EP-IP-300 EP-IP-310 EP-IP-315 EP-IP-330 EP-IP-400 EP-IP-410 Title Emergency Classification and Notification On-Call Emergency Director Emergency Plant Manager Company Spokesperson Control Room Augmentation TSC Activation and Response TSC/OSC Equipment Operation OSC Activation and Response Onsite Radiation Protection Emergency Security Organization Activation and

Response

EOF Activation and Response Offsite Radiation Protection Facilities Support Relocation of the EOF Communications Support EOF Equipment Operation Offsite Radiological Dose Protection Radiation Monitoring Team Activation and Response Personnel Monitoring Team Activation and Response Core Damage Protective Action Recommendations Evacuation/Assembly Effective Revision Date 14 9

1 3

7 11 5

3 5

8 9

5 7

3 2

3 3

4 4

2B 8

4 03/30/01 02/07/01 05/14/99 02/07/01 12/12/00 11/15/00 07/25/00 11/15/00 07/25/00 03/15/00 02/07/01 12/26/00 02/01/01 07/13/00 12/06/00 05/24/00 01/19/00 11/15/00 05/24/00 06/19/98 01/23/01 05/24/00 Revision 67 03/30/2001 Page 1 of 2 Revision 67 Page 1 of 2 03/30/2001

Emergency Plan Implementing Number:

N PNPS Procedure Manual N

RType H8.24 TABLE OF CONTENTS Number EP-IP-420 EP-I P-440 EP-IP-501 EP-IP-520 Title Search and Rescue Emergency Exposure Controls Transport of Contaminated Injured Personnel Transition and Recovery Eff ective Revision Date 3

02/12/01 5A 04/08/98 3

05/24/00 5

02/07/01 Revision bt 03/30/2001 Page 2 of 2 Revision 67/

Page 2 of 2 03/30/2001

RTYPE H8.24 PILGRIM NUCLEAR POWER STATION Procedure No. EP-IP-100 EMERGENCY CLASSIFICATION AND NOTIFICATION Stop Think STAR Act Review SAFETY REVIEW REQUIRED SAFETY RELATED EP-IP-100 Rev. 14

REVISION LOG REVISION 14 Pagqes Affected 7,32,35,40 7

12 15 21,22,24,26 34,37 REVISION 13 Pagqes Affected 5,6,27 8

27 REVISION 12 Pa-qes Affected All 8-10,14 41 42 Date Originated 3/01 Description Change the terms "Emergency Release" and "Release" to "Emergency Radioactive Release."

Clarify definition of Emergency Radioactive Release above/below PAGs.

In Step 5.3[3), delete sentence regarding update periodicity.

Rewrite Section 5.6 to provide enhanced detail.

In the Alert announcement, Section A, change "handicapped personnel" to "persons with disabilities." For the Alert, Site Area Emergency, and General Emergency announcements, eliminate Section D and rewrite the "Action Verification" section.

Change the term "auto-dialer" to "speed dialer" on the instructions for Attachments 6 and 7.

Date Originated 9/00 Description Revise to include design basis core cooling requirements (2/3 core height with Core Spray) specified in EOP-01.

Add new definition for radiation monitor readings.

Revise EAL 1.4.1.4 and EAL 1.4.1.3 with new EAL values for Drywell and Torus High Range Radiation Monitors.

Date Originated 1/00 Description All pages formatted to reflect the updated Procedures format.

Revision bars are not shown for reformatting.

Revise titles.

Revise titles, editorial changes, and changes for new CANS.

Revise titles and changes for new CANS.

EP-IP-100 Rev. 14 Page 2 of 47

TABLE OF CONTENTS Paae 1.0 P U R P O S E.........................................................................................................

5 2.0 R E F E R E N C E S..................................................................................................

5 3.0 D E F IN IT IO N S..........................................................................................

5 4.0 R E S P O N S IB IL IT IE S.........................................................................................

9 5.0 P R O C E D U R E...............................................................................................

.. 10 5.1 RECOGNIZING AN EMERGENCY.....................................................

10 5.2 INITIAL DECLARATION OF AN EMERGENCY FROM THE CO NTRO L RO O M.......................................................................

10 5.3 WHILE IN A CLASSIFIED EMERGENCY............................................

12 5.4 TRA NSITO 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 A TTA C H M E N T S............................................................................................

19 ATTACHMENT I - 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. 14 Page 3 of 47

TABLE OF CONTENTS (Continued)

_F 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 O R G A N IZ A T IO N..............................................................

ATTACHMENT 11 - DOCUMENT CROSS-REFERENCES..............................

ATTACHMENT 12 -IDENTIFICATION OF COMMITMENTS...........................

Age 32 35 38 40 42 46 47 EP-IP-100 Rev. 14 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, "Emergency Action 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 Spra( 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. 14 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°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.

[41 Computerized Automated Notification System (CANS) - A computer-assisted system that, when activated, has the following capabilities:

(a)

Activating the emergency pager system.

(b)

Accepting calls from authorized responders to inform them of an abnormal or emergency condition at PNPS.

(c)

Calling response personnel at their home or work phone to inform them of an abnormal or emergency condition at PNPS.

(d)

Maintaining an updated list of personnel responding and their estimated time of arrival at their facility.

[5]

Cannot Be Determined - The current value or status of an identified parameter relative to that specified in the Emergency Action Level (EAL) cannot be ascertained using all available indications (direct and indirect, singly or in combination).

EP-IP-100 Rev. 14 Page 6 of 47

[6]

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.

[7]

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[6].)

[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:

0 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]

Emergqency 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. 14 Page 7 of 47

[141 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.

[161 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 off site agencies.

[18]

Non-Essential Personnel - Personnel who are not assigned specific emergency response duties.

[191 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 B Above/Below EAL Threshold Readingqs.- 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.

[211 Shutdown - As regards Reactor status, the Reactor is shutdown if the Reactor is subcritical (power decreasing) and below the heating range (IRM range 7).

[22]

Site Area Emergency - Events are in progress or have occurred which involve actual or likely major failures of PNPS functions needed for the protection of the public. Any releases are not expected to exceed EPA Protective Action Guidelines exposure levels except near the site boundary.

[23]

Sustained Loss - Loss of power supply, system or component operability for which the return to service has not been determined to be imminent. It does not imply any specific time interval, but prolonged operation is not permitted without declaring the specified emergency condition based on the potential for degraded plant safety.

[24]

Termination - The point at which the event is no longer considered to be an emergency.

Termination of the emergency is formally identified by an Initial Notification message transmission and entry into Recovery.

[25]

Transitory Event - An event in which PNPS exceeded an Emergency Action Level (EAL) but conditions improved prior to classification.

EP-IP-100 Rev. 14 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 Operations Shift Superintendent, or the Control Room Supervisor if the Operations Shift Superintendent is incapacitated or away from the Control Room, shall be responsible for the initial emergency classification declaration and implementation of this Procedure.

[2]

The Operations Shift Superintendent, or Control Room Supervisor if the Operations Shift Superintendent 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 Operations Shift Superintendent).

[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. 14 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 Operations Shift Superintendent, or Control Room Supervisor if the Operations Shift Superintendent 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 Operations Shift Superintendent (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. 14 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 Production Maintenance personnel not already involved in the emergency and inform them to report to the Control Room or the OSC to stand by for repair and corrective action activities if necessary.

[5]

The Emergency Plant Operations Supervisor (EPOS) may relieve the Operations Shift Superintendent as Emergency Director until the on-call Emergency Director assumes responsibility for the position in the EOF.

[6]

The on-shift Emergency Director will remain in the Control Room until relieved by the on-call Emergency Director.

EP-IP-100 Rev. 14 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 upcqrade 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. 14 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), Unusual Event Notifications Checklist.

(b), Alert Notifications Checklist.

(c), 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. 14 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, "Transition and 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 longqer meet a classification level Complete and distribute an Initial Notification Form to specify the transitory event classification level and signify return to the current 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. 14 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, "Transition and 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 Operations Shift Superintendent) recognized and formally declared the new event classification level.

(b)

The "entered" check box is used when the first Initial Notification Form is completed for an emergency.

(c)

The "transitory" check box is used to provide a location to enter the highest classification level which was met during a transitory event.

(d)

The "upgraded to" check box is used to provide initial notification of emergencies which require the declaration of a higher classification.

(e)

The "downgraded to" check box is used to provide initial notification of emergencies which warrant lowering the classification level.

(f)

The classification level boxes are used to indicate the classification applicable to the notification.

EP-IP-100 Rev. 14 Page 15 of 47

[41 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, "Protective Actions", 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. 14 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.

[51 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, "Protective Actions", 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.

(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.

EP-IP-100 Rev. 14 Page 17 of 47

[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. 14 Page 18 of 47

7.0 ATTACHMENTS ATTACHMENT 1 - UNUSUAL EVENT NOTIFICATIONS CHECKLIST ATTACHMENT 2 - ALERT NOTIFICATIONS CHECKLIST ATTACHMENT 3 - SITE AREA EMERGENCY NOTIFICATIONS CHECKLIST 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. 14 Page 19 of 47

ATTACHMENT 1 Sheet I of 1 UNUSUAL EVENT NOTIFICATION OF STATION PERSONNEL - STANDBY STATUS, During a security threat it M8r'a L6 'dvjs~able NOT to sound an alarm.

Sound/have the Control Room sound the Operator Recall Alarm and make the following announcement over the public-address system, TWICE:

A. "Attention all personnel, attention all personnel: An Unusual Event has been declared due to (brief description of initiating event). All on-call members of the Emergency Response Organization stand by for further instructions. All other personnel continue with your present duties until additional instruction is given."

B. If there is a localized emergency (for example, high radiation, fire), announce its type and location and instruct personnel to stand clear of this area.

Time Completed:

NOTIFICATION OF THE ERO - STANDBY STATUS Notify or direct notification of the ERO in accordance with Attachment 10, Activation of the Emergency Response Organization.

Time Completed:

NOTIFICATION OF STATE AND LOCAL AGENCIES Within 15 minutes of the event classification transmit an Initial Notification Form (Attachment 6) to the Commonwealth and local authorities.

Time Completed:

NOTIFICATION OF THE NRC Inform the NRC of the event classification using the ENS or a commercial telephone (Attachment 6 Step 4).

Time Completed:

RETURN TO THE PROCEDURE (EITHER STEP 5.2[2] OR 5.411])

EP-IP-100 Rev. 14 Page 20 of 47

ATTACHMENT 2 Sheet 1 of 2 ALERT EP-IP-100 Rev. 14 Page 21 of 47 SITE & PUBLIC AREA NOTIFICATION - RELEASE OF NONESSENTIAL PERSONNEL CAUTION D
r
in
aa.
s.
r
~a e a'. i.sa b.e

.QI

t. sound..

Sound/have the Control Room sound the Operator Recall Alarm and make the following announcement over the public-address system, TWICE:

A. "Attention all personnel, attention all personnel: An Alert has been declared due to (brief description of initiatingI 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:

I

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:

rRETURN TO THE PROCEDURE (EITHER STEP 5.2[2], 5.3[2](a), OR 5.4[1])

I EP-IP-100 Rev. 14 Page 22 of 47 I

ATTACHMENT 3 Sheet 1 of 2 SITE AREA EMERGENCY ASSEMBLY AREA DESIGNATION Determine the Assembly Area based on meteorological conditions as follows:

Assembly Area Wind Direction (0 from)

IJ Support Building Cafeteria 0000-2890 or 3240-3600 LZ Chiltonville Training Center 290°-3230 EP-IP-100 Rev. 14 Page 23 of 47 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 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 from no event or an Unusual Event:

"'Attention all personnel, attention all personnel; A Site Area Emergency has been declared due to (brief description of event). All on-call Emergency Response Organization members report to your designated emergency response facility. All other personnel evacuate to (Assembly Area)."

If upeqradingq 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.

ATTACHMENT 3 Sheet 2 of 2 SITE AREA EMERGENCY (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. 14 Page 24 of 47 SITE & PUBLIC AREA NOTIFICATION - PROTECTED AREA EVACUATION (CONTINUED)

B. If there is a localized emergency (for example, high radiation, fire), announce its type and location and instruct personnel to stand clear of this area.

C. If there is a potential for an airborne radiological release, consider announcing that there will be no eating, drinking, or smoking until further notice.

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:

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:

I

ATTACHMENT 4 Sheet 1 of 2 GENERAL EMERGENCY ASSEMBLY AREA DESIGNATION Determine the Assembly Area based on meteorological conditions as follows:

Assembly Area Wind Direction (0 from)

L-Support Building Cafeteria 0000-2890 or 3240-3600 Ll Chiltonville Training Center 2900-3230 EP-IP-100 Rev. 14 Page 25 of 47 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 During a security threat it. may be advisable NOT to Sound an alarm.

Consid(ýr radiological conditions whhpeaigto evacuate personn6l. 'If high dose irates will, be 8 1npopntpred, it may be betteor to s h Ieltet nonssential persbptlel qn-sitp.

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 into a General Emergency from an Alert or lower: "Attention all personnel, attention all personnel: A General Emergency has been declared due to (brief description 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 upgrading from an Site Area Emergency: "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.

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:

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. 14 Page 26 of 47 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:

(

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ATTACHMENT 5 Sheet 1 of 5 1.0 REACTOR FUEL 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 microcunesiml total iodine.

20 microcuries/il total iodine.

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.

1.3.1.1 1.3 Thermal Limits IMCPR < Technical Specification fuel cladding integrity safety limit.

1.4 Radiation 1.4.1.4 1.4.1.3 1.4.1.2 Monitors Valid Drywell High Range Area Radiation Montor reading Valid Drywell High Range Area Radiation Monitor reading Refuel Floor Ventilation Exhaust Radiation (RFVE)

> 10,000 RPhr (RIT-1001-606A and B) or Valid Torus High

> 200 R/hr (RIT-1001--606A and B) or Valid Torus High Monitor 1705-8 Channel A(A/C) and Channel B(BID) High Range Area Radiation Monitor reading > 200 RPhr Range Area Radiation Monitor reading > 3 RPhr 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) a 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 < -160 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 2.2 Reactor required) 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 Boron injection into the RPV intentionally initiated (boron A reactor Scram has been initiated.

"Boron Injection Initiation Temperature" (BIIT) EOP injection required) with either:

AND Figure 4.

• Standby Liquid Control System (SBLC).

The reactor is not shutdown.

AND EITHER OR An SRV is open.

One or more of the methods detailed in PNPS OR Procedure 5.3-20, "Alternate Borate Injection."

• Drywell pressure > 2.2 psig.

EP-IP-100 Rev. 14 Page 27 of 47

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ATTACHMENT 5 Sheet 2 of 5 3.0 FRIMARY LUONTAINMENT 3.1 Drywell Temperature 3.2 Torus water Temperature 3.3 Containment Water Level 3.4 Primary Containment Pressure 3.5 Containment H2 & 02 Concentration 3.1.1.3 Bulk drywell temperature cannot be maintained < 280=F as determined by PNPS Procedure 2.1.27, "Drywell Temperature Indication."

Torus water temperature cannot be maintained below the 3.3.1.4 Primary containment water level cannot be maintained

< 77 feet.

3.3."1.3 F ue 3.3.1.3 Both torus water level and RPV pressure cannot be maintained below the "SRV Tail Pipe Level Limit" (SRVTPLL) EOP Figure 2.

3.3.2.3 Torus water level cannot be maintained > 90 inches.

I _________________________

.L 1

3.4.1.3 4 3.5.1.4 3.4.1.4 Torus pressure approaching "The Primary Containment Pressure Limit" (PCPL) EOP Figure 7 (prior to initiation of containment ventinol.

3.5.1.4 Drywell or torus hydrogen concentration > 6%.

AND Drywett or torus oxygen concentration > 5% (Prior to 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).

3.4.1.3 Torus bottom pressure cannot be maintained below the "Pressure Suppression Pressure" (PSP) EOP Figure 6 lexceot durina testno such as ILRT, etc.).

1.5.-1.3 Drywell or torus hydrogen concentration > 1%.

AND Drywell or torus oxygen concentration > 4%.

3.3.12 3.3.1.2 Torus water level cannot be maintained < 180 inches.

3.4.1.2 Prmary containment pressure cannot be maintained

< 2.2 psig (except during testing such as ILRT, etc.)

3.5.12 Drywell or torus hydrogen concentration > 1%.

3.1.1I 3.1.11.1 Bulk drywell temperature cannot be maintained < 150°F as determined by PNPS Procedure 2A1.27, "Drywell Temperature Indication."

AND Primar containment integrity is required.

3.2.1.1 Torus water temperature > 1 10-F.

3.3.1.1 Reactor coolant system to drywelt unidentified leakage

> 5 gpm with reactor coolant temperature > 212'F.

OR Reactor coolant system to drywell total leakage > 25 gpm with reactor coolant temperature > 212'F.

3.3.2.1 Torus water level cannot be maintained:

< 132 inches. (-1 inches. narrow range).

OR

> 127 inches (-6 inches. narrow range).

iaND Primar containment intec rd is re uired.

J I ________________________________

EP-IP-100 Rev. 14 Page 28 of 47

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3,U laRIMARY L;ONTAINMENT I

i 11

/

ATTACHMENT 5 Sheet 3 of 5 4.0 SECONDARY CONTAINMENT

__________I___

4.1 Secondary Containment Area Water Levels I

i 4.2 Secondary Containment Area Temperatures I

I 4.3 Secondary Containment Area Radiation Levels 4.1.1.3 Secondary containment area water levels exceed the "Maximum Safe Operating Value" in two or mere areas EOP Table L.

AND A primary system is discharging into the area.

AND Reactor coolant temperature > 212'F with irradiated fuel in the vessel.

4.2.1.3 Secondary containment area temperatures exceed the "Maximum Safe Operating Value" in two or more areas EOP Table L.

AND A pnmary system is discharging into the area.

AND Reactor coolant temperature > 212°F with irradiated fuel in the vessel Secondary containment radiation levels exceed thre "Maximum Safe Operating Value" in two or more areas SOP Table L AND

-I IT4.3.1.2 General area radiation levels measured in-plant which increase by a factor of 1000 times normal as a result of airborne radioactivity which cannot be attributed to a controlled process.

______________I A primary system as discharging into the area.

I________________________

4.1.1.1 Secondary containment area water levels exceed the "Maximum Safe Operating Value" in two or more areas EOP Table L.

AND Reactor coolant temperature > 212°F with irradiated fuel in the vessel.

4.2.1.1 Secondary containment area temperatures exceed the "Maximum Safe Operating Value' in two or more areas EOP Table L.

AND Reactor coolant temperature > 212'F with irradiated fuel in the vessel.

5.0 RADIOACTIVITY KELEASE 5.1,1.4 Valid Main Stack Process Radiation Monitor 1705-18 A and B Panel 910 reading > 2.4E5 cps.

5.1.1.,3 Valid Main Stack Process Radiation Monitor 1705-18 A and B Panel 910 reading > 2.4E4 cps.

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 mrerm whole body or 5000 mrerm 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 5.1.1I 5.1.1.2 Valid Reactor Building Ventilation Exhaust (RBVE) monitor 1705-32A and B Panel 910 high-high alarm which does not clear within 15 minutes from the time action is taken to isolate the source.

5.1.2.2 Valid Main Stack Process Radiation Monitor 1705-18A and B Panel 910 reading > 10.000 cps for greater than 15 minutes.

injury 5.1.1.1 5.1.1.1 Valid Reactor Building Ventilation Exhaust (RBVE) monitor 1705-32A and B Panel 910 high alarm which does not clear within 15 minutes from the time action is taken to isolate the source.

5.1.2.1 Main stack radioactivity effluents in excess of the high-high alarm setpoint for greater than 15 minutes as 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 i not isolated (FV-7214-A and B).

5.3.1.1 Transportation of a contaminated injured person to an nffaite medical facilitY.

EP-IP-100 Rev. 14 Page 29 of 47

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5.1 Effluent Monitors 4.0,.%ECONDARY (.;ONTAINMENT 5.U I*ADIOACTIVITY IXELEASE

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6.0 INTERNAL EVENTS GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT 6.1.1.1 6.1 Technical The plant is not brought to the required operating mode Specifications 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 15indicated 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 > 21 2F.

Reactor coolant temperature cannot be maintained Reactor coolant temperature > 212"F with irradiated fuel

< 212OF.

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 Saitre 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).

source (all 4kV buses de-energized).

Inability to power Bus AS from any onsite generator*.

AND 6.3.2.3 6.3.2.2 Inability to power Bus A6 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 Di6.

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 AS from any offsite power supply transformer'.

AND Inability to to immediately supply AC power to Bus A6 from any oftsite 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 In.4 caLoss oComplete loss of plant process computer alarm and Loss of indications and/or alarms which cause a Indication 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 > 212"F.

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-IO Rev. 14 Page 30 of 47 ATTACHMENT 5 Sheet 4 of 5

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ATTACHMENT 5 Sheet 5 of 5 7.0 EXTERNAL EVENTS Sheet"5_of_5 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 Operations Shift Superintendent has led to the loss of the Operations Shift Superintendent may lead to the loss determined by the Station Security Force.

as determined by the Station Security Force.

physical control of the plant.

of physical control 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 fOR Reactor coolant temperature> 212F.

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.

CoeSIa 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).

i Explosion (Unplanned).

ATWS/ARI 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 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 System 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 7.4.2.1 Standby Gas Treatment release of radioactivity:

Tornado Earthquake

• Hurricane Report of a tornado onsite.

Standby Liquid Control Tornado

• Other Natural Phenomena 7.4.3.1 Hurricane A.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:.

Water Reactor coolant temperature is > 212°F.

greater than Operating Basis Earthquake levels (0.08 g).

R Seismic monitor event alarm Panel gi1.

Service Water 7A4.2.3 "Seismic Recorder Operating" annunciator Panel C1 Any earthquake onsite which has been determined to be Right A-7.

greater then Safe Shutdown Earthquake levels (0.15 g).

Ground motion is felt by one or more plant operations personnel.

8.0 OTHER 8.1 Other 8.1J1.4 8.1.1.3 8.1.1.2 8.1.1.1 In the opinion of the Operations Shift Superintendent or In the opinion of the Operations Shift Superintendent or Any event which in the opinion of the Operations Shift Any event which in the opinion of the Operations Shift Emergency Director events are in progress which indicate Emergency Director events are in progress which indicate Superintendent or Emergency Director could or has Superintendent or Emergency Director could or has led to actual or imminent core damage and the potential for a actual or likely failures of plant systems needed to protect caused actual substantial degradation of the level of plant a potential degradation of the level of safety of the plant.

large release of radioactive material outside the site the public and pose a significant radioactivity release safety.

8.1.1 boundary.

potential.

Any event which in the opinion of the Operations Shift Superintendent or Emergency Director warrants the prompt notification of Commonwealth and local authorities and precautionary notification of Emergency Response Organization personnel.

EP-IP-100 Rev. 14 Page 31 of 47

PIGI NUCLAR OWE STIO 1

THIS IS:

[J A DRILL II AN ACTUAL E 2

AS OF:

PILGRIM NUCLEAR POWER STATION HAS ATTACHMENT 6 Sheet 1 of 3 No.T=

VENT time date J1 ENTERED:

LI HAD A TRANSITORY THEN ENTERED:

JI UPGRADED TO:

LI DOWNGRADED TO:

JI AN UNUSUAL EVENT F1 AN ALERT LJ A SITE AREA EMERGENCY F1 A GENERAL EMERGENCY LI RECOVERY BRIEF DESCRIPTION OF EVENT:

31 EAL No.

4] EMERGENCY RADIOACTIVE RELEASE:

LJ is JI IS N O T...................................................................

IN PRO G R ES S l IS ABOVE LI IS BELOW..................................

PROTECTIVE ACTION GUIDES SI METEOROLOGICAL DATA AS OF __

WIND DIRECTION FROM

° TO AT mph

_. PNPS's PROTECTIVE ACTION RECOMMENDATIONS (PARs):

FA NO PROTECTIVE ACTIONS NECESSARY

~ NEAEEMEJiEC IN M EMNVMDIWARE_5f

~~Nt iN~THEEOF:

'IK J

PROVIDED TO MEMA/MDPH

'dE'f

'MR__EC NbýdkiP~

ARE N' fPP_,-_EN-NTHE~ EdIF:

IJSHELTER SUBAREA(s) 1 2 3 4 5 6 7 8 9 10 11 J-I EVACUATE SUBAREA(s) 1 2 3 4 5 6 7 8 9 10 11 12 (circle the affected subareas) 7 NOTIFICATION INITIATED I BY

-A time date name 8

NOTIFICATION RECEIVED BY time date name EP-IP-100 Rev. 14 Page 32 of 47

ATTACHMENT 6 Sheet 2 of 3 INITIAL NOTIFICATION FORM (Cont.)1 No.l DO..

-,NOT TRAN S SH.EET OVE.R

.NN 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):

L1SHELTERSUBAREA(s) 1 2 3 4 5 6 7 8 9 10 11 L--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: L Emergency Director's Signature EP-IP-100 Rev. 14 Page 33 of 47 Ml IL

ATTACHMENT 6 Sheet 3 of 3 INITIAL NOTIFICATION FORM TRANSMISSION INSTRUCTIONS NO:

(Check off the boxes as steps are completed.)

Step 1: TRANSMIT THE FORM LIJ Verify Blocks 1 - 6 are complete, release is approved by signature, and then fill out Block 7 of the form. For guidance on individual Block descriptions refer to EP-IP-100.

[j Place only the first page of the completed form face down in the DNN fax machine.

LJ Follow the posted instructions at the DNN fax machine. Proceed immediately 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.

[J Pick up the DNN ring-down phone and read the following message twice:

"Attention, attention. Please standby for a roll call."

[3 Perform a roll call and check off the responding locations as they are identified.

LJ Middleboro State Police LJ Carver L1 Marshfield

-- Framingham MEMA nJ Duxbury LJ Plymouth L[ Bridgewater LI Kingston LJ Taunton LJ 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 Jl Read the information in Block 1 through Block 6.

L1 Tell those parties who have complete information to hang up, then provide missing information to remaining parties.

L1 Contact locations not answering roll call via BECONS or commercial telephone (speed-dialer) and read the information in Block I through Block 6.

Step 4: NOTIFY THE NRC Ll Using the ENS or commercial phone read the information in Block '-Ithrough 6.

Name of

Contact:

Time:

Step 5: ORGANIZE THE REPORT Jl Obtain the printed report from the DNN fax machine and staple it to this form.

LJ Inform the Emergency Director that transmission was completed at time:

COMPLETED BY:

Time:

Signature of person making notifications EP-IP-100 Rev. 14 Page 34 of 47

0 THIS IS:

LJ A DRILL L

AN ACTUAL I

_AS OF:

PILGRIM NUCLEAR POWER STATION IS STILl ATTACHMENT 7 Sheet 1 of 3 No.W

- AT A:

time date F] I "A

I AI r-\\KlZT [J Al ERT L-I SITE AREA EMERGENCY

[L GENERAL EMERGENCY S U IN UO U/

L._vn.l*

3 STATION CONDITIONS ARE:

J IMPROVING J

STABLE IJ DEGRADING 4

EAL No.

BRIEF DESCRIPTION OF EVENT:

OUTSIDE ASSISTANCE:

J HAS FIII HAS NOT BEEN REQUESTED

[1 AMBULANCE REASON FOR OUTSIDE ASSISTANCE:

FIRE DEPARTMENT L-- POLICE J

OTHER (Specify) 6 EMERGENCY RADIOACTIVE RELEASE:

F, is IS NOT IN PROGRESS J IS ABOVE I-1 IS BELOW..................................

PROTECTIVE ACTION GUIDES L

METEOROLOGICAL DATA AS OF STABILITY CLASS WIND DIRECTION FROM TO 0 AT mph 8J PNPS's PROTECTIVE ACTION -_L;UUIVIIVILINLA I IUONS trMRs).

[NO PROTECTIVE ACTIONS REQUIRED

&ENERAL

~~

EERENCY AND ýTiE I-PROVIDED TO MEMAIMDPH

-GENERAL EMERýGENCY ANID mMkmNMDIH ARIOTROkStNT: KNTHE Eý7F

[*SHELTERSUBAREA(s) 1 2 3 4 5 6 7 8 9 10 11 L EVACUATE SUBAREA(s) 1 2 3 4 5 6 7 8 9 10 11 12 (circle the affected subareas) 9 JNOTIFICATION INITIATED BY time date name 10 NOTIFICATION RECEIVED B

time date name EP-IP-100 Rev. 14 Page 35 of 47

ATTACHMENT 7 Sheet 2 of 3 I FOLLOW-UP INFORMATION FORM (Cont.)

No.

W Zbo NO IRA NSMIT 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):

L--SHELTERSUBAREA(s) 1 2 3 4 5 6 7 8 9 10 11 L-1EVACUATESUBAREA(s) 1 2 3 4 5 6 7 8 9 10 11 12 SINCE PREVIOUS NOTIFICATION, THIS RECOMMENDATION HAS:

• I CHANGED EJ REMAINED THE SAME THIS RECOMMENDATION IS BASED ON:

LJ PLANT CONDITIONS L3 PROJECTED RELEASE J ACTUAL RELEASE EMERGENCY DIRECTOR REVIEW AND APPROVAL:

THE EMERGENCY DIRECTOR SHALL REVIEW AND SIGN THIS FORM INDICATING VERIFICATION OF AND APPROVAL FOR INFORMATION RELEASE AND PROTECTIVE ACTION RECOMMENDATION (if given).

APPROVED FOR RELEASE: I Emergency Director's Signature EP-IP-100 Rev. 14 Page 36 of 47 I

=

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 J-- Verify Blocks I - 8 are complete, release is approved by signature, and then fill out Block 9 of the form. For guidance on individual Block descriptions refer to EP-IP-100..

L3 Place only the first page of the completed form face down in the DNN fax machine.

LJ Follow the posted instructions at the DNN fax machine. Proceed immediately to Step 2.

Step 2: CONTACT THE COMMONWEALTH AND LOCAL OFFICIALS If notification is made on anything other than dedicated communication links (DNN or BECONS), request a verification callback.

LI Pick up the DNN ring-down phone, and read the following message twice:

"Attention, attention. Please standby for a roll call."

LJ Perform a roll call and check off the responding locations as they are identified.

[J Middleboro State Police LJ Carver LJ Marshfield Ll Framingham MEMA L3 Duxbury LJ Plymouth U Bridgewater U Kingston LU Taunton

- - 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 LU Read the information in Block 1 through Block 8.

J Tell those parties who have complete information to hang up, then provide missing information to remaining parties.

Ll Contact locations not answering roll call via BECONS or commercial telephone (speed-dialer) and read the information in Block 1 through Block 8.

Step 4: NOTIFY THE NRC L-Using the ENS or commercial phone read the information in Block 1 through 8.

Name of

Contact:

Time:

Step 5: ORGANIZE THE REPORT U 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. 14 Page 37 of 47

ATTACHMENT 8 Sheet 1 of 2 TERMINATION CHECKLIST True False Conditions no longer meet an Emergency Action Level and it J

Ll 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 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 F1 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 r]

U* 1 given the plant conditions.

5.

The reactor is in a stable shutdown condition and long-term core LJ LJ cooling is available.

6.

The integrity of the Reactor Containment Building is within

!l Technical Specifications limits.

7.

The operability and integrity of radioactive waste systems, decontamination facilities, power supplies, electrical equipment, and plant instrumentation including radiation monitoring equipment are acceptable.

8.

Any fire, flood, earthquake, or similar emergency condition or threat to security no longer exists.

9.

Any contaminated, injured person has been treated and/or transported to a medical care facility.

n J)

J n

EP-IP-100 Page Rev. 14 38 of 47

ATTACHMENT 8 Sheet 2 of 2 TERMINATION CHECKLIST (CONTINUED)

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 local agencies and agreement has been reached and coordination established to terminate the emergency.

True False LIJ L

Ll IL LI L3 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:

Date/Time:

Emergency Director EP-IP-100 Rev. 14 Page 39 of 47 Approved:

ATTACHMENT 9 Sheet 1 of 2 FESSNTIAL INFORMATION CHECKLIST LI Initial Message Date:

Time:

Person Providinq Information:

Name:

Location:

Dh~nn" I. Update am/pm i~

j s

1

1) lassficaton o Stau Time Declared:

LI Off-Normal Event LI Unusual Event LI Alert LI Site Area Emergency LI General Emergency am/pm

4) R o

Conditions Emer.gency Radioactive Release Status:

I-None LI Imminent LI Controlled LI Below PAGs Projected Release Duration:

Offsite Protective Actions:

LI In Progress L[ Uncontrolled LI Above PAGs hr(s)

LI None Issued UI Provided to Commonwealth Onsite Protective Actions:

LI None LI Potassium Iodide LI Evacuation of Nonessential LI Other:

Personnel Acin inPorss Injuries: How Many___

Q No LI Yes 1002 liii

.~IJ r_.

V...

Pln Codiios On-Line Stable At Power L3 LI LI LI Off-Line Unstable Cooling Down Cold Shutdown Time of Reactor Shutdown:

am/pm LI Improving LI Same LI Deteriorating Describe equipment, instrument, or other problems:

N Overexposure:

L] No LI Minor Nature of injuries or contamination:

Yes Major

.6) Ofst Agec Notfictio NRC MEMA MDPH Local (last town)

Time:

am/pm Time:

am/pm Time:

am/pm Time:

am/pm 7)Oft

• Asssac Requested LI LI L)

None Police Other:

LI Fire Department LI Ambulance

8)

New Medi Notfictio LI L3 LI None Draft News Release News Release Approved Press Conference 19 Sintr an Title EP-IP-100 Rev. 14 Page 40 of 47 I

I mVyiI!

I Hi II I*

lJ V

I

ATTACHMENT 9 Sheet 2 of 2 ESSENTIAL INFORMATION CHECKLIST N

Additional Information:

EP-IP-100 Rev. 14 Page 41 of 47

/ i

/

ATTACHMENT 10 Sheet 1 of 4 ACTIVATION OF THE EMERGENCY RESPONSE ORGANIZATION Emergency Response Organization Notification Using CANS

[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.

[5]

Listen for verbal prompt and enter the proper code for present emergency classification.

The codes are:

1111 Unusual Event 0

2222 Alert 0

3333 Site Area Emergency 0

4444 General Emergency 0000 Termination of classifiable event/Recovery EP-IP-100 Rev. 14 Page 42 of 47 NOTE If at any time CANS cannot be contacted or does not respond as indicated, go to Section II (Notification Using Group Pages if CANS Fails) in this Attachment.

If the individual activating CANS is not the Operations Shift Superintendent, Control Room Supervisor, Shift Control Room Engineer, or the Operations Assistant, it is necessary for the individual to obtain a security code (Social Security number) from one of these individuals.

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.

ATTACHMENT 10 Sheet 2 of 4

[6]

If you are NOT satisfied with the emergency classification, press the # sign to re-enter classification.

OR If you are satisfied, hang up the phone to start the notification process.

[7]

Verify CANS operability by checking the emergency pager located in the locker in the Operations Shift Superintendent's office. Ensure that the pager is activated and indicates the proper emergency classification. Allow approximately 5 minutes for CANS to activate the pager.

I 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. 14 Page 43 of 47

ATTACHMENT 10 Sheet 3 of 4 II.

Notification Usinq 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 0

2222 Alert 3333 Site Area Emergency 4444 General Emergency 0000 Termination of classifiable event/Recovery

[5]

Press the # sign to complete the entry.

EP-IP-100 Rev. 14 Page 44 of 47

ATTACHMENT 10 Sheet 4 of 4 Il1.

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.)

Emergency Offsite Manager (EOF)

Name Response Time (min.)

EP-IP-100 Rev. 14 Page 45 of 47

ATTACHMENT 11 Sheet I 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

• Any revision to Attachment 5 of EP-IP-100 shall require a corresponding revision to EP-AD-600.

EP-IP-100 Rev. 14 Page 46 of 47

ATTACHMENT 12 Sheet I of 1 IDENTIFICATION OF COMMITMENTS This Attachment lists those external commitments (i.e., NRC commitments, QAA audit findings, and INPO inspection items) implemented in this Procedure.

Reference Document Commitment Affected Section(s)

NRC Inspection Finding Develop and implement a system for use by Att. 5, EAL 81-15-34 the Control Room staff to aid in promptly Chart classifying events.

NRC Inspection Finding Provide EALs which include specific and Att. 5 81-15-35 observable Control Room instrument readings for each EAL corresponding to the respective initiating condition.

NRC Inspection Finding Provide EALs which address and conform to Att. 5 81-15-35, 84-41-02, all pertinent initiating conditions contained in 86-33-01 Appendix 1 of NUREG-0654.

NRC Inspecting Finding Revise the offsite notification procedures to Att. 6 81-15-36 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 50-293/88-28 Item 2.4 and quantification for earthquake EALs.

(EAL 7.4.2.2 7.4.2.3 Modifications to transmitted portions of Initial Notification and Follow-Up Information Form shall be reviewed with the Commonwealth.

EP-IP-100 Rev. 14 Page 47 of 47