Text

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)
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Emergency Plan Implementing Number: i PNPS Procedure Manual N/A RType H8.24 TABLE OF CONTENTS Effective Revision Date Number Title Emergency Classification and Notification 14 03/30/01 EP-IP-100 9 02/07/01 EP-IP-200 On-Call Emergency Director 1 05/14/99 EP-IP-201 Emergency Plant Manager 3 02/07/01 EP-IP-202 Company Spokesperson 7 12/12/00 EP-IP-210 Control Room Augmentation 11 11/15/00 EP-IP-220 TSC Activation and Response 5 07/25/00 EP-IP-229 TSC/OSC Equipment Operation 3 11/15/00 EP-IP-230 OSC Activation and Response 5 07/25/00 EP-IP-231 Onsite Radiation Protection 8 03/15/00 EP-IP-240 Emergency Security Organization Activation and

Response

9 02/07/01 EP-IP-250 EOF Activation and Response 5 12/26/00 EP-IP-251 Offsite Radiation Protection 7 02/01/01 EP-IP-252 Facilities Support 3 07/13/00 EP-IP-253 Relocation of the EOF 2 12/06/00 EP-IP-254 Communications Support 3 05/24/00 EP-IP-259 EOF Equipment Operation 3 01/19/00 EP-IP-300 Offsite Radiological Dose Protection 4 11/15/00 EP-IP-310 Radiation Monitoring Team Activation and Response 4 05/24/00 EP-IP-315 Personnel Monitoring Team Activation and Response 2B 06/19/98 EP-IP-330 Core Damage 8 01/23/01 EP-IP-400 Protective Action Recommendations 4 05/24/00 EP-IP-410 Evacuation/Assembly Page 1 of 2 Revision 67 Revision 67 03/30/2001 Page 1 of 2

Emergency Plan Implementing Number: N PNPS Procedure Manual N RType H8.24 TABLE OF CONTENTS Eff ective Revision Date Number Title 3 02/12/01 EP-IP-420 Search and Rescue 5A 04/08/98 EP-I P-440 Emergency Exposure Controls 3 05/24/00 EP-IP-501 Transport of Contaminated Injured Personnel 5 02/07/01 EP-IP-520 Transition and Recovery Page 2 of 2 Revision bt 03/30/2001 Page 2 of 2 Revision 67/

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 Date Originated 3/01 Pagqes Affected Description 7,32,35,40 Change the terms "Emergency Release" and "Release" to "Emergency Radioactive Release."

7 Clarify definition of Emergency Radioactive Release above/below PAGs.

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

15 Rewrite Section 5.6 to provide enhanced detail.

21,22,24,26 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.

34,37 Change the term "auto-dialer" to "speed dialer" on the instructions for Attachments 6 and 7.

REVISION 13 Date Originated 9/00 Pagqes Affected Description 5,6,27 Revise to include design basis core cooling requirements (2/3 core height with Core Spray) specified in EOP-01.

8 Add new definition for radiation monitor readings.

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

REVISION 12 Date Originated 1/00 Pa-qes Affected Description All All pages formatted to reflect the updated Procedures format.

Revision bars are not shown for reformatting.

8-10,14 Revise titles.

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

42 Revise titles and changes for new CANS.

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

TABLE OF CONTENTS Paae 5

1.0 P U R 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 ..........................................................................................

9 4 .0 R E SP O N S IB ILIT IE S .........................................................................................

.. 10 5 .0 P R O C E D UR E ...............................................................................................

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

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

12 5.3 WHILE IN A CLASSIFIED EMERGENCY ............................................

13 5.4 TRA NSITO RY EV ENTS .......................................................................

........................ 14 5.5 DOWNGRADING EMERGENCY CLASSIFICATIONS 15 5.6 TRANSITION TO RECOVERY ............................................................

................................. 15 5.7 INITIAL NOTIFICATION FORM DESCRIPTION

......................... 17 5.8 FOLLOW-UP INFORMATION FORM DESCRIPTION

.. 18 6 .0 R E CO R D S ...................................................................................................

19 7.0 ATTA C H ME N T S ............................................................................................

CHECKLIST ...... 20 ATTACHMENT I - UNUSUAL EVENT NOTIFICATIONS

............................ 21 ATTACHMENT 2 - ALERT NOTIFICATIONS CHECKLIST CHECKLIST 23 ATTACHMENT 3 - SITE AREA EMERGENCY NOTIFICATIONS CHECKLIST. 25 ATTACHMENT 4 - GENERAL EMERGENCY NOTIFICATIONS

..................................... 27 ATTACHMENT 5 - EMERGENCY ACTION LEVELS EP-IP-100 Rev. 14 Page 3 of 47

TABLE OF CONTENTS (Continued)

Age

_F 32 ATTACHMENT 6 - SAMPLE - INITIAL NOTIFICATION FORM 35 FORM ...............

ATTACHMENT 7 - SAMPLE - FOLLOW-UP INFORMATION 38 ATTACHMENT 8 - SAMPLE - TERMINATION CHECKLIST 40 CHECKLIST .......

ATTACHMENT 9 - SAMPLE - ESSENTIAL INFORMATION

RESPONSE

ATTACHMENT 10 - ACTIVATION OF THE EMERGENCY 42 O R G A NIZAT IO N ..............................................................

46 ATTACHMENT 11 - DOCUMENT CROSS-REFERENCES 47 ATTACHMENT 12 -IDENTIFICATION OF COMMITMENTS EP-IP-100 Rev. 14 Page 4 of 47

1.0 PURPOSE at which specific emergency This Procedure provides instruction of the entry conditions implementation of the Emergency Plan, and classifications must be declared, guidelines for the and organizations.

the process used to notify response personnel

2.0 REFERENCES

Bases"

[1] EP-AD-600, "EmergencyAction Level Technical

[2] EP-PP-01, "PNPSEmergency Plan"

[3] PNPS Technical Specifications 3.0 DEFINITIONS Reactor sufficient to prevent rupturing

[1] Adequate Core Cooling - Heat removal from the adequate core cooling are the fuel clad. Three viable mechanisms for establishing steam cooling.

defined: core submergence, spray cooling, and the core. The core is (a) Submergence is the preferred method for cooling be determined that RPV water adequately cooled by submergence when it can All fuel nodes are then assumed to level is at or above the top of the active fuel.

boiling heat transfer.

be covered with water and heat is removed by a bounding axial power shape, (b) Adequate Spra( Cooling is provided, assuming into the RPV at the design when at least one Core Spray subsystem is injecting at or above the elevation of the jet flow rate (3,600 GPM) and RPV water level is the core is then cooled by pump suctions (-175 in.). The covered portion of cooled by the spray flow, The submergence while the uncovered portion is subsystem to ensure adequate required spray flow must be supplied by a single spray distribution to all fuel bundles.

level cannot be restored and (c) Steam Cooling is relied upon only if RPV water be determined, or must be maintained above the top of the active fuel, cannot fuel. The core is adequately intentionally lowered below the top of the active uncovered length of each fuel cooled by steam if the steam flow across the clad temperature below the bundle is sufficient to maintain the hottest peak can be injected, 1800°F if makeup appropriate limiting value; 1500°F if makeup core remains cooled by boiling cannot be injected. The covered portion of the cools the uncovered portion.

heat transfer and generates the steam which EP-IP-100 Rev. 14 Page 5 of 47

RPV water Steam cooling with makeup capability is established by maintaining

(-150 in.) or RPV level above the Minimum Steam Cooling RPV Water Level function of the pressure above the Minimum Alternate RPV Flooding Pressure (a is limited to number of open SRVs). In either case, the peak clad temperature 1500°F, the threshold for fuel rod perforation.

as long as RPV water Steam cooling without makeup capability is established Water Level (-160 in.).

level remains above the Minimum Zero-Injection RPV the threshold for The peak clad temperature is permitted to rise to 1800°F, transfer to steam and to significant metal-water reaction, to maximize the heat The minimum RPV delay the need for RPV depressurization as long as possible.

when makeup water level at which adequate steam flow exists is higher capability exists because:

limit of 1800°F The limiting fuel temperature is lower (1500°F). The higher is used only when cladding perforation cannot be avoided.

the energy

With injection, water at the core inlet is subcooled. Some of the temperature of produced by the core must then be expended in raising to cool the the liquid to saturation and less steam will be produced uncovered portions of the core.

involve an actual or potential

[2] Alert - Events are in progress or have occurred which Any releases are expected to be substantial degradation of the level of safety at PNPS.

exposure levels.

limited to small fractions of EPA Protective Action Guideline system.

[3] BECONS - The PNPS community offsite notification

- A computer-assisted system

[41 Computerized Automated Notification System (CANS) that, when activated, has the following capabilities:

(a) Activating the emergency pager system.

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

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

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

of an identified parameter relative

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

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

is not

[6] Cannot Be Maintained Above/Below - The value of the identified parameter(s) making an able to be kept above/below specified limits. This determination includes in relation to the evaluation that considers both current and future system performance that the actual value of current value and trend of the parameter(s). It does not imply the parameter must first pass the specified limit.

is not able

[7] Cannot Be Restored Above/Below - The value of the identified parameter(s) limits. This to be returned to above/below specified limits after having passed those and future determination includes making an evaluation that considers both current parameter(s). It system performance in relation to the current value and trend of the operation does not imply any specific time interval, but does not permit prolonged (May be used beyond the limit without declaring the specified emergency classification.

in combination with Definition 3.0[6].)

in an EAL

[8] Controlled Process - A preplanned activity for which the conditions specified Procedure.

are anticipated to be or are intentionally exceeded as part of an approved

[9] DNN - Digital Notification Network.

of offsite

[10] Emergency Radioactive Release is/is not in Progress - For purposes radioactive release notification, any release of radioactivity is considered 'an emergency in progress which:

0 Meets any EAL of Classification Subsection 5.1, Effluent Monitors OR is

Involves an actual or suspected Turbine Building or unmonitored release which associated with the emergency event.

Guides (PAGs)

[11] Emergqency Radioactive Release is above/below Protective Action or 5 rem CDE Thyroid.

PAGs are defined by the EPA as dose in excess of 1 rem TEDE is considered For purposes of offsite notification, an emergency radioactive release above PAGs when:

on having General Emergency EAL 5.2.1.4 or EAL 5.2.2.4 is exceeded based dose projections or offsite measurements.

OR General In the absence of having dose projections or offsite measurements.

Emergency EAL 5.1.1.4 is exceeded.

[12] ENS - NRC Emergency Notification System.

Director when

[13] Essential Information Checklist - The form used by oncoming Emergency this Procedure.

relieving present Emergency Director of the responsibilities outlined in and Corporate This form may also be used to provide information to Media Center personnel.

EP-IP-100 Rev. 14 Page 7 of 47

specific emergency response duties

[141 Essential Personnel - Those individuals assigned Procedures.

as identified in the PNPS Emergency Plan and Implementing to initiate and document periodic

[15] Follow-Up Information Form - The form used agencies.

emergency classification updates to offsite or have occurred which involve actual or

[161 General Emergency - Events are in progress with the potential for loss of imminent substantial core degradation or melting to exceed EPA Protective Action containment integrity. Releases can be expected area near the site boundary.

Guideline exposure levels for more than the and document initial emergency

[17] Initial Notification Form - The form used to initiate classification notifications to off site agencies.

who are not assigned specific emergency

[18] Non-Essential Personnel - Personnel response duties.

to the Primary System. - The pipes, valves, and other equipment which connect directly

[191 reduction in RPV pressure will effect a Reactor Pressure Vessel (RPV) such that a through an unisolated break in the decrease in the steam or water being discharged system.

value Above/Below EAL Threshold Readingqs.- The

[20] Radiation Monitor Channel A and B a threshold reading may not apply when of both channels statements above or below of service. The determination of a valid one channel is known to be inoperable or out EAL threshold constitutes that the intent of reading on either channel that exceeds the classification should be declared.

the EAL has been met and the associated the Reactor is shutdown if the Reactor is

[211 Shutdown - As regards Reactor status, heating range (IRM range 7).

subcritical (power decreasing) and below the or progress or have occurred which involve actual

[22] Site Area Emergency - Events are in for the protection of the public. Any likely major failures of PNPS functions needed Action Guidelines exposure levels releases are not expected to exceed EPA Protective except near the site boundary.

system or component operability for which the

[23] Sustained Loss - Loss of power supply, be imminent. It does not imply any specific return to service has not been determined to permitted without declaring the specified time interval, but prolonged operation is not for degraded plant safety.

emergency condition based on the potential is no longer considered to be an emergency.

[24] Termination - The point at which the event by an Initial Notification message Termination of the emergency is formally identified transmission and entry into Recovery.

exceeded an Emergency Action Level (EAL)

[25] Transitory Event - An event in which PNPS but conditions improved prior to classification.

EP-IP-100 Rev. 14 Page 8 of 47

a potential

[26] Unusual Event - Events are in progress or have occurred that indicate material requiring degradation of the level of safety at PNPS. No releases of radioactive of safety offsite response or monitoring are expected unless further degradation systems occurs.

4.0 RESPONSIBILITIES if the Operations

[1] The Operations Shift Superintendent, or the Control Room Supervisor Room, shall be Shift Superintendent is incapacitated or away from the Control implementation of responsible for the initial emergency classification declaration and this Procedure.

if the Operations

[2] The Operations Shift Superintendent, or Control Room Supervisor Emergency Director upon Shift Superintendent is unavailable, shall assume the role of continue to function as the initial declaration of any emergency classification and shall Emergency Director or Emergency Director until relieved of those duties by the on-call or off-shift other qualified individual (i.e., Emergency Plant Operations Supervisor Operations Shift Superintendent).

emergency

[3] The Emergency Director is the final authority for determining the to recovery). This classification level (initial classification, downgrading, or terminating authority may not be delegated.

notification of the

"[4] The Emergency Director is responsible for directing and overseeing on-call PNPS Emergency Response Organization.

is responsible for the

[5] The Control Room Operations Assistant or a designated alternate following:

Organization.

(a) When directed, notifying the on-call PNPS Emergency Response notification (b) Periodically checking on the status of personnel responding to the process.

on-call personnel (c) If CANS and BEEPS fail, Security is responsible for notifying using commercial telephone lines.

EP-IP-100 Rev. 14 Page 9 of 47

5.0 PROCEDURE 5.1 RECOGNIZING AN EMERGENCY will verify the

[1] When indications of abnormal conditions are received, personnel Action Levels symptoms/indications and then compare them with the Emergency (Attachment 5).

EALs are exceeded) for

[2] Identify the highest emergency classification level (if multiple 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.

release is in (b) If plant conditions indicate a possible radiological release or a dose-based EALs progress or suspected, evaluate the applicability of offsite (category 5.2).

condition no (c) If a classification level was met or exceeded but the classifiable longer exists (a lesser classification level may or may not still be appropriate),

refer to Section 5.4, Transitory Events.

CONTROL ROOM 5.2 INITIAL DECLARATION OF AN EMERGENCY FROM THE if the Operations

[1] The Operations Shift Superintendent, or Control Room Supervisor Room operating staff:

Shift Superintendent is unavailable, shall announce to the Control (a) That an emergency has been declared.

(b) The emergency classification level.

has (c) That the Operations Shift Superintendent (Control Room Supervisor) assumed the role of Emergency Director.

[2] Conduct initial emergency notifications as follows:

NOTE to Station personnel In the event the public address system is inoperative during notifications to plant personnel.

at any time, determine alternate means to disseminate information the General (a) For events which are classified as a General Emergency, complete 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 simultaneous classification level before the actual initial notification transmittal, do not send classification notifications. Generate and send a new notification form with the appropriate level.

(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 controls responsibilities of the Onsite Radiological Supervisor for emergency exposure until relieved by the on-call Onsite Radiological Supervisor.

personnel

[4] Contact (or direct an assistant to contact) on-shift Production Maintenance report to the Control Room or not already involved in the emergency and inform them to the OSC to stand by for repair and corrective action activities if necessary.

Shift

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

by the

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

EP-IP-100 Rev. 14 Page 11 of 47

5.3 WHILE IN A CLASSIFIED EMERGENCY that the

[1] As soon as possible, but no later than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after event classification, ensure ENS or a commercial telephone line is continuously staffed with a knowledgeable NRC.

individual to provide additional event notification and plant information to the Action Levels

[2] Emergency response personnel will continuously review the Emergency (Attachment 5) to ensure proper and appropriate event classification.

emergency (a) If the declaration of a higher classification is warranted, conduct initial notifications as follows:

(1) For events which are classified as a General Emergency complete the General Emergency Notifications Checklist (Attachment 4).

NOTE emergency If during the declaration process it becomes necessary to upcqrade the send simultaneous classification level before the actual initial notification transmittal, do not classification notifications. Generate and send a new notification form with the appropriate 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).

longer (b) If a higher classification level was met but that classifiable condition no refer to exists (a lesser classification level may or may not still be appropriate),

Section 5.4, Transitory Events.

refer to (c) If the emergency conditions support downgrading the classification level, 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.

Commonwealth

[3] Provide periodic updates (hourly or whenever conditions change) to the 7).

and local communities using Follow-Up Information Forms (Attachment available,

[4] As conditions improve and additional personnel and resources become 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.

be (b) Items contained on the Essential Information Checklist (Attachment 9) will 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.

as (c) Discuss any Protective Action Recommendations issued to offsite agencies applicable.

5.4 TRANSITORY EVENTS events

[1] For situations which begin under non-emergency conditions then experience which ultimately result in a classifiable emergency, enter and execute the following level:

Attachment which corresponds to the appropriate current classification (a) Attachment 1, Unusual Event Notifications Checklist.

(b) Attachment 2, Alert Notifications Checklist.

(c) Attachment 3, Site Area Emergency Notifications Checklist.

events which

[2] For situations which begin under non-emergency conditions, experience meet a qualify as a classifiable emergency, and result in conditions which no longer 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

the transitory event (b) Complete and distribute an Initial Notification Form to specify number 0.0.0.0 is used classification level and signify entry into Recovery (EAL to signify entry into Recovery).

Recovery."

(c) Exit this Procedure and enter EP-IP-520, "Transitionand experience events which

[3] For situations which begin in a classified emergency then ultimately result in:

(a) A return to the current classification level specify the transitory event Complete and distribute an Initial Notification Form to level.

classification level and signify return to the current classification NOTE directly result in a downgraded Transitory events which occur during an emergency cannot must be performed separately.

classification level or entry into Recovery. These actions level (b) A lower classification level or no longqer meet a classification specify the transitory event Complete and distribute an Initial Notification Form to level.

classification level and signify return to the current classification

~. [4] Return to Section 5.3.

5.5 DOWNGRADING EMERGENCY CLASSIFICATIONS to downgrade below the Alert

[1] Once in an Alert or higher classification level, the decision have been activated.

level shall only be made after the TSC, OSC, and EOF over the public address

[2] Have the Control Room make the following announcement system, TWICE:

classification level has "Attention all personnel, attention all personnel: The emergency been downgraded to a/an (applicable classification level)."

signify entry into the lower

[3] Complete and distribute an Initial Notification Form to 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, whether conditions complete the Termination Checklist (Attachment 8) to determine allow termination of the event and entry into Recovery.

into Recovery, exit this

[2] If conditions allow for termination of the emergency and entry Procedure and enter EP-IP-520, "Transitionand Recovery".

Recovery,

[3] If conditions do not support termination of the emergency and entry into of this Procedure.

continue following the guidance provided in Section 5.3 5.7 INITIAL NOTIFICATION FORM DESCRIPTION NOTE must coordinate the numbering Upon activation of the EOF, the Control Room and EOF are assigned to notification forms.

sequence of notifications to ensure consecutive numbers sequentially from the start of the

[1] Form Number: Notification form numbers are assigned Form as well as the emergency. The sequence includes the Initial Notification Follow-Up Information Form.

of a drill or exercise versus an

"-- [2] Block 1: Designation for notifications conducted as part actual event.

level applicable to the

[3] Block 2: Specifies the time, circumstance, and classification notification form as follows:

Director (or (a) The time and date denote the point at which the Emergency declared the new Operations Shift Superintendent) recognized and formally event classification level.

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

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

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

notification of (e) The "downgraded to" check box is used to provide initial level.

emergencies which warrant lowering the classification applicable to (f) The classification level boxes are used to indicate the classification 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, "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. 14 Page 16 of 47

5.8 FOLLOW-UP INFORMATION FORM DESCRIPTION start of the

[1] Form Number: Notification form numbers are assigned sequentially from the emergency. The sequence includes the Initial Notification Form as well as the Follow-Up Information Form.

versus an

[2] Block 1: Designation for notifications conducted as part of a drill or exercise 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:

the (a) For events with more than one EAL in the highest classification level, provide 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.

of

[6] Block 5: Indicates whether offsite assistance has been requested, the type assistance, and the reason for the request.

[7] Block 6: Provides indication of an emergency radioactive release and the relative whether magnitude. If necessary, refer to EP-IP-400, "ProtectiveActions", to determine release is above an emergency release is in progress, whether an emergency necessary.

protective action guides, and what protective action recommendations are the

[8] Block 7: Provides the most recent meteorological data obtained from any of available sources.

PNPS

[9] Block 8: Provides any applicable protective action recommendations made by 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.

and

[11] Block 10: Indicates the time and date when transmission of the form was received the name of the individual receiving the transmission.

made by

[12] Block 11: Provides the protective action recommendations and their bases the EOF PNPS ERO personnel when MEMA or MDPH representatives are present in (only applicable for General Emergency classifications).

[13] Block 12: Emergency Director approval signature.

6.0 RECORDS of this

[1] The following documents are generated as a result of the implementation 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 following

[2] All records shall be forwarded to Emergency Preparedness for final disposition 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 CHECKLIST ATTACHMENT 3 - SITE AREA EMERGENCY NOTIFICATIONS CHECKLIST ATTACHMENT 4 - GENERAL EMERGENCY NOTIFICATIONS 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 ORGANIZATION ATTACHMENT 10 - ACTIVATION OF THE EMERGENCY RESPONSE 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.

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

has been declared due A. "Attention all personnel, attention all personnel: An Unusual Event

Response

to (brief description of initiating event). All on-call members of the Emergency with your Organization stand by for further instructions. All other personnel continue present duties until additional instruction is given."

announce its type and B. If there is a localized emergency (for example, high radiation, fire),

location and instruct personnel to stand clear of this area.

Time Completed:

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

Time Completed:

NOTIFICATION OF STATE AND LOCAL AGENCIES Form (Attachment 6)

Within 15 minutes of the event classification transmit an Initial Notification to the Commonwealth and local authorities.

Time Completed:

NOTIFICATION OF THE NRC telephone Inform the NRC of the event classification using the ENS or a commercial (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 SITE & PUBLIC AREA NOTIFICATION - RELEASE OF NONESSENTIAL PERSONNEL CAUTION .<

Drinaa.s.r~a , e a'. i.sab.e t. sound.. .QI Sound/have the Control Room sound the Operator Recall Alarm and make the following announcement over the public-address system, TWICE:

(brief A. "Attention all personnel, attention all personnel: An Alert has been declared due to description of initiatingIevent). All on-call members of the Emergency Response Organization report to your designated emergency response facility. All Pilgrim Station await personnel assemble in your normal office or shop area, report to your supervisor, and instructions. All visitors, all nonessential contractor personnel, all declared pregnant females, and all persons with disabilities please leave the site at this time." I type and B. If there is a localized emergency (for example, high radiation, fire), announce its location and instruct personnel to stand clear of this area.

that there C. If there is a potential for an airborne radiological release, consider announcing 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 6)

Within 15 minutes of the event classification transmit an Initial Notification Form (Attachment to the Commonwealth and local authorities.

Time Completed:

EP-IP-100 Rev. 14 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. I 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

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 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.

EP-IP-100 Rev. 14 Page 23 of 47

ATTACHMENT 3 Sheet 2 of 2 SITE AREA EMERGENCY (Continued)

SITE & PUBLIC AREA NOTIFICATION - PROTECTED AREA EVACUATION (CONTINUED) and B. If there is a localized emergency (for example, high radiation, fire), announce its type location and instruct personnel to stand clear of this area.

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

I Time Completed:

NOTIFICATION OF THE ERO - EMERGENCY FACILITY ACTIVATION 10, If not already notified, notify or direct notification of the ERO in accordance with Attachment Activation of the Emergency Response Organization.

Time Completed:

NOTIFICATION OF STATE AND LOCAL AGENCIES (Attachment 6)

Within 15 minutes of the event classification transmit an Initial Notification Form 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 the time that accountability is complete and provide the names of missing persons, if any. Log 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], 5.3[2](a), OR 5.4[1])

EP-IP-100 Rev. 14 Page 24 of 47

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

Assembly Area Wind Direction (0 from)

L- Support Building Cafeteria 0000-2890 or 3240-3600 Ll 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 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. 'Ifhigh dose irates will, be 8 1npopntpred, it may be betteor to shIeltet 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 (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 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.

EP-IP-100 Rev. 14 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. 14 Page 26 of 47

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ATTACHMENT 5 Sheet 1 of 5 1.0 REACTOR FUEL ALERT UNUSUAL EVENT GENERAL EMERGENCY SITE AREA EMERGENCY 1.1.1.2 1.1.1.1 1.1 Coolant 1.1.1.4 Reactor coolant system sample activity Reactor coolant system sample activity Activity Reactor coolant system sample activity which indicates a > 200 microcunesiml total iodine. 20 microcuries/il total iodine.

core melt condition as determined by EP-IP-330, "Core 1.2.1.2 1.2.1.1 1.2 Off-gas Air ejector off-gas radiation monitors 1705-3A and B Air ejector off-gas radiation levels approaching Technical Activity 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.

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

Monitors Valid Drywell High Range Area Radiation Montor reading Monitor 1705-8 Channel A(A/C) and Channel B(BID) High

> 10,000 RPhr(RIT-1001-606A and B) or Valid Torus High > 200 R/hr (RIT-1001--606A and B) or Valid Torus High reading > 200 RPhr Range Area Radiation Monitor reading > 3 RPhr trip Panel 910.

Range Area Radiation Monitor degraded reactor fuel (RIT-1001-607A and B) due to degraded reactor fuel AND (RIT-1001-607A and B) due to Upscale alarm on two or more of the following Area integrity conditions, integrity conditions.

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 2.1.1.2 2.1.1.1 2.1 Reactor Water 2.1.1.4 2.1.1.3 RPV water level cannot be determined (RPV Flooding is RPV water level cannot be restored and maintained Sustained RPV water level < -160 inches. RPV water level cannot be maintained above -125 inches above +12 inches.

Level (TAF). required),

AND 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 2,2.1.2 2.2.1.1 Reactor 2.2 Pressure required) Sustained reactor vessel dome pressure > 1325 psig. Reactor vessel dome pressure cannot be maintained

< 1115 psig (except during RPV hydrostatic testing).

2.3.1.3 2.3.1.2 2.3 Reactor Power 2.3.1.4 A reactor Scram has been initiated.

Reactor power > 3% and torus temperature above the Boron injection into the RPV intentionally initiated (boron injection required) with either: AND "Boron Injection Initiation Temperature" (BIIT) EOP The reactor is not shutdown.

Figure 4.

Standby Liquid Control System (SBLC).

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,U laRIMARY L;ONTAINMENT 3.1.1I 3.0 FRIMARY LUONTAINMENT ___________ 3.1.11.1 Bulk drywell temperature cannot be maintained < 150°F 3.1 Drywell 3.1.1 .3 Bulk drywell temperature cannot be maintained < 280=F as determined by PNPS Procedure 2A1.27, "Drywell Temperature as determined by PNPS Procedure 2.1.27, "Drywell Temperature Indication."

Temperature Indication." AND Primar containment integrity is required.

3.2.1.1 I - i - 11 Torus water temperature > 110-F.

3.2 Torus water Torus water temperature cannot be maintained below the Temperature 3.3.1.1 3.3."1.3 F ue 3.3.12 Reactor coolant system to drywelt unidentified leakage 3.3.1.3 3.3.1.2 Torus water level cannot be maintained < 180 inches.

3.3 Containment 3.3.1.4 Both torus water level and RPV pressure cannot be > 5 gpm with reactor coolant temperature > 212'F.

Primary containment water level cannot be maintained Water Level maintained below the "SRV Tail Pipe Level Limit" OR

< 77 feet. Reactor coolant system to drywell total leakage > 25 gpm (SRVTPLL) EOP Figure 2.

with reactor coolant temperature > 212'F.

3.3.2.3 Torus water level cannot be maintained > 90 inches. 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.

I _________________________ .L 3.4.1.3 1 3.4.1.2 3.4 Primary 3.4.1.4 3.4.1.3 Prmary containment pressure cannot be maintained Torus bottom pressure cannot be maintained below the < 2.2 psig (except during testing such as ILRT, etc.)

Containment Torus pressure approaching "The Primary Containment "Pressure Suppression Pressure" (PSP) EOP Figure 6 Pressure Pressure Limit" (PCPL) EOP Figure 7 (prior to initiation of lexceot durina testno such as ILRT, etc.).

containment ventinol. 3.5.12 4 3.5.1.4 1.5.-1.3 Drywell or torus hydrogen concentration > 1%.

3.5 Containment 3.5.1.4 Drywell or torus hydrogen concentration > 1%.

H2 & 02 Drywell or torus hydrogen concentration > 6%.

AND AND Concentration Drywett or torus oxygen concentration >5% (Prior to Drywell ortorus 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). ________________________________ J ________________________________ I ________________________________

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

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ATTACHMENT 5 Sheet 3 of 5

(.;ONTAINMENT 4.0 ,.%ECONDARY 4.0 4.1.1.1 SECONDARY CONTAINMENT __________I___ Secondary containment area water levels exceed the 4.1.1.3 4.1 Secondary Secondary containment area water levels exceed the "Maximum Safe Operating Value" in two or more areas Containment "Maximum Safe Operating Value" in two or mere areas EOP Table L.

Area Water EOP Table L. AND AND Reactor coolant temperature > 212°F with irradiated fuel Levels A primary system is discharging into the area. in the vessel.

AND Reactor coolant temperature > 212'F with irradiated fuel in the vessel. 4.2.1.1 I i -I Secondary containment area temperatures exceed the 4.2.1.3 4.2 Secondary Secondary containment area temperatures exceed the "Maximum Safe Operating Value' in two or more areas Containment "Maximum Safe Operating Value" in two or more areas EOP Table L.

Area EOP Table L. AND AND Reactor coolant temperature > 212'F with irradiated fuel Temperatures A pnmary system is discharging into the area. in the vessel.

AND Reactor coolant temperature > 212°F with irradiated fuel in the vessel 4.3.1.2

_________ I I ITGeneral area radiation levels measured in-plant which 4.3 Secondary Secondary containment radiation levels exceed thre increase by a factor of 1000 times normal as a result of Containment "Maximum Safe Operating Value" in two or more areas airborne radioactivity which cannot be attributed to a Area Radiation SOP Table L controlled process.

Levels AND

______________I A primary system asdischarging into the area. I________________________

5.U I*ADIOACTIVITY IXELEASE 5.1.1.1 5.0 RADIOACTIVITY KELEASE ____________

5.1.1I 5.1.1.2Reactor Building Ventilation Exhaust (RBVE) 5.1.1.1 Valid Reactor Building Ventilation Exhaust (RBVE) 5.1,1.4 5.1.1.,3 Valid monitor 1705-32A and B Panel 910 high alarm which 5.1 Effluent Valid Main Stack Process Radiation Monitor 1705-18 A monitor 1705-32A and B Panel 910 high-high alarm which Monitors Valid Main Stack Process Radiation Monitor 1705-18 A and B Panel 910 reading > 2.4E4 cps. does not clear within 15 minutes from the time action is and B Panel 910 reading > 2.4E5 cps. 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 Main stack radioactivity effluents in excess of the Valid Main Stack Process Radiation Monitor 1705-18A high-high alarm setpoint for greater than 15 minutes as and B Panel 910 reading > 10.000 cps for greater than indicated by the Main Stack Process Radiation Monitors 15 minutes. 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).

5.2.1.4 5.2.1.3 5.2 Dose Dose projection based on effluent monitors or actual Projection & Dose projection based on effluent monitors or actual in environmental measurements which indicate doses in Environmental environmental measurements which indicate doses excess of 100 mrem whole body or 500 mrem thyroid at excess of 1000 mrerm whole body or 5000 mrerm thyroid at the site boundary or beyond.

Measurements 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 5.3.1.1 thyroid at the site boundary or beyond. Transportation of a contaminated injured person to an 5,3 Contaminated nffaite medical facilitY.

injury . .............. .

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

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ATTACHMENT 5 Sheet 4 of 5 6.0 INTERNAL EVENTS SITE AREA EMERGENCY ALERT UNUSUAL EVENT GENERAL EMERGENCY 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.

6.2.1.2 6.2.1.1 6.2.1.3 6.2 Safety Loss of Control Room habitability (e.g., fire, smoke, Failure of a reactor Safety Relief Valve (RV-203-3A thru Systems Evacuation of Control Room without establishment of D) to close following reduction of applicable pressure as plant control from remote shutdown stations within radiological hazards, etc.).

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 conditions as indicated by: *'SRV tailpipe temperature recorder TR-260-20 Steam line break outside primary containment without 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.

6.3.1.3 6.3.1.2 6.3.1.1 6.3 Electrical Loss of all AC power capability as indicated by the Loss of all vital onsite AC power capability as indicated System Sustained loss of all AC power capability as indicated by by:

Saitre the inability to power any 4kV bus (Al thru A6) from any inability to power any 4kV bus (Al thru A6) from any Failures source (all 4kV buses de-energized). source (all 4kV buses de-energized). Inability to power Bus AS from any onsite generator*.

AND 6.3.2.2 Inability to power Bus A6 from any onsite generator'.

6.3.2.3 Onsite generators are.

Sustained loss of all 125 VDC power capability as Loss of all 125 VDC power capability as indicated by:

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

Station Blackout Diesel Generator Voltage < 105 VDC Panel D-17.

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 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) 6.4.1.2 6.4.1.1 6.4 Loss of 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 Loss of most or all Control Room annunciators, equipment to an extent requiring shutdown by Technical Comm AND Specifications.

Capability AND Reactor coolant temperature is > 212'F.

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

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ATTACHMENT 5 Sheet 5 of 5 Sheet"5_of_5 7.0 EXTERNAL EVENTS 7.1.1.1 7.1.1.4 7.1.1.3 7.1.1.2 the Protected Area into Force.

Security 7.1 Security 10 minutes) as Any attempted by as determined the Station entry unauthorized in the judgment of An ongoing security the lossof compromise which in the judgment Any ongoingby determined security the Station Security(>

compromise Force.

Threats An ongoing security compromise which loss of the Operations Shift Superintendent may lead to the Operations Shift Superintendent has led to the of physical control of the plant 7.1.2.1 physical control of the plant.

Any indication of attempted sabotage.

7.1.3.1 Receipt of a credible bomb threat as determined by the Station Security Force.

7.2.1.2 7.2.1.1 7.2 Fire 7.2.1.3 Fire within the Protected Area lasting > 10 minutes from fire which has affected the ability of two or more Fire burning out of control in a plant vital area.

the time firefighting efforts begin (Fire Brigade fire fighting

_Any Table 7-1 Safety Systems safety systems (Table 7-1) to perform their intended function and poses a significant potential for release of efforts have begun when the Fire Brigade first applies fire fighting agents on the fire.).

radioactivity, fOR Residual Heat Removal AND Any fire onsite for which offsite fire fighting assistance is Reactor coolant temperature> 212F. requested (the required notification of the Plymouth Fire request Department for offsite for any fire assistance.

fighting fireonsite .

does not constitute a.

Core Spray CoeSIa 7.3.1.2 7.3.1.1 7.3 Man-made Emergency Diesel Generators 7.3.1.3 Any of the following events occurring which affect plant Any of the following events occurring onsite:

Any of the following which has affected the ability of two

Aircraft crash.

Events or more safety systems (Table 7-1) to perform their operation:

. Explosion (unplanned).

High Pressure Coolant Injection intended function and poses a significant potential for ° Aircraft crash on facility.

Missile impact from any source on facility.

Toxic or flammable gas release.

release of radioactivity:

Entry of toxic or flammable gas into a plant process Automatic Depressurization System . Aircraft crash on facility.

building atmosphere (includes significant Main

Missile impact from any source on facility, Entry of toxic or flammable gas into a plant process Generator hydrogen leaks).

Reactor Protection System building atmosphere. . Explosion (unplanned).

i Explosion (Unplanned).

ATWS/ARI AND Reactor coolant temperature > 212°F 7.4.1.2 7.4.1.1 7.4 Natural Events Primary Containment Isolation 7.4.1.3 Any of the following which causes damage to permanent Sustained winds (> 5 minutes) in excess of 75 mph as Any of the following which has affected the ability of two plant structures or equipment which affect plant operation: indicated on wind speed recorder Panel MT1.

System or more safety systems (Table 7-1) to perform their Earthquake 7.4.2.1 intended function and poses a significant potential for

Standby Gas Treatment

release of radioactivity:

Tornado Report of a tornado onsite.

. Earthquake

Hurricane Standby Liquid Control . Tornado

Other Natural Phenomena 7.4.3.1 A.3.1

. Hurricane Any earthquake detected by seismic instrumentation as Reactor Building Closed Cooling . Other Natural Phenomena 7.4.2.2 Any earthquake onsite which has been determined to be indicated by:.

AND greater than Operating Basis Earthquake levels (0.08 g). R Seismic monitor event alarm Panel gi1.

Water Reactor coolant temperature is > 212°F.

"Seismic Recorder Operating" annunciator Panel C1 Service Water 7A4.2.3 Right A-7.

Any earthquake onsite which has been determined to be greater then Safe Shutdown Earthquake levels (0.15 g). Ground motion is felt by one or more plant operations personnel.

8.0 OTHER 8.1.1.1 8.1.1.3 8.1.1.2 8.1 Other 8.1J1.4 Any event which in the opinion of the Operations Shift Any event which in the opinion of the Operations Shift In the opinion of the Operations Shift Superintendent or In the opinion of the Operations Shift Superintendent or Superintendent or Emergency Director could or has Superintendent or Emergency Director could or has led to Emergency Director events are in progress which indicate Emergency Director events are in progress which indicate a potential degradation of the level of safety of the plant.

actual or likely failures of plant systems needed to protect caused actual substantial degradation of the level of plant actual or imminent core damage and the potential for a 8.1.1 large release of radioactive material outside the site the public and pose a significant radioactivity release safety.

Any event which in the opinion of the Operations Shift boundary. potential.

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

ATTACHMENT 6 Sheet 1 of 3 PIGI NUCLAR OWE STIO No.T=

VENT 1 THIS IS: [J A DRILL II AN ACTUAL E 2 AS OF: PILGRIM NUCLEAR POWER STATION HAS time date J1 ENTERED: JI AN UNUSUAL EVENT F1 AN ALERT LI HAD A TRANSITORY THEN ENTERED: LJ A SITE AREA EMERGENCY JI UPGRADED TO: F1 A GENERAL EMERGENCY LI DOWNGRADED TO: LI RECOVERY BRIEF DESCRIPTION OF EVENT:

31 EAL No.

4] EMERGENCY RADIOACTIVE RELEASE:

LJ is JI IS NO 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 INMEMNVMDIWARE_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 Ml 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 L

I EP-IP-100 Rev. 14 Page 33 of 47

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 individualBlock descriptionsrefer 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. 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.

[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

ATTACHMENT 7 Sheet 1 of 3 No.W LJ A DRILL L AN ACTUAL I 0 THIS IS:

_AS OF: PILGRIM NUCLEAR POWER STATION IS STILl - AT A:

time date F]S IU IN UO I "A AI r-\KlZT [J Al ERT L-I SITE AREA EMERGENCY [L GENERAL EMERGENCY U/ L ._vn.l* - * . . .. .

3 STATION CONDITIONS ARE: J IMPROVING J STABLE IJ DEGRADING EAL No. BRIEF DESCRIPTION OF EVENT:

4 J HAS FIII HAS NOT BEEN REQUESTED OUTSIDE ASSISTANCE:

[1 AMBULANCE REASON FOR OUTSIDE ASSISTANCE:

FIRE DEPARTMENT L-- POLICE J OTHER (Specify) 6 EMERGENCY RADIOACTIVE RELEASE:

........ IN PROGRESS F, is

IS NOT J IS ABOVE I-1 IS BELOW .................................. PROTECTIVE ACTION GUIDES L METEOROLOGICAL DATA AS OF WIND DIRECTION FROM TO

,__ 0 AT mph STABILITY CLASS 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 BY (circle the affected subareas) 9 JNOTIFICATION INITIATED 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 IFOLLOW-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 INTHE 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).

I APPROVED FOR RELEASE: I=

Emergency Director's Signature EP-IP-100 Rev. 14 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 J-- Verify Blocks I - 8 are complete, release is approved by signature, and then fill out Block 9 of the form. Forguidance on individualBlock 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. Proceedimmediately to Step 2.

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

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

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

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, n J) 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.

J n EP-IP-100 Rev. 14 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.

LIJ L

11. Offsite conditions do not unreasonably limit access of outside support to the Station and qualified personnel and support LlIL services are available.

12. Discussions have been held with Federal, Commonwealth, and LI L3 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. 14 Page 39 of 47

ATTACHMENT 9 Sheet 1 of 2 I

FESSNTIAL INFORMATION CHECKLIST mVyiI! I Hi II I* lJ V ....

LI Initial Message I. Update 4) R o Conditions Date: Time: am/pm Status:

Emer.gency Radioactive Release I Person Providinq Information: I- None LI Imminent LI In Progress LI Controlled L[ Uncontrolled Name:

LI Below PAGs LI Above PAGs Location:

Projected Release Duration: hr(s)

Dh~nn"

- i~ j s - - _ . - - - _ _.

1 lassficaton

1) o Stau Offsite Protective Actions:

LI None Issued Time Declared: am/pm UI Provided to Commonwealth LI Off-Normal Event Onsite Protective Actions:

LI Unusual Event LI None LI Alert LI Potassium Iodide LI Site Area Emergency LI Evacuation of Nonessential Personnel LI General Emergency LI Other:

Acin inPorss Injuries: How Many___ Q No LI Yes V...

1002 liii N .~IJ r_.

Overexposure: L] No Yes LI Minor Major Nature of injuries or contamination:

.6) Ofst Agec Notfictio NRC Time: am/pm Pln Codiios MEMA Time: am/pm On-Line L3Off-Line MDPH Time: am/pm Stable LI Unstable Local (last town) Time: am/pm At Power LI Cooling Down Cold Shutdown 7)Oft *Asssac Requested Time of Reactor Shutdown: am/pm LI None LI Fire Department LI Police LI Ambulance LI Improving LI Same LI Deteriorating L) Other:

Describe equipment, instrument, or other 8) New Medi Notfictio problems:

LI None L3Draft News Release News Release Approved LI Press Conference 19 Sintr an Title I

EP-IP-100 Rev. 14 Page 40 of 47

ATTACHMENT 9 Sheet 2 of 2 ESSENTIAL INFORMATION CHECKLIST N

i/

/

Additional Information:

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

ATTACHMENT 10 Sheet 1 of 4 ACTIVATION OF THE EMERGENCY RESPONSE ORGANIZATION 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 Operations Shift Superintendent, Control Room Supervisor, Shift Control Room Engineer, or the Operations Assistant, it is necessary for the individual to obtain a security code (Social Security number) from one of these individuals.

[1] Ascertain the current emergency classification from the Emergency Director.

[2] Obtain the phone number for CANS from the Immediate Notification section of the PNPS Emergency Telephone Directory.

[3] Attempt to contact CANS using any touch-tone phone line.

[4] Listen for the introductory message and enter your security code (Social Security number) upon request followed by the # sign.

NOTE For activation of the ERO for drills and exercise, precede the following classification codes with DRILL (37455 on telephone keypad). For example, for a drill classification of Alert, enter DRILL 2222 (374552222) as the emergency classification code.

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

The codes are:

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

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 Ifcommunication 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 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months . 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

ML010930249

Contents

Text

Response

RESPONSE

2.0 REFERENCES

Response

Contact:

Contact:

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