Text

Revision 0 to EP-PS-137 TSC NRC Communicator
	ML031960420
Person / Time
Site:	Susquehanna
Issue date:	06/27/2003
From:	; Susquehanna
To:	; Document Control Desk, Office of Nuclear Security and Incident Response
References
	28401 EP-PS-137, Rev 0
	Download: ML031960420 (84)
	v • d • e

Jun. 27, 2003 Page 1 of 1 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2003-30982 USE INFORMATION: )

N :G ACH EM EMPL#:28401 CA#:0363 Ad ess:

Pho 254-319 TRANSMITTAL INFORMATION:

TO: C 2flT I^ f 1 t 06/27/2003 LOCATION: DOCUMENT CONTROL DESK FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2)

THE FOLLOWING CHANGES HAVE OCCURRED TO.THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNED TO YOU:

137 - 137 TSC NRC COMMUNICATOR REMOVE MANUAL TABLE OF CONTENTS DATE:

ADD MANUAL TABLE OF CONTENTS DATE: 06/26/2003 CATEGORY: PROCEDURES TYPE: EP ID: EP-PS-137 ADD: REV: 0 UPDATES FOR HARD COPY MANUALS WILL BE DISTRIBUTED WITHIN 5 DAYS IN ACCORDANCE WITH DEPARTMENT PROCEDURES. PLEASE MAKE ALL CHANGES AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX UPON RECEIPT OF HARD COPY. FOR ELECTRONIC MANUAL USERS, ELECTRONICALLY REVIEW THE APPROPRIATE DOCUMENTS AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX.

.- . IS~~~M

PROCEDURE COVER SHEET PPL SUSQUEHANNA, LLC NUCLEAR DEPARTMENT PROCEDURE TSC NRC COMMUNICATOR EP-PS-137 Emergency Plan Position Specific Instruction Revision 0 Page 1 of 3 QUALITY CLASSIFICATION: APPROVAL CLA IFICATON:

( ) QA Program (X) Non-QA Program ( ) PlarltA 7 ,( Non-Plant

( X) Insnbo EFFECTIVE DABt: ________X03 PERIODIC REVIEW FREQIJENCY: , Two Years PERIODIC REVIEW OU9iVATE:

,:' ;P X RECOMMENDED REVIEWS.

N.;

A Procedure Owner: Nuclear Emergency Planning Responsible Supervisor: Manager-Nuclear Operations Responsible FUM: Supv.-Nuclear Emergency Planning Responsible Approver: VP-Nuclear Operations FORM NDAP-QA-0002-1, Rev. 3, Page 1 of 1

EP-PS-137 Revision 0 Page 2 of 3 TECHNICAL SUPPORT CENTER (TSC) COMMUNICATOR: Emergency Plan-Position SDecific Procedure WHEN: Technical Support Center (TSC) is activated HOW NOTIFIED: Paged, 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s/day REPORT TO: Operations Coordinator WHERE TO REPORT: TSC OVERALL DUTY:

Summarize and transmit information about the emergency, until the EOF takes over communications. After EOF takeover, maintain the ENS hotlirn to answer NRC questions about the plant, and serve as technical advisor to the Operations Coordinator.

MAJOR TASKS: TAB: REVISION:

Perform required offsite notifications for event TAB A 0 upgrade until the arrival of the TSC E-Plan Communicator.

Obtain information on the nature and status of TAB B 0 the event and provide detailed information to the NRC on a continuing basis.

Make sure functions that are in progress during TAB C 0 shift relief are turned over smoothly.

EP-PS-1 37 Revision 0 Page 3 of 3 SUPPORTING INFORMATION: TAB:

Emergency Telephone Instructions TAB 1 Emergency Organization TAB 2 Logkeeping TAB 3 Emergency Classifications TAB 4 Brief Non-Technical Description of EAL TAB 5 NRC/TSC Communicator Phone Information TAB 6 Emergency Forms TAB 7 o Protective Action Recommendation Form o Emergency Notification Report Notification Matrix - TSC Communicator TAB 8 VHF Radio Instructions for Backup Communications TAB 9 NRC Required Information TAB 10

REFERENCES:

SSES Emergency Plan NUREG-0654, Planning Standards and Evaluation Criteria NUREG-0731, Guidelines for Utility Management Structure and Technical Resources, September 1980 NUREG-0696, Functional Criteria for Emergency Response Facilities Distribution Department Instruction 1-505, SSES Sirens: Tests, Maintenance and Repairs IE Notice 82-15 IE Notice 86-28 IE Notice 85-62 IE Notice 86-97 IE Notice 85-80 IE Notice 87-58

TAB A EP-PS-1 37-A Revision 0 Page 1 of 1

-MAJOR TASK:

Perform required offsite notifications for event upgrade until the arrival of the TSC E-Plan Communicator.

SPECIFIC TASKS: HOW:

NOTE:

Only the TSC NRC Communicator Is required for TSC activation. The TSC E-Pian Communicator is required within 60 minutes.

1. If the TSC is activated and an event 1a. Refer to EP-PS-1 27 to perform the upgrade is made, perform ENR offsite agency notifications.

notifications to Offsite Agencies until the arrival of the TSC E-Plan Communicator.

TAB B EP-PS-1 37-B Revision 0 Page 1 of 2 MAJOR TASK:

Obtain information on the nature and status of the event and provide detailed information to the NRC on a continuing basis.

SPECIFIC TASKS: HOW:

1. Obtain information required for NRC 1a. Obtain a copy of the NRC requested notification. information form from the Control Room NRC Communicator.

lb. Update the form from the Control Room NRC Communicator as necessary.

-HELP NRC REQUESTED INFORMATION See TAB 10

2. Initiate communication with the NRC NOTE:

via ENS phone line. Once this communication is Initiated expect to remain on the line until relieved by another TSC NRC Communicator.

NOTE:

The NRC communications function is not turned over to the EOF. It remains with the TSC.

2a. Communicate information obtained from Tab 10 to the NRC.

2b. Remain on the line with the NRC and respond to any questions or requests for additional information.

NOTE:

It is permissible to leave the phone for short periods but the line should remain open.

TAB B EP-PS-1 37-B Revision 0 Page 2 of 2 SPECIFIC TASKS: HOW:

3. Provide continuous updates to NRC 3a. Provide updated information on the via ENS phone line. following:

(1) Classification Upgrades (2) Protective Action Recommendations (3) Status of Release in Progress (4) Updated Information from "NRC Requested Information' Tab 10

TAB C EP-PS-1 37-C Revision 0 Page 1 of 1 MAJOR TASK:

Make sure functions that are in progress during shift relief are turned over smoothly.

SPECIFIC TASKS: HOW:

1. Remain at your duty station with full responsibility until properly relieved.

2. Brief the relieving Communicator on 2a. Make sure the relieving Communicator is the status of both the emergency and fully briefed on all pertinent emergency shift turnover. information and data.

(1) Current status of plant (2) Emergency classification (3) Big Picture (4) Status of notifications

3. Leave a contact telephone number with the TSC Administrative Coordinator.

Tab 1 EP-PS-137-1 EMERGENCY TELEPHONE INSTRUCTIONS DEFINITIONS:

1. Electric Tandem Network (ETN): The telephone system installed in all PPL Incorporated facilities, utilizing local network access codes, location numbers and attendant numbers. (Reference Electronic Tandem Network Telephone Directory).

Example: 8-321-6202 8 (represents the Network Access Code) 321 (represents the Location Number for Wilkes-Barre) 6202 (represents the Attendant Number)_

2. Centrex Telephone Network (CTN): The telephone system installed in all Nuclear Emergency Response Facilities to provide an alternate communications system with additional capabilities, (e.g. three digit conference calling, four digit calling to other Emergency Response Facilities without using a Network Access Code or three digit Location Code).

INSTRUCTIONS:

1. The location codes for calling within the PPL system to Emergency Response Facilities are:

254 - Control Room, Operations Support Center, Technical Support Center, and SSES Security.

321 - Emergency Operations Facility and Media Operations Center.

220 - General Office Support Personnel.

353 - To access Centrex Telephone Network extensions from the Electronic Tandem Network system.

Note: When calling one CTN telephone to another CTN telephone anywhere in the system, no location code is required. Just dial the four-digit CTN extension number. (Reference the Emergency Telephone Directory located in all the Emergency Response Facilities.)

EP-AD-000-320, Revision 3, Page 1of 2

Tab 1 EP-PS-1 37-1

2. The Location Codes when calling from outside telephone lines into the system are:

542 - Control Room, Operations Support Center, Technical Support Center and SSES Security.

831 - Emergency Operations Facility and Media Operations Center.

774 - General Office Support Personnel.

759 - To access the CTN System from an outside telephone line.

EP-AD-000-320, Revision 3, Page 2 of 2

(/ ~~~~~~~~~~~(

Tab 2 EP-PS-137-2 EMERGENCY ORGANIZATION CONTROL ROOM EMERGENCY DIRECTOR (SHIFT MANAGER)

I I I , , I EMERGENCY PLAN SHIFT TECHNICAL NRC OPERATORS ADVISOR (STA) COMMUNICATOR(S)

COMMUNICATOR EP-AD-000-406, Revision 16, Page 1 of 3

(

Tab 2 EP-PS-137-2 TSC ORGANIZATION EMERGENCY DIRECTOR*

TSC Communicators 1 Communicator*

Proposed NRC Rev. 5-02 Non-Operations Susquehanna Steam Electric Station Units I and 2 Support Personnel (9) .

Emergency Plan Ref. Sec. 6.2.12 TSC ORGANIZATION 9 report 0 6b minutes FIGURE 6.2 Support Personnel Ref. Sec. 6.2.12 reDort 0 90 minutes Designates minimum requirements in accordance with Table 6.1 for 60-minute response.

Individuals may be located In the OSC, TSC, or Field.

Designates positions required for TSC activation.

EP-AD-000-406, Revision 16, Page 2 of 3

( Tab 2 EP-PS-1 37-2 EOF ORGANIZATION EOF SUPPORT SUPERVISOR*

Proosed NRC Rev.

5-02 ._

Susquehanna Steam Electric Station Units 1 and 2 Emergency Plan EOF ORGANIZATION Designates minimum requirements in accordance with Table 6.1 for 90 minute response.

FIGURE 6.3

Designates positions required for EOF activation.

EP-AD-000-406, Revision 16, Page 3 of 3

Tab 3 EP-PS-1 37-3 LOGKEEPING Logs are chronological records of events and decisions used to reconstruct an event. To create a log that is useful, accurate, and legal, follow these instructions:

1. Make entries in black ink.

2. Correct mistakes by crossing them out with a single line, followed by your initials and the date you made the correction.

3. Begin each entry with the military time (Example: 0600 for 6:00 a.m., 1800 for 6:00 p.m.).

4. Ust changes, events, decisions, and/or conditions chronologically.

5. Explain any action that results from a decision-making process, when appropriate. If possible, answer these questions:

a. Who acted or made the decision?

b. What did they do or decide?

c. Why did they do or decide what they did?

Example: John Jones, Recovery Manager, recommends evacuation to Mr. Smith of PA DEP/BRP because Iodine concentrations rose above EP-AD-000-400, Revision 2, Page 1 of 1

Tab 4 EP-PS-1 37-4 EMERGENCY CLASSIFICATION CHECK 21 1.0 TIMING OF CLASSIFICATION 0 1.1 UNUSUAL EVENT An UNUSUAL EVENT shall be declared within 15 minutes of having information necessary to make a declaration.

01 1.2 ALERT An ALERT shall be declared within 15 minutes of havinginformation necessary to make a declaration.

01 1.3 SITE AREA EMERGENCY A SITE AREA EMERGENCY shall be declared within 15 minutes of having information necessary to make a declaration.

0o 1.4 GENERAL EMERGENCY A GENERAL EMERGENCY shall be declared within 15 minutes of having information necessary to make a declaration.

EP-AD-000-200, Revision 19, Page 1 of 38

Tab4 EP-PS-1 37-4 CLASSIFICATION OF EMERGENCY CONDITIONS USE OF EMERGENCY CLASSIFICATION MATRIX NOTE: CONFIRM THAT INDICATORS ANDIOR ALARMS REFLECT ACTUAL CONDITIONS PRIOR TO TAKING ACTION BASED ON THE INDICATOR OR ALARM.

The matrix is worded in a manner that assumes parameter values indicated are the actual conditions present in the plant.

The matrix is designed to make it possible to precisely classify an abrIbrmal occurrence into the proper emergency classification based on detailed Emergency Action Level (EAL) descriptions.

It is impossible to anticipate every abnormal occurrence. Therefore, before classifying any abnormal occurrence based on the EALs in the matrix, one should verify that the general conditions prevalent in-plant and offsite meet the general class description of the emergency classification. In addition, prior to classification, one should be aware of the ramifications in-plant 'and particularly offsite of that classification. Special consideration of offsite consequences should be made prior to declaring a GENERAL EMERGENCY.

EP-AD-000-200, Revision 19, Page 2 of 38

Tab 4 EP-PS-1 37-4 CLASS DESCRIPTIONS UNUSUAL EVENT - Events that are occurring or have occurred which indicate a potential degradation of the level of safety of the plant.

No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs.

ALERT - Events that are occurring or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant. Any releases are expected to be limited to small fractions of th- EPA Protective Action Guideline exposure levels.

SITE AREA EMERGENCY - Events that are occurring or have occurred which involve actual or imminent major failures of plant functions needed for protection of the public. Any releases are not.expected to exceed EPA Protective Action.Guideline exposure levels except inside the emergency planning boundary.

GENERAL EMERGENCY - Events that are occurring or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity. Expectation is that releases will exceed EPA Protective Action Guideline exposure levels beyond the emergency planning boundary.

EP-AD-000-200, Revision 19, Page 3 of 38

Tab 4 EP-PS-137-4 CATEGORY INDEX TO THE MATRIX FOR THE CLASSIFICATION OF EMERGENCY CONDITIONS TABLE OF CONTENTS CATEGORY EVENT PAGE 1 AIRCRAFT/TRAIN ACTIVITY ............................... 5 2 CONTROL ROOM EVACUATION ............................... 6 3 FUEL CLADDING DEGRADATION ............................... 7 4 GENERAL .............................. 10 5 INJURED/CONTAMINATED PERSONNEL .............................. 11 6 IN-PLANT HIGH RADIATION ................... - 12 7 LOSS OF AC POWER ................... 13 8 LOSS OF CONTROL ROOM ALARMS AND ANNUNCIATORS ................... 14 9 LOSS OF DC POWER ............................................. 15 10 LOSS OF DECAY HEAT REMOVAL CAPABILITY ........................................ 16 11 LOSS OF REACTIVITY CONTROL ................................ 17 12 LOSS OF REACTOR VESSEL INVENTORY .................................. ;.; 19 13 NATURAL PHENOMENA ................................. 21 14 ONSITE FIRE/EXPLOSION...........................................2..............................23 15 RADIOLOGICAL EFFLUENT ................................. 25 16 SECURITY EVENT ................................. 29 17 SPENT FUEL RELATED INCIDENT ................................. 31 18 STEAM LINE BREAK ................................. 33 19 TOXIC/FLAMMABLE GASES ................................. 36 20 TECHNICAL SPECIFICATION SAFETY LIMIT ................................. 37 21 DRY FUEL STORAGE ................................. 38 EP-AD-000-200, Revision 19, Page 4 of 38

Tab 4 EP-PS-137-4 1 - AIRCRAFT/TRAIN ACTIVITY UNUSUAL EVENT EAL# 1.1 Aircraft crash or train derailment onsite as indicated by:

Visual observation or notification received by control room operator.

ALERT EAL# 1.2 Aircraft or missile strikes a station structure as indicated by:

Direct observation or notification received by control room operator.

SITE AREA EMERGENCY EAL# 1.3 Severe damage to safe shutdown equipment from aircraft crash or missile impact when not in cold shutdown, determined by:

(A and B and C)

A. Direct observation or notification received by control room operator.

and B.: Shift Supervisor evaluation.

and C. Reactor Coolant temperature greater than 2000 F as indicated on Panel 1C651 (2C651).

GENERAL EMERGENCY EAL# 1.4 None.

EP-AD-000-200, Revision 19, Page 5 of 38

Tab 4 EP-PS-1 37-4 2 - CONTROL ROOM EVACUATION UNUSUAL EVENT EAL# 2.1 None.

ALERT EAL# 2.2 Control Room evacuation as indicated by:

(A and B)

A. Initiation of control room evacuation procedures.

and B. Establishment of control of shutdown systems from local stations.

SITE AREA EMERGENCY EAL# 2.3 Delayed Control Room Evacuation as indicated by:

(A and B)

A. Initiation of control room evacuation procedures.

and B.. Shutdown systems control at local stations not established within 15 minutes.

GENERAL EMERGENCY EAL# 2.4 None.

EP-AD-000-200, Revision 19, Page 6 of 38

Tab 4 EP-PS-137-4 3 - FUEL CLADDING DEGRADATION UNUSUAL EVENT EAL# 3.1 Core degradation as indicated by:

(A or B)

A. Valid Off-gas Pre-treatment Monitor high radiation alarm annunciation on Panel 1C651 (2C651) or indication on Panel 1C600 (2C600).

or B. Reactor coolant activity, determined by sample analysis greater than or equal to 2 gCVcc of 1-131 equivalent.

ALERT EAL# 3.2 Severe fuel cladding degradation as indicated by:

(A orB orC orlD)

A. Valid Off-gas Pre-treatment monitor High-High radiation alarm annunciation on Panel 1C651 (2C651) or indication on Panel 1C600 (2C600).

or B. Valid Reactor coolant activity greater than 300 iCVcc of equivalent 131, as determined by sample analysis.

or C. Valid Main Steam Une High radiation trip annunciation or indication on Panel 1C651 (2C651).

or D. Valid containment post accident monitor indication on Panel 1C601 (2C601) greater than 200 R/hr. (An 8R/hr correction factor must be added manually to the indication to offset a downscale error if primary containment temperature exceeds 225 degrees Fahrenheit. Reference EC-079-0521.)

(CONTINUED ON NEXT PAGE)

EP-AD-000-200, Revision 19, Page 7 of 38

Tab 4 EP-PS-1 37-4 3 - FUEL CLADDING DEGRADATION (continued)

SITE AREA EMERGENCY EAL# 3.3 Severely degraded core as indicated by:

(A or B)

A. Reactor coolant activity greater than 1,000 j+/-CVcc of equivalent 1-131 as determined by sample analysis.

or B. Valid containment post accident monitor indication on Panel 1C601 (2C601) greater than 400 R/hr. (An 8 R/hr correction factor must be added manually to the indication to offset a downscale error if primary containment temperature exceeds 225 degrees Fahrenheit. Reference EC-079-0521.)

(CONTINUED ON NEXT PAGE)

EP-AD-O00-200, Revision 19, Page 8 of 38

Tab 4 EP-PS-1 37-4 3 - FUEL CLADDING DEGRADATION (continued)

GENERAL EMERGENCY EAL# 3.4.a Fuel cladding degradation. Loss of 2 out of 3 fission product barriers (fuel cladding and reactor coolant pressure boundary) with potential loss of the third barrier (primary containment) as indicated by:

(A orB)

A. (1 and2)

1. Valid containment post accident monitor indication on Panel 1C601 (2C601) greater than 400 R/hr. (An 8 R/hr correction factor must be added manually to the indication to offset a downscale error if primary containment temperature exceeds 225 degrees Fahrenheit. Reference EC-079-0521.)

and

2. (a orb orc)

a. Containment pressure greater than 40.4 PSIG, indicated on Panel 1C601 (2C601).

or

b. A visual inspection of the containment indicates a potential for loss of containment (e.g. anchorage or penetration failure, a crack in containment concrete at tendon).

or

c. Other indications of potential or actual loss of primary containment.

or B. (1 and 2)

1. Reactor coolant activity greater than 1,000 giCVcc of equivalent 1-131 as determined by sample analysis.

and

2. Actual or potential failure of reactor coolant isolation valves to isolate a coolant leak outside containment as determined by valve position indication on Panel 1C601 (2C601) or visual inspection.

OR EAL# 3.4.b Core melt as indicated by:

(A and B)

A. Valid containment post accident monitor indication on Panel 1C601 (2C601) greater than 2000 R/hr. (An 8 R/hr correction factor must be added manually to the indication to offset a downscale error If primary containment temperature exceeds 225 degrees Fahrenheit. Reference EC-079-0521.)

and B. Containment high pressure indication or annunciation on Panel 1C601 (2C601).

EP-AD-000-200, Revision 19, Page 9 of 38

Tab 4 EP-PS-1 37-4 4- GENERAL UNUSUAL EVENT EAL# 4.1 Plant conditions exist that warrant increased awareness on the part of plant operating staff or state and/or local offsite authorities as indicated by:

Events that are occurring or have occurred which indicate a potential degradation of the level of safety of the plant. No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs.

ALERT EAL# 4.2 Other plant conditions exist that warrant precautionary activation of PPL, State, County, and local emergency centers as indicated by:

Events that are occurring or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant. Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels.

SITE AREA EMERGENCY EAL# 4.3 Other plant conditions exist that warrant activation of emergency centers and monitoring teams or a precautionary notification to the public near the site as indicated by:

Events that are occurring or have occurred which involve actual or imminent major failures of plant functions needed for protection of the public. Any releases are not expected to exceed EPA Protective Action Guideline exposure levels except inside the emergency planning boundary.

GENERAL EMERGENCY EAL# 4.4 Other plant conditions exist, from whatever, source, that make release of large amounts of radioactivity in a short time period available as indicated by:

Events that are occurring or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity. Expectation is that releases will exceed EPA Protective Action Guideline exposure levels beyond the emergency planning boundary.

EP-AD-000-200, Revision 19, Page 10 of 38

Tab 4 EP-PS-1 37-4 5.- INJURED/CONTAMINATED PERSONNEL UNUSUAL EVENT EAL# 5.1 Transportation of externally contaminated injured individual from site to offsite medical facility as deemed appropriate by Shift Supervisor.

ALERT EAL# 5.2 None.

SITE AREA EMERGENCY EAL# 5.3 None.

GENERAL EMERGENCY EAL# 5.4 None.

EP-AD-00O-200, Revision 19, Page 11 of 38

Tab4 EP-PS-1 37-4 6 - IN-PLANT HIGH RADIATION UNUSUAL EVENT EAL# 6.1 Unanticipated or unplanned concentrations of airborne activity exist in normally accessible areas, which are not due to planned maintenance activities, as indicated by:

Concentrations exceed 500 times the DAC values of 10CFR20 Appendix B, Table I values for a single isotope, or for multiple isotopes where CA + CB +.. CC CN 2 500 DACA DACB DACC DACN ALERT EAL# 6.2 Unexpected in-plant high radiation levels or airborne contamination which indicates a severe degradation in the control of radioactive material as indicated by:

Area Radiation Monitor reading 1000 times normal annunciation on Panel 1C601 (2C601) or indication on Panel 1C600 (2C600).

SITE AREA EMERGENCY EAL# 6.3 None.

GENERAL EMERGENCY EAL# 6.4 None.

EP-AD-000-200, Revision 19, Page 12 of 38

Tab 4 EP-PS-1 37-4 7 - LOSS OF AC POWER UNUSUAL EVENT EAL# 7.1 Loss of offsite power or loss of all onsite AC power supplies as indicated by:

(A or B)

A. Loss of power to Startup Transformer 10 and 20 annunciation or indication on Panel OC653.

or B. Failure of all diesel generators to start or synchronize to the emergency buses by indication or annunciation on Panel OC653.

ALERT EAL# 7.2 Loss of all offsite power and all onsite AC power supplies as indicated by:

(A and B)

A. Loss of power to Startup Transformer 10 and 20 annunciation or indication on Panel OC653.

and B. Failure of all diesel generators to start or synchronize to the emergency .buses by annunciation or indication on Panel OC653.

SITE AREA EMERGENCY EAL# 7.3 Loss of all offsite power and loss of all onsite AC power supplies for greater than 15 minutes as indicated by:

(A and B and C)

A. Loss of offsite power.

and B. Failure of all diesel generators to startup or synchronize to the emergency buses by indication or annunciation on OC653.

and C. The above conditions exist for greater than 15 minutes.

GENERAL EMERGENCY EAL# 7.4 None.

EP-AD-000-200, Revision 19, Page 13 of 38

Tab 4 EP-PS-1 37-4 8 - LOSS OF CONTROL ROOM ALARMS AND ANNUNCIATORS UNUSUAL EVENT EAL# 8.1 None.

ALERT EAL# 8.2 Loss of all control room annunciators as indicated by:

In the opinion of the Shift Supervisor, all Control Room annunciators and the Plant Process Computer are lost, or insufficient annunciators are available to safely operate the unit(s) without supplemental observation of plant systems.

SITE AREA EMERGENCY EAL# 8.3 All annunciators lost and plant transient initiated while annunciators are lost as indicated by:

(A and B)

A. In the opinion of the Shift Supervisor, all Control Room annunciators and the Plant Process Computer are lost, or insufficient annunciators are available -to safely operate the unit(s) without supplemental observation of plant systems.

and B. (1 or2 or3 or4)

1. Low-Low reactor water level indication on Panel 1C65.1 (2C651) followed by ECCS initiation on Panel 1C601 (2C601).

or

2. Reactor coolant temperature change greater than 1000 F per hour indication on recorder TR-1 R006 on Panel 1C007 (2C007) (Reactor Building elevation 683').

or

3. High reactor pressure indication on Panel 1C651 (2C651) and followed by scram indication on Panel 1C651 (2C651).

or

4. Any indication that transient has occurred or is in progress.

GENERAL EMERGENCY EAL# 8.4 None.

EP-AD-000-200, Revision 19, Page 14 of 38

Tab 4 EP-PS-1 37-4 9 - LOSS OF DC POWER UNUSUAL EVENT EAL# 9.1 None.

ALERT EAL# 9.2 Loss of onsite vital DC power as indicated by:

(A andB)

A. Less than 210 volts on the 250 VDC main distribution Panel buses, 1D652 (2D652) and 1D662 (2D662) as indicated by trouble alarms on Panel 1C651 (20651).

and B. Less than 105 volts on the 125 VDC main distribution busd& 1D612 (2D612), 1D622 (2D622), 1D632. (2D632), and 1D642 (2D642) as indicated by trouble alarms on Panel 1C651 (2C651).

NOTE: Buses are not tripped on undervoltage condition.

SITE AREA EMERGENCY EAL# 9.3 Loss of all vital onsite DC power sustained for greater than 15 minutes as indicated by:

(A and B and C)

A. Less than 210 volts on the 250 VDC main distribution Panel buses, 1D652 (2D652) and 1D662 (20662) as indicated by trouble alarms on Panel 1C651 (2C651).

and B. Less than 105 volts on the 125 VDC main distribution buses 1D612 (2D612), 1D622 (2D622), 1D632 (2D632), and 1D642 (2D642) as indicated by trouble alarms on Panel 1C651 (2C651).

and C. The above condition exists for greater than 15 minutes.

NOTE: Buses are not tripped on undervoltage condition.

GENERAL EMERGENCY EAL# 9.4 None.

EP-AD-000-200, Revision 19, Page 15 of 38

Tab 4 EP-PS-1 37-4 10 - LOSS OF DECAY HEAT REMOVAL CAPABILITY UNUSUAL EVENT EAL# 10.1 None.

ALERT EAL# 10.2 Inability to remove decay heat while in plant condition 4, inability to maintain the plant in cold shutdown as indicated by:

Inability to maintain reactor coolant temperature less than 2001F with the reactor mode switch in shutdown; exception is when testing per Special Test Exception TS 3.10.1 which allows maximum temperature of 2120 F.

SITE AREA EMERGENCY EAL# 10.3 Inability to remove decay heat while the plant is shutdown as indicated by:

(A and B and C)

A. Reactor Mode switch in shutdown.

and B. Reactor Coolant System temperature greater than 200OF and rising.

and C. Suppression Pool temperature greater than 120OF and rising.

GENERAL EMERGENCY EAL# 10.4 Inability to remove decay heat while the plant is shutdown with possible release of large amounts of radioactivity as indicated by:

(A and B and C)

A. Reactor mode switch in shutdown.

and B. Reactor coolant system temperature greater than 2000 F and rising.

and C. Suppression pool temperature greater than 2900 F indicated on the computer output (MAT 12,13,14,15 or 16).

EP-AD-000-200, Revision 19, Page 16 of 38

Tab 4 EP-PS-137-4 11 - LOSS OF REACTIVITY CONTROL UNUSUAL EVENT EAL# 11.1 Inadvertent Criticality as indicated by:

- Unexpected increasing neutron flux indication on Panel 1C651 (2C651).

ALERT EAL# 11.2 Failure of the Reactor Protection System or the Alternate Rod Insertion System to initiate and complete a scram that brings the reactor subcritical as indicated by:

(A or B) and (C and D and E)

A. Trip of at least one sub-channel in each trip system (RPS A and RPS B) as indicated by annunciators and trip status lights on Panel 1C651 (2C651).

or B. Trip of both trip systems (ARI A and ARI B) as indicated by annunciators on Panel 1C601 (2C601).

and C. Failure of control rods to insert, confirmed by the full core display indication on Panel 1C651 (2C651) or process computer indications.

and D. Failure to bring the reactor subcritical confirmed by neutron count rate on the neutron monitoring indication on Panel 1C651 (2C651).

and E. Reactor power >5% as indicated on Panel 1C651 (2C651).

(CONTINUED ON NEXT PAGE)

EP-AD-000-200, Revision 19, Page 17 of 38

Tab 4 EP-PS-1 37-4 11 - LOSS OF REACTIVITY CONTROL (continued)

SITE AREA EMERGENCY EAL# 11.3 Loss of functions needed to bring the reactor subcritical and loss of ability to bring the reactor to cold shutdown as indicated by:

(A and B and C and D)

A. Inability to insert sufficient control rods to bring the reactor subcritical as indicated by count rate on the neutron monitoring instrumentation on Panel 1C651 (2C651).

and B. (1 or2)

Failure of both loops of standby liquid control to inject into the vessel indicated by:

1. Low pump discharge pressure indication on Panel 1C601 (2C601).

or

2. Low flow indication on Panel 1C601 (2C601).

and C. Reactor coolant temperature greater than 2000F, indicated on Panel 1C651 (2C651).

and D. Reactor power >5% indicated on Panel 1C651 (2C651).

GENERAL EMERGENCY EALU 11.4 Loss of functions needed to bring the reactor subcritical and transient in progress that makes release of large amounts of radioactivity in a short period possible as indicated by:

(A or B) and (C and D)

A. Trip of at least one sub-channel in each trip system (RPS A and RPS B), indicated by annunciation or trip status lights on Panel 1C651 (2C651).

or B. Trip of both systems (ARI A and ARI B) as indicated by annunciators on Panel 1C601 (2C601).

and C. Loss of SLC system capability to inject, indicated by instrumentation on Panel 1C601 (2C601).

and D. Reactor power greater than 25% of rated, indicated on Panel 1C651 (2C651).

EP-AD-000-200, Revision 19, Page 18 of 38

Tab 4 EP-PS-1 37-4 12 - LOSS OF REACTOR VESSEL INVENTORY UNUSUAL EVENT EAL# 12.1 Valid initiation of an Emergency Core Cooling System (ECCS) System as indicated by:

(A or B)

A. Initiation of an ECCS System and low, low, low reactor water level (-129) annunciation or indication on Panel 1C651 (2C651).

or B. Initiation of an ECCS System and High Drywell Pressure annunciation or indication on Panel 1C601 (2C601).

ALERT EAL# 12.2 Reactor coolant system leak rate greater than 50 gpm as indicated by:

(A or B)

A. Drywell floor drain sump A or B Hi-Hi alarm on Panel 1C601 (2C601) and 2 or more drywell floor drain pumps continuously running as indicated on Panel 1C601 (2C601).

or B. Other estimates of Reactor coolant system leakage indicating greater than 50 gpm.

SITE AREA EMERGENCY EAL# 12.3 Known loss of coolant accident greater than make-up capacity as indicated by:

Water level below (and failure to return to) top of active fuel for greater than three minutes as indicated on fuel zone level indicator on Panel 1C601 (2C601).

(CONTINUED ON NEXT PAGE)

. EP-AD-000-200, Revision 19, Page 19 of 38

Tab 4 EP-PS-1 37-4 12 - LOSS OF REACTOR VESSEL INVENTORY (continued)

GENERAL EMERGENCY EALU 12.4.a Loss of coolant accident with possibility of imminent release of large amounts of radioactivity as indicated by:

Water level below (and failure to return to) top of active fuel for greater than 20 minutes as indicated on fuel zone level indicator on Panel 1C601 (2C601).

OR EAL# 12.4.b Loss of Reactor Vessel inventory. Loss of 2 out of 3 fission product barriers (fuel cladding & reactor coolant pressure boundary) with potential loss of the third barrier (primary containment), as indicated by:

(A or B)

A. (1 and2 and 3)

1. High drywell pressure annunciation or indication on Panel 1C601 (2C601).

and

2. (a orb or c)

a. Containment pressure exceeds 40.4 PSIG as indicated on Panel 1C601 (2C601).

or

b. A visual inspection of the containment indicates a potential or actual loss of containment (e.g. anchorage or penetration failure).

or

c. Containment isolation valve(s) fail to close as indicated by valve position indication on Panel 1C601 (2C601).

and

3. Reactor Vessel level drops below (and fails to return to) top of active fuel for greater than three minutes as indicated on fuel zone level indicator on Panel 1C601 (2C601).

or B. (1 and 2)

1. Failure of reactor pressure vessel isolation valves to isolate coolant break outside containment as indicated by valve position indication on Panel 1C601 (2C601) or visual inspection.

and

2. Reactor vessel level drops below (and fails to return to) top of active fuel for greater than three minutes as indicated on fuel zone level indicator on Panel 1C601 (2C601).

EP-AD-000-200, Revision 19, Page 20 of 38

Tab 4 EP-PS-1 37-4 13 - NATURAL PHENOMENA UNUSUAL EVENT EAL# 13.1 Natural phenomenon occurrence as indicated by:

(A orB orC)

A. Tornado impact on site.

or B. Hurricane impact on site.

or C. Earthquake detected by seismic instrumentation systems on Panel 0C696.

ALERT EAL# 13.2 Natural Phenomenon Occurrence as indicated by:

(A or B or C)

A. Tornado with reported wind velocities greater than 200 mph impacting on site.*

or B. Reported hurricane or sustained winds greater than 70 rmph.*

or C. Earthquake at greater than operating basis earthquake (OBE) levels as indicated on Panel 0C696.

Telephone numbers for the National Weather Bureau are located In the Emergency Telephone Directory.

(CONTINUED ON NEXT PAGE)

EP-AD-000-200, Revision 19, Page 21 of 38

Tab 4 EP-PS-1 37-4 13 - NATURAL PHENOMENA (continued)

SITE AREA EMERGENCY EAL# 13.3 Severe natural phenomenon occurrence, with plant not in cold shutdown, as indicated by.

(A and B)

A. Reactor Coolant Temperature greater than 2000 F as indicated on Panel 1C651 (2C651).

and B. (1 or2 or3)

1. Reported hurricane or sustained winds greater than 80 mph.*

or

2. Earthquake with greater than Safe Shutdown Earthquake (SSE) levels as indicated on Panel OC696.

or

3. Tornado with reported wind velocities greater than 220 mph impacting on site.*

GENERAL EMERGENCY EAL# 13.4 None.

Telephone numbers for the National Weather Bureau are located In the Emergency Telephone Directory.

EP-AD-000-200, Revision 19, Page 22 of 38

Tab 4 EP-PS-1 37-4 14 - ONSITE FIRE/EXPLOSION UNUSUAL EVENT EAL# 14.1 Significant fire within the plant as indicated by:

(A and B)

A. Activation of fire brigade by Shift Supervisor.

and B. Duration of fire longer than 15 minutes after time of notification.

OR Explosion inside security protected area, with no significant damage to station facilities, as indicated by:

Visual observation or notification received by control room operator and Shift Supervisor evaluation.

ALERT EAL# 14.2 On-site Fire/Explosion as indicated by:

(A or B)

A. Fire lasting more than 15 minutes and fire is in the vicinity of equipment required for safe shutdown of the plant and the fire is damaging or is threatening to damage the equipment due to heat, smoke, flame, or other hazard.

or B. (1 and2)

Explosion damage to facility affecting plant operation as determined by:

1. Direct observation or notification received by control room operator.

and

2. Shift Supervisor observation.

(CONTINUED ON NEXT PAGE)

EP-AD-000-200, Revision 19, Page 23 of 38

Tab 4 EP-PS-1 37-4 14 - ONSITE FIRE/EXPLOSION (continued)

SITE AREA EMERGENCY EAL# 14.3 Damage to safe shutdown equipment due to fire or explosion has occurred when plant is not in cold shutdown, and damage is causing or threatens malfunction of equipment required for safe shutdown of the plant as determined by:

(A and B and C)

A. Direct observation or notification received by control room operator.

and B. Shift Supervisor evaluation.

and C. Reactor Coolant Temperature greater than 2000 F as indicated on Panel 1C651 (2C651).

GENERAL EMERGENCY EAL 14.4 None.

EP-AD-OOO-200, Revision 19, Page 24 of 38

Tab 4 EP-PS-1 37-4 15 - RADIOLOGICAL EFFLUENT UNUSUAL EVENT EAL# 15.1 Any unplanned release of gaseous or liquid radioactivity to the environment that exceeds 2 times the Technical Requirements Manual limits for 60 minutes or longer.

EAL# 15.1 (1 or 2 or 3)

1. Valid Noble Gas vent stack monitor reading(s) that exceeds a total site release rate of 2.OE+6 gCimin and that is sustained for 60 minutes or longer.

OR

2. Confirmed sample analyses for airborne releases indicates total site release rates at the site boundary with a release duration of 60 minutes or longer resulting in dose rates of:

a) Noble gases >1000 mrem/year whole body, or b) Noble gases >6000 mrem/year skin, or c) 1-131, 1-133, H-3, and particulates with haf lives >8 days >3000 mrem/year to any organ (inhalation pathways only).

OR

3. Confirmed sample analyses for liquid releases indicates concentrations with a release duration of 60 minutes or longer in excess of two time the Technical Requirements Manual liquid effluent limits.

(CONTINUED ON NEXT PAGE)

EP-AD-000-200, Revision 19, Page 25 of 38

Tab 4 EP-PS-1 37-4 15 - RADIOLOGICAL EFFLUENT (continued)

ALERT EAL# 15.2 Any unplanned release of gaseous or liquid radioactivity to the environment that exceeds 200 times Technical Requirement Manual limits for 15 minutes or longer.

EAL# 15.2 (1 or 2 or 3)

1. Valid Noble Gas vent stack monitor reading(s) that exceeds a total site release rate of 2E+8 Ci/min and that is sustained for 15 minutes or longer.

OR 2 Confirmed sample analyses for airborne releases indicates total site release rates at the site boundary for 15 minutes or longer resulting in dose rates of:

a) Noble gases >1.OE+5 mrem/year whole body, or b) Noble gases >6.OE+5 mrem/year skin, or c) 1-131, 1-133, H-3, and particulates with half-lives >8 days >3.OE+5 mrem/year to any organ (inhalation pathways only).

OR

3. Confirmed sample analyses for liquid releases indicates concentrations in excess of 200 times the Technical Requirements Manual liquid effluent limits for 15 minutes or longer.

(CONTINUED ON NEXT PAGE)

EP-AD-000-200, Revision 19, Page 26 of 38

Tab 4 EP-PS-1 37-4 15'- RADIOLOGICAL EFFLUENT (continued)

SITE AREA EMERGENCY EAL# 15.3 Dose at the Emergency Plan boundary resulting from an actual or imminent release of gaseous radioactivity exceeds 100 mrem whole body TEDE or 500 mrem child thyroid CDE for the actual or projected duration of release.

EAL# 15.3 (I or 2 or 3 or 4 or 5)

1. Valid Noble Gas vent stack monitor readings(s) that exceeds a total release rate 6.2E8 ILCimin for greater than 15 minutes and Dose Projections are not available.

Note: If the required dose projection cannot be completed within the 15 minute period, then the declaration must be made based on a valid sustained monitor reading(s).

OR

2. Valid dose assessment using actual meteorology indicates projected doses greater than 100 mrem whole body TEDE or 500 mrem child thyroid CDE at or beyond the EPB.

OR

3. A valid reading sustained for 15 minutes or longer on the RMS perimeter radiation monitoring system greater than 100 mR/hr.

OR

4. Field survey results indicate Emergency Planning boundary dose rates exceeding 100 mR/hr expected to continue for more than one hour.

OR

5. Analyses of field survey samples indicate child thyroid dose commitment at the Emergency Planning Boundary of 500 mrem for one hour of inhalation.

(CONTINUED ON NEXT PAGE)

EP-AD-000-200, Revision 19, Page 27 of 38

Tab 4 EP-PS-1 37-4 15 - RADIOLOGICAL EFFLUENT (continued)

GENERAL EMERGENCY EAL# 15.4 Dose at the Emergency Planning Boundary resulting from an actual or imminent release of gaseous radioactivity exceeds 1000 mrem whole body TEDE or 5000 mrem child thyroid CDE for the actual or projected duration of the release using actual meteorology.

EAL# 15.4 (1 or 2 or 3 or 4 or 5)

1. Valid Noble Gas vent stack monitor readings(s) that exceed a total release rate of 6.2E9 jiCimin for greater that 15 minutes and Dose Projections are not available.

Note: If the required dose projection cannot be completed within the 15 minute period, then the declaration must be made based on a valid sustained monitor reading(s).

OR

2. Valid dose assessment using actual meteorology indicates projected doses greater than 1000 mrem whole body TEDE or 5000 mrem child thyroid CDE at or beyond the EPB.

OR

3. A valid reading sustained for 15 minutes or longer on the RMS perimeter radiation monitoring system greater than 1000 mR/hr.

OR

4. Field survey results indicate Emergency Planning Boundary dose rates exceeding 1000 mR/hr expected to continue for more than one hour.

OR

5. Analyses of field survey samples indicate child thyroid dose commitment at the Emergency Planning Boundary of 5000 mrem for one hour of inhalation.

EP-AD-000-200, Revision 19, Page 28 of 38

Tab 4 EP-PS-137-4 16 - SECURITY EVENT UNUSUAL EVENT EAL# 16.1 Security threat or attempted entry or attempted sabotage as indicated by:

(A or B or C)

A. A report from Security of a security threat, attempted entry, or attempted sabotage of the owner controlled area adjacent to the site.

or B. Any attempted act of sabotage which is deemed legitimate in the judgment of the SHIFT SUPERVISOR/EMERGENCY DIRECTOR, and affects plant operation.

or C. A site specific credible security threat notification.

ALERT EAL# 16.2 Ongoing Security Compromise as indicated by:

(A or B)

A. A report from Security that a security compromise is at the site but no penetration of protected areas has occurred.

or B. Any act of sabotage which results in an actual or potential substantial degradation of the level of safety of the plant as judged by the SHIFT SUPERVISOR/EMERGENCY DIRECTOR.

SITE AREA EMERGENCY EAL# 16.3 An ongoing adversary event threatens imminent loss of physical control of plant as indicated by:

(A or B)

A. Report from Security that the security of the plant vital area is threatened by unauthorized (forcible) entry into the protected area.

or B. Any act of sabotage which results in actual or likely major failures of plant functions needed for protection of the public as judged by the SHIFT SUPERVISOR/EMERGENCY DIRECTOR.

(CONTINUED ON NEXT PAGE)

EP-AD-000-200, Revision 19, Page 29 of 38

Tab 4 EP-PS-1 37-4 16 - SECURITY EVENT (continued)

GENERAL EMERGENCY EAL# 16.4 Loss of physical control of facilities as indicated by:

(A or B)

A. Report from Security that a loss of physical control of plant vital areas has occurred.

or B. Any act of sabotage which results in imminent significant cladding failure or fuel melting with a potential for loss of containment integrity or the potential for release of significant amounts of radioactivity in a short time as judged by the SHIFT SUPERVISOR/EMERGENCY DIRECTOR.

EP-AD-000-200, Revision 19, Page 30 of 38

Tab 4 EP-PS-137-4 17 - SPENT FUEL RELATED INCIDENT UNUSUAL EVENT EAL# 17.1 Unanticipated or unplanned concentrations of airborne activity exist in normally accessible areas, which is not due to planned maintenance activities, as indicated by:

Concentrations exceed 500 times the DAC values of 10CFR20 Appendix B, Table I values for a single isotope, or full multiple isotopes where CA + CB + CC .C 2 500 DACA DACB DACC DACN ALERT EAL# 17.2 Unexpected in-plant high radiation levels or airborne contamination which indicates a severe fuel handling accident as indicated by:

Refuel floor area radiation monitor reading 1000 times normal annunciation on Panel 1C601 (2C601) or indication on Panel 1C600 (2C600).

(CONTINUED ON NEXT PAGE)

. EP-AD-000-200, Revision 19, Page 31 of 38

Tab 4 EP-PS-1 37-4 17 - SPENT FUEL RELATED INCIDENT (continued)

SITE AREA EMERGENCY EAL# 17.3.a Major- damage to irradiated fuel with actual or clear potential for significant release of radioactive material to the environment as indicated by:

(A and B)

A. Dropping, bumping, or otherwise rough handling of a new OR irradiated fuel bundle with irradiated fuel in the pool.

and B. (1 or2)

1. Refueling floor area radiation monitor reading 1000 times normal annunciation on Panel 1C601 (2C601) or indication on Panel 1C600 (2C600).

or

2. Reactor Building vent stack monitoring system high radiation annunciation or indication on Panel 0C630 or 0C677.

OR EAL# 17.3.b Damage to irradiated fuel due to uncontrolled decrease in the fuel pool level to below the level of the fuel as indicated by:

(A and B)

A (1 or2)

1. Uncovering of irradiated fuel confirmation by verification of significant leakage from spent fuel pool.

or

2. Visual observation of water level below irradiated fuel in the pool.

and B. (1 or2)

1. Refueling floor area radiation monitor annunciation on Panel 1C651 (2C651) or indication on Panel 1C600 (2C600).

or

2. Reactor Building vent stack monitoring system high radiation annunciation or indication on Panel 0C630 or 0C677.

GENERAL EMERGENCY EAL# 17A None.

EP-AD-000-200, Revision 19, Page 32 of 38

Tab 4 EP-PS-1 37-4 18 - STEAM LINE BREAK UNUSUAL EVENT EAL# 18.1 None.

ALERT EAL# 18.2 MSIV malfunction causing leakage as indicated by:

(A and B)

A. Valid MSIV closure signal or indication on Panel 1C601 (2C601).

and B. (1 or2)

1. Valid Main Steam Line flow indication on Panel 1C652 (2C652).

or

2. Valid Main Steam Line radiation indication on Panel 1C600 (2C600).

(CONTINUED ON NEXT PAGE)

EP-AD-000-200, Revision 19, Page 33 of 38

Tab 4 EP-PS-1 37-4 18 - STEAM LINE BREAK (continued)

SITE AREA EMERGENCY EAL# 18.3 Steam line break occurs outside of containment without isolation as indicated by:

(A orB orC orD)

A. (1 and2)

1. Failure of both MSIVs in the line with the leak to close as indicated by position indication on Panel 1C601 (2C601).

and

2. (a orb)

a. High MSL flow annunciation on Panel 1C601 (2C601) or indication on Panel 1C652 (2C652).

or

b. Other indication of main steam leakage outside containment.

or B. (1 and 2)

1. Failure of RCIC steam isolation valves HV-F008 and HV-F007 to close as indicated on Panel 1C601(2C601).

and

2. (a orb orc ord ore orf)

a. RCIC steamline pipe routing area high temperature annunciation on Panel 1C601 (2C601), or indication on Panel 1C614 (2C614).

or

b. RCIC equipment area high temperature annunciation on Panel 1C601 (2C601) or indication on Panel 1C614 (2C614).

or

c. RCIC steamline high flow annunciation on Panel 1C601 (2C601).

or

d. RCIC steamline tunnel ventilation high delta temperature annunciation on Panel 1C601(2C601).

or

e. RCIC turbine exhaust diaphragm high pressure annunciation on Panel 1C601 (2C601).

or

f. Other indication of steam leakage from the RCIC system.

(CONTINUED ON NEXT PAGE)

EP-AD-000-200, Revision 19, Page 34 of 38

Tab 4 EP-PS-1 37-4 18 - STEAM LINE BREAK (continued)

SITE AREA EMERGENCY (continued) or

0. (1 and2)

1. Failure of HPCI steam isolation valves HV-F002 and HV-F003 to close as indicated by position indicator on Panel 1C601 (2C601).

and

2. (a orb orc ord ore orf)

a. HPCI steamline pipe routing area high temperature annunciation on Panel 1C601 (2C601), or indication on Panel 1C614 (2C614).

or

b. HPCI equipment area high temperature annunciation on Panel 1C601 (2C601) or indication on Panel 10614 (2C614). -

or

c. HPCI steamline high flow annunciation on Panel 1C601(2C601).

or

d. HPCI steamline tunnel ventilation high delta temperature annunciation on Panel 1C601(2C601).

or

e. HPCI turbine exhaust diaphragm high pressure annunciation on Panel 1C601 (2C601).

or

f. Other indication of steam leakage from the HPCI system.

or D. Any other un-isolatable steam line breaks.

GENERAL EMERGENCY EAL# 18.4 None.

EP-AD-000-200, Revision 19, Page 35 of 38

Tab 4 EP-PS-1 37-4 19 - TOXICIFLAMMABLE GASES UNUSUAL EVENT EAU# 19.1 Nearby or onsite release of potentially harmful quantifies of toxic or flammable material as indicated by:

Visual observation or notification received by the control room operator.

ALERT EAL# 19.2 Entry of toxic or flammable gases into the facility, with subsequent habitability problem as indicated by:

Visual observation, direct measurement, or notification received by the control room operator.

SITE AREA EMERGENCY EAL# 19.3 Toxic or flammable gases enter vital areas, restricting access and restricted access constitutes a safety problem, as determined by:

(A and B)

A. Shift Supervisor's evaluation.

and B. Visual observation, direct measurement, or notification received by control room operator.

GENERAL EMERGENCY EAL# 19.4 None.

EP-AD-000-200, Revision 19, Page 36 of 38

Tab 4 EP-PS-1 37-4 20 - TECHNICAL SPECIFICATION SAFETY LIMIT UNUSUAL EVENT EAL#: 2O.1 Abnormal occurrences which result in operator complying with any of the Technical Specification SAFETY LIMIT ACTION statements indicated by:

(A orB orC orD)

A. Exceeding THERMAL POWER, low pressure or low flow safety limit 2.1.1.1.

or B. Exceeding THERMAL POWER, high pressure and high flow safety limit 2.1.1.2.

or C. Exceeding REACTOR VESSEL WATER LEVEL safety limit 2.1.1.3.

or D. Exceeding REACTOR COOLANT SYSTEM PRESSURE safety limit 2.1.2.

ALERT EAL# 20.2 None.

SITE AREA EMERGENCY EAL# 20.3 None.

GENERAL EMERGENCY EAL# 20.4 None.

EP-AD-000-200, Revision 19, Page 37 of 38

Tab 4 EP-PS-1 37-4 21 - DRY FUEL STORAGE UNUSUAL EVENT EAL# 21.1.a. Situations are occurring or have occurred during the transport of the irradiated spent fuel to the onsite storage facility, which jeopardize the integrity of the spent fuel or its container as indicated by:

(A or B)

A. Radiological readings exceed 2 Rl/hour at the external surface of any transfer cask or horizontal storage module.

or B. Radiological readings exceed 1 R/hour one foot away from the external surface of any transfer cask-or horizontal storage module.

OR -

EAL# 21.11.b. Situations are occurring or have occurred at the irradiated spent fuel storage facility, which jeopardize the integrity of the dry cask storage system as indicated by:

(A or B)

A. Radiological readings exceed 2 R/hour at the external surface of any transfer cask or horizontal storage module.

or B. Radiological readings exceed 1 R/hour one foot away from the external surface of any transfer cask or horizontal storage module.

ALERT EAL# 21.2 None.

SITE AREA EMERGENCY EAL# 21.3 None.

GENERAL EMERGENCY EAL# 21.4 None EP-AD-000-200, Revision 19, Page 38 of 38

Tab 5 EP-PS-1 37-5 BRIEF NON-TECHNICAL DESCRIPTIONS OF EAL EAL# 1.1: Aircraft/Train Activity Unusual Event I Brief Non-Technical

Description:

(Aircraft crash/Train derailment) within the plant security fence (protected area). Based on current plant conditions, the safety of the general public is not threatened.

EAL# 1.2: AircraftiTrain Activity Alert Brief Non-Technical

Description:

(Aircraft crash/Projectile strike) onto a permanent plant structure. Based on current plant conditions, the safety of the general public is not threatened.

EAL# 1.3: Aircraft/Train Activity Site Emergency Brief Non-Technical

Description:

(Aircraft crash/Projectile strike) which caused damage to some equipment used to safely shut down the reactor.

EP-AD-000-201, Revision 4, Page 1 of 23

Tab 5 EP-PS-137-5 EAL# 2.2: Control Room Evacuation Alert Brief Non-Technical

Description:

The Control Room was evacuated, then control of plant systems was established from another location within the plant Based on current plant conditions, the safety of the general public is not threatened.

EAL# 2.3: Control Room Evacuation Site Emergency Brief Non-Technical

Description:

Within 15 minutes of evacuating the Control Room, operators have been unable to establish remote stations for controlling plant systems.

EP-AD-000-201, Revision 4, Page 2 of 23

Tab 5 EP-PS-1 37-5 EAL# 3.1: Fuel Cladding Degradation Unusual Event Brief Non-Technical

Description:

Minor damage has occurred to the metal tubes that hold uranium fuel pellets. Based on current plant conditions, the safety of the general public is not threatened.

lEAL# 3.2: Fuel Cladding Degradationl Alert Brief Non-Technical

Description:

There has been significant damage to metal tubes that hold uranium fuel pellets. Based on current plant conditions, the safety of the general public is not threatened.

lEAL# 3.3: Fuel Cladding Degradationl Sfte Emergency Brief Non-Technical

Description:

Severe damage has taken place to the metal tubes that hold uranium fuel pellets. Abnormally high radiation levels are present in the water which acts as a reactor coolant or in the containment structure surrounding the reactor.

EAL# 3.4.a: Fuel Cladding Degradation

--- GeneralEmergency Brief Non-Technical

Description:

Severe damage to metal tubes that hold uranium fuel pellets. Higher than normal radiation levels in reactor coolant or containment structure surrounding reactor, with a potential for off-site radioactivity release.

EP-AD-000-201, Revision 4, Page 3 of 23

Tab 5 EP-PS-1 37-5 EAL# 3.4.b: Fuel Cladding Degradation GeneralEmergency I Brief Non-Technical

Description:

Indication of uranium fuel melting. Potential for off-site radioactivity release.

EP-AD-000-201, Revision 4, Page 4 of 23

Tab 5 EP-PS-1 37-5 EAL# 4.1: General E

!- ~~~~~UnusualEvent Brief Non-Technical

Description:

I Specific Event ) which potentially threatens the safety of the plant. Based on current plant conditions, the safety of the general public is not threatened.

lEAL# 4.2: Generall Alert Brief Non-Technical

Description:

( Snecific Event ) which actually threatens the safety of the plant. Based on current plant conditions, the safety of the general public is not threatened.

lEAL# 4.3: Generall Site Emergency Brief Non-Technical

Description:

( Specific Event ) has occurred which indicates an (actualimminent) loss of important plant safety systems.

EAL# 4.4: General General Emergency I Brief Non-Technical

Description:

Snecific Event ) has occurred which indicates an (actual/imminent) major release of radioact~ity.

EP-AD-00O-201, Revision 4, Page 5 of 23

Tab 5 EP-PS-1 37-5 EAL# 5.1: Injured/Contaminated Personnel Unusual Event Brief Non-Technical

Description:

An injured person(s), contaminated with radioactive material, is or has been moved outside the immediate area of the plant. Based on current plant conditions, the safety of the general public is not threatened.

EP-AD-00O-201, Revision 4, Page 6 of 23

Tab 5 EP-PS-1 37-5 EAL# 6.1: In-plant High Radiation Unusual Event Brief Non-Technical

Description:

High levels of airborne radioactivity have been detected inside the plant. Based on current plant conditions, the safety of the general public is not threatened.

EAL# 6.2: In-plant High Radiation Alert Brief Non-Technical

Description:

Very high levels of radiation have been detected in the plant. Based on current plant conditions, the safety of the general public is not threatened.

EP-AD-000-201, Revision 4, Page 7 of 23

Tab 5 EP-PS-1 37-5 EAL# 7.1: Loss of AC Power Unusual Event Brief Non-Technical

Description:

AC electrical power from either off-site or on-site sources is needed to operate plant safety equipment. Either the off-site or on-site source has been lost; however, power is still available from the other source. Based on current plant conditions, the safety of the general public is not threatened.

EAL# 7.2: Loss of AC Power Alert Brief Non-Technical

Description:

All AC electrical power (from both on-site and off-site) needed to operate plant safety equipment has been temporarily lost. Based on current plant conditions, the safety of the general public is not threatened.

EAL# 7.3: Loss of AC Power :

Site Emergency Brief Non-Technical

Description:

All AC electrical power (from both on-site and off-site) needed to operate plant safety equipment has been lost for a sustained period of time (15 minutes). Based on current plant conditions, the safety of the general public is not threatened.

EP-AD-000-201, Revision 4, Page 8 of 23

Tab 5 EP-PS-1 37-5 EAL# 8.2: Loss of Control Room Alarms and Annunciators Alert Brief Non-Technical

Description:

All control room alarms have been lost. Based on current plant conditions, the safety of the general public is not threatened.

EAL# 8.3: Loss of Control Room Alarms and Annunciators Site Emergency - --

Brief Non-Technical

Description:

All control room alarms have been lost in combination with another plant operating problem (plant transient).

EP-AD-000-201, Revision 4, Page 9 of 23

Tab 5 EP-PS-1 37-5 EAL# 9.2: Loss of DC Power

_-- - - - -- , Alert Brief Non-Technical

Description:

All DC electrical power in the plant has been lost temporarily. Based on current plant conditions, the safety of the general public is not threatened.

EAL# 9.3: Loss of DC Power Site Emergency Brief Non-Technical

Description:

All DC electrical power-needed to operate some plant safety equipment-has been lost for more than 15 minutes.

EP-AD-000-201, Revision 4, Page 10 of 23

Tab 5 EP-PS-1 37-5 EAL# 10.2: Loss of Decay Heat Removal Capability Alert I Brief Non-Technical

Description:

While the reactor is shutdown (cold shutdown), equipment needed to maintain reactor water temperature below 2000 F has been lost. Based on current plant conditions, the safety of the general public is not threatened.

lEAL# 10.3: Loss of Decay Heat Removal Capabilityl

[ 1" 1_ ~~~Site Emnergencyx Brief Non-Technical

Description:

While the unit is shutdown, operators are unable to effectively cool the reactor.

lEALO 10.4 Loss of Decay Heat Removal Capabilityl GeneralEmnergency Brief Non-Technical

Description:

Operators are unable to cool the reactor; a release of radioactivity is possible.

EP-AD-000-201, Revision 4, Page 11 of 23

Tab 5 EP-PS-137-5 EAL# 11.1: Loss of Reactivity Control Unusual Event Brief Non-Technical

Description:

Reactor power has increased in a way that was not anticipated. Based on current plant conditions, the safety of the general public is not threatened.

EAL# 11.2: Loss of Reactivity Control l l -

go l- ~~~AlertI Brief Non-Technical

Description:

During attempted reactor shutdown, the reactor's control rods failed to insert fully (scram). Based on current plant conditions, the safety of the general public is not threatened.

EAL# 11.3: Loss of Reactivity Control Site Emergency Brief Non-Technical

Description:

Operators are unable to shut down and cool the reactor. Reactor control rods failed to fully insert.

A back-up chemical control system also failed.

EAL# 11.4: Loss of Reactivity Control General Emergency Brief Non-Technical

Description:

Operators are unable to shut down and cool down the reactor. Reactor control rods failed to fully insert The back-up chemical control system also failed. The situation could lead to a radioactivity release.

EP-AD-000-201, Revision 4, Page 12 of 23

Tab 5 EP-PS-1 37-5 EAL# 12.1: Loss of ReactorVessel Inventory Unusual Event I Brief Non-Technical

Description:

To maintain reactor water level, an emergency cooling system has been activated. Based on current plant conditions, the safety of the general public is not threatened.

EAL# 12.2: Loss of Reactor Vessel Inventory l N~ell Brief Non-Technical

Description:

Excessive water is leaking from the reactor coolant systems into the containment structure surrounding the reactor vessel. Based on current plant conditions, the safety of the general public is not threatened.

EAL# 12.3: Loss of Reactor Vessel Inventory Site Emergency Brief Non-Technical

Description:

The ability to maintain water level above the fuel has been lost.

EP-AD-000-201, Revision 4, Page 13 of 23

Tab 5 EP-PS-137-5 EAL# 12.4.a: Loss of Reactor Vessel Inventory GeneralEmergency Brief Non-Technical

Description:

The ability to maintain an adequate water level in the reactor vessel has been lost; severe fuel damage and release of radioactivity are possible.

EAL# 12.4.b: Loss of Reactor Vessel Inventory GeneralEmergency Brief Non-Technical

Description:

Fuel damage and a reactor coolant leak have occurred, with a potential loss of the ability to contain radioactive releases.

EP-AD-000-201, Revision 4, Page 14 of 23

Tab 5 EP-PS-1 37-5 EAL# 13.1: Natural Phenomena Unusual Event Brief Non-Technical

Description:

(Tomadot Hurricane/ Earthquake) has struck the plant site. Based on current plant conditions, the safety of the general public is not threatened.

EAL# 13.2: Natural Phenomena Alet Brief Non-Technical

Description:

(Tornado/ Hurricane/ Earthquake) has struck the plant and could affect plant safety. Based on current plant conditions, the safety of the general public is not threatened. The event may be severe enough to impact plant equipment.

BrEAL# 13.3: Natural Phenomenan:

Site Emergency Brief Non-Technical

Description:

Severe (Tornado/ Hurricane/ Earthquake) is affecting plant safety while plant is not in cold shutdown.

EP-AD-000-201, Revision 4, Page 15 of 23

Tab 5 EP-PS-1 37-5 lEAL# 14.1: 'On-site Fire/Explosionl UnusualEventI Brief Non-Technical

Description:

A (fire! explosion) has occurred on-site, within the (plant/ security fence). Based on current plant conditions, the safety of the general public is not threatened.

lEAL# 14.2:0n-Sfte Fire/Explosionl Alert Brief Non-Technical

Description:

A (fire/ explosion) has occurred on-site that has affected plant operation. Based on current plant conditions, the safety of the general public is not threatened.

EA14 1.3: On-site Fire/Explosionl Site Emergency Brief Non-Technical

Description:

A (fire! explosion) has damaged equipment needed to safely shut down the reactor.

EP-AD-000-201, Revision 4, Page 16 of 23

Tab 5 EP-PS-137-5 EAL# 15.1: Radiological Effluent Unusual Event Brief Non-Technical

Description:

Radioactivity is being released from the plant that exceeds plant operating license limits (Technical Specifications) for liquid releases or exceeds 2 times plant operating license limits for gaseous releases. Based on current plant conditions, the safety of the general public is not threatened.

EAL# 15.2: Radiological Effluent Alert Brief Non-Technical

Description:

Radioactivity is being released at levels at least ten times higher than those allowed by the plant operating license limits (Technical Specifications) for liquid release or exceeds 200 times plant operating license limits for gaseous limits. Based on current plant conditions, the safety of the general public is not threatened.

EAL# 15.3: Radiological Effluent Site Emergency Brief Non-Technical

Description:

Radioactivity is being or has been released which may result in low levels of exposure to people outside the immediate plant area (emergency planning boundary).

EAL# 15.4 Radiological Effluent General Emergency Brief Non-Technical

Description:

Radioactivity is being released that exceeds federal guidelines which specify actions like sheltering or evacuation to protect the public.

EP-AD-000-201, Revision 4, Page 17 of 23

Tab 5 EP-PS-1 37-5 EAL# 16.1: Security Event Unusual Event Brief Non-Technical

Description:

An attempt has been made to breach station security or a site-specific credible threat has been received. Based on current plant conditions, the safety of the general public is not threatened.

EAL# 16.2: Security Event Alert Brief Non-Technical

Description:

A compromise of Station security has occurred or is imminent. Based on current plant conditions, the safety of the general public is not threatened.

EAL# 16.3: Security Event Site Emergency Brief Non-Technical

Description:

Security has been compromised in a way that threatens plant safety systems.

EAL# 16.4: Security Event General Emergency Brief Non-Technical

Description:

Security has been compromised in a way that has caused loss of control of some or all vital areas of the plant.

EP-AD000-201, Revision 4, Page 18 of 23

Tab 5 EP-PS-1 37-5 EAL# 17.1: Spent Fuel Related Incident UnusualEvent Brief Non-Technical

Description:

Used fuel assemblies (groups of the metal rods containing irradiated uranium fuel pellets), being stored in the units spent fuel pool, are leaking radioactive material. This is causing abnormally high radiation levels in some areas of the plant. Based on current plant conditions,, the safety of the general public is not threatened.

EAL# 17.2: Spent Fuel Related Incident Alert I Brief Non-Technical

Description:

Used fuel assemblies (groups of the metal rods containing irradiated uranium fuel pellets), being stored in the units spent fuel pool are leaking radioactive material. This is causing very high radiation levels in some areas of the plant. Based on current plant conditions, the safety-of the general public is not threatened.

lEAL# 17.3.a: Spent Fuel Related Incidentl Site Emnergency Brief Non-Technical

Description:

Severe damage has occurred to some used fuel assemblies (metal rods containing irradiated uranium fuel pellets) stored in the units spent fuel pool. A radioactivity release is possible.

EAL# 17.3.b: Spent Fuel Related Incident Site Emergency Brief Non-Technical

Description:

Used (irradiated) fuel assemblies in the units spent fuel pool are damaged and no longer covered with cooling water. A radioactive release is possible.

EP-AD-000-201, Revision 4, Page 19 of 23

Tab 5 EP-PS-137-5 EAL# 18.2: Steam Line Break Alert Brief Non-Technical

Description:

Isolation valves have failed to completely shut off the flow of radioactive steam from the reactor to the turbine-generator. Based on current plant conditions, the safety of the general public is not threatened.

EAL# 18.3: Steam Une Break Site Emergency Brief Non-Technical

Description:

Isolation valves have failed to properly shut and there is significant flow of radioactive steam from the reactor to areas outside the primary containment.

EP-AD-000-201, Revision 4, Page 20 of 23

Tab 5 EP-PS-1 37-5 EAL# 19.1: Toxic/Flammable Gases ,

Unusual Event .

Brief Non-Technical

Description:

(Toxic/ flammable) gas has been released (near-site/ on-site). Based on current plant conditions, the safety of the general public is not threatened.

EAL# 19.2: Toxic/Flammable Gases Alert I Brief Non-Technical

Description:

(Toxic/ flammable) gas has entered plant facilities. Based on current plant conditions, the safety of the general public is not threatened.

EAL# 19.3: Toxic/Flammable Gases Site Emergency Brief Non-Technical

Description:

(Toxic! flammable) gas has entered areas within plant buildings which contain vital safety equipment (plant vital areas).

EP-AD-000-201, Revision 4, Page 21 of 23

Tab 5 EP-PS-1 37-5 EAL# 20.1v Technical Specification Safety Limit Unusual Event Brief Non-Technical

Description:

An abnormal plant condition has occurred. Based on current plant conditions, the safety of the general public is not threatened.

EP-AD-000-201, Revision 4, Page 22 of 23

Tab 5 EP-PS-1 37-5 EAL# 21.1.a: Irradiated Spent Fuel in Dry Storage Unusual Event Brief Non-Technical

Description:

While transporting the used (spent) fuel assemblies (groups of rods containing irradiated uranium fuel pellets) from the spent fuel pool to the onsite storage facility, radiological readings indicate that the spent fuel or its container may be damaged.

EAL#21.1.b: Irradiated Spent Fuel in Dry Storagel

. Unusual Event Brief Non-Technical

Description:

After the used (spent) fuel assemblies (groups of rods containing irradiated uranium fuel pellets) have been transported from the spent fuel pool and placed in the horizontal storage module (a concrete structure which will house the steel canister of spent fuel), radiological readings indicate that the fuel storage system may be damaged.

EP-AD-000-201, Revision 4, Page 23 of 23

Tab 6 EP-PS-137-6 NRCITSC COMMUNICATOR PHONE INFORMATION

1. Transmission Control Center Dial 8-1-484-634-4090 Give the classification.

2. Offsite Agency Phone Numbers INPO: 800-321-0614 Pennsylvania Rural Electric Assn:

717-233-5704 American Nuclear Insurers:

860-561-3433 PPL Insurance Group:

o J. Diacogiannis:

220-4961 (W) 610-865-4410 (H) o T. Novatnack:

220-4962 (W) 610-867-7296 (H)

EP-AD-000-509, Revision 0, Page 1 of 1

Tab 7 EP-PS-1 37-7 Control #

I EMERGENCY NOTIFICATION REPORT I Dl THIS IS A DRILL M THIS IS NOT A DRILL

1. This is: at Susquehanna Steam Electric Station.

(Communicator's Name)

My telephone number is: . The time is (Callback telephone number) (Time notification initiated)

2. EMERGENCY CLASSIFICATION:

ED UNUSUAL EVENT El SITE AREA EMERGENCY E] ALERT El GENERAL EMERGENCY El The event has been terminated.

UNIT: El ONE T IME: DATE:

D Two (Time classification/ (Date classification/

El ONE& TWO termination declared) termination declared)

El INmAL DECLARATION THIS REPRESENTS AIAN:

El ESCALATION El No CHANGE S

} IN CLASSIFICATION STATUS For initial declaration, static update, or escalation, provide current EAL number only.

0 For status reports, significant events, or when directed by the

3. BRIEF NON-TECHNICAL ED, RM, or EOFSS, provide a brief description.

DESCRIPTION OF THE EVENT: For termination, write emermencv has been terminated.

4. THERE IS: El No El AN AIRBORNE NON-ROUTINE RADIOLOGICAL RELEASE IN PROGRESS El A LQUID

5. WHEN GENERAL EMERGENCY IS THE INITIAL EVENT, PROVIDE PROTECTIVE ACTION RECOMMENDATIONS BELOW: (Control Room Use only, TSC and EOF mark NA.)

6. WIND DIRECTION IS FROM: _ WIND SPEED IS: mph.

(Data from 10 meter meteorological tower, available on PICSY.)

E THIS IS A DRILL El THIS IS NOT A DRILL APPROVED: Time: Date:

(ED, RM, or EOFSS) (Time form approved) (Date form approved)

EP-AD-000-310, Revision 4, Page 1 of 1

Tab 7 EP-PS-137-7 EMERGENCY NOTIFICATION LOG SHEET EMERGENCY CLASSIFICATION TIME ACCOUNTABILITY INITIATED/COMPLETED /

UNUSUAL EVENT ALERT TIME SITE EVACUATION SITE AREA EMERGENCY INITIATED/COMPLETED _

GENERAL EMERGENCY EMERGENCY NOTIFICATION STATIC UPDATE REPORT (ENR) CONTROL NO.

TIME OF DECLARATION PROTECTIVE ACTION RECOMMENDATION FORM (PAR) CONTROL NO.

TIME OF TERMINATION TIME ENR FORM PAR FORM AGENCY NAME OF CONTACT TRANSMITTED -TRANSMITTED TRANSMITTED PEMA N/A LCEMA NA CODES N/A MOC WA NRC DEP/BRP ADDITIONAL INFORMATION EP-AD-000-308, Revision 2, Page 1 of 1

( ( (

Tab 7 EP-PS-1 37-7 NOTIFICATION MATRIX TECHNICAL SUPPORT CENTER COMMUNICATOR PROTECTIVE ACTION UPGRADE or SIGNIFICANT HAZARDOUS RECOMMENDATION AGENCY/CONTACT PHONE NUMBER DOWNGRADE STATIC UPDATE EVENT MATERIAL FORM TERMINATION PEMA (4960/4961) 191 x x x X NA X CCDPS (4955/4956) Within Every hour MOC (4903/4902) 15minutes Nuclear Regulatory ENSor X X X X X X Commission 1-301-816-5100 Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Transmission Control 8-1484-6344090 X X Center After NRC notification Institute of Nuclear 8-1-800-321-0614 X X Power (INPO) Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months NA American Nuclear 8-1-860-561-3433 X X Insurers Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

PA Rural Electric 8-1-717-233-5704 X X Assn. Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Note: Additional telephone numbers are located In the Emergency Telephone Directory available at each workstation.

EP-AD-000-350, Revision 14, Page 1 of 1

Tab 8 EP-PS-1 37-8 VHF RADIO INSTRUCTIONS

1. Inform HP Radioman you need to use the VHF radio base unit to make notifications to LCEMA and CCDPS.

2. Turn the VHF base unit to Channel 1.

3. Contact LCEMA and CCDPS, then inform them you are using this method for Emergency Notification Report notifications.

4. Transmit Emergency Notification Report information.

5. Turn VHF base station back to HP Radioman.

EP-AD-000-351, Revision 2, Page 1 of 1

Tab 10 EP-PS-137-10 NRC REQUIRED INFORMATION Time: - Date: Plant: Susquehanna SES NOTE (1): This is not a form to be read to the NRC but the information is the type of information that the NRC will request.

NOTE (2): Items in Bold

should be obtained from/discussed with Shift Manager/ED or TSC ED.

Initials indicate information concurred with by SM/ED or TSC ED.

1. Your Name/phone number/and position in the Control Room, i.e. PCO, SRO, STA

2. Affected Unit 3*. Current EAL Classification and Declaration time 4*. Basis for declaration - This information should explain in general terms the basis for the declaration 5*. Is there a Release in Progress Yes _ _ No 6*. Protective Action Recommendations made to the State_

7*. Any local area/RCANSite evacuations ordered Yes No (Specify) 8*. Mitigating actions in progress:

To Restore critical safety functions

To bring plant to cold shutdown

Restore vital equipment

9. Has NERO been activated Yes No

10. Has accountability been initiated Yes No 11*. Prognosis for escalation or termination (from Shift Manager)

12. Have off-site notifications been initiated Yes No

13. Provide a reference for RPV level, i.e. TAF is-161" 14*. EOP's in use to mitigate the event O RPV Control El Rad Release a RPV Flooding Dl PC Control El Emerg. Depressurization Dl SC Control El ATWS EP-AD-000-512, Revision 0, Page 1 of 3

Tab 10 EP-PS-1 37-1 0 PARAMETER DATA FORM TIME>>>>>> UNIT l l l_ l REACTOR POWER ' I______

RX VESSEL LEVEL T T__-____

PRIMARY PRESSURE FEEDWATER FLOW GPM .

RCIC FLOW GPM CORE SPRAY FLOW A GPM CORE SPRAY FLOW B GPM -

LPCI/RHR FLOW A GPM LPCI/RHR FLOW B GPM .

SRV STATUS O/C DRYWELL SUMP LEVEL =

DRYWELL PRESSURE DRYWELL TEMP OF SUPPRESS POOL LEVEL =

SUPPRESS POOL TEMP OF.

HYDROGEN CONCEN. %

OXYGEN CONCEN. %

DRYWELL RADIATION =

WETWELL RADIATION =

EP-AD-000-512, Revision 0, Page 2 of 3

Tab 10 EP-PS-1 37-10 PLANT CONTROL STATUS FORM (BOILING WR)

Reactivity Control All Control Rods Inserted? El Yes El No: Number rods Reactor Subcritical? El Yes El No Standby Uquid Control Initiated? El Yes 0 No Shutdown Margin within Tech Specs? E Yes El No Reactor Vessel Level Control Level controlled by one or more of the following:

o Condensate/Feedwater al RHR Service Water a RCIC rl Fire Water El HPCI/HPCS rl Control Rod Drive El Core Spray E Other:

0 LPCI Reactor Vessel Pressure Control Main Steam Isolation Valves: E All Open E] All Closed E] Other.

Reactor Vessel Pressure Control by:

El Turbine Bypass or Turbine Control O Safety Relief Valves (SRV)/ Automatic Depressurization System (ADS)

O Other:

Stuck Open Safety Relief Valve El No El Yes: Number Heat Sink Control E Condenser E Suppression Pool E Residual Heat RemovaVShutdown Cooling

Isolation Condenser, where applicable (N/A for Susquehanna) a Other Containment Control Containment Spray E On ElO ff Suppression Pool Cooling E On oOff Standby Gas Treatment E On D off Hydrogen Control: El Recombiner

Igniter (N/A for Susquehanna)

El Containment Atmosphere Dilution EP-AD-000-512, Revision 0, Page 3 of 3

ML031960420

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