ML031960417
| ML031960417 | |
| 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-135, Rev 0 | |
| Download: ML031960417 (86) | |
Text
Jun. 27, 2003 Page 1 of 1 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2003-30967 USER/FORMATION Namn:GE ACH* SE M EN[PL#:28401 CA#:0363 Ad ress:
P o 254-31 TRANSMITTAL INFORMATION:
TO: 7 -. - luo'
.s! 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:
135 - 135 NRC COMMUNICATOR REMOVE MANUAL TABLE OF CONTENTS DATE:
ADD MANUAL TABLE OF CONTENTS DATE: 06/26/2003 CATEGORY: PROCEDURES TYPE: EP ID: EP-PS-135 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.
PROCEDURE COVER SHEET PPL SUSQUEHANNA, LLC I NUCLEAR DEPARTMENT PROCEDURE NRC COMMUNICATOR EP-PS-135 Emergency Plan Position Specific Instruction Revision 0 Page 1 of 3 QUALITY CLASSIFICATION: APPROVAL CLASSIFIC TION:
( ) QA Program (X) Non-QA Program ( ) Plant,"dl .( Non-Plant
( X) Insrtin EFFECTIVE DATE: _________, _____
PERIODIC REVIEW FREJtfENkY: Two Years PERIODIC REVIEW I) DA1E: ___________ z RECOMMENDED REVIEWS: '
All i 4df:
Prfocedure Owner: Nuclear Emergency Planning Responsible Supervisor: Primary Operations Coordinator Responsible FUM: Supv.-Nuclear Emergency Planning Responsible Approver Primary TSC Emergency Director FORM NDAP-QA-0002-1, Rev. 3, Page 1 of 1
EP-PS-1 35 Revision 0 Page 2 of 3 NRC COMMUNICATOR Emergency Plan-Position Specific Procedure WHEN: Emergency Plan is activated HOW NOTIFIED: Assigned while on duty REPORT TO: Shift Manager/ED WHERE TO REPORT: Control Room OVERALL DUTY:
Communicate information on emergency to the Nuclear Regulatory Commission, implement activation of NERO, activate the ERDS System and-perform other Emergency Plan actions as directed by the Shift Manager/ED.
MAJOR TASKS: TAB: REVISION:
As directed by the Shift Manager/ED initiate TAB A 0 activation of the NERO or notification of Key Managers and perform other communications.
Activate the ERDS system and obtain TAB B .0 information of the nature and status of the event, perform notifications to the NRC resident inspector (s) and provide detailed information to the NRC on a continuing basis.
EP-PS-135 Revision 0 Page 3 of 3 SUPPORTING INFORMATION: TAB:
Emergency Telephone Instructions TAB 1 Emergency Organization TAB 2 Logkeeping TAB 3 NRCITSC Communicator Phone Information TAB 4 Emergency Forms TAB 5
- Emergency Notification Report
- Emergency Notification Logsheet Brief Non-Technical Descriptions of EALs TAB 6 Emergency Classification TAB 7 ERDS System Operating Instructions TAB 8 NRC Requested Information TAB 9
REFERENCES:
NUREG-0654, Planning Standards and Evaluation Criteria NUREG-0696, Functional Criteria for Emergency Response Facilities NUREG-0731, Guidelines for Utility Management Structure and Technical Resources, September 1980 SSES Emergency Plan NDAP-00-0316, Station Communications NDAP-QA-0300, Conduct of Operations OP-AD-003, Shift Routine - Log taking Letter dated February 25, 2002, from Samuel J. Collins, Director, Office of Nuclear Reactor Regulations, to Robert G. Byram, Senior Vice President and Chief Nuclear Officer.
TAB A EP-PS-135-A Revision 0 Page I of 3 MAJOR TASK:
As directed by the Shift Manager initiate activation of the NERO or notification of Key Managers.
SPECIFIC TASKS: HOW:
Initiate Activation of NERO. la. Ask Shift Manager/ED if NERO is to be activated.
1b. If NERO is to be activated perform step 1c.
If only Key Manager Notification is required proceed to step 2.
NOTE: _
NERO activation is required for an Alert and higher classification.
1c. Activation of NERO pagers using the telephone Hot Button-Green Button.
(1) Remove the telephone handset from the twenty button telephone on the center console.
(2) Press the green activation button, (the fifth button in the first row of ten.)
(3) After approximately 30 seconds reset the Green button by pressing any other button and hanging up the telephone handset.
NOTE:
If the green button Is not reset, the pagers will activate again when the handset Is picked up again.
(4) Contact the ASCC at CTN 4918:
(5) Verify pager activation (6) Request TNS activation of NERO
TAB A EP-PS-1 35-A Revision 0 Page 2 of 3 SPECIFIC TASKS: HOW:
- 2. If NERO is not activated at the Unusual Event, contact the ASCC and request notification of Key Managers.
- 3. If the TSC is not activated at the 3a. Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of event declaration Unusual Event Level, perform transmit the emergency classification to additional notifications as directed by other off-site agencies:
the Emergency Director.
(1) Institute of Nuclear Power Operations (INPO)
(2) Pennsylvania Rural Electric Cooperative (3) American Nuclear Insurers (ANI)
(4) PPL Insurance Group HELP NRC Communicator Phone Information Matrix See TAB 4
- 4. If directed by the Shift Manager/ED (1) Obtain password from Shift Manager activate ALTERNATE NERO. key locker.
(2) Dial 1-570-440-1014.
(3) When prompted, enter password xxxx.
(4) When prompted (voice or rapid three tone signal), enter "99999."
(5) Usten for corroboration or depress #
key.
(6) Return password to SM key locker.
(7) Instruct Security to:
o Validate "99999" pager activation.
° Activate the NERO using TNS.
TAB A EP-PS-1 35-A Revision 0 Page 3 of 3 SPECIFIC TASKS: HOW:
- 5. If directed by Shift Manager/ED, 4a. Make the following Page announcement announce Evacuation of non-essential twice "Attention all personnel, a security personnel from site. emergency has been declared. All non-essential personnel evacuate the site."
- 6. When TSC Communicator announces he or she is taking over, report to the Shift Manager/ED to provide help where you're needed.
- 7. If an Unusual Event was declared and the NERO was not activated, then when your job is completed because the emergency has been terminated, give all documentation and records, including your log to the STA.
TAB B EP-PS-1 35-B Revision 0 Page 1 of 2 MAJOR TASK:
Activate the ERDS system and obtain information of the nature and status of the event, perform notifications to the NRC resident inspector (s) and provide detailed information to the NRC on a continuing basis.
SPECIFIC TASKS: HOW:
- 1. Provide assistance to the Control 1a. As directed by the Shift Manager Room Operating Crew in dealing perform actions to stabilize the with the event. affected unit.
OR 1b. As directed by the Shift Manager perform actions to insure the unaffected unit is in stable condition.
- 2. Within one hour of entry into the 2a. Confirm the following information E-Plan, obtain information with the Shift Manager:
concerning the affected Unit and event status.
(1) Affected Unit (2) Current EAL Classification (3) Basis for Classification (4) Release in Progress information (5) Prognosis for escalation/termination
- 3. Within one hour of entry into the 3a. Provide the information obtained E-Plan, notify NRC Resident above in step 2a.
Inspectors of the event.
- 4. Within one hour of entry into the HELP E-Plan, activate the Emergency ERDS Operating Instructions Response Data System. See TAB 8
TAB B EP-PS-135-B Revision 0 Page 2 of 2 SPECIFIC TASKS: HOW:
- 5. Within one hour, obtain HELP information required for NRC NRC Requested Information Telephone Notification. See TAB 9
- 6. Within one hour, initiate 6a. NOTE:
communication with the NRC via Once this communication Is ENS Phone Une. initiated expect to remain on the phone until relieved by a TSC Communicator.
- 1. Communicate information-btained from Tab 9 to the NRC.
- 2. 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 to obtain additional Information but the line should remain open.
- 7. When the TSC Communicator announces that he or she is taking over, report to the Shift Manager to provide help where needed.
- 8. If an Unusual Event was declared and the NERO was not activated, then when your job is completed because the emergency has been terminated, give all documentation and records, including your log to the STA.
Tab 1 EP-PS-1 35-1 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 1 of 2
Tab 1 EP-PS-1 35-1
- 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-1 35-2 EMERGENCY ORGANIZATION CONTROL ROOM EMERGENCY DIRECTOR (SHIFT MANAGER)
. .~~~~~~~~~~~~~~~~~~
IW .- . ..
EMERGENCY PLAN SHIFT TECHNICAL NRC OPERATORS COMMUNICATOR ADVISOR (STA) COMMUNICATOR(S)
EP-AD-000-406, Revision 16, Page 1 of 3
( (
Tab 2 EP-PS-1 35-2 TSC ORGANIZATION EMERGENCY DIRECTOR*
Admin Staff [si7 ['o oordator Coodinat TSC Communicators 1Communicator Proposed NRC Rev. 5-02 Susquehanna Steam Electric Station Non-Operatlons Units 1 and 2 Support Personnel (9)
Emergency Plan Ref. Sec. ,.2.12 TSC ORGANIZATION 9 report 0 60 minutes FIGURE 6.2 Non-Operations Support Personnel Ref. Sec. 6.2.12 5 report 0 90 minutes Designates minimum requirements in accoIrdance 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 35-2 EOF ORGANIZATION LENVIRONMENTAL SAMPLING TEAM Proposed 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 2 EP-PS-135-2 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., 1600 for 6:00 p.m.).
- 4. List 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 DEPIBRP because- Iodine concentrations rose above EP-AD-000-400, Revision 2, Page 1 of 1
Tab 5 EP-PS-1 35-5 Control #
IEMERGENCY NOTIFICATION REPORT THIS IS A DRILL 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:
El UNUSUAL EVENT El SITE AREA EMERGENCY El ALERT rl GENERAL EMERGENCY D3 The event has been terminated.
UNIT: El ONE TIME: DATE:
El Two (lime classification/ (Date classification/
al ONE &TWo termination declared) termination declared)
THIS REPRESENTS AIAN: El E
El INITIAL DECLARATION ESCALATION No CHANGE
} IN CLASSIFICATION STATUS 0 For initial declaration, static update, or escalation, provide current EAL number only.
S For status reports, significant events, or when directed by the
DESCRIPTION OF THE EVENT: . , For termination. write emeraenev has been terminated-
- 4. THERE IS: El No El AN AIRBORNE NON-ROUTINE RADIOLOGICAL RELEASE IN PROGRESS El A LIQUID
- 5. WHEN GENERAL EMERGENCY IS THE INMAL EVENT, PROVIDE PROTECTIVE ACTION RECOMMENDATIONS BELOW: (Control Room Use only, TSC and EOF mark NWA.)
- 6. WIND DIRECTION IS FROM: _ WIND SPEED IS: mph.
(Data from 10 meter meteorological tower, available on PICSY.)
El 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 5 EP-PS-1 35-5.
EMERGENCY NOTIFICATION LOG SHEET EMERGENCY CLASSIFICATION TIME ACCOUNTABILITY INITIATED/COMPLETED I 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 ENRFORM PAR FORM AGENCY NAME OF CONTACT TRANSMUTED -TRANSMITTED TRANSMITTED PEMA N/A LCEMA NA CCDES _ WA MOC WA NRC _ _
DEPIBRP ADDITIONAL INFORMATION EP-AD-000-308, Revision 2, Page 1 of 1
Tab 6 EP-PS-1 35-6 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: Aircraft/Train 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 6 EP-PS-1 35-6 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 6 EP-PS-1 35-6 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.
EAL# 3.2: Fuel Cladding Degradation 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 Site Ernergency 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 General Emergency 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-00O-201, Revision 4, Page 3 of 23
Tab 6 EP-PS-1 35-6 EAL# 3.4.b: Fuel Cladding Degradation GeneralEmergency Brief Non-Technical
Description:
Indication of uranium fuel melting. Potential for off-site radioactivity release.
EP-AD-00O-201, Revision 4, Page 4 of 23
Tab 6 EP-PS-1 35-6 EAL# 4.1: General E Unusual Event Brief Non-Technical
Description:
( Specific Event ) which potentially threatens the safety of the plant Based on current plant conditions, the safety of the general public is not threatened.
EAL# 4.2: General 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.
EAL# 4.3: General Site Emergency Brief Non-Technical
Description:
r Snecific Event ) has occurred which indicates an (actualimminent) loss of important plant safety systems.
EAL# 4.4: General General Emergency Brief Non-Technical
Description:
Specific Event ) has occurred which indicates an (actual/imminent) major release of radioactivity.
EP-AD-000-201, Revision 4, Page 5 of 23
Tab 6 EP-PS-1 35-6 EAL# 5.1: Injured/Contaminated Personnel Unusual Event l 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-000-201, Revision 4, Page 6 of 23
Tab 6 EP-PS-1 35-6 EAL# 6.1: In-plant High Radiation UnusualEvent I 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-00-201, Revision 4, Page 7 of 23
Tab 6 EP-PS-1 35-6 EAL# 7.1:
N Loss of AC Power Unusual Event I 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 EmergencyI 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 6 EP-PS-1 35-6 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 I 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 6 EP-PS-1 35-6 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 6 EP-PS-1 35-6 EAL# 10.2: Loss of Decay Heat Removal Capability l L. , ~~~~Aeft 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.
EAL# 10.3: Loss of Decay Heat Removal Capability Site Emergency Brief Non-Technical
Description:
While the unit is shutdown, operators are unable to effectively cool the reactor.
EAL# 10.4: Loss of Decay Heat Removal Capability General Emergency I 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 6 EP-PS-135-6 EAL# 11.1: Loss of Reactivity Control UnusualEvent 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 Alert 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.
lEAL# 11.3: Loss of Reactivity Controll 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# 1 1A Loss of Reactivity Control GeneralEmergency 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 6 EP-PS-1 35-6 EAL# 12.1: Loss of Reactor Vessel Inventory UnusualEvent 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 Alert 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 Emnergency.
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 6 EP-PS-1 35-6 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 6 EP-PS-1 35-6 EAL# 13.1: Natural Phenomena Unusual Event l Brief Non-Technical
Description:
(Tomado/ 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 Alert 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.
EAL# 13.3: Natural Phenomena Site Emergency Brief Non-Technical
Description:
Severe (Tornado! Hurricane! Earthquake) is affecting plant safety while plant is not in cold shutdown.
EP-AD-00O-201, Revision 4, Page 15 of 23
Tab 6 EP-PS-1 35-6 EAL# 14.1: On-site Fire/Explosion Unusual Event 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.
EAL# 14.2: On-Site Fire/Explosion
_Aert I 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.
EAL# 14.3: On-site Fire/Explosion Site Emergency I Brief Non-Technical
Description:
A (firef explosion) has damaged equipment needed to safely shut down the reactor.
EP-AD-0OO-201, Revision 4, Page 16 of 23
Tab 6 EP-PS-1 35-6 EAL# 15.1: Radiological Effluent Unusual Event l 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 I
Brief Non-Technical
Description:
Radioactity 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:
Radioactvity 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 GeneralEmergency 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 6 EP-PS-1 35-6 l EAL# 16.1:
l Security Event Unusual Event -
I 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 I 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.
lEAL# 16.3: Secunity Eventl Site Emergency 1_1 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-AD-000-201, Revision 4, Page 18 of 23
Tab 6 EP-PS-1 35-6 EAL# 17.1: Spent Fuel Related Incident Unusual Event 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.
lEAL#17.2: Spent Fuel Related Incidentl Alert Brief Non-Technical
Description:
Used fuel assemblies (groups of the metal rods containing irradiated uranium fuel pellets), being stored in the unit's 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.
EAL# 17.3.a: Spent Fuel Related Incident 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.
lEAL# 17.3.b: Spent Fuel Related Incidentl Site Emnergency Brief Non-Technical
Description:
Used (irradiated) fuel assemblies in the unWs 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 6 EP-PS-1 35-6 EAL# 18.2: Steam Line Break Alert I 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 Line 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 6 EP-PS-135-6 EAL# 19.1: Toxic/Flammable Gases Unusual Event I Brief Non-Technical
Description:
(Toxict flammable) gas has been released (near-site/ on-site). Based on current plant conditions, the safety of the general public is not threatened.
lEAL# 19.2: Toxic/Flammable Gasesl
_ ~~~~Alert 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
_ Emergency
~~~~~~Site 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 6 EP-PS-1 35-6 EAL# 20.1: Technical Specification Safety Limit l --- 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 6 EP-PS-135-6 EAL# 21.1.a: Irradiated Spent Fuel in Dry Storage Ilkl__ - 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 Storage UnusualEvent 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 7 EP-PS-1 35-7 EMERGENCY CLASSIFICATION CHECK E 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.
0: 1.2 ALERT An ALERT shall be declared within 15 minutes of having-information necessary to make a declaration.
0: 1.3 SITE AREA EMERGENCY A SITE AREA EMERGENCY shall be declared within 15 minutes of having information necessary to make a declaration.
11 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
Tab 7 EP-PS-135-7 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 abnormal 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-00O-200, Revision 19, Page 2 of 38
Tab 7 EP-PS-1 35-7 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 thd-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 7 EP-PS-1 35-7 CATEGORY INDEX TO THE MATRIX FOR THE CLASSIFICATION OF EMERGENCY CONDITIONS TABLE OF CONTENTS CATEGORY EVENT PAGE 1 AIRCRAFTITRAIN 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 FIREIEXPLOSION ................... : 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 7 EP-PS-1 35-7 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 7 EP-PS-135-7 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 7 EP-PS-135-7 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 gCicc of 1-131 equivalent.
ALERT EAL# 3.2 Severe fuel cladding degradation as indicated by:
(A orB orC orD)
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 gCi/cc of equivalent 1-131, as determined by sample analysis.
or C. Valid Main Steam Line 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 7 EP-PS-1 35-7 3- FUEL CLADDING DEGRADATION (continued)
SITE AREA EMERGENCY EAL# 3.3 Severely degraded core as indicated by:
(A orB)
A. Reactor coolant activity greater than 1,000 ,uCi/cc 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-000-200, Revision 19, Page 8 of 38
Tab 7 EP-PS-135-7 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 or B)
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 gCi/cc 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 Rthr. (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 7 EP-PS-1 35-7 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 EALU 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 7 EP-PS-1 35-7 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-000-200, Revision 19, Page 11 of 38
Tab 7 EP-PS-1 35-7 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 + Cs +.. cc Cm 0 DACA DACB DACc DACN 0 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.
GENERALEMERGENCY EAL# 6.4 None.
EP-AD-000-200, Revision 19, Page 12 of 38
Tab 7 EP-PS-1 35-7 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 orB)
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 7 EP-PS-135-7 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 1C651 (2C651) followed by ECCS initiation on Panel 1C601 (2C601).
or
- 2. Reactor coolant temperature change greater than 100OF 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 7 EP-PS-135-7 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 and B)
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 (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).
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 (20652) and 1D662 (2D662) 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 (20632), 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 7 EP-PS-135-7 10 - LOSS OF DECAY HEAT REMOVAL CAPABILITY UNUSUAL EVENT EAU 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 2000 F with the reactor mode switch in shutdown; exception is when testing per Special Test Exception TS 3.10.1 which allows maximum temperature of 212 0F.
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 2000 F 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 7 EP-PS-135-7 11 - LOSS OF REACTIVITY CONTROL UNUSUAL EVENT EAL# 11.1 Inadvertent Criticality as indicated by:
Unexpected increasing neutron flux indication on Panel lC651 (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 7 EP-PS-1 35-7 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 10651 (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(20651).
and D. Reactor power >5% indicated on Panel 1C651(20651).
GENERAL EMERGENCY EAL# 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 orB) and(C andD)
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(20651).
or B. Trip of both systems (ARI A and ARI B) as indicated by annunciators on Panel 10601 (20601).
and C. Loss of SLC system capability to inject, indicated by instrumentation on Panel 1C601 (20601).
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 7 EP-PS-135-7 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 7 EP-PS-135-7 12 - LOSS OF REACTOR VESSEL INVENTORY (continued)
GENERAL EMERGENCY EAL# 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 and3)
- 1. High drywell pressure annunciation or indication on Panel 1C601 (2C601).
and
- 2. (a orb orc)
- 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 7 EP-PS-1 35-7 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 orB orC)
A. Tornado with reported wind velocities greater than 200 mph impacting on site.*
or B. Reported hurricane or sustained winds greater than 70 mph.*
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 7 EP-PS-1 35-7 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 200OF 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 7 EP-PS-135-7 14 - ONSITE FIREIEXPLOSION 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 and 2)
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 7 EP-PS-1 35-7 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 200OF as indicated on Panel 1C651 (2C651).
GENERAL EMERGENCY EAL# 14A None.
EP-AD-000-200, Revision 19, Page 24 of 38
Tab 7 EP-PS-1 35-7 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.
- 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 half lives >8 days >3000 mrem/year to any organ (inhalation pathways only).
- 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 7 EP-PS-1 35-7 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 or2or3)
- 1. Valid Noble Gas vent stack monitor reading(s) that exceeds a total site release rate of 2E+8 gCimin 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 mremlyear to any organ (inhalation pathways only).
- 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 7 EP-PS-1 35-7 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 (1 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 IiCi/min 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).
- 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.
- 3. A valid reading sustained for 15 minutes or longer on the RMS perimeter radiation monitoring system greater than 100 mR/hr.
- 4. Field survey results indicate Emergency Planning boundary dose rates exceeding 100 mR/hr expected to continue for more than one hour.
- 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 7 EP-PS-1 35-7 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 or2or3or4or5)
- 1. Valid Noble Gas vent stack monitor readings(s) that exceed a total release rate of 6.2E9 j+/-CVmin 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).
- 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.
- 3. A valid reading sustained for 15 minutes or longer on the RMS perimeter radiation monitoring system greater than 1000 mR/hr.
- 4. Field survey results indicate Emergency Planning Boundary dose rates exceeding 1000 mR/hr expected to continue for more than one hour.
- 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 7 EP-PS-1 35-7 16 - SECURITY EVENT UNUSUAL EVENT EAL# 16.1 Security threat or attempted entry or attempted sabotage as indicated by:
(AorBorC)
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 orB)
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 7 EP-PS-1 35-7 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 7 EP-PS-1 35-7 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 DACA CR + .. C CNC 2 500 DACA DACq 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 7 EP-PS-1 35-7 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 OC630 or OC677.
GENERAL EMERGENCY EAL# 17.4 None.
EP-AD-000-200, Revision 19, Page 32 of 38
Tab 7 EP-PS-1 35-7 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 (ZC652).
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 7 EP-PS-1 35-7 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 10652(20652).
or
- b. Other indication of main steam leakage outside containment.
or B. (1 and2)
- 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 (20601), or indication on Panel 1C614(2C614).
Or
- b. RCIC equipment area high temperature annunciation on Panel 110601 (20601) or indication on Panel 1C614(20614).
or
- c. RCIC steamline high flow annunciation on Panel 1C601 (2C601).
or
- d. RCIC steamline tunnel ventilation high delta temperature annunciation on Panel 10601 (20601).
Or
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 7 EP-PS-1 35-7 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 1C614 (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
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 7 EP-PS-135-7 19 - TOXIC/FLAMMABLE GASES UNUSUAL EVENT EAL# 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 andB)
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
- I Tab 7 EP-PS-1 35-7 20 - TECHNICAL SPECIFICATION SAFETY LIMIT UNUSUAL EVENT EAL# 20.1 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 7 EP-PS-1 35-7 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 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.
OR EAL# 21.1.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 Rfhour 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 8 EP-PS-1 35-8 EMERGENCY RESPONSE DATA SYSTEM (ERDS)
OPERATING INSTRUCTIONS 1.0 Initiating the ERDS Unk 1.1 From the PICSY FORMAT SCREEN, type: SEND2NRC <ENTER>.
The EMERGENCY RESPONSE DATA SYSTEM screen will appear (see Attachment A).
1.2 Move cursor to and click on the ACTIVATE box under ACTIONS.
1.2.1 The computer will dial the NRC to establish communications.
1.2.2 When communications are established, the EMERGENCY RESPONSE DATA SYSTEM screen STATUS column will change, showing CONNECT, ACCEPTING, and TRANSMIuTING (see Attachment A).
1.2.3 Data transmission to the NRC is transmitted once every minute. The COMMUNICATION TASK section of the STATUS column will toggle between IDLE and TRANSMIlTING (see Attachment B).
2.0 Reconnecting the ERDS Link NOTE: A noisy telephone circuit may cause the NRC link to disconnect. This is especially true during damp weather. If PICSY is not transmitting data, the EMERGENCY RESPONSE DATA SYSTEM screen STATUS column will display Disconnected, Terminated, Inactive (see Attachment C)..
2.1 Move the cursor to and click on the RECONNECT box under ACTIONS on the EMERGENCY RESPONSE DATA SYSTEM screen.
2.1.1 The computer will then go through the same action steps as described in section 1.0 and reestablish communications with the NRC.
3.0 Terminating the ERDS Link 3.1 Move the cursor to and click on the TERMINATE box under ACTIONS on the EMERGENCY RESPONSE DATA SYSTEM screen (see Attachment C).
The computer will disconnect from the NRC connection.
EP-AD-000-275, Revision 3, Page 1 of 4
Tab 8 EP-PS-1 35-8 ATTACHMENT A ERDS DISPLAY
-CONNECT, ACCEPTED, TRANSMITTING SCREEN" Eel/
Ii i
EP-AD-00-275, Revision 3, Page 2 of 4
Tab 8 EP-PS-1 35-8 ATTACHMENT B ERDS DISPLAY
-CONNECT, ACCEPTED, IDLE SCREENW
- I I
EP-AD-000-275, Revision 3, Page 3 of 4
Tab 8 EP-PS-1 35-8 ATTACHMENT C ERDS DISPLAY SCREEN
-DISCONNECTED, TERMINATED, INACTIVE" i
EP-AD-000-275, Revision 3, Page 4 of 4
Tab 9 EP-PS-1 35-9 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
Initials indicate information concurred with by SM/ED or TSC ED.
- 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 1P. 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 rl RPV Control El Rad Release D RPV Flooding El PC Control El Emerg. Depressurization n SC Control El ATWS EP-AD-000-512, Revision 0, Page 1 of 3
Tab 9 EP-PS-1 35-9 PARAMETER DATA FORM TIME>>>>>> UNIT________
REACTOR POWER_______
RX VESSEL LEVEL 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 0/C DRYWELL SUMP LEVEL =
DRYWELL PRESSURE X DRYWELL TEMP OF SUPPRESS POOL LEVEL _ .
SUPPRESS POOL TEMP 0F.
HYDROGEN CONCEN. %
OXYGEN CONCEN. %
DRYWELL RADIATION _
WETWELL RADIATION I EP-AD-000-512, Revision 0, Page 2 of 3
Tab 9 EP-PS-1 35-9.
PLANT CONTROL STATUS FORM (BOILNG WR)
Reactitv Control All Control Rods Inserted? E Yes M No: Number_ _ rods Reactor Subcritical? E Yes El No Standby Liquid Control Initiated? a Yes El1 No Shutdown Margin within Tech Specs? E Yes 0F No Reactor Vessel Level Control Level controlled by one or more of the following:
El Condensate/Feedwater E RHR Service Water a] RCIC E Fire Water E HPCVHPCS E Control Rod Drive a Core Spray El Other.
E LPCI Reactor Vessel Pressure Control Main Steam Isolation Valves: D All Open n All Closed O Other:
Reactor Vessel Pressure Control by:
El Turbine Bypass or Turbine Control El Safety Relief Valves (SRV)/ Automatic Depressurization System (ADS)
El Other.
Stuck Open Safety Relief Valve E No. E Yes: Number Heat Sink Control E Condenser E Suppression Pool E Residual Heat RemovaVShutdown Cooling
- Isolation Condenser, where applicable (N/A for Susquehanna) 0 Other Containment Control Containment Spray On E Off Suppression Pool Cooling El On D Off Standby Gas Treatment El On D Off M
Hydrogen Control:
nEl Recombiner El Igniter (N/A for Susquehanna)
El Containment Atmosphere Dilution EP-AD-000-512, Revision 0, Page 3 of 3