ML021910567
| ML021910567 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 07/02/2002 |
| From: | Susquehanna |
| To: | Document Control Desk, Office of Nuclear Security and Incident Response |
| References | |
| EP-PS-100 | |
| Download: ML021910567 (84) | |
Text
Jul. 02, 2002 Page 1 of 1
/
MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2002-32.
USER INFORMATION:
FLAI*LAUREL - EMPL#:23244 CA#: 0386 Adalress : N'UCSAz Phone#: 254-3658 TRANSMITTAL INFORMATION:
TO. ELA.
AURth-,. 07/02/2002 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:
100 - 100 - EMERGENCY DIRECTOR/CONTROL ROOM:
EMERGENCY PLAN-POSITION SPECIFIC PROCEDURE REMOVE MANUAL TABLE OF CONTENTS DATE: 05/07/2002 ADD MANUAL TABLE OF CONTENTS DATE: 07/01/2002 CATEGORY: PROCEDURES TYPE: EP ID: EP-PS-100 ADD: PCAF 2002-1436 REV: N/A 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 CHANGE PROCESS FORM
- 1. PCAF NO. 2002-1436 2. PAGE 1 OF 1/3. PROC. NO. EP-PS-100 REV. 15
- 4. FORMS REVISED -4 R , -5L. R , RR, R -R_ R_, - R
- 5. PROCEDURE TITLE EMERGENCY DIRECTOR-CONTROL ROOM: Emergency-Plan-Position-Specific Instruction
- 6. REQUESTED CHANGE PERIODIC REVIEW Z NO '-1 YES INCORPORATE PCAFS Z NO El YES # #_# #
REVISION r- PCAF [ DELETION [] (CHS, ONLY)
- 7.
SUMMARY
OF! REASON FOR CHANGE all,
- 1) Tab A, Task 3 added to reference 'new' Tab for Security EAL's. R'
- 2) TabV new Tab providing guidance on managing site specific security ie Ns2d/or threats.
Continued El
- 8. DETERMINE COMMITTEE REVIEW REQUIRý,MlrNTTS (Refer to Section 6.1.4)
PORC REVIEW REQ'D? .. VES Y'"N', 9. PORC MTG# NA BLOCKS 11 THRU 16 ARE ON PA FORO
- 17. William Tabor -/ 5 / 6/4/02 18. COMMUNICATION OF CHANGE REQUIRED?
PREPARER "ETN DATE E] NO Z YES (TYPE) OPS BULLETIN (Print or Type)
- 19. SIGNATURE ATTESTS THAT RESPONSIBLE SUPERVISOR HAS
- 19. 6* /f . CONDUCTED QADR AND TECHNICAL REVIEW UNLESS OTHERWISE ZDOCUMENTED IN BLOCK 16 OR ATTACHED REVIEW FORMS.
- ONSIBLE--
R1-EO SUP=ERVISOR 7t /A, E.
fr-"= CROSS DISCIPLINE REVIEW (IFREQUIRED) HAS BEEN COMPLETED BY SIGNATURE INBLOCK 16 OR ATTACHED REVIEW FORMS.
- 20. fill_____
I UUJM'APPROVAL DATE
- 21. RSNSIBE APPROVER ENTER N/A IF FUM HAS APPROVAL AUTHORITY ONITIALS "DATEI FORM NDAP-QA-0002-8, Rev. 8, Page 1 of 2 (Electronic Form)
PROCEDURE CHANGE PROCESS FORM
- 1. PCAF NO. 2002-1436 12. PAGE 2 OF r 13. PROC. NO. EP-PS-100 REV. 15
- 11. This question documents the outcome of the 50.59 and 72.48 Review required by NDAP-QA-0726. Either 1 a, b, c or d must be checked "YES" and the appropriate form attached or referenced.
- a. This change is an Administrative Correction for which 50.59 and 72.48 are not r YES Z N/A applicable.
- b. This change is a change to any surveillance, maintenance or administrative Z YES [ N/A procedure for which 50.59 and 72.48 are not applicable.
- c. This change is bounded by a 50.59/72.48 Screen/Evaluation, therefore, no new r YES Z N/A 50.59/72.48 Evaluation is required.
Screen/Evaluation No.
- d. 50.59 and/or 72.48 are applicable to this change and a 50.59/72.48 [ YES Z N/A Screen/Evaluation is attached.
- 13. Should this change be reviewed for potential effects on Training Needs or Material? [ YES [ NO If YES, enter an Action Item @ NIMS/Action/Gen Work Mech/PICN
- 14. Is a Surveillance Procedure Review Checklist required per NDAP-QA-0722? r YES Z NO
- 15. Is a Special, Infrequent or Complex Test/Evolution Analysis Form required per YES Z NO NDAP-QA-0320? (SICT/E form does not need to be attached.)
- 16. Reviews may be documented below or by attaching Document Review Forms NDAP-QA-01 01-1.
REVIEWED BY WITH DATE REVIEW NO COMMENTS QADR TECHNICAL REVIEW REACTOR ENGINEERING/NUCLEAR FUELS IST **
OPERATIONS NUCLEAR SYSTEMS ENGINEERING NUCLEAR MODIFICATIONS MAINTENANCIE HEALTH PHYSICS NUCLEAR TECHNOLOGY CHEMISTRY OTHER 10CFR50.54q (,, -4
&._ 'z-..
"* Required for changes that affect, or have potential for affecting core reactivity, nuclear fuel, core power level indication or impact the thermal power heat balance. (s8)
"Requiredfor changes to Section XI Inservice Test Acceptance Criteria.
FORM NDAP-QA-0002-8, Rev. 8, Page 2 of 2 (Electronic Form)
IIAA 2 FY -E EP-PS-I 00 Revision 15 Page 2 of 4 EMERGENCY DIRECTOR (ED) - CONTROL ROOM: Emergency Plan-Position Specific Procedure WHEN: Anytime an abnormal event is occurring HOW NOTIFIED: On shift REPORT TO: Duty Manager WHERE TO REPORT: Control Room OVERALL DUTY:
Take charge of the plant from the Control Room during an emergency condition, assigning duties and directing operations as necessary to return to a safe plant condition (NDAP-QA-300).
MAJOR TASKS: TAB: REVISION:
AF Classify the emergency as conditions indicate. TAB A 7 PC Manage the UNUSUAL EVENT. TAB B 11 Manage the ALERT EMERGENCY. TAB C 9 Manage the SITE AREA EMERGENCY. TAB D 11 Manage the GENERAL EMERGENCY. TAB E 8 AF Manage.the Security Threat or Event EAL series 16 TAB G 0 Pr.
S--..°-EP-PS-1 00 LL~IjL~ 1 Revision 15 I? pat.. Page 3 of 4 SUPPORTING INFORMATION: TAB:
Emergency Telephone Instructions TAB I Emergency Organization TAB 2 Brief Non-Technical Description of EAL's TAB 3 Emergency Classification TAB 4 Public Protective Action Recommendation Guide TAB 5 PPL Emergency Personnel Dose Assessment and "TAB 6 Protective Action Recommendation (PAR) Guide Personnel AseembIy ei Accountability TAB 7 Restoration Organization Guidelines TAB 8 Emergency Forms TAB 9 o Potassium Iodine (KI) Tracking Form o Emergency Notification Report o Protective Action Recommendation Form
L..1-r *.2 5 *J, Revision 15 etF --2002-1436 Page 4 of 4
REFERENCES:
ICRP Publication 28, The Principles and General Procedures for Handling Emergency and Accidental Exposures of Workers. International Commission on Radiation Protection. (1978)
NCRP Report 39, Basic Radiation Protection Criteria, National Council on Radiation Protection and Measurements. (1971)
NCRP Report 55, Protection of the Thyroid Gland in thO Event of Releases of Radioiodine National Council on Radiation Protection and Measurements. (1977)
SSES Emergency Plan Environmental Protection Agency Manual of Protective Action Guides and Protective Actions for Nuclear Incidents. (1979)
NDAP-QA- 1190, Nuclear Department Radiation Protection Program and Policies NDAP-QA-1 191, ALARA Policy and Program IE Notice, 83-28 NUMARC Graded Response Study NUREG-0654, Planning Standards and Evaluation Criteria NUREG-073 1, Guidelines for Utility Management Structure and Technical Resources, September 1980 SP-00-308, Emergency Medical Response, Search/Rescue FF "Letterdated February 25, 2002 from Samuel J. Collins, Director, Office of Nuclear Reactor Regulations, to Robert G. Byram, Senior Vice President and Chief Nuclear Officer.
TAG'A EP-PS-100-A C_2002-1436 Revision 7 PCAF ;O Page 1 of 1' PAGF OF.
MAJOR TASK:
Classify the emergency as conditions indicate.
SPECIFIC TASKS: HOW:
I a. Obtain updated information from:
- 1. Evaluate information. (1) STA for rad release (2) US for plpait status.
(3);. US/AUS for status of Damage Control Teams and plant rad conditions.
(4) SCC for security events.
HELP
- 2. Choose most appropriate Emergency Classifications Emergency Classifications Classification level from Emergency Emergency See TAB 4 Classification Matrix.
- 3. Manage all Security EAL's 3a. Go to Tab "G" IPcAF 4a. "EMERGENCY CLASSIFICATION
- 4. Immediately go to appropriate TAB LEVELS" for all other emergency level selected. UNUSUAL TAB "B" EVENT ALERT TAB "C" SITE AREA TAB "D" GENERAL TAB "E" 5a. Notify HP at Unit 2 Control
- 5. If a release is in progress, but the Point Request that OSCAR criteria for entry to an emergency and a Dose Calculator report to classification is not exceeded, initiate the Control Room.
off-site Dose Calculations.
- TAB G 00-G EP-PS-1 PCAF #-7-2002,OFd Z436.
--q REVISION 0 PAGE PAGE 1 OF 2 MAJOR TASK:
Manage site Specific Security Threat or Event EAL series 16.
cnPrTU!C' L Li'.RZR.-
TAk
= HOW:
vi-irvird- Ir A QW!
la. Determine classification based on EAL
- 1. Determine, document, lb. Determine appropriate actions based on and communicate guidance in this tob emergency classification 1c. Announce td'Control Roomr personnel:
(1) I am assuming duties of Emergency Director (2) Emergency Classification is (3) Time of classification is _
(4) Initiate Event Notification Report (5) Appoint Control Room Communicator 2a. Have Communicator enter EP-PS-126 Tab F
- 2. If security declares 1 NERO per Task 9 2b. Activate ALTERNATE condition 4 site specific 2c. Evacuate site, initiate accountability per Task CREDIBLE threat 10 2d. Implement Tab B (at Task 4)
FCAF 3a. Have Communicator enter EP-PS-126 Tab F
- 3. If security declares condition 4 site specific 3b. Activate ALTERNATE NEROQ per Task 9 CREDIBLE INSIDER 3c. Evacuate site, initiate accountability per Task 10 threat 3d. Activate two-man rule per Task 11 3f. Implement Tab B (at Task 4) 4a. Have Communicator enter EP-PS-126 Tab F
- 4. If security declares condition 4 site specific 4b. Activate ALTERNATE NER. per Task 9 4c. Evacuate site, initiate accountability per Task CREDIBLE IMMINENT 10 threat 4d. Implement Tab C (at Task 3) 5a. Have Communicator enter EP-PS-126 Tab F
- 5. If security declares 5b. Activate ALTERNATE NERO per Task 9 condition 4 site specific 5c. Evacuate site, initiate accountability per Task CREDIBLE MMINENT 10 INSIDER threat 5d. Activate two-man rule per Task 11 5e. Implement Tab C (at Task 3)
TAB G PCAF # 2002-]g36 EP-PS-1 00-G REVISION 0 PAGE-LOFs PAGE 2 OF 2 SPECIFIC TASK: HOW:
- 6. If security enters code Blue, Red or Black. 6a. Declare appropriate emergency classification.
6b. Enter appropriate Tab C, D or E.
- 7. For any act of sabotage. 7a. Review security EAL series 16.
7b. Declare appropriate emergency Classification.
7c. Enter appropriate Tab B, C, D or E.
- 8. If Security declares other actual security 8a. Review event with security.
condition 214/5.
8b. Declare emergency classification if required.
8c. Enter appropriate Tab B, C, D or E.
- 9. Activate ALTERNATE NERO, (all on-call 9a. Activate 99999 page.
to EOF), when specified by Task 2, 3, 4 or 1) Obtain password from SM key locker.
- 5. 2) Dial 1-570-440-1014
- 3) When prompted, enter password XXXX.
- 4) When prompted, (voice or rapid three tone signal), enter "99999".
- 5) Return password to SM key locker.
9b. Instruct Security to:
- 1) Validate "99999" pager activation.
- 2) Activate the NERO using TNS.
- 10. Evacuate non-essential personnel from 10a. Make page announcement twice: "Attention site and initiate accountability when all personnel, a security emergency has been specified in Task 2, 3, 4 or 5. declared. All non-essential personnel evacuate the site, NERO personnel report to the Emergency Operations Facility."
lOb. Repeat 1Oa in five minutes.
1Oc. Initiate accountability in about fifteen minutes or when evacuation is determined complete.
- 11. Activate two-person rule for vital area 11 a. Call-out complete second shift of personnel:
access when specified by Task 3 or 5 as 1) Operations personnel become available unless doing, 2) Chemistry so will adversely impact personnel or 3) Health Physics plant or security as determined by the 4) Security SSS or SM.
11 b. Establish two person teams, (line of sight)
- 1) Instruct Unit Supervisor and OSC Coordinator to establish two person teams.
- 2) Instruct Security to establish two man teams at gatehouse for facility access.
- 3) Instruct Accountability Area Leaders to establish two-person teams to report to the TSC.
'TAB 3 EP-PS-1 00-3 BRIEF NON-TECHNICAL DESCRIPTIONS OF EAL EAL# 1.1: Aircraft/Train Activity UnusualEvent 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 I 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 I of 23
,TAB 3 EP-PS-1 00-3 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 3 EP-PS-1 00-3 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 I 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.
EAL# 3.3: Fuel Cladding Degradation Site 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 General Emergency I 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 3 EP-PS-1 00-3 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-000-201, Revision 4, Page 4 of 23
'TAB 3 EP-PS-1 00-3 EAL# 4.1: General UnusualEvent 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 I Brief Non-Technical
Description:
( Specific 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:
Specific Event ) has occurred which indicates an (actual/imminent) 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 3 EP-PS-1 00-3 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-000-201, Revision 4, Page 6 of 23
"TAB3 EP-PS-1 00-3 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 3 EP-PS-1 00-3 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 I 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 3 EP-PS-1 00-3 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
"TAB3 EP-PS-100-3 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 I 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 3 EP-PS-1 00-3 EAL# 10.2: Loss of Decay Heat Removal Capability Alert 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 I 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 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 3 EP-PS-1 00-3 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 Alert I 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 GeneralEmergency I 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 3 EP-PS-1 00-3 EAL# 12.1: Loss of Reactor Vessel Inventory UnusualEvent 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 Emergency I 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 3 EP-PS-100-3 EAL# 12.4.a: Loss of Reactor Vessel Inventory General Emergency 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.
Loss of Reactor Vessel Inventory EAL# 12.4.b:
GeneralEmergency I 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
",TAB3 EP-PS-1 00-3 EAL# 13.1: Natural Phenomena Unusual Event Brief Non-Technical
Description:
(Tornado/ 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 I 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 I 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 3 EP-PS-1 00-3 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 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.
EAL# 14.3: On-site Fire/Explosion 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 3 EP-PS-1 00-3 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 I 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 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 3 EP-PS-1 00-3 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.
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 GeneralEmergency 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 3 EP-PS-100-3 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 unit's 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 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 Emergency I Brief Non-Technical
Description:
Severe damage has occurred to some used fuel assemblies (metal rods containing irradiated uranium fuel pellets) stored in the unit's 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 unit's 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 3 EP-PS-1 00-3 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 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 3 EP-PS-1 00-3 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 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 3 EP-PS-1 00-3 EAL# 20.1: 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 3 EP-PS-1 00-3 EAL# 21.1 .a: Irradiated Spent Fuel in Dry Storage Unusual Event I 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 I 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 4 EP-PS-1 00-4 EMERGENCY CLASSIFICATION CHECK 0 1.0 TIMING OF CLASSIFICATION O 1.1 UNUSUAL EVENT An UNUSUAL EVENT shall be declared within 15 minutes of having information necessary to make a declaration.
O 1.2 ALERT An ALERT shall be declared within 15 minutes of having information necessary to make a declaration.
o 1.3 SITE AREA EMERGENCY A SITE AREA EMERGENCY shall be declared within 15 minutes of having information necessary to make a declaration.
O 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 16, Page 1 of 39
TAB 4 EP-PS-100-4 CLASSIFICATION OF EMERGENCY CONDITIONS USE OF EMERGENCY CLASSIFICATION MATRIX NOTE: CONFIRM THAT INDICATORS AND/OR 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-000-200, Revision 16, Page 2 of 39
TAB 4 EP-PS-1 00-4 POLICY STATEMENT ON EMERGENCY DECLARATIONS Policy When an emergency action level (EAL) is exceeded but the plant quickly returns below the EAL, the emergency should be declared. If appropriate, the emergency can also be downgraded or terminated at essentially the same time and the Emergency Notification Form can say the emergency was declared and terminated (or downgraded) minutes later.
Example The main steam lines isolate on high radiation due to a large oil intrusion into the vessel. The isolation on high radiation is a trigger to declare an Alert. If it can quickly be determined that the cause was not damage to the fuel and we should not be in an Alert, then the Alert should be declared and terminated with the same notification report.
Basis Declaring the emergency will notify interested offsite personnel and will demonstrate that we recognize that we exceeded an EAL. Immediately terminating-or downgrading will avoid activation of company and offsite facilities that are not required for this event.
EP-AD-000-200, Revision 16, Page 3 of 39
TAB 4 EP-PS-1 00-4 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 the 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 16, Page 4 of 39
TAB 4 EP-PS-1 00-4 CATEGORY INDEX TO THE MATRIX FOR THE CLASSIFICATION OF EMERGENCY CONDITIONS TABLE OF CONTENTS CATEGORY EVENT PAGE 1 AIRCRAFT/TRAIN ACTIVITY ............................................................ 6 2 CONTROL ROOM EVACUATION ..................................................... 7 3 FUEL CLADDING DEGRADATION ................................................... 8 4 G EN E RA L ....................................................................................... 11 5 INJURED/CONTAMINATED PERSONNEL .................................... 12 6 IN-PLANT HIGH RADIATION .......................................................... 13 7 LOSS O F AC POW ER ..................................................................... 14 8 LOSS OF CONTROL ROOM ALARMS AND ANNUNCIATORS ....... 15 9 LOSS OF DC POW ER ..................................................................... 16 10 LOSS OF DECAY HEAT REMOVAL CAPABILITY ......................... 17 11 LOSS OF REACTIVITY CONTROL ................................................. 18 12 LOSS OF REACTOR VESSEL INVENTORY .................................. 20 13 NATURAL PHENOMENA ................................................................ 22 14 ONSITE FIRE/EXPLOSION .......................................................... 24 15 RADIOLOGICAL EFFLUENT .......................................................... 26 16 SECURITY EVENT ......................................................................... 30 17 SPENT FUEL RELATED INCIDENT ............................................... 32 18 STEAM LINE BREAK .................................................................... 34 19 TOXIC/FLAMMABLE GASES .......................................................... 37 20 TECHNICAL SPECIFICATION SAFETY LIMIT ............................... 38 21 DRY FUEL STORAGE ..................................................................... 39 EP-AD-000-200, Revision 16, Page 5 of 39
TAB 4 EP-PS-1 00-4 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:
(Aand 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# 1.4 None.
EP-AD-000-200, Revision 16, Page 6 of 39
TAB 4 EP-PS-100-4 2 - CONTROL ROOM EVACUATION UNUSUAL EVENT EAL# 2.1 None.
ALERT EAL# 2.2 Control Room evacuation as indicated by:
(Aand 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:
(Aand 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 16, Page 7 of 39
TAB 4 EP-PS-1 00-4 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 ACi/cc 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 jCi/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 16, Page 8 of 39
TAB 4 EP-PS-100-4 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 gCi/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 16, Page 9 of 39
TAB 4 EP-PS-1 00-4 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 or B)
A. (1 and 2)
- 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 or c)
- 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 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 16, Page 10 of 39
TAB 4 EP-PS-1 00-4 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 PP&L, 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 16, Page 11 of 39
TAB 4 EP-PS-100-4 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-000-200, Revision 16, Page 12 of 39
TAB 4 EP-PS-100-4 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
+DA.c "
CNN >500 DACA DACB DA Cc DA CN 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 16, Page 13 of 39
TAB 4 EP-PS-1'00-4 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 0C653.
or B. Failure of all diesel generators to start or synchronize to the emergency buses by indication or annunciation on Panel 0C653.
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 0C653.
and B. Failure of all diesel generators to start or synchronize to the emergency buses by annunciation or indication on Panel 0C653.
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 0C653.
and C. The above conditions exist for greater than 15 minutes.
GENERAL EMERGENCY EAL# 7.4 None.
EP-AD-000-200, Revision 16, Page 14 of 39
TAB 4 EP-PS-1 00-4 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 andB)
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 16, Page 15 of 39
TAB 4 EP-PS-1 00-4 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 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 1 D642 (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 (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 1 D642 (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 16, Page 16 of 39
TAB 4 EP-PS-1 00-4 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 200OF 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 0 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 200OF and rising.
and C. Suppression pool temperature greater than 290°F indicated on the computer output (MAT 12,13,14,15 or 16).
EP-AD-000-200, Revision 16, Page 17 of 39
TAB 4 EP-PS-100-4 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 16, Page 18 of 39
TAB 4 EP-PS-1 00-4 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 2000 F, indicated on Panel 1C651 (2C651).
and D. Reactor power >5% indicated on Panel 1C651 (2C651).
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 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 16, Page 19 of 39
TAB 4 EP-PS-1 00-4 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 16, Page 20 of 39
TAB 4 EP-PS-100-4 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 and 3)
- 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 16, Page 21 of 39
TAB 4 EP-PS-100-4 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 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 16, Page 22 of 39
TAB 4 EP-PS-1 00-4 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 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 0C696.
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 16, Page 23 of 39
TAB 4 EP-PS-100-4 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 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 16, Page 24 of 39
TAB 4 EP-PS-1 00-4 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 200OF as indicated on Panel 1C651 (2C651).
GENERAL EMERGENCY EAL# 14.4 None.
EP-AD-000-200, Revision 16, Page 25 of 39
TAB 4 EP-PS-1 00-4 15 - RADIOLOGICAL EFFLUENT UNUSUAL EVENT EAL# 15.1.a Radiological gaseous effluents exceed 2 times the Technical Requirement Limits for 60 minutes or longer as indicated by:
(A orB)
A. Valid Building Vent Stack Monitoring System (SPING) indications on Panel 0C630 or 0C677.
- 1. Noble gases >1.70E+6 ,Ci/min., or
- 2. 1-131 >2.08E+2 j+/-Ci/min., or
- 3. Particulate >1.54E+3 gCi/min., or or B. Confirmed sample analyses for gaseous releases indicating total site release rates exceed:
- 1. Noble gases >1000 mrem/year whole body, or
- 2. Noble gases >6000 mrem/year skin, or
- 3. 1-131, 1-133, H-3, and particulates with half-lives >8 days >3000 mrem/year to any organ (inhalation pathways only).
OR EAL# 15.1.b Radiological liquid effluents exceed Technical Requirement Limits for instantaneous release as indicated by:
Report of radiological liquid effluent exceeding Technical Requirement Limits. This includes effluent sources such as Service Water or RHR Service Water Loops A or B.
(CONTINUED ON NEXT PAGE)
EP-AD-000-200, Revision 16, Page 26 of 39
TAB 4 EP-PS-1 00-4 15- RADIOLOGICAL EFFLUENT (continued)
ALERT EAL# 15.2.a Radiological gaseous effluents exceed 200 times the Technical Requirement Limits for 15 minutes or longer as indicated by:
(A or B)
A. Valid Building Vent Stack Monitoring System (SPING) indications on Panel 0C630 or 0C677.
- 1. Noble gases >1.70E+8 jCi/min., or
- 2. 1-131 >2.08E+4 p.Ci/min., or
- 3. Particulate >1.54E+5 gCi/min.
or B. Confirmed sample analyses for gaseous releases indicating total site release rates exceed:
- 1. Noble gases >1.OE+5 mrem/year whole body, or
- 2. Noble gases >6.OE+5 mrem/year skin, or
- 3. 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 EAL# 15.2.b Radiological liquid effluents exceed 10 times Technical Requirement Limits for instantaneous release as indicated by:
Report of radiological liquid effluent release exceeding 10 times Technical Requirement Limits. This includes effluent sources such as Service Water or RHR Service Water Loops A orB.
(CONTINUED ON NEXT PAGE)
EP-AD-000-200, Revision 16, Page 27 of 39
TAB 4 EP-PS-1I00-4 15 - RADIOLOGICAL EFFLUENT (continued)
SITE AREA EMERGENCY EAL# 15. 3 Radiological effluent corresponds to greater than 50 mrem W.B.(') or 250 mrem thyroid( 2) for a half-hour or 500 mrem W.B.(1) or 2500 mrem thyroid(2 ) for 2 minutes at the emergency plan boundary as indicated by:
OR Emergency plan boundary dose is projected to exceed 500 mrem W.B. (1)within 1 hou-r as indicated by:
(Aor B)
A. Dose projections based on:
(1 or2)
- 1. Building vent stack monitoring system indications on Panel 0C630 or 0C677.
or
- 2. Field monitoring data onsite or offsite.
or B. Dose projections based on:
(1 or2)
- 1. Building vent stack monitoring system indications on Panel 0C630 or 0C677.
or
- 2. Field monitoring data onsite or offsite (CONTINUED ON NEXT PAGE)
(1) The sum of the Effective Dose Equivalent resulting from the exposure to external sources and the Committed Effective Dose Equivalent incurred from all significant inhalation pathways during the early phase.
(2) Committed Dose Equivalent to the thyroid from radioiodine.
EP-AD-000-200, Revision 16, Page 28 of 39
TAB 4 EP-PS-1 00-4 15 - RADIOLOGICAL EFFLUENT (continued)
GENERAL EMERGENCY EAL# 15.4 Radiological effluent release corresponds to 1 rem whole body(i) or 5 rem(2) thyroid at the emergency plan boundary as indicated by:
OR Offsite doses are projected to exceed 1 rem whole body(0) or 5 rem thyroid(2 ) due to the event as indicated by:
(Aor B)
A. Dose projections based on:
(1 or2 or3)
- 1. Building Vent Stack Monitoring System indication on Panel 0C630 or 0C677.
or
- 2. Field monitoring data onsite or offsite.
or
- 3. In-plant conditions.
or B. Dose projections based on:
(1 or2 or3)
- 1. Building Vent Stack Monitoring System indication on Panel 0C630 or 0C677.
or
- 2. Field monitoring data onsite or offsite.
or
- 3. In-plant conditions.
(1) The sum of the Effective Dose Equivalent resulting from the exposure to external sources and the Committed Effective Dose Equivalent incurred from all significant inhalation pathways during the early phase.
(2) Committed Dose Equivalent to the thyroid from radioiodine.
EP-AD-000-200, Revision 16, Page 29 of 39
TAB 4 EP-PS-100-4 16 - SECURITY EVENT UNUSUAL EVENT EAL# 16.1 Security threat or attempted entry or attempted sabotage as indicated by:
(AorB orC)
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:
(Aor 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 16, Page 30 of 39
TAB 4 EP-PS-1 00-4 16 - SECURITY EVENT (continued)
GENERAL EMERGENCY EAL# 16.4 Loss of physical control of facilities as indicated by:
(A orB)
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 16, Page 31 of 39
TAB 4 EP-PS-100-4 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 CN >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 16, Page 32 of 39
TAB 4 EP-PS-1 00-4 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# 17.4 None.
EP-AD-000-200, Revision 16, Page 33 of 39
TAB 4 EP-PS-1 00-4 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 16, Page 34 of 39
TAB 4 EP-PS-1 00-4 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 orlD)
A. (1 and 2)
- 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
or
- f. Other indication of steam leakage from the RCIC system.
(CONTINUED ON NEXT PAGE)
EP-AD-000-200, Revision 16, Page 35 of 39
TAB 4 EP-PS-100-4 18 - STEAM LINE BREAK (continued)
SITE AREA EMERGENCY (continued) or
- 0. (1 and 2)
- 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
- o. 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 16, Page 36 of 39
TAB 4 EP-PS-1 00-4 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 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 16, Page 37 of 39
TAB 4 EP-PS-1 00-4 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 16, Page 38 of 39
TAB 4 EP-PS-100-4 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 orB)
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:
(Aor 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 16, Page 39 of 39
TAB 6 EP-PS-100-6 PP&L EMERGENCY PERSONNEL DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATION (PAR) GUIDE TABLE OF CONTENTS Section Page 1.0 EMERGENCY DOSE LIMITS 2 2.0 EMERGENCY EXPOSURE/ACCIDENTAL OVEREXPOSURE 3 3.0 PROTECTIVE ACTIONS 3 4.0 EMERGENCY EXPOSURE NOTIFICATION AND HEALTH CONSEQUENCE INVESTIGATION 4 EMERGENCY EXPOSURE EXTENSIONS 5 HEALTH PHYSICS AND ALARA CONSIDERATIONS DURING AN EMERGENCY 8 EMERGENCY EXPOSURE EXTENSION REQUEST FORM and POTASSIUM IODIDE TRACKING FORM can be found immediately following EP-AD-000-125.
EP-AD-000-125, Revision 7, Page 1 of 10
TAB 6 EP-PS-100-6 PP&L EMERGENCY PERSONNEL DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATION (PAR) GUIDE (continued)
CHECK El 1.0 Limits for EMERGENCY doses.
0 1.1 An EMERGENCY DOSE AUTHORIZATION (see EMERGENCY EXPOSURE EXTENSIONS) may be granted in order to protect facilities, and or equipment to substantially limit the escape of radioactive effluents or control fires. The maximum planned doses are:
1.1.1 Whole body (TEDE)(1 ) dose shall not exceed 10 Rem.
1.1.2 Dose to any organ (CDE)(2 ), including the skin and extremity (SDE)(3),
shall not exceed 100 Rem.
1.1.3 Dose to the lens of the eye shall not exceed 30 Rem (LDE)(4).
0 1.2 An EMERGENCY dose authorization may be granted for life-saving actions or protection of large populations. The maximum doses are:
1.2.1 Planned whole body (TEDE)(1) doses shall not exceed 25 Rem.
1.2.2 Planned dose to any organ (CDE)(2), including skin and extremity doses, shall not exceed 250 Rem.
1.2.3 Dose to the lens of the eye shall not exceed 75 Rem (LDE)(4).
1.3 RARE situations may occur in which a dose GREATER THAN those specified in SECTION 1.2 above for emergency dose would be unavoidable to carry out a lifesaving operation or to avoid extensive exposure of large populations. It is not possible to prejudge the risk that one should be allowed to take to save lives of others, therefore no upper limit has been established.
(1) The sum of the Effective Dose Equivalent resulting from the exposure to external sources and the committed effective Dose Equivalent incurred from all significant inhalation pathways during the early phase.
(2) The Committed Dose Equivalent to the thyroid from radioiodine.
(3) Shallow Dose Equivalent.
(4) Lens Dose Equivalent.
EP-AD-000-125, Revision 7, Page 2 of 10
TAB 6 EP-PS-1 00-6 PP&L EMERGENCY PERSONNEL DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATION (PAR) GUIDE (continued)
CHECK 0 2.0 For any EMERGENCY EXPOSURE OR ACCIDENTAL OVEREXPOSURE, the assessment actions in step 2 of the EMERGENCY EXPOSURE EXTENSIONS must be performed.
3.0 PROTECTIVE ACTIONS 0 3.1 Potassium Iodide 3.1.1 For emergency workers entering areas where a committed dose equivalent, (CDE)(2), to the thyroid from radioiodine could be 25 Rem or greater, the Consulting Radiological Physician should provide input concerning the administration and cessation of KI intake. (See Emergency Telephone Directory for telephone number.)
3.1.2 For thyroid exposures that are strongly expected to exceed 25 Rem, (CDE)(2), KI doses of 130 mg (100 mg - iodine) per day should be administered.
Unless the EMERGENCY DIRECTOR or RECOVERY MANAGER instructs personnel to do otherwise, the KI tablets should generally be taken as soon as possible after thyroid exposure exceeding 25 Rem (CDE)(2) is projected.
NOTE: Stable Iodine (KI) is most effective when administered immediately prior to exposure to radiolodine. Significant blockage of the thyroid dose can be provided by administration within one or two hours after uptake of radiolodine.
(1) The sum of the Effective Dose Equivalent resulting from the exposure to external sources and the committed effective Dose Equivalent incurred from all significant inhalation pathways during the early phase.
(2) The Committed Dose Equivalent to the thyroid from radioiodine.
(3) Shallow Dose Equivalent.
(4) Lens Dose Equivalent.
EP-AD-000-125, Revision 7, Page 3 of 10
TAB 6 EP-PS-100-6 PP&L EMERGENCY PERSONNEL DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATION (PAR) GUIDE (continued)
CHECK El 3.1.3 Onsite issuance of KI for iodine prophylaxis requires the approval of the EMERGENCY DIRECTOR. Issuance to EOF and FIELD EMERGENCY MONITORING/SAMPLING TEAM personnel requires the approval of the RECOVERY MANAGER when the EOF has relieved the TSC of emergency management activities. The EMERGENCY DIRECTOR will approve issuance prior to that time.
These approvals must be documented on the POTASSIUM IODIDE (KI) TRACKING FORM.
3.1.4 For an injured and/or contaminated worker sent to a hospital for treatment, the patient will be under the care of the attending physician.
As such, plant procedures no longer apply and KI issuance will be at the discretion of the attending physician. The physician can rely on a senior Health Physics Technician Level il or Health Physics Management to provide the in-plant radiological data on which to base their decision.
El 3.2 Protective measures should be implemented for EOF personnel at the direction of the DOSE ASSESSMENT SUPERVISOR.
El 3.3. Exposures to members of local offsite support groups, (ambulance workers, fire fighters) shall not exceed 500 mrem (TEDE)(1 )for the performance of support duties on the site of the Susquehanna SES.
4.0 EMERGENCY EXPOSURE NOTIFICATIONS AND A HEALTH CONSEQUENCE INVESTIGATION must be conducted for any emergency exposure as outlined in step 6 of the Emergency Exposure Extensions.
(1) The sum of the Effective Dose Equivalent resulting from the exposure to external sources and the committed effective Dose Equivalent incurred from all significant inhalation pathways during the early phase.
(2) The Committed Dose Equivalent to the thyroid from radioiodine.
(3) Shallow Dose Equivalent.
(4) Lens Dose Equivalent.
EP-AD-000-125, Revision 7, Page 4 of 10
TAB 6 EP-PS-100-6 EMERGENCY EXPOSURE EXTENSIONS CHECK 0l
- 1. Fill out the attached EMERGENCY EXPOSURE EXTENSION REQUEST Form.
- 2. Review the following factors:
[3 Rescue personnel should be volunteers or professional rescuers.
O Other considerations being equal (e.g., skill, potential need for person on another mission) personnel above the age of 45 are preferred.
0l Rescue personnel should be familiar and briefed with the consequences of exposure.
El Women capable of reproduction should not take part in an effort requiring EMERGENCY exposure.
El Use of personnel with high lifetime cumulative exposure should be discouraged.
El All reasonable measures must be taken to control contamination and internal exposure.
o Exposure under these conditions shall be limited to once in a lifetime.
El For exposures greater than 25 Rem whole body (TEDE), the persons undertaking any emergency operation in which the dose will exceed 25 Rem to the whole body (TEDE) should do so only on a voluntary basis and with full awareness of the risks involved, including the numerical levels of dose at which acute effects of radiation will be incurred and numerical estimates of the risk of delayed effects. See the following two tables for general information concerning Health Effects & Cancer Risks.
EP-AD-000-125, Revision 7, Page 5 of 10
TAB 6 EP-PS-1 00-6 EMERGENCY EXPOSURE EXTENSIONS (continued)
CHECKE Health Effects Associated with Whole Body Absorbed Doses Received Within a Few Hours(a)
Whole Body Absorbed Earl Fatalitiesb Whole Body Absorbed Prodromal Effectsc Dose (rad) -percent) Dose (rad) (percent affected) 140 5 50 2 200 15 100 15 300 50 150 50 400 85 200 85 460 95 250 98 a Risks will be lower for protracted exposure periods.
b Supportive medical treatment may increase the dose at which these frequencies occur by approximately 50 percent.
c Symptoms (nausea, vomiting) which occur within a few hours after exposure to large doses of radiation and which usually precede more serious health effects.
Approximate Cancer Risk to Average Individuals from 25 Rem Effective Dose Equivalent Delivered Promptly Average Years of Life Lost if Age at Exposure Approximate Risk of Premature Death Premature Death Occurs (years) (deaths per 1,000 persons exposed) (years) 20 to 30 9.1 24 30to 40 7.2 19 40 to 50 5.3 15 50 to 60 3.5 11
- 3. Review the HEALTH PHYSICS AND ALARA CONSIDERATIONS DURING EMERGENCIES which is attached.
- 4. Obtain appropriate approval signatures as outlined in the table below.
EXTENSION APPROVAL ACTIONS FROM TO mrem mrem (TEDE) (TEDE) 4000 <25000 ED and RPC/RM and DASU ALARA REVIEW AND APPLY EMERGENCY EXPOSURE CONSIDERATIONS ALL OF ABOVE AND
>25000 ED and RPC/RM and DASU BRIEFING ON RISKS EP-AD-000-125, Revision 7, Page 6 of 10
TAB 6 EP-PS-1 00-6 EMERGENCY EXPOSURE EXTENSIONS (continued)
CHECK 0
- 5. Ifthe Emergency Dose Extension is for greater that 4 Rem (TEDE), have the volunteer sign the EMERGENCY EXPOSURE REQUEST Form acknowledging that they are a volunteer and are fully aware of the radiological risks of acute and delayed effects.
- 6. Upon completion of the activity requiring the Emergency Exposure perform the following:
El Collect, process, and evaluate personnel dosimetry devices when technically appropriate.
El Investigate the circumstances of all emergency exposures and confirm the dose received.
El Notify the NRC of emergency exposure as follows:
Immediate notification of the NRC is required for:
Notification of the NRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is required for:
.0 Assess the health consequences of all emergency exposures. Consult with a physician to determine the need for and extent of physical and biochemical examinations.
"El Whole body greater than 25 Rem (TEDE) should result in an examination of the exposed person by a physician.
"El If internal exposure is suspected, quantitative measurements should be made immediately. Bioassays are required based on the following:
"*Nasal smear or facial contamination greater than 1,000 cpm above background.
"*Greater than 4 DAC-HRS in a day or less, or 20 DAC-HRS in a week or less.
EP-AD-000-125, Revision 7, Page 7 of 10
TAB 6 EP-PS-100-6 HEALTH PHYSICS AND ALARA CONSIDERATIONS DURING EMERGENCIES CHECK 0 1.0 Evaluate radiological conditions.
0 1.1 Obtain detailed survey data to ascertain:
1.1.1 Beta-Gamma radiation levels 1.1.2 Need for neutron measurements 1.1.3 Contamination levels and protective clothing requirements 1.1.4 Airborne radioactive materials 1.1.5 Variability of conditions over space and time 0 1.2 Evaluate personnel status.
1.2.1 Determine available dose under normal administrative dose objectives.
1.2.2 If essential, obtain approval from RADIATION PROTECTION
- COORDINATOR/EMERGENCY DIRECTOR for persons expected to exceed administrative objectives.
1.2.3 Follow criteria in PP&L Emergency Personnel Dose Assessment and Protective Action Recommendation Guide when emergency exposures are deemed appropriate by EMERGENCY DIRECTOR.
1.2.4 Assess individual's history of exposure to airborne materials.
1.2.5 Assess individual's skills in relation to proposed task.
1.2.6 Assess individual's lifetime exposure history.
EP-AD-000-125, Revision 7, Page 8 of 10
TAB 6 EP-PS-100-6 HEALTH PHYSICS AND ALARA CONSIDERATIONS DURING EMERGENCIES (continued)
CHECK 0 0 1.3 Determine proper type and placement of dosimeters.
1.3.1 Evaluate need for additional whole body dosimeters.
NOTE: For emergency exposures above 4 rem, the placement of several dosimeters on an individual is recommended to determine spatial distribution of dose to the individual.
1.3.2 Evaluate need and placement of extremity dosimeters.
1.3.3 Evaluate need for additional dosimetry devices such as high range self-reading dosimeters, electronic dosimeters, and neutron dosimeters.
1.3.4 Evaluate need for time keeping.
0 1.4 Determine proper respirator equipment required to perform task.
NOTE: For tasks expected to last more than several hours, consider need for relief of team members.
0 1.5 Review the following ALARA items:
NOTE: The detail and scope of ALARA reviews are to be commensurate with the magnitude of doses expected, numbers of people involved, and urgency of required task.
1.5.1 Consider the trend of exposures vs. the importance of the task:
- a. Important and critical task with rising exposure rates will require the dispatch of teams as quickly as possible to reduce exposures.
- b. Unimportant or less critical task could be delayed until exposure rates begin to trend downward.
EP-AD-000-125, Revision 7, Page 9 of 10
TAB 6 EP-PS-100-6 HEALTH PHYSICS AND ALARA CONSIDERATIONS DURING EMERGENCIES (continued)
CHECK 01 1.5.2 When time permits the following should be included in the ALARA review:
- a. Consider the use of remote handling devices or other special tools.
- b. Consider the use of portable shielding.
- c. Consider the need for mock-ups or other practice exercises.
- d. Assess the number of people required to assure all have essential productive roles.
- e. Consider the magnitude of doses received by team members in transit to work location.
EP-AD-000-125, Revision 7, Page 10 of 10
TAB 7 EP-PS-100-7 PERSONNEL ACCOUNTABILITY (As defined in SP-00-309, Personnel Accountability)
ACCOUNTABILITY READER LOCATIONS SITE BUILDING READER LOCATION Service & Administration Building - North S&A Cafeteria S&A Large Conference Room 2 nd Floor Effluents Management Meeting Area Facilities Management Meeting Area Warehouse Facility Large Conference Room 2 nd Floor South Building - Two Story First Floor Main Hallway - East Doorway Main Hallway - West Doorway Main Hallway - Center Second Floor Main Hallway - North Exit Main Hallway - South Exit Main Hallway - West Exit South Building - Three Story First Floor North End Near Elevator South End Near Doorway to Maintenance Center Hallway Second Floor North End Near Elevator South End Near West Stairway Third Floor North End Near Elevator South End Near West Stairway EP-AD-000-445, Revision 8, Page 1 of 3
TAB 7 EP-PS-1 00-7 PERSONNEL ACCOUNTABILITY AREAS AND LEADER ASSIGNMENTS Accountability Area Accountability Area Designator Accountability Area Work Groups Leader ACCOUNTABILITY S&A Building Cafeteria All Personnel located PRIMARY: Industrial AREA A ETN 254-1624 in S&A Building Safety Supervisor All floors except those noted in Assembly Area B ACCOUNTABILITY Effluents Management Effluents Management PRIMARY: Effluents AREA-B Meeting Area Facilities Management Mgmt. Supervisor ETN 254-1644 Chemistry Admin ISI-ISD ACCOUNTABILITY Warehouse Large Procurement PRIMARY: Mgr.-Nuc AREA C Conference Room Procurement ETN 254-3186 ACCOUNTABILITY Electrical Maintenance All Personnel located PRIMARY: Production AREA D I&C Shop in the Two Story Supervisor I&C 1st Floor Two Story South Building South Building ETN 254-3713 ACCOUNTABILITY Cafeteria All Personnel located PRIMARY: Production AREA E Conference Room on the 1 st Floor of the Supervisor 1 st Floor Three Story Three Story Maintenance South Building South Building ETN 254-1685 ACCOUNTABILITY Conference Room 211 All Personnel located PRIMARY: Radiation AREA F 2 nd Floor of the Three on the 2nd and 3 rd Floor Protection Manager Story South Building of the Three Story ETN 254-1211 South Building _
ACCOUNTABILITY Technical Support All Personnel PRIMARY: TSC AREA G Center Responding to Fill Administrative Control Structure Emergency Plan Coordinator Elevation 741 Positions in the TSC ETN 254-3045 1 EP-AD-000-445, Revision 8, Page 2 of 3
TAB 7 EP-PS-1 00-7 ACCOUNTABILITY ROSTER ACCOUNTABILITY AREA: DATE: _ /
ACCOUNTABILITY AREA LEADER:
Name (Last, First) Badge # Name (Last, First) Badge #
INSTRUCTIONS:
- 1. The Accountability Area Leader will direct all personnel in the assembly area to complete this roster in the event the Accountability Card Reader system is inoperable.
- 2. On-site Personnel will print their name and SSES badge number in the areas provided on this form.
- 3. After completion, notify Security and follow their direction to forward the rosters.
EP-AD-000-445, Revision 8, Page 3 of 3