ML033510644
| ML033510644 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 12/08/2003 |
| From: | Susquehanna |
| To: | Document Control Desk, Office of Nuclear Security and Incident Response |
| References | |
| 28401 EP-PS-250, Rev 0 | |
| Download: ML033510644 (52) | |
Text
Dec. 08, 2003 Page 1 of 1 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2003-58069 USER TNFORMATION:
GE H* EMPL#:28401 CA#: 0363 Addr : CSA2 one#: 254-31 TRANSMITTAL INFORMATION:
TO: 12/08/2003 LOCATION: FDOCUMENT CONTROL DESK FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER NUCSA-2)
\ jHE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNED TO YOU:
250 - 250 EOF TECHNICAL ADVISOR REMOVE MANUAL TABLE OF CONTENTS DATE: 12/04/2003 ADD MANUAL TABLE OF CONTENTS DATE: 12/05/2003 CATEGORY: PROCEDURES TYPE: EP ID: EP-PS-250 REPLACE: REV:0 REMOVE: REV:0 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 EOF TECHNICAL ADVISOR: EP-PS-250 Emergency Plan Position-Specific Instruction Revision 0 Page 1 of 3 QUALITY CLASSIFICATION: APPROVAL CLASSIFICATION:
( ) QA Program (X) Non-QA Program ( ) Plant \
- ',>/ ( Non-Plant (X) Instructiori/
EFFECTIVE DATE: .'_____________
PERIODIC REVIEW FREQUENCY: Two Years PERIODIC REVIEW DUEDATE:
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/v-o c -X>
IN RECOMMENDED REVIEWS:
All Procedure Owner Nuclear Emergency Planning
( '.d Responsible Supervisor: Primary Engineering Support Supervisor Responsible FUM: Supv-Nuclear Emergency Planning Responsible Approver: General Manager-Plant Support FORM NDAP-QA-0002-1, Rev. 3, Page 1 of 1
EP-PS-250 Revision 0 Page 2 of 3 EOF Technical Advisor: Emergency Plan Position-Specific Procedure WHEN: Emergency Operations Facility is activated.
HOW NOTIFIED: Paged (TNS)
REPORT TO: Emergency Operations Facility WHERE TO REPORT: EOF Engineering Support Supervisor OVERALL DUTY:
Using the guidelines provided, assess overall event situation by reviewing available data, discussions with STA and SAM coordinator, and providing a "Big Picture" perspective of the event to the Recovery Manager and EOF organization.
MAJOR TASKS: TAB: REVISION:
Report to the EOF, obtain pertinent plant data, TAB A 0 assess overall status of plant conditions, and assist EOF organization with understanding of the event.
EP-PS-250 Revision 0 Page 3 of 3 SUPPORTING INFORMATION: TAB:
Emergency Organization TAB 1 Emergency Classifications TAB 2 Public Protective Actions TAB 3
REFERENCES:
TABA EP-PS-250-A Revision 0 Page 1 of 1 MAJOR TASK:
Report to the EOF, obtain pertinent plant data, assess overall status of plant conditions, and assist EOF organization with understanding of the event.
SPECIFIC TASKS: HOW:
NOTE:
This position is an augmented position and therefore is not required for EOF activation or within 90 minutes.
- 1. Assess overall status of Plant 1a. Review current plant indications Condition and assist EOF available from the Control Room, PICSY, organization with understanding of the and discussions with the STA and TSC event. SAM coordinator.
NOTE:
There is a direct tie line to the SAM Coordinator that can be utilized to obtain this information.
lb. Review current EAL and mitigating actions and assess if they are consistent with your understanding of the cause and progression of the event.
1c. Ensure the EOF organization has a clear understanding of the results of your assessment.
1d. For critical breaking information:
- Provide your information and assessment to the EOF immediately by discussing the situation with the Recovery Manager.
- Provide the same information to the Engineering Support Supervisor and Dose Assessment Supervisor.
1e. If information is not critical:
Tab 1 EP-PS-250-1 EMERGENCY ORGANIZATION CONTROL ROOM EMERGENCY DIRECTOR (SHIFT MANAGER)
I I I I EMERGENCY PLAN SHIFT TECHNICAL NRC OPERATORS COMMUNICATOR ADVISOR (STA) COMMUNICATOR(S)
EP-AD-000-406, Revision 16, Page 1 of 3
(7 (7 (.
Tab 1 EP-PS-250-1 TSC ORGANIZATION EMERGENCY DIRECTOR*
TSC Communicators 1Communicator*
Proposed NRC Rev. 5-02 Susquehanna Steam Electric Station Non-Operations I Units 1 and 2 Support Personnel (9)
Emergency Plan Ref. Sec. 6.2.12 TSC ORGANIZATION 9 report @ 60 minutes FIGURE 6.2 Non-Operations I Support Personnel I Ref. Sec. 6.2.12 5 report @ 90 minutes Designates minimum requirements in accordance with Table 6.1 for 60-minute response.
Individuals may be located in the OSC, TSC, or Field.
- Designates positions required for TSC activation.
EP-AD-000-406, Revision 16, Page 2 of 3
( C Tab 1 EP-PS-250-1 EOF ORGANIZATION 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-250-2 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.
El 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.
0: 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 21, Page 1 of 38
Tab 2 EP-PS-250-2 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 21, Page 2 of 38
Tab 2 EP-PS-250-2 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 21, Page 3 of 38
Tab 2 EP-PS-250-2 CATEGORY INDEX TO THE MATRIX FOR THE CLASSIFICATION OF EMERGENCY CONDITIONS TABLE OF CONTENTS CATEGORY EVENT PAGE 1 AIRCRAFT/TRAIN ACTIVITY ............................................... 5 2 CONTROL ROOM EVACUATION ................................................ 6 3 FUEL CLADDING DEGRADATION ................................................ 7 4 GENERAL .............................................. 10 5 INJURED/CONTAMINATED PERSONNEL ............................................... 11 6 IN-PLANT HIGH RADIATION ............................................... 12 7 LOSS OF AC POWER ............... 13 8 LOSS OF CONTROL ROOM ALARMS AND ANNUNCIATORS ................... 14 9 LOSS OF DC POWER ............................................... 15 10 LOSS OF DECAY HEAT REMOVAL CAPABILITY ....................................... 16 11 LOSS OF REACTIVITY CONTROL .............................................. 17 12 LOSS OF REACTOR VESSEL INVENTORY .............................................. 19 13 NATURAL PHENOMENA .............................................. 21 14 ONSITE FIRE/EXPLOSION .................................. 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 21, Page 4 of 38
Tab 2 EP-PS-250-2 1 - AIRCRAFTITRAIN 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 2001F as indicated on Panel 1C651 (2C651).
GENERAL EMERGENCY EAL# 1.4 None.
EP-AD-000-200, Revision 21, Page 5 of 38
Tab 2 EP-PS-250-2 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 21, Page 6 of 38
Tab 2 EP-PS-250-2 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 pCVcc 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 annunciation on Panel 1C651(2C651) or indication on Panel 1C600 (2C600).
or B. Valid Reactor coolant activity greater than 300 IiCi/cc of equivalent 1-131, as determined by sample analysis.
or C. Valid Main Steam Line High-High radiation 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 21, Page 7 of 38
Tab 2 EP-PS-250-2 3 - FUEL CLADDING DEGRADATION (continued)
SITE AREA EMERGENCY EAL# 3.3 Severely degraded core as indicated by:
(A or B)
A. Reactor coolant activity greater than 1,000 giCi/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 21, Page 8 of 38
Tab 2 EP-PS-250-2 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 and2)
- 1. Reactor coolant activity greater than 1,000 plCi/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 21, Page 9 of 38
Tab 2 EP-PS-250-2 4-GENERAL UNUSUAL EVENT EAL# 4.1 Plant conditions exist that warrant increased awareness on the part of plant operating staff or state and/or local offsite authorities as indicated by:
Events that are occurring or have occurred which indicate a potential degradation of the level of safety of the plant. No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs.
ALERT EAL# 4.2 Other plant conditions exist that warrant precautionary activation of PPL, State, County, and local emergency centers as indicated by:
Events that are occurring or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant. Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels.
SITE AREA EMERGENCY EAL# 4.3 Other plant conditions exist that warrant activation of emergency centers and monitoring teams or a precautionary notification to the public near the site as indicated by:
Events that are occurring or have occurred which involve actual or imminent major failures of plant functions needed for protection of the public. Any releases are not expected to exceed EPA Protective Action Guideline exposure levels except inside the emergency planning boundary.
GENERALEMERGENCY 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 21, Page 10 of 38
Tab 2 EP-PS-250-2 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 21, Page 11 of 38
Tab 2 EP-PS-250-2 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 Co CC CN DACA DA CB DACC DACs 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 21, Page 12 of 38
Tab 2 EP-PS-250-2 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 21, Page 13 of 38
Tab 2 EP-PS-250-2 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 21, Page 14 of 38
Tab 2 EP-PS-250-2 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 (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).
and C. The above condition exists for greater than 15 minutes.
NOTE: Buses are not tripped on undervoltage condition.
GENERALEMERGENCY EAL# 9.4 None.
EP-AD-000-200, Revision 21, Page 15 of 38
Tab 2 EP-PS-250-2 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 2121F.
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 1201F 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 2900F indicated on the computer output (MAT 12,13,14,15 or 16).
EP-AD-000-200, Revision 21, Page 16 of 38
Tab 2 EP-PS-250-2 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 21, Page 17 of 38
Tab 2 EP-PS-250-2 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 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 (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 21, Page 18 of 38
Tab 2 EP-PS-250-2 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 21, Page 19 of 38
Tab 2 EP-PS-250-2 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 and 2 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 and2)
- 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 21, Page 20 of 38
Tab 2 EP-PS-250-2 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 21, Page 21 of 38
Tab 2 EP-PS-250-2 13 - NATURAL PHENOMENA (continued)
SITE AREA EMERGENCY EAL# 13.3 Severe natural phenomenon occurrence, with plant not in cold shutdown, as indicated by:
(A and B)
A. Reactor Coolant Temperature greater than 2000 F as indicated on Panel 1C651 (2C651).
and B. (1 or2 or3)
- 1. Reported hurricane or sustained winds greater than 80 mph.*
or
- 2. Earthquake with greater than Safe Shutdown Earthquake (SSE) levels as indicated on Panel OC696.
or
- 3. Tornado with reported wind velocities greater than 220 mph impacting on site.*
GENERAL EMERGENCY EAL# 13.4 None.
- Telephone numbers for the National Weather Bureau are located in the Emergency Telephone Directory.
EP-AD-000-200, Revision 21, Page 22 of 38
Tab 2 EP-PS-250-2 14 - ONSITE FIRE/EXPLOSION UNUSUAL EVENT EAL# 14.1 Significant fire within the plant as indicated by:
(A and B)
A. Activation of fire brigade by Shift Supervisor.
and B. Duration of fire longer than 15 minutes after time of notification.
OR Explosion inside security protected area, with no significant damage to station facilities, as indicated by:
Visual observation or notification received by control room operator and Shift Supervisor evaluation.
ALERT EAL# 14.2 On-site Fire/Explosion as indicated by:
(A or B)
A. Fire lasting more than 15 minutes and fire is in the vicinity of equipment required for safe shutdown of the plant and the fire is damaging or is threatening to damage the equipment due to heat, smoke, flame, or other hazard.
or B. (1 and2)
Explosion damage to facility affecting plant operation as determined by:
- 1. Direct observation or notification received by control room operator.
and
- 2. Shift Supervisor observation.
(CONTINUED ON NEXT PAGE)
EP-AD-000-200, Revision 21, Page 23 of 38
Tab 2 EP-PS-250-2 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 21, Page 24 of 38
Tab 2 EP-PS-250-2 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 2or 3)
- 1. Valid Noble Gas vent stack monitor reading(s) that exceeds a total site release rate of 2.OE+6 iiCimin 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 mremfyear 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 mrernlyear 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 21, Page 25 of 38
Tab 2 EP-PS-250-2 15 - RADIOLOGICAL EFFLUENT (continued)
ALERT EAL# 15.2 Any unplanned release of gaseous or liquid radioactivity to the environment that exceeds 200 times Technical Requirement Manual limits for 15 minutes or longer.
EAL# 15.2 (1 or 2 or 3)
- 1. Valid Noble Gas vent stack monitor reading(s) that exceeds a total site release rate of 2E+8 ipCimin and that is sustained for 15 minutes or longer.
OR 2 Confirmed sample analyses for airborne releases indicates total site release rates at the site boundary for 15 minutes or longer resulting in dose rates of:
a) Noble gases >1.OE+5 mrem/year whole body, or b) Noble gases >6.OE+5 mrem/year skin, or c) 1-131, 1-133, H-3, and particulates with half-lives >8 days >3.OE+5 mrem/year to any organ (inhalation pathways only).
- 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 21, Page 26 of 38
Tab 2 EP-PS-250-2 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 gCi/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 21, Page 27 of 38
Tab 2 EP-PS-250-2 15 - RADIOLOGICAL EFFLUENT (continued)
GENERAL EMERGENCY EAL# 15.4 Dose at the Emergency Planning Boundary resulting from an actual or imminent release of gaseous radioactivity exceeds 1000 mrem whole body TEDE or 5000 mrem child thyroid CDE for the actual or projected duration of the release using actual meteorology.
EAL# 15.4 (1 or 2 or 3 or 4 or 5)
- 1. Valid Noble Gas vent stack monitor readings(s) that exceed a total release rate of 6.2E9 piCimin 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 21, Page 28 of 38
Tab 2 EP-PS-250-2 16 - SECURITY EVENT UNUSUAL EVENT EAL# 16.1 Security threat or attempted entry or attempted sabotage as indicated by:
(A or B or C)
A. A report from Security of a security threat, attempted entry, or attempted sabotage of the owner controlled area adjacent to the site.
or B. Any attempted act of sabotage which is deemed legitimate in the judgment of the SHIFT SUPERVISOR/EMERGENCY DIRECTOR, and affects plant operation.
or C. A site specific credible security threat notification.
ALERT EAL# 16.2 Ongoing Security Compromise as indicated by:
(A or B)
A. A report from Security that a security compromise is at the site but no penetration of protected areas has occurred.
or B. Any act of sabotage which results in an actual or potential substantial degradation of the level of safety of the plant as judged by the SHIFT SUPERVISOR/EMERGENCY DIRECTOR.
SITE AREA EMERGENCY EAL# 16.3 An ongoing adversary event threatens imminent loss of physical control of plant as indicated by:
(A or B)
A. Report from Security that the security of the plant vital area is threatened by unauthorized (forcible) entry into the protected area.
or B. Any act of sabotage which results in actual or likely major failures of plant functions needed for protection of the public as judged by the SHIFT SUPERVISOR/EMERGENCY DIRECTOR.
(CONTINUED ON NEXT PAGE)
EP-AD-000-200, Revision 21, Page 29 of 38
Tab 2 EP-PS-250-2 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 21, Page 30 of 38
Tab 2 EP-PS-250-2 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 C B CC CN >502 DA CA DA C. DA CcDA CN 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 21, Page 31 of 38
Tab 2 EP-PS-250-2 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 21, Page 32 of 38
Tab 2 EP-PS-250-2 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 21, Page 33 of 38
Tab 2 EP-PS-250-2 18 - STEAM LINE BREAK (continued)
SITE AREA EMERGENCY EAL# 18.3 Steam line break occurs outside of containment without isolation as indicated by:
(A orB orC orD)
A. (1 and2)
- 1. Failure of both MSIVs in the line with the leak to close as indicated by position indication on Panel 1C601 (2C601).
and
- 2. (a orb)
- a. High MSL flow annunciation on Panel 1C601 (2C601) or indication on Panel 1C652 (2C652).
or
- b. Other indication of main steam leakage outside containment.
or B. (1 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 (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 21, Page 34 of 38
Tab 2 EP-PS-250-2 18 - STEAM LINE BREAK (continued)
SITE AREA EMERGENCY (continued) or C. (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 21, Page 35 of 38
Tab 2 EP-PS-250-2 19 - TOXICIFLAMMABLE 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 21, Page 36 of 38
Tab 2 EP-PS-250-2 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 21, Page 37 of 38
Tab 2 EP-PS-250-2 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 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.
ALERT EAL# 21.2 None.
SITE AREA EMERGENCY EAL# 21.3 None.
GENERAL EMERGENCY EAL# 21.4 None EP-AD-000-200, Revision 21, Page 38 of 38
Tab 3 EP-PS-250-3 PAR AIRBORNE RELEASES EP ENTERED MONITOR CONDITIONS:
- PLANT STATUSIPROCEDURES CONU
- ONSITE RAD CONDITONS ASSESSMENT)
- STATUS OF RELEASE
- DOSE PROJECTIONS P PA-1
<EMERGENCY BEEN NO YES
/PROJECTIONINDICTNDO RECOMMEND EVACUATION DOSES OF 21 REM TEDE OR YES CITIZENS TO TAKE K IN
\2 5 REM THYROID CDE AT A ACCORDANCE WITH THE ISTANCE OF 2 2 MILES STATES EMERGENCY PLANS.
PA-P NO OR UNKNOWN INRECOMMEND EVACUATING T 0-2 MILES AND SHELTERING I CONTIN VE D 2-10 MILES AND ADVISE CDTEZENS GU DESITI.
TO TAKE K- IN ACCORDANCE WITH T O THE STATES EMERGENCY PLANS. PA-1 PA-4 NOTES:
- 1. PA-# CAN BE USED TO REFER TO PROCEDURE STEPS FOR MORE DETAILED INFORMATION ON THE ACTION TO BE TAKEN.
- 2. DOSE PROJECTIONS DOfNOT INCLUDE DOSE ALREADY RECEIVED.
- 3. TEDE - WHOLE BODY (TEDE) IS THE SUM OF EFFECTIVE DOSE EQUIVALENT RESULTING FROM EXPOSURE TO EXTERNAL SOURCES. THE COMMITTED EFFECTIVE DOSE EQUIVALENT (CEDE) FROM ALL SIGNIFICANT INHALATION PATHWAYS AND THE DOSE DUE TO GROUND DEPOSITION.
- 4. CDE - COMMITTED DOSE EQUIVALENT TO THE CHILD THYROID.
EP-AD-000-1 26, Revision 11, Page 1 of 6
Tab 3 EP-PS-250-3 PAR LIQUID RELEASES INDICATIONS OF A POTENTIAL UQUID RELEASE
- UNISOLABLE RADWASTE TANK RELEASE
- LEAK TO COOUNG TOWER BASIN
- LEAK TO SPRAY POND PL-1 ENSURE CHEMIESD TAKES AND ANALYZES SAMPLES PL-2 NPLANNED REL ONTINU TO THE RIVER No REURED MONITORIIN TIIBUJTABLE TO T EC Values EVENT?
RADIONUCUDE (pCImI) PL-3 Co4Oo 3E' Yes Sr-gl 2E-6 w e-199 2E9G RAD PERSONNEL NOTIFY Te-132 9E4 DEPIBRP THAT A RELEASE 1-131 1E' HAS OCCURRED 1-133 7E' 1-134 4E'4 PW No 1-135 3E' :
Cs-134 9E7
- Cs-1 36 6E' , TECH REQUIREMENTS(AT Cs-i137 1E'f RELEASE POINT?
Ba-139 2E'4 Ba-140 BE- , PL-5 Ba-141 3E ' Yes Np-239 2E' Ye:s RAD PERSONNEL NOTIFY DANVILLE THAT A RELEASE HAS OCCURRED PL-6 CHEMIFTD EVALUATES
- RELEASE vs PAG PL-7
- 1. PL- CAN BE USED TO REFER TO ES RELEASE EXCEE RAD PERSONNEL PROCEDURE STEPS FOR MORE ANY OF THE SINGLE-NUCLIDE NOTIFY DEPIBRP DETAILED INFORMATION ON THE EC VALUES OR DOES THE No THAT NO PAR IS ACTION TO BE TAKEN. SUM OF EC FRACTIONS
- 2. CALLS TO DANVILLE ARE COURTESY EXCEED 0.85 REQUIRED INFORMATION CALLS ONLY. AT DANVIE? PL-10 PROTECTIVE ACTION RECOMMENDATION CALLS MUST BE PLD MADE BY DEPIBRP. I Yes RAD PERSONNEL NOTIFY DEPIBRP FOR DOWNSTREAM USERS TO DIVERT WATER SUPPLY & ESTIMATED TIME OF ARRIVAL OF RELEASE AT DANVILLE PL-9 EP-AD-000-1 26, Revision 11, Page 2 of 6
Tab 3 EP-PS-250-3 PUBLIC PROTECTIVE ACTION RECOMMENDATION GUIDE AIRBORNE RELEASES O PA-1 MONITOR CONDITIONS FOR PAR APPLICATION The following conditions should be continuously evaluated to determine if a PAR should be implemented or changed:
0 Plant status and prognosis for changes in conditions 0
Onsite radiological conditions 0
Status of actual or potential radioactive releases 0
Offsite dose projections or actual offsite radiological conditions Escalation in Emergency Classification (i.e., General)
(Go to PA-2)
El PA-2 HAS A GENERAL EMERGENCY BEEN DECLARED?
o YES - Ifa GENERAL EMERGENCY has been declared, a PAR must be made within 15 minutes of the emergency declaration. The PAR requirement is found in NUREG-0654. (Go to PA-3)
O NO- Ifa GENERAL EMERGENCY has not been declared, continue to monitor plant status, parameter trends, and prognosis for termination or escalation of the event. (Go to PA-1)
Eo PA-3 IS THERE A VALID DOSE PROJECTION INDICATING DOSES OF > 1 REM TEDE OR 2 5 REM CDE CHILD THYROID AT A DISTANCE OF > 2 MILES?
o YES - Ifthe projected doses at 2 miles are 21 REM TEDE or 2 5 REM CDE child thyroid, then full evacuation (0-10 miles) is recommended. (Go to PA-5)
O NO/UNKNOWN - (Go to PA-4)
O PA-4 RECOMMEND EVACUATION 0-2 MILES; SHELTER 2-10 MILES AND ADVISE CITIZENS TO TAKE KI IN ACCORDANCE WITH THE STATE'S EMERGENCY PLANS.
Limited Evacuation (0-2 miles) and sheltering is appropriate for events that are significant enough to cause a General Emergency classification and dose projections are low, unknown, or below full evacuation guidelines. A recommendation is also given to the state to advise citizens to take KI in accordance with the state's emergency plans.
O PA-5 EVACUATE 0-10 MILES AND ADVISE CITIZENS TO TAKE KI IN ACCORDANCE WITH THE STATE'S EMERGENCY PLANS.
Full evacuation of members of the general public is recommended at this point based on the emergency classification and dose projections. A recommendation is also given to the state to advise citizens to take KI in accordance with the state's emergency plans.
EP-AD-000-1 26, Revision 11, Page 3 of 6
Tab 3 EP-PS-250-3 LIQUID 0 PL-1 ENTRY This section is entered when there are indications of a potential unplanned radioactive liquid release.
Indications of potential unplanned releases include:
- an unisolable radwaste tank release
- leaks to cooling tower basin
- leak to spray pond (Go to PL-2) o PL-2 CHEMISTRY/ENVIRONMENTAL SAMPLING DIRECTOR (ESD)
TAKES AND ANALYZES SAMPLE (Go to PL-3)
PL-3 IS THERE AN UNPLANNED RELEASE TO THE RIVER?
O YES - An unplanned release to the river has occurred when event-related radioactive materials are released to the river that are not controlled by the release methodologies described in the ODCM and applicable Chemistry procedures.
(Go to PL-4)
O NO- If there is no unplanned release to the river, then no notifications are required and monitoring should continue.
o PL-4 RAD PERSONNEL NOTIFY DEP/BRP THAT A RELEASE HAS OCCURRED Depending on which facility is activated, the notification to BRP will be made by the RPC (TSC), Dose Assessment Supervisor, or Radiological Liaison at the EOF.
DO NOT MAKE ANY PROTECTIVE ACTION RECOMMENDATIONS AT THIS TIME.
(Go to PL-5)
EP-AD-000-1 26, Revision 11, Page 4 of 6
Tab 3 EP-PS-250-3 LIQUID (CONT'D)
PL-5 IS RELEASE 2 TECHNICAL REQUIREMENTS LIMITS (AT THE RELEASE POINT)?
E YES - Releases are at or greater than Technical Requirements limits when Chemistry determines that the limits are exceeded based on methodologies described in the ODCM and applicable Chemistry procedures.
(Go to PL-6) 0 NO- If the release is < Technical Requirements limits, then no further notifications are required and monitoring should continue.
o PL-6 RAD PERSONNEL NOTIFY DANVILLE THAT A RELEASE HAS OCCURRED Depending on which facility is activated, the notification to Danville will be made by the RPC (TSC), Dose Assessment Supervisor, or Radiological Liaison at the EOF.
DO NOT MAKE ANY PROTECTIVE ACTION RECOMMENDATIONS AT THIS TIME.
(Go to PL-7) o PL-7 CHEM/FTD EVALUATES RELEASE VERSUS PAGs The results of the sample analysis are compared to the PAGs for radionuclides in drinking water. The analysis calculates the expected concentration at Danville, taking into account the dilution afforded by the river.
PL-8 DOES RELEASE EXCEED PAGs (AT DANVILLE)?
O YES - Ifa single isotope exceeds its effluent concentration (EC) value or the sum of EC fractions exceeds 0.85, then a protective action recommendation should be made for downstream water users (e.g.,
Danville) to DIVERT DRINKING WATER supply to a backup supply or terminate user intake until the release has passed.
(Go to PL-9)
O NO- If the PAGs are not exceeded, monitoring should continue and the State should be notified that no PAR for the liquid release is required.
(Go to PL-10)
EP-AD-000-1 26, Revision 11, Page 5 of 6
Tab 3 EP-PS-250-3 LIQUID (CoNT'D) 0 PL-9 RAD PERSONNEL NOTIFY DEP/BRP OF PAR Depending on which facility is activated, the PAR notification to DEP/BRP will be made by the RPC (TSC), Dose Assessment Supervisor, or Radiological Liaison at the EOF. The PAR FORM shall be used to document the PAR.
DO NOT COMMUNICATE THE PROTECTIVE ACTION RECOMMENDATION TO DANVILLE. THE DEP/BRP IS RESPONSIBLE FOR THIS COMMUNICATION AND ANY COMMUNICATION TO OTHER DRINKING WATER SUPPLIERS OR WATER USERS.
O PL-10 RAD PERSONNEL NOTIFY DEP/BRP No PAR is required. Depending on which facility is activated, the RPC (TSC), Dose Assessment Supervisor, or Radiological Liaison at the EOF shall notify DEP/BRP that no PAR is required.
EP-AD-000-1 26, Revision 11, Page 6 of 6