ML022340589
| ML022340589 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 08/13/2002 |
| From: | Abney T Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML022340589 (128) | |
Text
Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 August 13, 2002 10 CFR Part 50, App E U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Gentleman:
In the Matter of
)
Docket Nos.
50-259 Tennessee Valley Authority
)
50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS 1, 2, and 3 EMERGENCY PLAN IMPLEMENTING PROCEDURE (EPIP) REVISIONS TVA is submitting this notification in accordance with the requirements of 10 CFR Part 50, Appendix E, Section V.
Specifically, several EPIPs were revised:
(1) EPIP-1, Revision 33; (2)
EPIP-2, Revision 23; (3)
EPIP-3, Revision 26; (4) EPIP-4, Revision 25; (5)
EPIP-5, Revision 30; and (6)
EPIP-8, Revision 15.
The revisions have an effective date of July 30, 2002.
The enclosed information is being sent by certified mail.
The signed receipt signifies that you have received this information.
If you have any questions, please telephone me at (256) 729-2636.
Ma er of Lice sing and Industry Affairs f~j5 Pnnted on recyc papw
U.S. Nuclear Regulatory Commission Page 2 August 13, 2002 cc (Enclosure):
NRC Resident Inspector (Enclosure provided by Browns Ferry Nuclear Plant BFN Document Control Unit)
P.O. Box 189 Athens, Alabama 35611 Mr. Paul E.
Fredrickson (2 Enclosures)
U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street S.W.,
Suite 23T85 Atlanta, Georgia 30303-8931 Mr.
Kahtan N. Jabbour, Senior Project Manager (w/o Enclosure)
U.S. Nuclear Regulatory Commission One White Flint, North (MS 08G9)
Office of Nuclear Reactor Regulation 11555 Rockville Pike Rockville, Maryland 20852-2738
ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT UNITS 1, 2,
AND 3 EMERGENCY PLAN IMPLEMENTING PROCEDURES (EPIP)
EPIP-1, EPIP-2, EPIP-3, EPIP-4, EPIP-5, AND EPIP-8 SEE ATTACHED
-S GENERAL REVISIONS GENERIC FILING INSTRUCTIONS FILE DOCUMENTS AS FOLLOWS:
PAGES TO BE REMOVED PAGES TO BE INSERTED EPIP-1 REVISION 32 (AFFECTED PAGES)
EPIP-2 Revision 22 EPIP-3 Revision 25 EPIP-4 Revision 24 EPIP-5 Revision 29 EPIP-8 Revision 14 EPIP-1 REVISION 33 (SUPPLIED PAGES)
EPIP-2 Revision 23 EPIP-3 Revision 26 EPIP-4 Revision 25 EPIP-5 Revision 30 EPIP-8 Revision 15
TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-1
-EMERGENCY CLASSIFICATION PROCEDURE REVISION 33 PREPARED BY: T. W. CORNELIUS RESPONSIBLE ORGANIZATION: EMERGENCY PREPAREDNESS APPROVED BY: GILBERT LITITLE EFFECTIVE DATE: 07/30/2002 LEVEL OF USE: REFERENCE USE QUALITY-RELATED PHONE: 2038 DATE: 07/22/2002
'K
REVISION LOG Procedure Number:
EPIP-I Revision Number 33 Pages Affected:
1,57,177 Description of Change:
IC - 42 EPIP 1, rev. 31 revision is being conducted to change the Site Boundary Radiation Reading from a beta-gamma value to gamma only value. This change does not involve the niumerical value. This revisi6n is in compliance with the REP and doesn't affect the BFN EP standard emergency classification and action level scheme. This revision is being conducted to ensure consistency with NUMARC/NESP-007, Reg Guide 1.101, and NEI 99-01 (Rev. 4).
IC - 43 EPIP 1, rev. 32 is being conducted t6 modify information that support EAL 1. 1-GI, 1.1-G2, and 1.2-G. The revision incorporates changes resulting from modifications to calculations that support Minimum Alternate RPV Flooding Pressures (MARFP) and Minimum Steam Cooling Reactor Water Level (MSCRWL). Revisions to these calculations were conducted in support of the EOI Program Manual Revision 21 (U3C 11).
IC-44 EPIP 1, rev. 33 is being issued to modify EAL 6.7-U. The revision incorporates changes resulting from the letter from NEI to NRC (to Mr. Bruce A. Boger) dated December 18, 2001 requesting confirmation for EAL basis change to include response to a Site -Specific Credible Threa( This was developed in response to' NRC's October 6, 2001 Safeguards Advisor. Th-is is additional information and does not change existing criteria in the EAL Basis.
-1) 11
'EPIP-1 EMERGENCY CLASSIFICATION PROCEDURE TABLE OF CONTENTS PAGE NUMBER REVISION TABLE OF CONTENTS............................................................................
1 33 SECTION I INTRODUCTION CLASSIFICATION INSTRUCTIONS............................................
3 29 G LO SSA RY...................................................................................
5 29 EVENT CLASSIFICATION INDEX............................................
11 29 SECTION II EVENT CLASSIFICATION MATRIX 1.0 R EA CTO R..............................................................................
13 30 2.0 PRIMARY CONTAINMENT.................................................
21 28 3.0 SECONDARY CONTAINMENT...........................................
29 29 4.0 RADIOACTIVITY RELEASES...........................................
!..33 30 5.0 LOSS OF POWER...........
... 39 29 6.0 H AZA RD S..............................................................................
45 30 7.0 NATURAL EVENTS..............................................................
61 28 8.0 EMERGENCY DIRECTOR JUDGEMENT............................
67 29 SECTION III BASIS 1.0 RE A CTO R..............................................................................
75 30 2.0 PRIMARY CONTAINMENT.......................
97 28 3.0 SECONDARY CONTAINMENT.........................................
116 29 4.0 RADIOACTIVITY RELEASE..............................................
126 30 5.0 LOSS OF POWER................................................................
139 29 6.0 H AZARD S...........................................................................
155 30 7.0 NATURAL EVENTS............................
183 28 8 0 EMERGENCY DIRECTOR JUDGEMENT..........................
190 29 PAGE 1 OF 207-R S
3 REVISION 33
'EPIP-1 EMERGENCY CLASSIFICATION PROCEDURE THIS PAGE INTENTIONALLY BLANK PAGE 2 OF 207 R*I 2f REVISION 33
EMERGENCY-
ý CLASSIFICATION PROCEDURE EPIP-1 SECTION II
-VENT CLASSIFICATION MATRIX HAZARDS 6.0 PAGE 45 OF 207 R ES*3 6.0 HAZARDS REVISION 30 6.0 HAZARDS
EPIP-1 SECTION II EVENT CLASSIFICATION MATRIX 6.0 HAZARDS EMERGENCY CLASSIFICATION PROCEDURE.' - "
CURVES/TABLES:
PAGE 46 OF 207 NOTES:
6.0 HAZARDS REVISION 30
EMERGENCY, -_
,CLASSIFICATION PROCEDURE EPIP-1 "
SECTION HI EVENT CLASSIFICATION MATRIXA RADIOLOGIAL DESCRIPTION DESCRIPTION 6 1-U Valid, unexpected increase of ANY in plant ARM reading to 1000 mrem/hr (except TIP Room)
OPERATING CONDITION:
-All 6 I-Al
- 6. 1-A2 Valid, unexpected increase of ANY in plant ARM Control Room radiation levels >15 mrem/hr reading to 1000 mrenlhr (except TIP Room)
AND Personnel actions required in the affected area(s)
OPERATING CONDITION:
OPERATING CONDITION
-All
-All
- 11 z*
- z 6.0 HAZARDS PAGE 47 OF 207 REVISION 30 "UI 0-4 S6.0 HAZARDS
, REVISION 30
-6.0 HAZARDS PAGE 47 OF 207 ' %'5
EPIP-1 SECTION II EVENT CLASSIFICATION MATRIX 6.o HAZARDS EMERGENCY^ -.
CLASSIFICATION PROCEDURE CURVES/TABLES:
<-Iý PAGE 48 OF 207 6: H NOTES:
REVISION 30 6.0 HAZARDS
EMERGENCY CLASSIFICATION PROCEDURE EPIP-1 SECTION III EVENT CLASSIFICATION MATRIX
,6.0 HAZARDS COTO ROM "TURIN DESC64rIPIO DESCRIPTION 6.3-U Turbine failure resulting in casing penetration OR Significant damage to turbine or generator seals during operation OPERATING CONDITION:
-Mode l
- Mode 2 al al oz 6.2-A 6.3-A Control Room Abandonment from entry into AOI-l00-Turbine failure resulting m visible structural damage to 2 or SSI-16 for ANY Unit Control Room.
' :or len&ration of ANY of the folloving structures from missiles ctor Building
..D- -iesel Generator Building
-Intake Str6uttre-s OPERATING CONDITION Control Bay,
-All OPERATING CONDITION
-Mode I
-Mole2 6.2-S Control Room Abandonment from enty into AOI-100-2 or SSI-16 for ANY Unit Control Room
-AND Control ofReactor %ute level, Reactor pressure, and Reactor poever(forModes 1,2,&3)ordecayheatremoval (for.Modes 4& 5)perAOI-100-2 or SSI-16 asapplicable CANNOTe be st~ablished within 20 minutes after evacuation is initiated.
OPERATING CONDITION.
-All 600 REVISION 30 6.0 HAZARDS PAGE 49 OF 207 - -+
EPIP-1 SECTION II EVENT CLASSIFICATION MATRIX" 6:0 HAZARDS EMERGENCY CLASSIFICATION PROCEDURE'..
NOTES:
I CURVES/TABLES:
TABLE 6.4-UI APPLICABLE PLANT AREA REACTOR BUILDING REFUEL FLOOR 4KV SHUTDOWN BOARD ROOMS,-,-,,,
4KV SHUTDOWN BOARD BATTERY ROOMS 480V SHUTDOWN BOARD ROOMS 3A and 3B RMOV BOARD ROOMS 4KV BUS TIE BOARD ROOM "
CONTROL BAY ELEVATION 593'. 606' and 617' DIESEL GENERATOR BUILDINGS (ALL ELEVATIONS)
TURBINE BUILDING (ALL ELEVATIONS IN OR ADJACENT TO AREAS CONTAINING SAFE SHUTDOWN EQUIPMENT INTAKE PUMPING STATION (ALL ELEVATIONS) 4 RADNWASTE BUILDING (ALL ELEVATIONS)
CABLE TUNNEL (INTAKE TO TURBINE BUILDING)
STANDBY GAS TREATMENT BUILDING TABLE 6.4-A.
APPLICABLE PLANT AREA REACTOR BUILDING..
REFUEL FLOOR 4KV SHUTDOWN BOARD ROOMS 4KV SHUTDOWN BOARD BATTERY ROOMS 480V SHUTDOWN BOARD ROOMS
.3A and 3B RMOV BOARD ROOMS 4KV BUS TIE BOARD ROOM CONTROL BAY ELEVATION 593', 606' and 617'
-DIESEL GENERATOR BUILDINGS (ALL ELEVATIONS)
INTAKE PUMPING STATION (ALL ELEVATIONS)
CABLE TUNNEL (INTAKE TO TURBINE BUILDING):
STANDBY GAS TREATMENT BUILDING REVISION 30 PAGE 50 OF 207,,',,
6.0 HAZARDS I
EMERGENCY" CLASSIFICATION PROCEDURE EPIP-1 SECTION HI EVENT CLASSIFICATION MATRIX6 DESCRIPTION DESCRIPTION
.1 6.0 HAZARDS PAGE 51 OF.207 2.
REVISION 30
ýz 6.4-U I 6.4-U2 Confinred fire in ANY plant area listed m Table 6 4-U1 Unanticipated explosion within the protected area AND resulting in -visible damage to ANY permanent NOT extinguished \\vithin 15 minutes structure or equipment OPERATING CONDITION OPERATING CONDITION.
-All
-All 6.4-A Fire or explosion in ANY plant area listed in Table 6 4-A affecting safety system performance OR Fire or explosion causing visible damage to permanent structures or safety systems in ANY area listed in Table 64-A OPERATING CONDITION
-All M0 Tl
= " z 6.0 HAZARDS
- REVISION 30 6.0 HAZARDS PAGE 51 OF.207 :,-
EPIP-1, SECTION HI EVENT CLASSIFICATION MATRIX`ý--'
6.0 HAZARDS EMERGENCY -,
CLASSIFICATION PROCEDURE * '
CURVES/TABLES:
TABLE 6.5/6.6 APPLICABLE PLANT AREA REACTOR BUILDINGS REFUEL FLOOR CONTROL BAY DIESEL GENERATOR BUILDINGS TURBINE BUILDING INTAKE PUMPING STATION RADWASTE BUILDING CABLE TUNNEL (INTAKE TO TURBINE BUILDING)
STANDBY GAS TREATMENT BUILDING PAGE 52 OF 207 NOTES:
L-PROCEDURE),!`
L 4
REVISION 30 6.0 HAZARDS
EMERGENCY CLASSIFICATION PROCEDURE DESCRIPTION EPIP-1 SECTION II' EVENT CLASSIFICATION MATRIX DESCRIPTION 6.5-U EITHER of the follovving conditions exists
"* Normal operations impeded due to access restrictions caused by toxic gas concentrations within any building or structure listed in Table 6 5/6 6.
"* Confirmed report by Local, County, or State Officials that a large offsite toxic gas release has occurred within one mile of the site wvith potential to enter the site boundary in concentrations at or above the Permissible Exposure Linmt (PEL) causing an evacuation of any site personnel OPERATING CONDITION:
-All 6.5-A K
ALL of the following conditions exists 6.5-A IK1 I
Plant personnel report toxic gas vithin any building or stictuire listed in Table 6 5/6 6 Plant personnel report severe adverse health reactions due to toxic gas (i e, burmng eyes, throat, or dizmess) or Sampling results by Fire Protection or Industrial Safety personnel indicate levels above the Permissible Exposure Limit (PEL)
Determination by the Site Emergency Director that plant personnel would be unable to p.erform actions-necessary to-e-tablish and maintain cold shuitdown conditions while S.......utilizing appropriate personnel protective equipment. -
OPERATING CONDITION
- r.
t 0
S.
z 0n z*
0n z
6.0 hAZARDS PAGE53OF2O7 REVISION 30 6.0 HAZARDS
-'TOXICGASES REVISION 30
,6.0 HAZARDS PAGE 53 OF 207 -
EPIP-1 SECTION II EVENT CLASSIFICATION MATRIX' 6.0 HAZARDS EMERGENCY' CLASSIFICATION PROCEDURE' 1
CURVES/TABLES:
TABLE 6.516.6 APPLICABLE PLANT AREA, REACTOR BUILDINGS REFUEL FLOOR CONTROL BAY DIESEL GENERATOR BUILDINGS TURBINE BUILDING INTAKE PUMPING STATION
, RADWASTE BUILDING CABLE TUNNEL (INTAKE TO TURBINE BUILDING)
STANDBY GAS TREATMENT BUILDING PAGE 54 OF 207 -6 NOTES:
I REVISION 30 6.0 HAZARDS
EMERGENCY CLASSIFICATION PROCEDURE EPIP-1 '"
SECTION II EVENT CLASSIFICATION MATRIX6.
A A
AS DESCRIPTION DESCRIPTION EITHER of the followiang conditions exists Release of flammable gas within the site boundary in concentrations at or above 25% of the Lower Explosive Limit (LEL) for any three readings obtained in a 10 ft triangular area as indicated by Fire Protection or Industrial Safety personnel using appropriate monitonng instrumentation Confirmed report bý Local, County, or State Officials that a large offsite flammable gas release has occurred vithin one mile of the site with potential to enter the site boundary in concentrations at or above 25% of the Lover Explosive Limit (LEL)
OPERATING CONDITION
-All 6.6-A K Release of flammable gases within any building or sti'ucture listed in Table 6 5/6.6 in concentrations at or above 25% of the Lower Explosive Limit (LEL) for any three readings obtained in a 10 ft triangular area as indicated by Fire Protection or Industrial Safety personnel using appropriate monitoring instrumentation OPERATING CONDITION
-All tt~
zt 0
MT 6.0 HAZARDS PAGE 55 OF 207..;
REVISION 30 6.0 HAZARDS REVISION 30 o 6.0 HAZARDS PAGE 55 OF 207-.-
EPIP-1 -ý :
SECTION HI EVENT CLASSIFICATION MATRIX 6.0 HAZARDS EMERGENCY CLASSIFICATION PROCEDURE "
CURVES/TABLES:
IJ PAGE 56 OF 207 NOTES:
REVISION 30 6.0 HAZARDS
EMERGENCY' CLASSIFICATION PROCEDURE EPIP-1 "
SECTION II EVENT CLASSIFICATIONWMATRIX "
"6.0 HAZARDS SECURIT DESCRIPTION DESCIV"1IIJIN 6.7-U ANY of the followning conditions exist:
Bomb device discovered -within the plant protected area but NOT within a vital area Attempted or imminent attempt by a hostile force to penetrate the plant protected area barrier SCivil disturbance ongoing on the owner controlled property outside the protected area that threatens to interrupt plant operations Hostage/Extortion situation that threatens to interrupt plant operations A credible site-specific security threat notification OPERATING CONDITION
-All 6.7-A Bomb device discovered within ANY plant vital area OR Actual intrusion into the plant protected area by a hostile force.
OPERATING CONDITION
-All 6.7-S Intrusion into ANY plant vital area by a hostile force.
OPERATING CONDITION
-All 6.7-G Intrusion by a hostile force into Control Rooms, backup control areas, or plant vital areas which results in a loss of physical control of equipment or functions required to reach and maintain safe shutdown or remove decay heat from any unit.
OPERATING CONDITION:
-All Iz
-1 I
REVISION 30
' 6.0 HAZARDS PAGE -57 OF 207
EPIP-1 SECTION II EVENT CLASSIFICATION MATRIX 6.d HAZARDS EMERGENCY CLASSIFICATION PROCEDUREV -,
NOTES:
CURVES/TABLES:
PAGE 58 OF 207 i
REVISION 30 6.0 HAZARDS
EMERGENCY
,CLASSIFICATION PROCEDURE,,-
EPIP-1."
SECTION II,,
EVENT CLASSIFICATION MATRIX
-6.0 HAZARDS DESCRIPTION DESCRIPTION 6.8-U I
Vehicle crash (for example; aircraft or barge) into plant structures or systems within the protected area boundary.
OPERATING CONDITION
-All C1 M
6.8-A Vehicle crash (for example, aircraft or barge) into ANY Plant vital area.
OPERATING CONDITION
-All t,'
,REVISION 30 PAGE 59 OF 207 :,
,- 6.0 HAZARDS
EPIP-1 SECTION II EVENT'CLASSIFICATION MATRIX"-'
'6.0 HAZARDS EMERGENCY CLASSIFICATION PROCEDURE,)-ý4 THIS PAGE INTENTIONALLY BLANK PAGE 60 OF 207 L-REVISION 30 6.0 HAZARDS
EMERGENCY CLASSIFICATION PROCEDURE EPIP-I SECTION III TECHNICAL BASIS TECHNICAL BASIS 6.0 HAZARDS
-,a2 40;
-r t-
%I-#.
HAZARD S 6.0 PAGE 155 OF 207 6.0 HAZARDS 6.0 HAZARDS REVISION 30
EMERGENCY CLASSIFICATION PROCEDURE EPIP-1 SECTION III TECHNICAL BASIS 6.0 HAZARDS UNUSUAL EVENT Valid, unexpected increase of ANY in plant Area Radiation Monitor (ARM) reading to 1000 mrem/hr (except TIP Room).
OPERATING All CONDITION BASIS This event classification addresses unexpected increases in plant radiation levels that represent a degradation in the control of radioactive material, and constitute a potential degradation in the level of safety of the plant.
The term valid means that the instrument reading can be confirmed by other plant instrumentation indications, is consistent with an on-going transient or unplanned event, or that the condition is verified by RADCON. The term unexpected implies an increase not attributable to an anticipated transient such as a radwaste resin transfer, radiography, calibration activity, etc.
The Control Room is not included because it is an area which requires continuous occupancy and is covered under event classification 6.1-A 2. The TIP Room is not included because high ARM readings may not necessarily indicate a degradation in the control of radioactive materials and no personnel actions are required in the TIP area to safely shutdown the plant or maintain safe shutdown Escalation to Alert is based on operations required in the affected area(s) to safely shutdown the plant or maintain safe shutdown.
REFERENCES Reg Guide 1.101 Rev. 3, (NUMARC-AU2 EXAMPLE 4)
RIMS R38 940916 970 EOI Program Manual, Section V-E PAGE 156 OF 207 REVISION 30 6.0 HAZARDS
EMERGENCY EPIP-1 CLASSIFICATION SECTION III PROCEDURE TECHNICAL BASIS 6.0 HAZARDS
--1.
ALERT Valid, unexpected increase of ANY in plant Area Radiation Monitor (ARM) reading to 1000 mrem/hr (except TIP Room)
AND Personnel actions required in the affected area(s).
OPERATING All CONDITION BASIS This event classification addresses increased radiation levels that may impede necessary access to critical operating areas when conditions necessitate equipment operation or maintenance in those areas in order to maintain safe operation or achieve safe shutdown The impaired ability to perform inplant operations represents an actual or potential degradation in the level of safety of the plant. It is appropriate to ensure that additional personnel are onsite to perform necessary operations and maintenance and provide proper approvals, surveys, and radiation protection; therefore, the alert classification is justified The term valid means that the instrument reading can be confirmed by other plant instrumentation indications or is verified by RADCON.
The term unexpected implies an increase not attributable to an anticipated transient such as a radwaste resin transfer, radiography, calibration activity, etc.
The Control Room is not included because it is an area which requires continuous occupancy and is covered under event classification 6.1-A.2. The TIP Room is not included because no personnel actions are required in the area to safely shutdown the plant or maintain safe shutdown.
Escalation to Site Area Emergency or General Emergency is based on Secondary Containment radiation, radiological release, or fission product barrier event classifications.
PAGE 157 OF 207 REVISION 30 6.0 HAZARDS
EMERGENCY CLASSIFICATION PROCEDURE EPIP-1 SECTION III TECHNICAL BASIS 6.0 HAZARDS ALERT (CONTINUED)
REFERENCES Reg Guide 1.101 Rev. 3, (NUMARC-AA3 EXAMPLE 2)
RIMS R38 940916 970 EOI Program Manual, Section V-E PAGE 158 OF 207 REVISION 30 6.0 HAZARDS
EMERGENCY CLASSIFICATION PROCEDURE EPIP-1 SECTION III TECHNICAL BASIS 6.0 HAZARDS ALERT Control Room radiation levels >15 mrem/hr.
OPERATING CONDITION BASIS All This event classification applies to areas requiring continuous occupancy to maintain safe operation or safely shutdown the plant.
At Browns Ferry the Control Room is the only area within the plant that should require continuous manning under these conditions. Other areas (e.g, TSC, OSC) can be relocated to an area of lower dose. Radwaste operations can be suspended and the Radwaste Control Room can be evacuated. The Central Alarm Station (CAS) is not included because of the location at the plant entrance away from the main building.
It would not be possible to achieve these levels at the CAS without already reaching alert classification through radiological release.
This event classification may be redundant to fission product barrier and radiological release event classifications; however the cause of the event is not a concern. This event classification is only intended to address exposures to personnel who must be present at required operating stations for long term operation.
Escalation to Site Area Emergency or General Emergency is based Containment radiation, radiological release, or fission product classifications.
REFERENCES on Secondary barrier event Reg Guide 1.101 Rev. 3, (NUMARC-AA3 EXAMPLE 1)
PAGE 159 OF 207 REVISION 30 6.0 HAZARDS
EMERGENCY CLASSIFICATION PROCEDURE EPIP-1 SECTION III TECHNICAL BASIS TECHNICAL BASIS 6.0 HAZARDS S
'0
'06 A
A 5
A ALERT Control Room Abandonment from entry into AOI-100-2 or SSI-16 for ANY Unit Control Room.
OPERATING All
.CONDITION BASIS With the control room evacuated, additional support, monitoring, and direction through the Technical Support Center and/or other Emergency Operations Centers may be necessary The Alert declaration ensures centers are manned to provide the necessary additional support.
Escalation to Site Area Emergency is based on inability to establish plant control from outside the control room within 20 minutes.
REFERENCES Reg Guide 1.101 Rev. 3, (NUMARC-HA5)
PAGE 160 OF 207
'4' 6.0 HAZARDS REVI1SION 30 6.0 HAZARDS
PAGE 161 OF 207 EMERGENCY EPIP-1 CLASSIFICATION SECTION III PROCEDURE TECHNICAL BASIS 6.0 HAZARDS SITE AREA EMERGENCY Control Room Abandonment from entry into AOI-100-2 or SSI-16 for ANY Unit Control Room.
AND Control of Reactor water level, Reactor pressure, and Reactor power (for Modes 1,2, & 3) or decay heat removal (for Modes 4 & 5) per AOI-100-2 or SSI-16, as applicable, CANNOT be established within 20 minutes after evacuation is initiated.
OPERATING All CONDITION BASIS This event classification is intended to recognize loss of control of critical parameters either by failure of equipment designed to automatically initiate for control of the parameter or failure to expeditiously transfer safety system control to the backup controls. Fission product barrier damage may not yet be indicated but should be considered by assessing available parameters versus the status of safety systems and the ability to control critical parameters In Mode 4 and Mode 5 operator concern should be directed towards maintaining core cooling using decay heat removal systems In power operation, hot standby, and hot shutdown operator concern is primarily directed toward maintaining critical parameters, (i e.,
level, pressure, power, and heat sink) and thereby assuring fission product barrier integrity.
The 20 minute time period is based on time required for personnel to leave the control room, arrive at the appropriate backup control station, and take control of critical parameters before core uncovery or core damage has occurred This timeframe has been projected within the Tennessee Valley Authority, Browns Ferry Nuclear Plant, Fire Protection Report - Unit 2 and 3. During execution of procedures and transfer of equipment control, the listed critical parameters may be considered as being controlled if the parameters can be verified as being maintained within safe value ranges by appropriate equipment and automatic initiation functions designed to control the parameter (example: HPCI auto initiated and raised RPV level to a value above the initiation setpoint.).
Escalation to General Emergency is by fission product barrier degradation radioactivity release, or Emergency Director Judgement event classification REVISION 30 6.0 HAZARDS
EMERGENCY CLASSIFICATION PROCEDURE EPIP-1 SECTION III TECHNICAL BASIS TECHNICAL BASIS 6.0 HAZARDS SITE AREA EMERGENCY (CONTINUED)
REFERENCES Reg Guide 1.101 Rev. 3, (NUMARC-HS2)
Fire Protection Report Units 2 and 3 PAGE 162 OF 207 6.0 HAZARDS 6.0 HAZARDS REVTISION 30
EMERGENCY CLASSIFICATION PROCEDURE EPIP-1 SECTION III TECHNICAL BASIS 6.0 HAZARDS UNUSUAL EVENT Turbine failure resulting in casing penetration OR Significant damage to Turbine or Generator seals during operation.
OPERATING Mode I CONDITION Mode 2 BASIS This event classification is intended to address Main Turbine rotating component failures of sufficient magnitude to cause observable damages to the Turbine casing or to the seals of the Turbine or Generator. Of major concern is the potential for leakage of combustible fluids (lubricating oil) and gases (hydrogen) into the plant and environs Actual fires and flammable gas buildup are classified under other event classification This event classification is consistent with unusual event while maintaining the anticipatory nature desired and recognizing the risk to nonsafety related equipment.
Escalation to higher event classification is based on potential damage to safety related equipment from missiles generated by the failure or by radioactivity release.
REFERENCES Reg Guide 1.101 Rev. 3, (NUMARC-HU1 EXAMPLE 6)
PAGE 163 OF 207 REVISION 30 6.0 HAZARDS
EMERGENCY CLASSIFICATION PROCEDURE EPIP-1 SECTION III TECHNICAL BASIS 6.0 HAZARDS ALERT Turbine failure resulting in visible structural damage to or penetration of ANY of the following structures from missiles:
"* Reactor Building
"* Diesel Generator Building
"* Intake Structures
"* Control Bay OPERATING Mode I CONDITION Mode 2 BASIS This event classification is intended to address the threat to safety-related equipment imposed by missiles generated by Main Turbine rotating component failures Areas included are plant areas containing safety related equipment required to safely operate or safely shutdown the plant. The Alert classification assures adequate personnel are available to perform thorough assessment of damage to structures and equipment in the affected areas.
Escalation to higher event classification is based on system malfunction, fission product barrier degradation, radioactivity release, or Emergency Director Judgement event classifications.
REFERENCES Reg Guide 1.101 Rev. 3, (NUMARC-HA 1 EXAMPLE 6)
PAGE 164 OF 207 REVISION 30 6.0 HAZARDS
EMERGENCY CLASSIFICATION PROCEDURE EPIP-1 SECTION III TECHNICAL BASIS 6.0 HAZARDS UNUSUAL EVENT Confirmed fire in ANY plant area listed in Table 6.4-U1 AND NOT extinguished within 15 minutes.
OPERATING All CONDITION BASIS The purpose of this event classification is to address the magnitude and extent of fires that may be potentially significant precursors to damage to safety systems.
This excludes such items as fires within administration buildings, waste basket fires, and other small fires with no safety significance. This event classification applies to plant vital areas, buildings and areas contiguous to plant vital areas, or areas which have the potential to cause significant release of radioactive material such as Radwaste. These areas are included in Table 6.4-U1.
Confirmation of fire includes those actions listed in the appropriate Alarm Response Procedure (ARP) to verify the alarm is not spurious or by visual observation by personnel in the field.
If confirmation cannot be positively ascertained within -15 minutes and symptoms indicative of a fire persists then confirmation should be assumed and this event classification declared Allowance of fifteen minutes for extinguishment is provided to exclude small fires, easily extinguishable, with no significant safety consequence.
Escalation to Alert is based on fire affecting the operability of plant safety systems required for the current operating condition.
REFERENCES Reg Guide 1.101 Rev. 3, (NUMARC-HU2)
Browns Ferry Nuclear Plant Safe Shutdown Program PAGE 165 OF 207 REVISION 30 6.0 HAZARDS
EMERGENCY CLASSIFICATION PROCEDURE EPIP-I SECTION III TECHNICAL BASIS TECHNICAL BASIS 6.0 HAZARDS UNUSUAL EVENT (CONTINUED)
CURVES/TABLES TABLE 6.4-Ul[
APPLICABLE PLANT AREA REACTOR BUILDING REFUEL FLOOR 4KV SHUTDOWN BOARD ROOMS 4KV SHUTDOWN BOARD BATTERY ROOMS 480V SHUTDOWN BOARD ROOMS 3A and 3B RMOV BOARD ROOMS 4KV BUS TIE BOARD ROOM CONTROL BAY ELEVATION 593'. 606' and 617' DIESEL GENERATOR BUILDINGS (ALL ELEVATIONS)
TURBINE BUILDING (ALL ELEVATIONS IN OR ADJACENT TO AREAS CONTAINING SAFE SHUTDOWN EQUIPMENT INTAKE PUMPING STATION (ALL ELEVATIONS)
RADWASTE BUILDING (ALL ELEVATIONS)
CABLE TUNNEL (INTAKE TO TURBINE BUILDING)
STANDBY GAS TREATMENT BUILDING PAGE 166 OF 207 6.0 HAZARDS REVISION 30 6.0 HAZARDS
EMERGENCY CLASSIFICATION PROCEDURE EPIP-1 SECTION II1 TECHNICAL BASIS PROCEDUBSIR60EAZRD UNUSUAL EVENT Unanticipated explosion within the protected area resulting in visible damage to ANY permanent structure or equipment.
OPERATING CONDITION BASIS REFERENCI r
All The purpose of this event classification is to recognize only those explosions of sufficient force to damage permanent structures or equipment within the protected area.
An explosion is defined as rapid, violent, unconfined combustion, or a catastrophic failure of pressurized equipment that potentially imparts significant energy to nearby structures and materials.
This event classification makes no attempt to assess the actual magnitude of the damage.
The occurrence of the explosion with reports of evidence of damage (e.g., deformation and scorching) is sufficient for declaration. The Site Emergency Director also needs to consider any security aspects of the explosion if applicable.
Escalation to Alert is based on explosion affecting safety system performance or causing visible damage to structures or equipment required for safe shutdown.
ES Reg Guide 1.101 Rev. 3, (NUMARC-HUI EXAMPLE 5)
PAGE 167 OF 207 ow"RiT 6.0 HAZARDS REVISION 30 6.0 HAZARDS
EMERGENCY EPIP-1 CLASSIFICATION SECTION III PROCEDURE TECHNICAL BASIS 6.0 HAZARDS ALERT Fire or explosion in ANY plant area listed in Table 6.4-A affecting safety system performance OR Fire or explosion causing visible damage to permanent structures or safety systems in ANY area listed in Table 6.4-A.
OPERATING All CONDITION BASIS This event classification is intended to address the magnitude and extent of fires that potentially or actually affect one or more redundant trains of safety systems or structures containing safety systems. Areas listed in Table 6.4-A are those plant areas that contain systems or functions required for the safe shutdown of the plant.
With regard to explosions, only those explosions of sufficient force to damage permanent structures or equipment required for safe operation within the identified plant area should be considered.
An explosion is defined as a rapid, violent, unconfined combustion, or a catastrophic failure of pressurized equipment that potentially imparts significant energy to nearby structures and materials.
The occurrence of an explosion with reports of visible damage is sufficient evidence for determination of this event. No attempt should be made to perform a detailed assessment before declaration is considered. Declaration of Alert with subsequent manning of support personnel will provide adequate personnel to make a detailed assessment.
The Site Emergency Director should also consider any security aspects of the explosion.
Escalation to Site Area Emergency is based on system malfunction, fission product barrier degradation, radioactivity release, or Emergency Director Judgement.
PAGE 168 OF 207 REVISION 30 6.0 HAZARDS
EMERGENCY CLASSIFICATION PROCEDURE EPIP-1 SECTION III TECHNICAL BASIS TECHNICAL BASIS 6.0 HAZARDS ALERT (CONTINUED)
REFERENCES Reg Guide 1.101 Rev. 3, (NUMARC-HA2)
Browns Ferry Nuclear Plant Safe Shutdown Program CURVES/TABLES TABLE 6.4-A APPLICABLE PLANT AREA REACTOR BUILDING REFUEL FLOOR 4KV SHUTDOWN BOARD ROOMS 4KV SHUTDOWN BOARD BATTERY ROOMS 480V SHUTDOWN BOARD ROOMS 3A and 3B RMOV BOARD ROOMS 4KV BUS TIE BOARD ROOM CONTROL BAY ELEVATION 593'. 606' and 617' DIESEL GENERATOR BUILDINGS (ALL ELEVATIONS)
INTAKE PUMPING STATION (ALL ELEVATIONS)
CABLE TUNNEL (INTAKE TO TURBINE BUILDING)
STANDBY GAS TREATMENT BUILDING PAGE 169 OF 207 6.0 HAZARDS REVISION 30 6.0 HAZARDS
EMERGENCY CLASSIFICATION PROCEDURE EPIP-1 SECTION MI TECHNICAL BASIS 6.0 HAZARDS UNUSUAL EVENT EITHER of the following conditions exists:
- Normal operations impeded due to access restrictions caused by toxic gas concentrations within any building or structure listed in Table 6.5/6.6.
Confirmed report by Local, County, or State Officials that a large offsite toxic gas release has occurred within one mile of the site with potential to enter the site boundary in concentrations at or above the Permissible Exposure Limit (PEL) causing an evacuation of any site personnel.
OPERATING All CONDITION BASIS This event classification is based on significant releases of toxic gases that could affect the health and safety of plant personnel or affect the safe operation of the plant with the plant being within the evacuation area of an offsite event (i.e., tanker truck or barge accident releasing toxic or flammable gas, etc.). The evacuation area is determined from the Department of Transportation (DOT) Evacuation Tables for selected hazardous materials, in the DOT Emergency Response Guide for hazardous materials.
Table 6.5/6.6 contains plant vital areas, buildings and areas contiguous to plant vital areas, and other significant plant buildings or structures where operations may be required to assure safe operation of the plant.
Escalation to Alert is based on gases entering plant structures and affecting safe operation of the plant REFERENCES Reg Guide 1.101 Rev. 3, (NUMARC-HU3)
REVISION 30 PAGE 170 OF 207 M3. :¶!'
6.0 HAZARDS
EMERGENCY CLASSIFICATION PROCEDURE EPIP-1 SECTION III TECHNICAL BASIS TECHNICAL BASIS 6.0 HAZARDS UNUSUAL EVENT (CONTINUED)
CURVES/TABLES STANDBY GAS TREATMENT BUILDING PAGE 171 OF 207 TABLE 6.5/6.6 APPLICABLE PLANT AREA REACTOR BUILDINGS REFUEL FLOOR CONTROL BAY DIESEL GENERATOR BUILDINGS TURBINE BUILDING INTAKE PUMPING STATION RADWASTE BUILDING CABLE TUNNEL (INTAKE TO TURBINE BUILDING) 6.0 HAZARDS REVISION 30 6.0 HAZARDS
EMERGENCY CLASSIFICATION PROCEDURE EPIP-1 SECTION III TECHNICAL BASIS 6.0 HAZARDS N44 ALERT ALL of the following conditions exists:
- Plant personnel report toxic gas within any building or structure listed in Table 6.5/6.6.
Plant personnel report severe adverse health reactions due to toxic gas (i.e., burning eyes, throat, or dizziness)
OR Sampling results by Fire Protection or Industrial Safety personnel indicate levels above the Permissible Exposure Limit (PEL).
Determination by the Site Emergency Director that plant personnel would be unable to perform actions necessary to establish and maintain Mode 4 conditions while utilizing appropriate personnel protective equipment.
OPERATING All CONDITION BASIS This event classification is based on toxic gases that have entered a plant structure affecting safe operation of the plant. This event classification applies to buildings and areas contiguous to plant vital areas or other significant buildings or areas (i e.,
intake and Standby Gas Treatment buildings)
The intent of this event classification is not to include buildings (i.e, warehouses and administration buildings) or other areas that are not contiguous or immediately adjacent to plant vital areas It is appropriate that increased monitoring be performed to ascertain whether consequential damage has occurred Escalation to higher emergency class is based on system malfunction, fission product barrier degradation, radioactivity release, or Emergency Director Judgement event classification.
PAGE 172 OF 207 REVISION 30 6.0 HAZARDS
EMERGENCY CLASSIFICATION PROCEDURE EPIP-1 SECTION III TECHNICAL BASIS TECHNICAL BASIS 6.0 HAZARDS ALERT (CONTINUED)
REFERENCES CURVES/TABLES Reg Guide 1.101 Rev. 3, (NUMARC-HA3)
STANDBY GAS TREATMENT BUILDING PAGE 173 OF 207 TABLE 6.516.6 APPLICABLE PLANT AREA REACTOR BUILDINGS REFUEL FLOOR CONTROL BAY DIESEL GENERATOR BUILDINGS TURBINE BUILDING INTAKE PUMPING STATION RADWASTE BUILDING CABLE TUNNEL (INTAKE TO TURBINE BUILDING) 6.0 HAZARDS REVISION 30 6.0 HAZARDS
EMERGENCY CLASSIFICATION PROCEDURE EPIP-1 SECTION III TECHNICAL BASIS 6.0 HAZARDS UNUSUAL EVENT EITHER of the following conditions exists:
Release of flammable gas within the site boundary in concentrations at or above 25% of the Lower Explosive Limit (LEL) for any three readings obtained in a 10 ft. triangular area as indicated by Fire Protection or Industrial Safety personnel using appropriate monitoring instrumentation.
Confirmed report by Local, County, or State Officials that a large offsite flammable gas release has occurred within one mile of the site with potential to enter the site boundary in concentrations at or above 25% of the Lower Explosive Limit (LEL).
OPERATING All CONDITION BASIS This event classification is based on significant releases of flammable gases that could affect the safe operation of the plant with the plant being within the evacuation area of an offsite event (i.e., tanker truck or barge accident releasing toxic or flammable gas, etc.).
The evacuation area is determined from the Department of Transportation (DOT) Evacuation Tables for selected hazardous materials, in the DOT Emergency Response Guide for hazardous materials.
Escalation to Alert is based on flammable gases entering plant structures and affecting safe operation of the plant.
REFERENCES Reg Guide 1.101 Rev. 3, (NUMARC-HU3)
PAGE 174 OF 207 REVISION 30 6.0 HAZARDS
EMERGENCY CLASSIFICATION PROCEDURE EPIP-1 SECTION mI TECHNICAL BASIS 6.0 HAZARDS
T:
'
ALERT-Release of flammable gases within any building or structure listed in Table 6.5/6.6 in concentrations at or above 25% of the Lower Explosive Limit (LEL) for any three readings obtained in a 10 ft. triangular area as indicated by Fire Protection of Industrial Safety personnel using appropriate monitoring instrumentation.
OPERATING All CONDITION BASIS This event classification is based on flammable gases that have entered a plant structure with potential to affect safe operation of the plant.
This event classification applies to buildings and areas contiguous to plant vital areas or other significant buildings or areas (i.e., intake and Standby Gas Treatment buildings).
The intent of this event classification is not to include buildings (i.e., warehouses and administration buildings) or other areas that are not contiguous or immediately adjacent to plant vital areas.
It is appropriate that increased monitoring be performed to ascertain whether consequential damage has occurred.
Escalation to higher emergency class is based on system malfunction, fission product barrier degradation, radioactivity release, or Emergency Director Judgement event classification REFERENCES Reg Guide 1.101 Rev. 3, (NUMARC-HA3 EXAMPLE 1&2)
PAGE 175 OF 207 REVISION 30 6.0 HAZARDS
EMERGENCY CLASSIFICATION PROCEDURE EPIP-1 SECTION III TECHNICAL BASIS TECHNICAL BASIS 6.0 HAZARDS ALERT (CONTINUED)
CURVES/TABLES STANDBY GAS TREATMENT BUILDING PAGE 176 OF 207 7"
TABLE 6.5/6.6 APPLICABLE PLANT AREA REACTOR BUILDINGS REFUEL FLOOR CONTROL BAY DIESEL GENERATOR BUILDINGS TURBINE BUILDING INTAKE PUMPING STATION RADWASTE BUILDING CABLE TUNNEL (INTAKE TO TURBINE BUILDING) 6.0 HAZARDS 6.0 HAZARDS REVISION 30
EMERGENCY EPIP-1 CLASSIFICATION SECTION III PROCEDURE TECHNICAL BASIS 6.0 HAZARDS UNUSUAL EVENT ANY of the following conditions exists:
0 Bomb device discovered within the plant protected area but NOT within a vital area.
9 Attempted or imminent attempt by a hostile force to penetrate the plant protected area barrier.
- Civil disturbance ongoing on the owner controlled property outside the protected area that threatens to interrupt plant operations.
0 Hostage/Extortion situation that threatens to interrupt plant operations.
- A credible site-specific security threat notification OPERATING All CONDITION BASIS This event classification represents a potential degradation in the level of safety of the plant due to potential damage to permanent plant structures, intrusion or attempted intrusion of the protected area or disturbance that may affect plant operations; therefore, the Unusual Event classification is appropriate For the purposes of this event classification the following definitions apply:
Civil Disturbance - A group of 20 or more persons violently protesting station operations or activities at the site; Extortion - An attempt to cause an action at the station by threat or force; Hostage - Person(s) held as leverage against the station to ensure that demands will be met by the station.
A credible site-specific security information has been received.
The intent of"a credible site-specific security notification" is to ensure that appropriate notifications are made on a timely manner. Only the plant to which the specific threat is made need declare the Notification of Unusual Event.
The determination of "credible" is made by senior plant management through use of information found in the Safeguards Contingency Plan Escalation to Alert is based on bomb device being discovered within a plant vital area or actual intrusion into the plant protected area by a hostile force.
REFERENCES Reg Guide 1.101 Rev. 3, (NUMARC-HU4 EXAMPLE 1 & 2)
Browns Ferry Physical Security/Contingency Plan PAGE 177 OF 207 REVISION 30 6.0 HAZARDS
EMERGENCY CLASSIFICATION PROCEDURE EPIP-1 SECTION III TECHNICAL BASIS 6.0 HAZARDS ALERT Bomb device discovered within ANY plant vital area OR Actual intrusion into the plant protected area by a hostile force.
OPERATING All CONDITION BASIS The first part of this event classification represents a potential substantial degradation in the level of safety of the plant due to the threat to vital safety systems.
Actual discovery of the device is required to meet this classification.
Any detonation of an explosive device could result in declaration under Fire/Explosion event classifications.
The second part of this event classification represents a substantial degradation in the level of safety of the plant due to the extreme measures that must be taken by an intruder to enter the protected area. Hostile intent must be suspected to meet this classification A civil disturbance which penetrates the protected area boundary can be considered a hostile force Escalation is by actual intrusion into a vital area by a hostile force.
REFERENCES Reg Guide 1.101 Rev. 3, (NUMARC-HA4 EXAMPLE 1 & 2)
Browns Ferry Physical Security/Contingency Plan PAGE 178 OF 207 REVISION 30 6.0 HAZARDS
EMERGENCY CLASSIFICATION PROCEDURE EPIP-1 SECTION III TECHNICAL BASIS 6.0 HAZARDS SITE AREA EMERGENCY Intrusion into ANY plant vital area by a hostile force.
OPERATING All CONDITION BASIS This event represents a substantial degradation in the level of safety of the plant due to the extreme measures that must be taken by an intruder to enter a vital area Hostile intent must be suspected to meet this classification. This event represents a possible threat to the public and an escalated threat to plant safety above that contained in the Alert event classification in that a hostile force has progressed from the protected area to the vital area.
Escalation is by actions occurring involving a hostile force which results in a loss of physical control of equipment or functions required to reach and maintain safe shutdown or remove decay heat from any unit.
REFERENCES Reg Guide 1.101 Rev. 3, (NUMARC-HS1 EXAMPLE 1)
PAGE 179 OF 207 li,-
AC-4i REVISION 30 6.0 HAZARDS
EMERGENCY CLASSIFICATION PROCEDURE EPIP-1 SECTION III TECHNICAL BASIS 6.0 HAZARDS GENERAL EMERGENCY Intrusion by a hostile force into Control Rooms, backup control areas, or plant vital areas which results in a loss of physical control of equipment or functions required to reach and maintain safe shutdown or remove decay heat from any unit.
OPERATING All CONDITION BASIS This event represents an extreme threat to the safety of the plant and possible substantial threat to the public. This event encompasses conditions under which a hostile force has taken physical control of vital areas required to reach and maintain safe shutdown.
REFERENCES Reg Guide 1.101 Rev. 3, (NUMARC-HG1 EXAMPLE I & 2)
PAGE 180 OF 207 REVISION 30 6.0 HAZARDS
EMERGENCY CLASSIFICATION PROCEDURE EPLP-1 SECTION III TECHNICAL BASIS TECHNICAL BASIS 6.0 HAZARDS
'A sqb UNUSUAL EVENT Vehicle crash (for example; aircraft or barge) into plant structures or systems within the protected area boundary.
OPERATING CONDITION BASIS REFERENC r
All This event classification is intended to address such items as plane, helicopter, or barge crash that may potentially damage plant structures containing functions and systems required for safe shutdown of the plant The crash should be of sufficient impact to cause structural damage to a plant system or structure Visual observation of structural damage is sufficient to trigger this event classification.
Escalation to higher emergency class is based on crash into any plant area affecting equipment required for safe shutdown or by system malfunction event classifications.
ES Reg Guide 1.101 Rev. 3, (NUMARC-HUI EXAMPLE 4)
PAGE 181 OF 207 6.0 HAZARDS REVISION 30 6.0 HAZARDS
EMERGENCY CLASSIFICATION PROCEDURE EPIP-1 SECTION I1 TECHNICAL BASIS 6.0 HAZARDS ALERT Vehicle crash (for example; aircraft or barge) into ANY Plant vital area.
OPERATING All CONDITION BASIS This event classification is intended to address such items as plane, helicopter, or barge crash into a plant vital area. In cases where structural damage has occurred it may be assumed that the area and associated equipment has been subjected to forces beyond design limits and thus damage may be assumed to have occurred to plant safety systems.
It should not be interpreted that a lengthy damage assessment is necessary prior to classification. Declaration of Alert with subsequent manning of support personnel will provide adequate personnel to make a detailed assessment.
The Site Emergency Director should also consider any security aspects of the crash.
Escalation to higher emergency classification is based on system malfunction, fission product barrier degradation, radioactivity release, or Emergency Director Judgement event classification.
REFERENCES Reg Guide 1.101 Rev. 3, (NUMARC-HA1 EXAMPLE 5)
PAGE 182 OF 207 6.0 HAZARDS REVISION 30
PREPARED BY: T W. CORNELIUS PHONE. 2038 RESPONSIBLE ORGANIZATION: EMERGENCY PREPAREDNESS APPROVED BY: GILBERT LITTLE DATE: 07/22/2002 EFFECTIVE DATE: 07/30/2002 LEVEL OF USE: REFERENCE USE QUALITY-RELATED TENNESSEE VALLEY AUTHORITY
'-**"ffDWNS FERRY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-2 NOTIFICATION OF UNUSUAL EVENT REVISION 23
REVISION LOG Procedure Number:
EPIP-2..
Revision Number: 23 Pages Affected: 2,3,4,7,11 Description of Change:
IC-27 Tins change is being conducted to incorporate the management of NRC Commitment changes as prescribed in the correspondence from site licensing RIMS R08000217713. to remo% e the Public Information Officer from the notification form and to human factor the notification and folloNN -up notification forms Page 2 - change to step 3.1.1 involves human factoring the Notification Formn Title Page 7 - changes inN ohles removing the -NRC Commitmnent Brackets to step requiring the review of PORC and the human factoring of applicable steps.
Page 7 - change invohN es human factoring attachment title.
Page 8 - change invol\\ es human factoring attachment title and modify mg information to ensure consistency Nxith NRC guidance.
Page 9 - change involves removing the Public Information Officer from the Attachment B notifications along with the NRC Commitment Brackets Page 10 - change mnvoh ed adding a clanfy statement concerning the appropriate use of the FolloNx up Notification Form.
IC-28 EPIP-2. re\\ ismon 23 is being issued to incorporate changes resulting from the letter. NEI to NRC (to Mr. Bruce A. Boger) dated December 18. 2001 requesting confinration for EAL basis change to include response to a Site-Specific Security Credible Threat. This letter was developed in response to the NRC's October 6. 2001 Safeguards Advisory. The change to this EPIP is a consequence to the EAL change. Under specific conditions this change Ni ill activate the ERO along Ni t1h assenubly/accountability. The revision also incorporates standardization of telephone numbers and actions taken by the Unit 1. Unit Operator during ERO staffing.
Page 2 - provide the action to staff the ERO wx hen a credible site security threat notification exists Page 3-provide the action to assembly/account site personnel for the purpose of establishing the
"'TNo Person (Line of Sight) Rule".
Page 4 - standardize the review of PORC for actual eents.
P a g e 7 - a d d a tta c h m e n t D.
I I I '
Page 11 - add attachment D. actions taken by the Unit 1 Unit operator to staff the ERO.
NOTIFICATION OF BROWNS FERRY UNUSUAL EVENT
_P
'-;"NUCLEAR PLANT 1.0 PURPOSE 1.1 Provide for timely nfotification of appropriate individuals or organizations when the
- ,Shift Manager has determined byEPIP-I -that an incident has occurredwhich is classified as a NOTIFICATION OF UNUSUAL EVENT.
1.2 Provide for periodic analysis of the current situation by the Shift Manger/Site Emergency Director (SED) lo determine whether the NOTIFICATION OF UNUSUAL EVENT should be terminated, continued, or upgraded to a more serious classification 2.0 SCOPE This procedure applies to emergency events that are classified as'a Notification of Unusual Event by EPIP-1, Emergency Classification Procedure I.
J°
,; I' A*-~A "PAGE 1 OF 12 1'
REVISION 23 1
NOTIFICATION OF UNUSUAL EVENT EPIP-2 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS 3.1 Notification of the Operations Duty Specialist (ODS)
Note: The ODS should be notified within 5 minutes after the emergency event is declared Date:
/
/
3.1.1 CompleteAttachment A (Initial Notification Form) 3.1.2 If the NOUE has been declared due to the Security Emergency Action Level (EAL) 6 7-U, "A credible site specific security threat notification", Then direct the Unit. 1, Unit Operator to implement Attachment'D, "Activation of the Emergency Paging System/Staffing of Emergency Responders".
3.1.3 Notify the ODS and Provide the information from Attachment A Note: Utilize the direct ring-down ODS phone when making this notification or as applicable dial direct.
ODS Telephone Numbers 5-751-1700 5-751-2495 If the ODS cannot be reached within 10 minutes, Then contact the State of Alabama directly by requesting the Rad Health Duty Officer at:
Day Shift 8 a.m. - 5 p.m.
9-1-334-206-5391 Holidays-Weekends-Offshifts 9-1-334-242-4378 3.1.4 Fax a copy of Attachment A to the ODS for confirmation of information or state if contacted directly ODS Fax 5-751-8620 AL Rad Health 9-1-334-206-5387 PAGE 2 OF 12 INITL.LS TL%1E INITLALS FLAIE I r,,1TLA LS FLMNE INITLMLS rife REVISION 23
NOTIFICATION OF UNUSUAL EVENT
.EPIP-2 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 0 t
I 3.1.5 Receive confirmation call from the ODS (to verify notification of the State of Alabama) (NA this step if the INTLALS State was contacted directly).
3.2 NOTIFICATION OF SITE PERSONNEL 3.2.1 Provide the Unit 1, Unit Operatornwith a completed copy of Attachment A 3.2.2 Direct theUUnit 1, Unit Operator to make notifications.
from Attachment.B (-Unit 1, Unit Operator Notifications), utilizing information from Attachment A.
3.2.3 Make the following plant P.A. announcement:
I.-ITLILS T1rE IN1TLS.LS TnfE "BINTLALS.
TLME THIS IS (NAME), SHIFT MANAGER. A
---,--,NOTIFICATION OF UNUSUAL EVENT HAS BEEN:
DECLARED ON UNIT I HAVEASSUM D
THE DUTIES OF SITE EMERGENCY DIRECTOR.
3.2.4 Notify the Plant Manager or alternate:
.I INITILLS CAUTION:
Do not initiate m
Ase'bly and Accountability if:
- 1.
A severe weather condition exist or projected on-site, such as a Tornado.
- 2.
A on-site security risk condition exists (Consult with Nuclear Security).
3.3 ACCOUNTABILITY 3.3.1 If the NOUE has been declared due to Security EAL, 6.7-U, and Nuclear Security recommends Accountability to establish the "Two Person (Line of Sight) Rule",
Then implement EPIP-8, Appendix C, for Assembly and Accountability only.
INMTrALS TnIE REVISION 23 1
TLME Star
'. r PAGE, 3 OF 12
NOTIFICATION OF UNUSUAL EVENT EPIP-2 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.4 OFFSITE DOSE ASSESSMENT 3.4.1 Evaluate the need for offsite dose assessment.
(N/A STEP IF NOT APPLICABLE) 3.4.1.1 When offsite dose assessment is required obtain the information from the CECC when operational.
3.4.1.2 If the CECC is not operational, contact the TSC, when staffed 'or the RADCON Shift Superisor and request the implementation ofdEPIP 14, for dose assessnient 3.5 NOTIFICATION OF THE NRC 3.5.1 Notify the NRC immediately or within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and if requested by the NRC maintain an open and continuous communications channel.
Note. Utilize the Emergency Notification System (ENS) when making this notification. Dial the first number listed-on, the sticker affixed to the ENS telephone, by dialing 9-1 "The Ten Dikt Number Listed on the ENS Telephones".
If the number is busy, Then select in order, the alternate numbers until a connection is achieved. No access codes are required.
INITLSLs LMiE BNTrLXLS TIME PAGE 4 OF 12 REVISION 23
NOTIFICATION OF BROWNS FERRY UNUSUAL EVENT
.EPIPr 2
rzNUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.6 PERIODIC EVALUATION OF THE EVENT 3.6.1 Continue to Evaluate the event by using EPIP-1 as conditions warrant.
3.6.2 If other EAL conditions exist indicating the current emergency classification or significant changes in plant conditions have'occurred since the last update to the ODS, and the CECC is not'staffed, ]j*ýj Complete the "Follow-Up" Notification Form (Attachment C), notify the ODS and provide the new information Utilize the direct ring-down ODS phone when making this notification or as applicable dial
--direct.
.ODS-5-751-1700 5-751-2495 Note If the ODS cannot be reached, Then contact the State of Alabama directly by requesting the Rad Health Duty Officer at:
Day Shift 8a.m. -5 p.m 9-1-334-206-5391 Holidays-Weekends-Offshifts 9-1-334-242-4378 3.6.3 If the conditions warrants upgrading' to a higher classifications, Then initiate the appropriate EPIP.
3.6.4 If the conditions warrant termination of the classification, Then enter the Termination section of this procedure at step 3.7.
3.6.5 Re-enter this procedural section as conditions warrant at step 3.6.1 or until directed to exit this procedure by steps 3 6.3 or 3.6.4.
REVISION 23 1
.iPAGE 5OF 12
NOTIFICATION OF UNUSUAL EVENT EPIP-2 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.7 TERMINATION OF THE EVENT If the situation no longer exists terminate the event and notify the following:
Date:
/
/
3.7.1 Notify the ODS of the termination of the emergency or the state directly if the ODS cannot be contacted.
3.7.2 Notify the NRC of the termination of the emergency.
3.7.3 Notify the Plant Manager or Alternate of the termination of the emergency.
3.7.4 Complete Attachment A by providing the time and date of termination.
3.7.4 Notify the Unit 1, Unit Operator. Provide the Unit 1, Unit Operator with the iermination timie and date and direct the Unit 1, Unit Operator to notify the individuals contacted on Attachment B of the termination of the emergency.
INITLALS TIME INITLALS TIME INTLALS TiNE IWiTIALS TIME INITIALS TimE PAGE 6 OF 12 REVISION 23
NOTIFICATION OF
'UNUSUAL'EVENT SEPIP-2 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.8 CLOSURE OF THE NOTIFICATION OF UNUSUAL EVENT 3.8.1 Upon termination of the'Notificati6n of Unus'al Event, the Shift Manager shall send the completed EPIP-2 and B mLS TImE all attachments to Emergency Preparedness (EP).
3.8.2 Upon receipt of completed EPIP-2 and all attachments,
-ThIE Emergency Preparedn~ss-shhll forward documents for?
the purpose of documentation storage.
4.0 ATTACHMENTS Attachment A - Initial Notification Form Notification of Unusual Event' Attachment B - Unit 1, Unit Operator Notifications Attachment C - Follow Up Information Form Notification of Unusual Event Attachment D - Activation of the Emergency Paging System (EPS)/Staffing of Emergency Responders I}
',
I 4" I
I
-'I A.-
- PAGE 7 OF 12 REVISION 23
NOTIFICATION OF BROWNS FERRY UNUSUAL EVENT EPIPr-2 NUCLEAR PLANT ATTACHMENT A (Page 1 of 1)
INITIAL NOTIFICATION FORM-NOTIFICATION OF UNUSUAL EVENT F-1 THIS IS AN ACTUAL EVENT F-1 THIS IS AN EXERCISE This is A NOTIFICATION OF UNUSUAL EVENT has been declared at Browns Ferry affecting:
[-- Unit 1
[I Unit 2
-' Unit 3
-' Common Event Declared:
Time:
Date EAL Designator:
Brief Description of the Event:
Radiological Conditions:
F-- No Abnormal Releases Offsite F-- Airborne Release Offsite
-- Liquid Release Offsite
-- Release Information Not Known at this time There is no Protective Action Recommendation at this time.
Ask,-"Please repeat the information you have received to ensure accuracy."
PAGE 8 OF 12 REVISION 23
NOTIFICATION OF UNUSUAL EVENT EPIP-2 BROWNS FERRY NUCLEAR PLANT ATTACHMENT.B (Page 1 of 1)
UNIT 1; UNITOPERATOR NOTIFICATIONS Date:
/
/
Note-All notifications should be made utilizing the information located on EPIP 2, Attachment A Received a completed copy of EPIP 2, Attachment A from the Site Emergency Director.
Personnel Notifications Notify the Operations Manager (from the weekly duty list)
Notify the Vice President (from the weekly duty list)
Notify the REP maniager (from the weekly duty list)
Notify the Nuclear Security Shift Supervisor Ext. 3150 or2219 Notify the NRC Resident Ext.
2573, or 2572 or from the weekly duty list
' Initial Notifications
'Termination N 4
I.
Initials Time Initials
'Tien Initials
Time.
Initials Time Initials Time Initials Ini1tials, Initials Initials 4f 1' 4 4
4 4 4 it 4
4 4
44 4
4 44 2
44444,44 44 4
4 4,
44 4
444 4
47",,
4 PAGE 9 OF 12 INITLMXS TIME Fotifications Time
%Time Initials Time Time Time I
REVISION 23
NOTIFICATION OF BROWNS FERRY EVENT rEPIP-2 NUCLEAR PLANT ATTACHMENT C (Page 1 of 1)
FOLLOW-UP INFORMATION FORMI NOTIFICATION OF UNUSUAL EVENT
["I THIS IS A REAL EVENT
-] THIS IS A DRILL Note: This form is for conducting Follow-up Information only.
This is at Browns Ferry Name There has been a NOTIFICATION OF UNUSUAL EVENT declared at Browns Ferry affecting:
n-Unit 1 EL Unit 2
'] Unit 3 El Common The Reactor is n-Shutdown Eli At Power Plant Conditions are -] Stable I Deteriorating "Follow-Up" Information (e.g., Key Events, Status Changes)
Current Radiological Conditions are:
-- No Abnormal Releases Offsite
[- Airborne Release Offsite L" Liquid Release Offsite
-- Release Information Not Known Additional Rad information: (e.g., release duration)
F1-There is no Protective Action Recommendation at this time.
Please repeat the information you have received to ensure accuracy The time for this follow up is:
Time:
Date:
SIGNATURE:
PAGE 10 OF 12 REVISION 23
NOTIFICATION OF
'UNUSUAL EVENT EPIPR-2 BROWNS FERRY NUCLEAR PLANT "ATTACHMENT D (Page 1 of 2)
-ACTIVATION OF THIE EMERGENCY PAGING SYSTEM (EPS) / STAFFING OF
- " EMERGENCY.RESPONDERS NOTES: (1) The Emergency Paging System consists of a dedicated touch screen CRT. Activation of any screen feature requires the user place their fingertip within the boundary of the select button and leave it there for at least 1 se 6nd, !The CRT Screen will normally display a large rectangle that indicates that the paging system is'available but currently inactive.
(2) If the EPS fails to operate, contact tie SM/SED immediately.,Request thht the ODS be contacted to initiate the system from his' bcation -'If the system fails to operate from the ODS area, then utilize the Weekly Duty List and Call-Ouit List to manually staff the Emergency Responders, implementing this attachment at step 5.:.
PRESS the EPS CRT Screen once to activate the paging options
- 2.
PRESS the appropriate option 0
0 0
PAGER TEST DRILL EMERGENCY ABORT PRESS the START Button to initiate the option or ABORT to deny the option request.
4 IMonitor the Paging System Terminal Display A
IF... A "NO" response is observed OR The position being paged has not responded within approximately 20 minutes THEN...Utilize the Weekly Duty List and attempt to contact the position representative with available information. (No Fitness for Duty Question Required)
B.
IF... The individual cannot be reached utilizing the Weekly Duty List THEN..Utilize the Call-Out List and attempt to contact an alternate position representative. (Fitness for Duty Question Reiqiired)
INITIALS TIME INITIALS TIME INITIALS TIME INITIALS TIME REVISION 23 1
1.
" PAGEll1OF 12
NOTIFICATION OF UNUSUAL EVENT EPIP-2 BROWNS FERRY NUCLEAR PLANT ATTACHMENT D (Page 2 of 2)
ACTIVATION OF THE EMERGENCY PAGING SYSTEM (EPS) / STAFFING OF 9 EMERGENCY RESPONDERS
- 5.
Manual Call-Out (N/A step if EPS operates normally)
A.
Utilize the current Weekly Duty List and contact positions as listed.,
B.
If a position can not be reached from the current Weekly Duty List, then refei" to the Call-Out List as applicable to fill all 'vacant positions.
INITIALS TIME
- 6.
CONTINUE until all positions have been filled INITIALS TIME LAST PAGE PAGE 12 OF 12 1 1--1)
REVISION 23
TENNESSEE VALLEY AUTHORITY BROWNS rEfatRYT E)XiffW".
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-3
'ALERTV REVISION 26 PREPARED BY: T. W. CORNELIUS RESPONSIBLE ORGANIZATION: EMERGENCY PREPAREDNESS APPROVED BY: GILBERT LITTLE EFFECTIVE DATE: 07/3012002 LEVEL OF USE: REFERENCE USE
-PHONE: 2038 DATE: 07/22/2002 QUALITY-RELATED I 1
.1.,
REVISION LOG Procedure Number:
EPIP-3 Revision Numbe-rv.-26 Avow" XWnw
ý Pages Affected: 3,16,8,9 Description of Change:
IC-30 This change is being conducted to incorporate the management of NRC Commitment changes as prescribed in the correspondence from site licensing RIMS R08000217713, and to human factor the notification and follow-up notification forns.
Page 2 - change to step 3.2.1 involves human factoring the Notification Forn Title.
Page 6 - changes involves removing the "NRC Commitment Brackets to step requiring the review of PORC and the human factoring of applicable steps.
Page 7 - change involves human factoring attachment title and modifying information to ensure consistency wiith NRC guidance.
Page 8 - change involves adding information regarding the support of the Unit 1 Operator in staffing the ERO.
Page 9 - Updated information for the Unit Operator to use during the ERO staffing process.
Page 10 - change involved adding a clarify statement concerning the appropriate use of the Follow up Notification Form.
IC-3 1 EPIP-3, revision 26 is being issued to incorporate changes regarding assembly and accountability actions. All actions to initiate the accountability and evacuation processes are now located in EPIP-8. The revision additionally standardizes telephone numbers, and PORC revieN~s. This revision also adds clarification for the actions taken by the Unit 1 Unit Operator during their staffing of the ERO process.
Page 3 - added a statement to the caution information regarding security threat. Clarified steps 3.4.1 and 3.4.2 to implement EPIP-8 regarding actions to be taken for assembly/accountability and evacuation.
Page 6 - standardize Alert procedure closure information.
Page 8,9 - Clarify actions taken by the Unit 1 Unit Operator during the notification attachment
ALERT EPIP-3 BROWNS FERRY NUCLEAR PLANT 1.0 PURPOSE 1.1
'-,Provide for timely notification of appropriate individuals or organizations when the Shift Manager/Site Emergency Director (SED) has determined by EPIP-1 that an incident has occurred which is classified as an ALERT.
1.2 Provide for periodic evaluation of the current situation by the Shift Manager/SED to determine whether the ALERT should be terminated, continued, or upgraded to a more serious classification 2.0 SCOPE This procedure applies to emergency events that are classified as Alert by EPIP-1, E
tmergency Classification Procedure.
'"-i I
(N i
-
t C
1 PAGE 1 OF 10 I
REVISION 26
ALERT EPIP-3 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS Date:
/
/'
3.1 If all Emergency Centers'ARE STAFFED,, Then notify the following that an ALERT Emergency Classification has been issued and EPIP 3 is being implemented, and continue in this procedure at Step 3.4. If all Emergency Centers ARE'NOT STAFFED, Then N/A this step and continue in this procedure.
Control Rooms Plant PA Announcement, 0 This is N Site Emergency Director, an Alert has been declared at BFN, we are currently implementing EPIP-3 Standby for further updates.
IN ALS TimE 3.2 Notification'of the Operations Duty Specialist (ODS) & Emergency Responders Note: The ODS should be notified within 5 minutes after the emergency event is declared.
3.2.1 Complete Attachment A (Initial Notification Form).
3.2.2 Direct the Unit 1, Unit Operator to make notifications from Attachment B (Unit 1, Unit Operator Notifications) 3.2.3 Notify the ODS and Provide the information from Attachment A.
Note: Utilize the direct ring-down ODS phone when making this notification or as applicable dial direct.
ODS Telephone Numbers 751-1700,or 2495 If the ODS cannot be reached within 10 minutes, Then contact the State of Alabama directly by requesting the Rad Health Duty Officer at:
Day Shift 8 a.m. - 5 p.m. - Holidays-Weekends-Off-Shifts 9-1-334-206-5391 9-1-334-242-4378 3.2.4 Fax a copy of Attachment A to the ODS for confirmation of information or state if the state was contacted directly.
ODS Fax AL Rad Health Fax 5-751-8620 9-1-334-206-5387 3.2.5 Receive confirmation call from the ODS (to verify notification of the State of Alabama)(NA this step, if the state was contacted directly).
INITnILS TImE INULS TImE INMALS TIE INTIMALS INMrALS TI'E PAGE 2 OF 10 CECC I TSC
[
oSC EI]
REVISION 26
ALERT I,,
)EPIP.73 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.3 NOTIFICATION OF SITE PERSONNEL 3.3.1 Make the following plant P.A. announcement:-
____I BLnTIAIS TLIE THIS IS (NAME), SHIFT MANAGER.,A ALERT HAS BEEN DECLARED ON UNIT
. I HAVE ASSUMED THE DUTIES OF SITE EMERGENCY DIRECTOR. REPORT TO YOUR ASSIGNED EMERGENCY RESPONSE FACILITY, AT THIS.
TIME.
CAUTION: Do not initiate Assembly and Accountability if
- 1.
A severe weather condition exist or projected on-site, such as a Tornado
- 2.
An on-site security risk condition exists (Consult with Nuclear Security) 3.4 ACCOUNTABILITY 3.4.1 If the emergency situation warrants an Assembly, Accountability, Then implement EPIP-8, Appendix C, concurrently with this procedure.
(N/A STEP IF NOT APPLICABLE) 3.4.2 If the emergency situation does not warrant an Assembly, Accountability at this time, Continue to assess the situation, implementing EPIP-8 when necessary.
3.5 OFFSITE DOSE ASSESSMENT 3.5.1 Evaluate the need for offsite dose assessment.
(N/A STEP IF NOT APPLICABLE) 3.5.1.1 When offsite dose assessment is required obtain the information from the CECC when operational.
3.5.1.2 If the CECC is not operational, contact the TSC, when staffed or the RADCON Shift Supervisor and request the implementation of EPIP 14, for dose assessment.
INmTnAIS TLIE INTrIALS TwiE
,, PAGE 3 OF 10 REVISION 26
ALERT EPIP-3 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.6 NOTIFICATION OF THE NRC 3.6.1 Notify the NRC immediately or within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and if' requested by the NRC maintain an open and continuous communicatiohs'channel.
Note: Utilize the Emergency Notification System (ENS) when' making this notification: Dial the first number listed on' the sticker affix&d tfo the ENS telephon&, by'dialing 9-1 "The Ten Digit Number Listed on the ENS Telephones".
If the number is busy, Then select in order, the alternate numbers until a connection is achieved. No hccess codes are required.
IfL INITIALS TLIE PAGE 4 OF 10 I,
REVISION 26
ALERT EPI 3
BROWNS FERRY Lu 11*-NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.7 PERIODIC EVALUATION OF THE EVENT 3.7.1 Continue to Evaluate the event using EPIP-1 as conditions warrant.
3.7.2 If plant conditions warrant the need for follow up information; Complete the Follow Up Notification Form, Attachment C.
Note: Conditions that warrant this evaluation are as a minimum when other EAL conditions exist indicating'the current emergency classification or significant changes in plant conditions have occurred., '
3.7.3 If the CECC is not staffed, Then notify the ODS and provide follow up information from the completed Attachment C form. Utilize the direct ring-down ODS phone when making this notification or as applicable dial direct.
I.
f ODS 751-2495, 1700 Note: If the ODS cannot be reached, Then contact the State of Alabama directly by requesting the Rad Health Duty Officer at: " - "
Day Shift 8 a.m. - 5 p.m.
Holidays-Weekends-Offshifts 9-1-334-206-5391 9-1-334-242-4378 3.7.4 If the conditions warrant upgrading to a higher classification, Then initiate the appropriate EPIP.
3.7.5 If the conditions warrants termination of the classifications, Then enter EPIP-16, Termination and Recovery Procedure.
3.7.6 After the evaluation has been completed, if staffed, Notify the following of the status:
"* NRC (ENS) 0 CONTROLRooMs
"* TSC
- PLANT PA ANNOUNCEMENT 3.7.7 Re-enter this procedural section as conditions warrant at step 3.7.1 or until directed to exit this procedure by steps 3.7.4 or 3.7.5.
PAGE 5 OF 10 REVISION 26
ALERT 1-1
-EPIP_-3 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.8 CLOSURE OF THE ALERT 3.8.1 Upon termination of the Notification of Alert, the Shift Manager shall send the completed EPIP-3 and all attachments to Emergency Preparedness (EP).
3.8.2 Upon receipt of completed EPIP-3 and all attachments, Emeigency Preparedness shall forward documents for the purpose of documentation storage.
4.0 ATTACHMENTS Attachment A - Initial Notification Form Alert Attachment B - Unit 1, Unit Operator Notifications Attachment C - Follow Up Information Form Alert INIALS TImE INITALS TimEm PAGE 6 OF 10 REVISION 26
ALERT EPIP-3 BROWNS FERRY NUCLEAR PLANT ATTACHMENT A (Page 1 bf 1)
INITIAL NOTIFICATION FORM ALERT -
L-I THIS IS A REAL-EVENT
" I THIS ISADRILL This is An ALERT has been declared at Browns Ferry affecting:
lJ 1
UiI
-- Unit 2 Event Declared:,
El Unit 3 Time: _
_I_
I
-] Common Date: __
EAL Designator.
Brief Description of the Event:
Radiological Conditions:
- No Abnormal Releases Offsiie D-Airborne Release Offsite F-1 Liquid Release Offsite--
- ell,
-- Release Information Not KIiown at this time L-There is no Protective Action Recommendation At this time.
[- Ask "Please repeat the information you yave ieceie6d tb'ensure accuracy."
ý PAGE 7 OF 10 REVISION 26
ALERT
, EPIP-3 BROWNS FERRY NUCLEAR PLANT ATTACHMENT B (Page 1 of 2)
UNIT 1, UNIT OPERATOR NOTIFICATIONS Date:
/
/
NOTES: (1) The Emergency Paging System (EPS) consists of a dedicated touch screen CRT.
Activation of any screen feature requires the user place their fingertip within the boundary of the select button and leave it there for at least 1 second. The CRT Screen will normally display a large rectangle that indicates that the paging system is available but currently inactive.
(2) If the EPS fails to operate, contact the SM/SED immediately. Request that the ODS be contacted to initiate the system from his location. If the system fails to operate from the ODS area, then utilize the Weekly Duty List hnd Call-OutList t6 manually staff the Emergency Responders, implementing this attachment at step E.
- 1. Activation of the Emergency Paging System (EPS).
A.
PRESS the EPS' CRT Screen once to activate the paging options.
B.
PRESS the appropriate option 0
0 S
0 PAGER TEST DRILL EMERGENCY ABORT INITIALS
-TIME!
INITIALS TIME C.
PRESS the START Button to initiate the option or ABORT to deny the option request.
D.
MONITOR the Paging System Terminal Display
- 1. IF... A "NO" response is observed OR The position being paged has not responded within approximately 20 minutes THEN... Utilize the Weekly Duty List and attempt to contact the position representative with available inf6rmation. (No Fitness f6r Duty Question Required)
- 2.
IF... The individual cannot be reached utilizing the Weekly Duty List THEN... Utilize the Call-Out List and attempt to contact an alternate position
. representative: (Fitness for Duty Question, Required)
PAGE 8 OF 10 INITIALS TIME INITIALS
- TIME,
-4 REVISION 26 1
ALERT EPIP-3 BROWNS FERRY NUCLEAR PLANT ATTACHMENT.B (Page 2 of 2)
UNIT 1,°UNIT OPERATOR NOTIFICATIONS Date:
-E.
Manual Call-Out (N/A step ifEPS operates normally).
INITIALS
- 1.
Utilize the current Weelky DutyList and contact positions as listed.
- 2.
If a position can not be reached from the current Weekly Duty list, then refer to the Call-Uit List as applicable to fill all vacant positions.
F.
CONTINUE until all positions have been filled.
- 2. Notify the Unit Supervisors on shift.
- 3. Notify Nuclear Security Shift Supervisor and state "AN ALERT HAS BEEN DECLARED"- and direct to activate EPIP-11, Security and Access Control.
INITIALS TIME
-INITIALS TIME INITIALS TIME Plant Extension 3150 or 2219
- 4. Notify the Chemistry Lab Supervisor and state "ANWALERT HAS' BEEN DECLARED" and direct to implement 2/3-TI-331,4.
Post Accident Sampling Procedure and CI-900 series, Analysis Procedures.
k, 1 14 INITIALS 44*2,
)
1*r Plant Extension 2367 or2368 "5. -Notify the RADCON Shift Supervisor and state "AN ALERT HAS.......
BEEN DECLARED" and -direct to activate EPIP-14,
--INITIALS-Radiological Control Procedure.
Plant Extension 7865 or 3104
' *.4'S '4 44:
TIME
- TIME
,,4
- 6. Notify the "On-Call', NRC Resident and state "AN ALERT HAS BEEN DECLARED," per BFN.:EPIP-03.
INITIALS TIME.'
......,Plant Extension 2572 [Secretary] -or from weekly-..
duty list 44-,
"2
] '*
REVISION 26 1
TIME
,, PAGE 9 OF-10
ALERT SEPIP-3 BROWNS FERRY NUCLEAR PLANT
--ATTACHMENT C (Page 1 of 1)
FOLLOW-UP INFORMATION FORM ALERT I-- THIS IS A REAL EVENT r-- THIS IS A DRILL Note: This form is for conducting Follow-up Information only.
This is at Browns Ferry Name There has been a Alert declared at Browns Ferry affecting:
-] Unit 1
-- Unit 2
,L Unit 3 EL Common The Reactor is EI Shutdown
[- At Power Plant Conditions are F-- Stable M" Deteriorating "Follow-Up" Information (e.g., Key Events, Status Changes)
Current Radiological Conditions are:
-1I No Abnormal Releases Offsite D Airborne Release Offsit6 -_
3/4 F] Liquid Release Offsite I Release Information Not Known Additional Rad information: (e.g., release duration) n There is no Protective Action Recommendation at this time'.'
Please repeat the information you have received to'ensure accuracy:
The time for this follow up is':
Time':
D_____
Date:
SIGNATURE:
LAST PAGE PAGE 10 OF 10 REVISION 26 I
TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLAIT EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-4,'
SITE AREA EMERGENCY" REVISION 25 PREPARED BY: T. W. CORNELIUS RESPONSIBLE ORGANIZATION:,EMERGENCY PREPAREDNESS APPROVED BY: GILBERT LITTLE EFFECTIVE DATE: 07/30/2002 LEVEL OF USE: REFERENCE USE PHONE: 2038 DATE: 07/22/2002 QUALITY-RELATED
REVISION LOG Prbcedure Number:
EPIP-4 Revision Number: 25 Pages Affected: ALL Description of Change:'
IC-31 This change is being conducted to incorporate a manual method of evacuating on-site, non emergency response personnel during 6mergency situations. In addition changes to the procedure are being conducted to incorporate the management of NRC Commitment changes as prescribed in the correspondence from site licensing RIMS R08000217713, and to human factor the notification and follow-up notification forms.
Page 2 - change to step 3.2.1 involves human faciorinfg the Notification Form Title Page 3- -changes to steps 3.4.1 - 3.4.5 involves information regarding steps for the SED to take N'ihen conducting an Accountably/Assembly and Evacuation Page 6 - changes involves removing the "NRC Commitment Brackets to step requiring the review of PORC and the human factoring of applicable steps.
Page 7 - change involves human factoring attachment title.
Page 8 - change involves human factoring attachment title and modifying information to ensure consistency with NRC guidance.
Page 9 - change involves adding information for Unit 1 Operator regarding ERO staffing support.
Page 10 - updated information for the Unit Operator to use dunng the ERO staffing process.
Page 11 - change involved adding a clarify statement concerning the appropriate use of the Follow up Notification Form.
IC-32 EPIP-4, revision 25 is being issued to incorporate changes regarding assembly and accountability actions. All actions to initiate the accountability and evacuation processes are now located in EPIP
- 8. The revision additionally standardizes telephone numbers, and PORC reviews. This revision also adds clarification for the actions taken by the Unit 1 Unit Operator during their staffing of the ERO process.
Page 3 - added a statement to the caution information regarding security tlieat. Clarified'steps 13.4.1 and 3.4.2 to implement EPIP-8 regarding actions to be taken for assembly/accountability and evacuation.
Page 6 - standardize Site Area Emergency procedure closure information Page 8,9 - Clarify actions taken by the Unit 1 Unit Operator during the notification attachment.
SITE AREA BROWNS FERRY EMERGENCY',,
Erjr 4 NUCLEAR PLANT 1.0 PURPOSE 1.1 Provide for timely, notification of appropriate individuals or organizations when the Shift Manager/Site Emergency Director,(SED) has determined by EPIP-I that an incident has occurred which is classified as a SITE AREA EMERGENCY (SAE).
1.2 Provide for periodic evaluation of the current situation by the Shift Manager/SED to determine whether the SAE should be terminated, continued, or upgraded to a more serious ciassification. "
2.0 SCOPE This procedure applies to emergency events that are classified as Site Area Emergency by
- EPIPI1, Emergenc' Classification Proce'dulf.
I
.. 7 a
I t..
. +
+
+
- +,,7 ;, + <,
a a
a r
+aa+
l,
.I
+
a+0 I
I PAGETLOF 10 REVISION 25
SITE AREA
- EMERGENCY'.
" EPIP-4 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS Date: __
I.
3.1 If all Emergency Centers ARE STAFFED, Then notify the following that a SITE AREA EMERGENCY Emerigency Classification has been issued and EPIP 4 is being impl~m fited, and Continiid in this procedure at Step 3.4. If all Emergency Centers ARE NOT STAFFED, Then N/A this step and continue in this procedure.
CECC C ontrol Rooms LNTHnuS TIME TSC
[L1 OSC IEl Plant PA Announcement, El This is NAM Site Emergency Director, an SAE has been declared at BFN, we are currently implementing EPIP-4. Standby for further updates.
3.2 Notification of the Operations Duty Specialist (ODS) & Emergency Responders Note: The ODS should be notified within 5 minutes after the emergency event is declared.
3.2.1 Complete Attachment A (Initial Notification Form).
3.2.2 Direct the Unit 1, Unit Operator to make notifications from Attachment B (Unit 1, Unit Operator Notification) 3.2.3 Notify the ODS and Provide the information from Attachment A.
Note: Utilize the direct ring-down ODS phone when making this notification or as applicable dial direct.
ODS Telephone Numbers 5-751-1700, 2495 If the ODS cannot be reached within 10 minutes, Then contact the State of Alabama directly by requesting the Rad Health Duty Officer at:
Day Shift 8 a.m. - 5 p.m. - Holidays-Weekends-Offshifts 9-1-334-206-5391 9-1-334-242-4378 3.2.4 Fax a copy of Attachment A to the ODS for confirmation of information or if the state is contacted directly.
ODS Fax AL Rad Health Fax 5-751-8620 9-1-334-206-5387 3.2.5 Receive confirmation call from the ODS (to verify notification of the State of Alabama)(NA this step, if the state was contacted directly).
PAGE 2 OF 10 INTInAs TIME INMITALS TIME INITIALS TIME LinrLus TImE L*TnALs TImE REVISION 25
SITE AREA EMERGENCY IP -4 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.3 NOTIFICATION OF SITE PERSONNEL 3.3.1 Make the following plant P.A. announcement:
THIS IS (NAME), SHIFT MANAGER. A SITE AREA EMERGENCY-HAS BEEN DECLARED ON UNIT
_ I HAVE ASSUMED THE DUTIES OF SITE -i EMERGENCY DIRECTOR. REPORT TO YOUR, ASSIGNED EMERGENCY RESPONSE FACILITY AT THIS TIME..
t
- S SINITIALS TIME I
CAUTION: Do not initiate Assembly and Accountability if:.
- 1. A severe weather condition exist or projected on-site,'such as a Tornado.
- 2. A on-site security risk condition exists (Consult with Nuclear Security).
3.4 ACCOUNTABILITY AND EVACUATION OF NON-EMERGENCY RESPONDERS 3.4.1 If Assembly and Accountability has not been conducted,,
Then, implement EPIP-8, Appendix C concurrently with INITIALS this procedure. If Accountability has been conducted, Then N/A this step and continue in this procedure at step 3.4.2.
3.4.2 If an order to evacuate non-emergency responders has, not be issued, Then upon completioniiofAssembly and INITIALS Accountability, initiate the order to evacuate non emergency responders, through the implementation of EPIP-8, Appendix F, concurrently with this procedure. If the order to evacuate non-emergency responders has been conducted, Then continue in this procedure at step 3.5.1.
TIME TIME r," PAGE 3OER 10
- r.
REVISION 25
SITE AREA EMERGENCY, SEPIP-4 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.5 DOSE ASSESSMENT 3.5.1 Evaluate the need for offsite dose assessment.
(N/A STEP IF NOT APPLICABLE) 3.5.1.1 When offsite dose assessment is I-equired, obtain the information from the CECC when.'
operational.
3.5.1.2 If the CECC is not operational, contact the TSC, when staffed, or the RADCON Shift Supervisor and request the implementation of EPIP 14, for dose assessment.
3.6 NOTIFICATION OF THE NRC 3.6.1 Notify the NRC immediately or within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, and if requested by the NRC maintain an open and continuous communications channel.
Note: Utilize the Enmergency Notification System (ENS) when making'this notification,' Dial the first number listedbn the sticker affixed to the ENS telephone, by dialing 9-1 "The Ten Digit Number Listed on the ENS Telephones".
If the number is busy, Thenselecf in'order, the alternate' numbers until a connection is achieved. No acces' codes are required.
1, INITIALS TIME INITIALS TIME PAGE 4 OF 10
-4s- -
4PQ REVISION 25
SITE AREA BROWNS FERRY EMERGENCY INUCLEARPLANT 3.0 INSTRUCTIONS (CONTINUED) 3.7 PERIODIC EVALUATION OF THE EVENT 3.7.1 Continue to Evaluate the event using EPIP-1 as conditions warrant.
3.7.2 If plant conditions warrant the need for follow up information, Complete the Follow Up Notification Form, Attachment C.
Note: Conditions that warrant this evaluation are as a minimurn when other EAL conditions exist indicating the current emergency classification or "significant changes in plant cdnditions have'6 ccurred.-"
3.7.3 If the CECC is not staffed, Then notifythe ODS and provide follow up information from the completed Attachment C formi Utilize the direct iifig'-down ODS phone when making this notification or as applicable dial direct.
ODS' '5-751-2495, 1700 Note: If the ODS cannot be reached, Then contact the State of Alabama directly by requesting the Rad Health Duty Officer at:
Day Shift 8 a.mn. - 5 p.m.
Holidays-Weekends-Offshifts 9-1-334-206-5391 9-1-334-242-4378 3.7.4 If the conditions warrants upgrading to a higher classification, Then initiate EPIP-5, General Emergency.
3.7.5 If the conditions warrant termination of the classification, Then enter EPIP-16, Termination and Recovery Procedure.
4.
" fi, I
" PAGE 5 OF 10 REVISION 25
SITE 'AREA T2'TITT-4 BROWNS FERRY EMERGENCY
>NUCLEARPLANT 3.0 INSTRUCTIONS (CONTINUED) 3.7 PERIODIC EVALUATION OF THE EVENT (CONTINUED),
3.7.6 After the evaluation has been completed, if staffed, Notify the following of the status:
"* CECC
- OSC,
"* NRC (ENS)
CONTROL ROOMS
" TSC PLANT PA ANNOUNCEMENT 3.7.7 Re-enter this procedural section as conditions warrant at step 3.7.1 or until directed to exit this procedure by steps 3.7.4"or 3.7.5.'
3.8 CLOSURE OF THE SITE AREA EMERGENCY 3.8.1 Upon termination of the Notification of Site Area Emergency, the Shift Manager shall send the completed INITIALS TIME EPIP-4 and all attachments to Emergency Preparedness (EP).
3.8.2 Upon receipt of completed EPIP-4 and all attachments, INITIALS TIME Emergency Pieparedness shall forward documents for the purpose of documentation storage.
4.0 ATTACHMENTS Attachment'A - Initial Notification Form Site Area Emergency Attachment B - Unit 1, Unit Operator Notifications Attachment C - Follow Up Information Form Site Area Emergency PAGE 6 OF 10 REVISION 25 1
SITE AREA EMERGENCY EPIP-4 BROWNS FERRY NUCLEAR PLANT IATTACHMENT A (Page4 1of 1)
INITIAL NOTIFICATION FORM SITE AREA EMERGENCY LI1 THIS IS A REAL EVENT This is "L] THI S ISA DRILL.
3/4 I
NA.ME A SITE AREA EMERGENCY has been declared 'at Br64wnsFerry affecttig DJ ii
.7.
I-Unit 1,"
L;I Unit 2' nit3 E] C.ommon Evet Declared:
Time:
EAL Designator:
Brief Description of the Event:
" Date:
I)'
Radiological Conditions:
r-No Abnormal Releases,Offsite
.I -Airborne Release Offsite nI Liqu Release Offsite L-Release Information Not Known at this time n-There is no Protective Action Recommendation ait this time."
r-l Meteorological conditions ari:
Wind Speed:
.h Wind Direction From:
degr'ee I-I Ask "Please repeat the information you have received to ensure accuracy.
- '-.
.4 REVISION 25 1
>*l,
- -PAGE 7 OF 10
SITE AREA EMERGENCY EPIP-4 BROWNS FERRY NUCLEAR PLANT t ATTACHMENT B (Page 1 of 2)
UNIT 1, UNIT-OPERATOR NOTIFICATIONS "J,.
Date:
/
/
NOTES: (1) The Emergency Paging System consists of a dedicated touch screen CRT:-
Activation of ahy screen feature requires the user place theii fingertip within the' boundary of the select button and leave it there for at least 1 second. The CRT Screen will normally display a large rectangle that indicates that the paging system is available but currently inactive..
(2) If the'EPS fails to ojp'rate, 66ntact the SM/SSED immediaitlyr. Request that the ODS be contacted to initiate the system from his location. If the system fails to operate from the ODS area, then utilize the Weekly Duty List and Call-Out List to manually staff the Emergency Responders, implementing this attachment at step E.
- 1. Activation of the Emergency Paging System (EPS).
A.
PRESS the EPS CRT Screen once to activate the paging options.
B.
PRESS the appropriate option PAGER TEST DRILL EMERGENCY ABORT C.
PRESS the START Button to initiate the option or ABORT to deny the option request.
D.
MONITOR the Paging System Terminal Display'
- 1. IF... A "NO" response is observed OR The position being paged has not responded within approximately 20 minutes,.'
THEN... Utilize the Weekly Duty List and attempt,,,
to contact the position representative with available information. (No Fitness for, Duty Question Required)
- 2.
I&F.. The individual cannot bereachediutihzingthe Weekly Duty List THEN... Utilize the Call-Out List and attempt to contact an alternate position representative. (Fitness for Duty Question Required)
PAGE 8 OF 10 INITIALS TIME INITIALS TIME INITIALS TIME r INITIALS TIME REVISION 25
SITE AREA' EMERGENCY I EPIP-4 BROWNS FERRY NUCLEAR PLANT ATTACHMENT B (Page 2 of 2)
UNIT, 1, UNIT, OPERATOR NOTIFICATIONS Date: __ _
E.'-
Manual Call-Out (N/A step ifEPS operates normally)
INITIALS TIME;"
- 1.
Utilize the current Weelky Duty List and contact "positions as listed.
- 2.
'If a position 6an not be reached from the current Weekly Duty list, then iefer to the Call-out List'a applicable to fill all vacant positions.
F.
CONTINUE until all positions have been-filled.
- 2. Notify the Unit Supervisors on shift..".
Ls
- 3. Notify Nuclear Security Shift Supeivisor and state "AN SITE AREA EMERGENCY HAS BEEN DECLARED" a-nddireci to activate EPIP-11, Security and Access-C6itfr-o-l.
INITIALS INITIALS INITIALS TIME TIME' TIME.
Plant Extension 3150 or 2219
- 4. Notify the Chemistry Lab Supervisor and state "AN SITE AREA EMERGENCY HAS BEEN DECLARED" and direct to INITIALS implement 2/3-TI-331, Post Accident Sampling Procedure and CI-900 series, Analysis Procedures _,
-1..,
1, TIME '
0 Plant Extension 2367 or. 2368,.',,.,- -,
- 5. Notify the RADCON Shift Supervisor and state "AN SITE AREA EMERGENCY HAS BEEN DECLARED" and direct to activate EPIP-14, Radiological Control Procedure.
Plant Extension 7865 or 3104 INITIALS TIME
- 6. Notify the "On-Call" NRC Resident and state "AN SITE AREA EMERGENCY HAS BEEN DECLARED".'
C INITIALS '- TIME Plant Extension 2572 [Secretary] or from weekly dutylist..
, PAGE 9 OF,10
- 11-P REVISION 25
SITE AREA
'EMERGENCY BROWNS FERRY NUCLEAR PLANT
, I. ATTACHMENT C (Page 1 of 1)
FOLLOW-UP INFORMATION FORM SITE AREA EMERGENCY L-THIS IS A REAL EVENT L-THIS IS A DRILL Note: This form is for conducting Follow-up Information only.
This is at Browns Ferry.
Name There has been a Site Area Emergency declared at Browns Ferry affecting:
'- Unit I-Unit 2, F" Unit 3 EL Common The Reactor is -] Shutdown L-At Power Plant Conditions are '- Stable F1-Deteriorating "Follow-Up" Information (e.g., Key Events, Status Changes)
Current Radiological Conditions are:
L-No Abnormal Releases'Offsite L--
Airboriie Release Offsi'e,;
F-- Liquid Release Offsite F-- Release Information Not Known Additional Rad information: (e.g., release duration)
FI There is no Protective Action Recommendation at this time.
Please repeat the information you have received to ensure accuracy.
The time for this follow up is:
Time:
Date:
SIGNATURE:
LAST PAGE PAGE 10 OF 10 REVISION 25
TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-5 GENERAL EMERGENCY a
REVISION 30
.P ORGANIZATION:
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APRPAROED BY: T.LER WCONLITTS DAT
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APRPAROED BY:T W.
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DAT'+HOE: 0/22002 EFFECTIVE DATE: 07/30/2002 LEVEL OF USE: REFERENCE USE QUALITY-RELATED
I REVISION LOG
-Proeduxre-Number:
EPIP-5 Revision Number; -30 Pages Affected:
All Description of Chang'e:'
IC-37 This change is being conducted to incorporate a manual method of evacuating on-site, non emergency response personnel during emergency situations. In addition changes to the procedure are being conducted to incorporate the management of NRC Commitment changes as prescribed in the correspondence from site licensing RIMS R08000217713, and to human factor the notification and follovw-up notification forms.
Page 2 - change to step 3.2.1 involves human factonng the Notification Form Title and revised telephone for Morgan County.
Page 3/4 - changes to steps 3.4.1,- 3.4.5 involves information regarding steps for the SED to take w~hen conducting an Accountably/Assembly and Evacuation.
Page 6 - changes involves removing the "NRC Commitment Brackets to step requiring the review of PORC and the human factoring of applicable steps.
Page 7 - change involves human factoring attachment title.
Page 8 - change involves human factoring attachment title.
Page 9 - change involves adding information for Unit I Operator regarding ERO staffing support.
Page 10 - revised to update information supporting Unit I Operator actions regarding ERO staffing support.
Page 11 - revised Protective Action Recommendation Flowchart.
Page 12 - change involved adding a clarify statement concerning the appropriate use of the Follow-up Notification Form.
IC-38 EPIP-4, revision 25 is being issued to incorporate changes regarding assembly and accountability actions. All actions to initiate the accountability and evacuation processes are now located in EPIP
- 8. The revision additionally standardizes telephone numbers, and PORC reviews. This revision also adds clarification for the actions taken by the Unit, 1 Unit Operator during their staffing of the ERO process.
Page 3 - added a statement to the caution information regarding security threat. Clarified steps 3.4.1 and 3.4.2 to implement EPIP-8 regarding actions to be, taken for assembly/accountability and evacuation.
"i Page 6 - standardize Site Area Emergency procedure closure information.
Page 8,9 - Clarify actions taken by the Unit 1 Unit Operator during the notification attachment.
GENERAL.
EMERGENCY-
-,EPIP-5 BROWNS FERRY NUCLEAR PLANT K)
-L if if P 4
4 i71
'if' 1'
-if.
4
,if if
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if if if, if r if-if
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if if if if if PAGE VOFli REVISION 30 I
1.0 PURPOSE 1.1, Provide for timely notification of appropriate individuals, or.organizations when the Shift Manager/Site Emergency Director (SED) has determined by EPIP-1 that an incident'has occurred which is classified as a GENERAL EMERGENCY (GE).
1.2 Provide for periodic evaluation of the current situation by the Shift Manager/SED to determine whether the GE should be terininated, or continued.
2.0 SCOPE This procedure applies to emergency events that are classified as General Emergency by EPIP-1, Emergency Classification Procedure.
GENERAL EMERGENCY EPIP-5 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS Date:
/
/
S3.1 If all Emergency Centers ARE STAFFED, Then notify the following that a GENERAL EMERGENCY Emergency Classification has been issued and EPIP 5 is being implemented, and continue in this procedure at Step 3.4. If all Emergency Centers ARE NOT STAFFED, Then N/A this step and continue in this procedure.
CECC [-
Control Rooms LnITtuS TlmE TSC
[-
Plant PA Announcement E7 OSC El This is NAME Site Emergency Director, an GE has been declared at BFN, we are currently implementing EPIP-5. 'Standby for further updates..
3.2 Notification of the Operations Duty Specialist (ODS) & Emergency Responders Note: The ODS should be notified within 5 minutes after the emergency event is declared.
3.2.1 Complete Attachment A (Initial Notification Form).
3.2.2 Direct the Unit 1, Unit Operator to make notifications from Attachment B (Unit 1, Unit Operator Notifications) 3.2.3 Notify the ODS and Provide the information from Attachment A.
Note: Utilize the direct ring-down ODS phone when making this notification or as applicable dial direct.
ODS Telephone Numbers 5-751-1700, 2495 Ifthe ODS cannot be reached within 10 minutes, Then contact the following and Provide the information from Attachment A:
- 1. Limestone County:
9-232-0111 INITnLS TIME INIT*US TIME INITIALS TIME 9-1-256-432-2143 9-1-256-974-7641
- 4. Lauderdale County:
9-1-256-760-9117
- 5. State of Alabama Rad Health Duty Officer:
Day Shift 8 a.m. - 5 p.m.
9-1-334-206-5391 Holidays-Weekends-Offshifts 9-1-334-242-4378 INrTnLs TBIE IITrIALS TIME INMTlALS TnIE INIIIALS TIME INrMAIs TnEE K>
REVISION 30
- 2. Morgan County:
- 3. Lawrence County:
PAGE 2 OF I1I
GENERAL.
,EMERGENCY
-EPIP-5 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.2.4 Fax a copy of Attachment A to the ODS for confirmation --
of information or the state if contacted directly.
INITIALS AL Rad Health 9-1-334-206-5387 3.2.5 Receive confirmation call from the ODS (to verify - *7 notification of the State of Alabama), (N/A this step if the State was contacted directly).
3.3 NOTIFICATION OF SITE PERSONNEL 3.3.1 Make the following plant P.A. 'announcement:
THIS IS (NAME), SHIFT MANAGER. ;XGENERALý EMERGENCY HAS BEEN DECLARED ON UNIT
. I HAVE AýSSUMED THE DUTIES OF SITE EMERGENCY DIRECTOR. REPORT TO YOUR ASSIGNED EMERGENCY RESPONSE FACILITY AT THIS TIME.
INITIALS TIME INITIALS CAUTION: Do not initiate Assembly and Accountability-if:-,
- 1. A severe vWeather'c6nditiori exist or projected on-site, such as a Tornado.
- 2. An on-site security' risk conditi6n exists (Consult with Nuclear Security) 3.4 ACCOUNTABILITY AND EVACUATION OF NON-EMERGENCY RESPONDERS 3.4.1 If Assembly and Accountability has not been conducted, Then, implement EPIP-8, Appendix C concurrently with INITIALS this procedure. If Accountability has been conducted' Then, continue in this procedure at step 3.4.2.-
3.4.2 If an order to evacuate non-emergency responders has not be issued, Then upon completion of Assembly and Accountability, Initiate the order to evacuate non emergency responders, through the implementation of EPIP-8, Appendix F, concurrently with this procedure. If the order to evacuate non-emergency responders has been conducted, Then continue in this procedure at step 3.5.1.
INITIALS
, PAGE 3 OF 11
- ODS Fax 5-751-8620 TIME TIME TIME TIME REVISION 30
GENERAL EMERGENCY EPIP-5 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.5 DOSE ASSESSMENT-',
3.5.1 Evaluate the need for offsite dose assessment.
(N/A STEP IF NOT APPLICABLE) 3.5.1.1 When offsite dose assessment is required Obtain the information from the CECC when operationai.
t 3.5.1.2 If the CECC is not operational, Contact the TSC, when staffed or the RADCON Shift' Supervisor and Request the implementation of EPIP 14, for dose assessment.
3.6 NOTIFICATION OF THE NRC 3.6.1 Notify the NRC immediately or within,1, hour and if requested by the NRC maintain an open and continuous communications channel.
Note: Utilize the Emergency Notification System (ENS) when making this notification., Dial the first number listed on.
the sticker affixed to the ENS telephone, by dialing 9:l-.
"The Ten Digit Number Listed on the ENS Telephones".
If the number is busy, Then select in order, the alternate numbers until a connection is achieved. No access codes are required.
3.7 PROTECTIVE ACTION RECOMMENDATION 3.7.1 If the CECC is not staffed, Then make a Protective Action Recommendation (PAR) using Attachment C.
(This PAR shall be made only by the SED.)
(N/A STEP IF NOT APPLICABLE)
INITIALS TIME INITIALS TIME INITIALS TIME REVISION 30 1
11-1:J PAGE 4OFll
GENERAL EMERGENCY,
" EPIP-5 BROWNS FERRY NUCLEAR PLANT
- 3.0 INSTRUCTIONS (CONTINUED) 3.8 PERIODIC EVALUATION OF THE EVENT 3.8.1 Continue to Evaluate the event usingEPIP-1 as conditions warrant.
3.8.2 If plant conditions warrant the need for follow-up'information, Complete the Follow-Up Notification Form, Attachment D.
-Note: Conditions that warrant this evaluation are as a minimum when other EAL conditions exist indicating'the current emergency classification or significant changes in plant conditions have occurred.-,',-,
3.8.3 If the CECC is not staffed, Then notify the ODS and provide follow up information from the completed Attachment D form. Utilize the directring-down ODS phone when making this notification or as applicable dial direct.
ODS 751-2495, 1700 Note: If the ODS cannot be reached, Then contact the State of Alabama directly by requesting the Rad Health Duty Officer at:
"1 1 1 Day Shift 8 a m:- 5 p.m
- °*,:, "Holidays-Weekends-Offshifts 9-1-334-206-5391 9-1-334-242-4378 3.8.4 If the conditions warrant termination of the classification, Then enter EPIP-16, Termination and Recovery Procedure.
3.8.5 After the evaluation has been completed, if staffed, Notify the following of the status:
"* CECC
"* NRC (ENS)
"* TSC
- OSC CONTROLRooMs PLANT PA ANNOUNCEMENT 3.8.6 Re-enter this procedural section as conditions warrant at step 3.8.1 or until directed to exit this procedure by steps 3.8.4.
PAGE 5 OF 11
ýý 17ý_ LZI I
REVISION 30
GENERAL EMERGENCY
,-EPIP-5 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.9 CLOSURE OF THE GENERAL EMERGENCY 3.9.1 Upon termination of the Notification of General, Emergency, the Shift Manager shall send the completed EPIP-5 and all attachments to Emergency, Preparedness (EP).
I, 3.9.2 Upon receipt of completed EPIP-5 and all attachments, Emergency Preparedness shall forward documents for the purpose of documentation storage. "
4.0 -
ATTACHMENTS Attachment A - Initial Notification Form General Emergency Attachment B - Unit 1, Unit Operator Notifications Attachment C - Protective-Action Recommendations Attachment D - Follow Up Information Form General Emergency INITIALS TIME INITIALS TIME REVISION 30 PAGE 6 OF I I
GENERAL EMERGENCY
- EPIP-5 BROWNS FERRY NUCLEAR PLANT ATTACHMENT-A (Page 1 of 1)
'INITI1AL NOTIFICATION FORM GENERAL EMERGENCY
['7 THIS IS A REAL EVENT This is S-THIS IS A-DRILL, There has been-a GENERAL EMERGENCY "de6laied at Browns Ferry affeting'
-- UnitA' FT Unit 2 f.,Y
",WUnit,3:
Common Event Declared:
Time:
4 44
EAI-Desigfittbir..
Date.
"4 4,
Brief Description of the Event:
Radiological Conditions:
LI No Abnormal Releases Offsite
[- --Airborne Release Offsite L-Liquid Release Offsite
-- Release Information Not Known at this time The following Protective Action Recommendation is provided,'
I-Recommendation 1 - Evacuate 2 mile radius and 10 miles downwind and shelter remainder of 10 mile EPZ.
-4 F-1 Recommendation 2': Evactate 2 mile'radiuis4.fid 5.miles downwind and shelter remainder of 10 mile EPZ:
44" 44 Meteorological Conditions are:,,
Wind Speed: ______ph.__
Wind Direction From:
degrees a'
44 *4 a
E-' Ask, "Please repeat the information you have received to ensure accuracy."
C' I
C' -
1 F
PAGE 7 OF 11 j,
REVISION 30
GENERAL EMERGENCY' EPIP-5 BROWNS FERRY NUCLEAR PLANT
'ATTACHMENT B (Page 1 of 2)
UNIT. 1, UNIT OPERATOR NOTIFICATIONS r
- *Date:
/
/
(1) The Emergency Paging System consists of a dedicated touch screen CRT.
Activation of any screen feature requires the user plade their fingertip within the!
boundary of the select button and leave it there for at least 1 second. The CRT Screen will normally display a large rectangle that indicates that the paging system, is available but currently inactive.
(2) If the EPS fails to operate, contact the SM/SED immediately. Request that the ODS be contacted to initiate the' system from his location. If the system fails to 0 operate from the ODS area, then iutilize the Weekly Duty List and Call-Out List to' manually staff the Emergency Responders, implementing this attachment at step E.
- 1. Activation of the Emergency Paging System (EPS).
A PRESS the EPS CRT Screen once to activate the paging options.
B.
PRESS the appropriate option 0
0 0
0 PAGER TEST DRILL EMERGENCY ABORT C
PRESS the START Button to initiate the option or ABORT to deny the option request.
D.
MONITOR the Paging System Terminal Display
- 1.
IF... A "NO" response is observed O R,
The position being paged has not responded within approximately 20 minutes THEN... Utilize the Weekly Duty List and attempt
,tocontact the position representative with available information. (No Fitness for Duty Question Required)
- 2.
IF... The individual cannot be reached utilizing the Weekly Duty List THEN... Utilize the Call-Out List and attempt to S-contact an alternate position, representative. (Fitness -for Duty Question Required)
PAGE 8 OF I I INITIALS TIME INITIALS TIME
- INITIALS, TIME INITIALS TIME REVISION 30 SNOTES:
F 4
GENERAL.
EMERGENCY IEPIP-5 BROWNS FERRY NUCLEAR PLANT ATTACHMENT B (Page 2 of 2)
UNIT 1, UNIT OPERATOR NOTIFICATIONS I- *
- 1 Date:'
/
E.
-Manual Call-Out (N/A step ifEPS op&ates normally)
- 1.
Utilize the currenfWeelky Duty List and contact positions as listed.
2."
If a position can not be reached from the current Weekly Duty list, then refer to the Call-out List as applicable to fill all vacant positions.,
F.
CONTINUE until all positions have been filled.
- 2. Notify the Unit Supervisors on shift.
- 3. Notify Nuclear Security'Shift Supervisor and state "A GENERAL EMERGENCY HAS BEEN DECLARED" and direct to activate EPIP-1 1, Security and Access Control.
S:*
Plant Extension 3150 or 2219
- 4. Notify the Chemistry Lab Supervisor and state "A GENERAL EMERGENCY HAS BEEN DECLARED" and direct to implement 2/3-TI-331, Post Accident Sampling Procedure' "and CI-900 series, Analysis Procedures.
Plant Extension 2367 or.2368
- 5. Notify the RADCON Shift Supervisor and state "A GENERAL EMERGENCY HAS BEEN DECLARED" and direct to activate EPIP-14, Radiological Control Procedure.
Plant Extension -7865 or 3104 -
INITIALS INITIALS INITIALS e
- 6. Notify the "On-Call"NRC Resident and state "A GENERAL EMERGENCY HAS BEEN DECLARED".7--,--7,
'Plant Extension 2572 [Secretary] or from weekly duty list
- , PAGE9OF11 INITIALS TIME TIME TIME TIME INITIALS TIME INITIALS TIME I
- INITIALS I
TIME REVISION 30
GENERAL EMERGENCY EPIP-5 BROWNS FERRY NUCLEAR PLANT IATTACHMENT C (Page 1 of 1)
PROTECTIVE ACTION RECOMMENDATIONS Note 1: If conditions are unknown~ utilizing the flowchart, then answer NO.
General Emergenec
- Declared, CONTIH
- Modify, p on availal monitorih orLocate aM At hot spots.'
5/ miles is the Projected*
NO
or Measured Dose Greater than PAG Y-ES UE ASSESSMENT rotective actions based ble Plant and field ag information.
id evaluate localized A
4 PAGE 10 OF 11
'4 RECOMMENDATION 1 EVACUATE 2 miles radius' and 10 miles downwind AND',,
I SHELTER remainder of 10 mile EPZ I
RECOMMENDATION 2 "EVACUATE 2 mile radius and 5 miles downwind AND SHELTER remainder of 10 mile EPZ TABLE 1 Protective Action Guides TYPE LIMIT Measured 3.9E-6 micro Ci/cc of Iodine 131 or 1 REM/hr External Dose Projected 1 REM TEDE or 1 5 REM Thyroid CDE
'I 4F P
6 A
A 6 REVISION 30
z Ii' i
GENERAL EMERGENCY EPIP-5 BROWNS FERRY NUCLEAR PLANT ATTACHMENT D (Page 1 of 1)
FOLLOW-UP INFORMATION FORM GENERAL EMERGENCY
-i THIS IS A REAL EVENT F1 THIS IS A DRILL Note: This form is for conducting Follow-up Information only.
This is at Browns Ferry.
Name There has been a General Emergency declared at Browns Ferry affecting.
Ei Unit 1 i-Unit 2 L-i Unit 3 El Common The Reactor is L-i Shutdown Plant Conditions are Li Stable Li At Power Li Deteriorating "Follow-Up" Information (e.g., Key Events, Status Changes, Status of any Plant Evacuations)
Current Radiological Conditions are:
-1i No Abnormal Releases Offsite Li Airborne Release Offsite Li Liquid Release Offsite Li1 Release Information Not Known Additional Rad information: (e.g., release duration)
The current meteorological conditions from the site are:
Wind Speed
, Wind Direction from The following Protective Action Recommendation is provided:
Li Recommendation 1 Li Recommendation 2 Please repeat the information you have received to ensure accuracy.
The time for this follow up is:
Time-Date:
SIGNATURE:
LAST PAGE PAGE 11 OF 11 REVISION 30 I
REVISION 30 1
PAGE 11 OF 11
TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT "IEMERGENCY, PLAN IMPLEMENTING PROCEDURE EPIP-8 PERSONNEL ACCOUNTABILITY AND EVACUATION
"-REVISION 15 PREPARED BY: T. W. CORNELIUS PHONE: 2038 RESPONSIBLE ORGANIZATION: EMERGENCY PREPAREDNESS APPROVED BY: GILBERT LITTLE DATE: 07/22/2002 EFFECTIVE DATE: 0713012002 LEVEL OF USE: REFERENCE USE QUALITY-RELATED
HISTORY OF REVISIONIREVIEW REASON FOR CURRENT REVISION 14 3/20/02 15 6/8/02 6,10 IC-17 This revision is being conducted to add the Contractor Facility Complex (CFC) to the list of buildings located outside the protected area for the assembly of organizations not reporting to a assembly area inside the protected area.
Page 6 - Revise the "Note" to include the Contractoi Facility Complex in the list of reporting areas for assembly outside the protected area.
Page 10 - Revise the evacuation checklist for "Outside the Protected Area" assembly areas to include the Contractor Facility Complex (CFC)
All IC-18 Format EPIP to EPIP Wnters Guide specifications and place the Security Advisory information in procedure. EPIP a8, revision 15 is being issued to incorporate changes resulting from the letter, NEI to NRC (to Mr. Bruce A. Boger) dated December 18, 2001 requesting confirmation for EAL basis change to include response to a Site-Specific Credible Threat. This letter waskd6ieloped in response to the NRC's October 6, 2001 Safeguards Advisor. The change to this EPIP is a consequence to the EAL change and other information contained in the order. This revision more effectively provides'actions'and guidance for-all personnrel within the BFN Owner Controlled Area.
REV.
NO.
DATE:
REVISED PAGES K>
TABLE OF, CONTENTS
1.0 INTRODUCTION
................................................................................................ I 1.1 P u rp o s e.........................................................
c' 1
2.0 REFERENCES
..I 1
2.1 INDUSTRY DOCUMENTS........
A. NUREG-0654, Criteria for Preparation and Evaluation of Radiological Emergency............................ 1 Response Plans and Preparedness in Support of Nuclear Power Plants B. 10 CFR 50.47, Code of Federal Regulations..................................................................................
1 C. NRC Information Notice 2002-14, Ensuring a Capability to Evacuate Individuals, Including...................... 1 Members of the Public, from the Owner-Controlled Area 2.2 Plant Instructions...........................................................................................................................................
1 A. TVA Radiological Emergency Plan......................................................................................................
1 B. Emergency Plan Implementing Procedure - 2.......................................................................................
I C. Emergency Plan Implementing Procedure - 3...........................................................................................
1 D. Emergency Plan Implementing Procedure - 4......................................................................................
1 E. Emergency Plan Implementing Procedure - 5...........................................................................
I F. Emergency Plan Implementing Procedure - 14....................................................................................
1 3.0 INSTRUCTIONS............................................................................................................................................
I 3.1 Activation of the Assembly and Accountability Process............................................................................
I A. Shift Manager/Site Emergency Director.....................................................................................................
3.2 General Personnel Information.......................................................................................................................
1 A. Entering and Exiting the Plant Protected Area...........................................................................................
1 3.3 Particular Area Evacuation.............................................................................................................................
2 3.4 Site Assembly and Accountability...........................................................................................................
2 A. Non-Emergency Responders W ith Assigned Assembly Area.................................................. 2 B. Non-Emergency Responders W ith No Assigned Assembly Area................................................................
3 C. Emergency Responders............................................................................................................................
3 D. Emergency Responders with Escort Responsibilities.............................................................................
3 E. Visitors...................................................................................................................................................
3 F. Special Conditions concerning Assembly and Accountability.................................................................
3 G. Shift Manager/Site Emergency Director................................................................................................
3 H. Nuclear Security........................................................................................................................................
4 I. Radiological Control...................................................................................................................................
4 3.5 Evacuation of Site Non-Emergency Response Personnel...........................................................................
4 A. Non-Emergency Response Personnel within the Plant Protected Area................................................
4 B. Non-Emergency Response Personnel within the Owner Controlled Area excluding the Plant Protected Area..........................................................................................................................................................
5 C. Emergency Response Personnel..........................................................................................................
5 D. Shift Manager/Site Emergency Director................................................................................................
5 E. Nuclear Security........................................................................................................................................
5 F. Radiological Control..................................................................................................................................
5 4.0 DOCUMENTATION.......................................................................................................................................
6
5.0 ILLUSTRATIONS/APPENDICES..................................................................................................................
6 Appendix A - Non-Emergency Responders Assembly Areas...................................................
7 Appendix B - Emergency Responders Emergency Facility/Assembly Areas..........................
8 Appendix C - Shift Manager/Site Emergency Director-Assembly and Accountability Actions.....
9 Appendix D - Nuclear Security - Assembly and Accountability Actions..............................
12 Appendix E - Radiological Control - Assembly and Accountability Actions..............................................
15 Appendix F - Shift Manager/Site Emergency Director - Evacuation Actions..........................
16 Appendix G - Nuclear Security - Evacuation Actions...............................................................................
17 Appendix H - Radiological Control - Evacuation Actions........................................................................
20 A ppendix I - Accountability Roster..........................................................................................................
. 20
BROWNS FERRY PERSONNEL ACCOUNTABILITY AND EVACUATION P
1.0 INTRODUCTION
1.1 Purpose The purpose of this procedure is to provide a means for administering a protective action response such as the capability to account for all individuals within the Protected Area (PA), the
'evacuation of all non-emergency personnel within the Owner Controlled Area and PA, in addition to the evacuation of personnel in specific affected plant area(s). The scope of this procedure includes emergency and non-emergency response personnel, visitors, contractor/construction personnel and other persons who may be within the Owner Controlled Area during an emergency situation.
This procedure will be initiated ordinarily by way of an emergencyclassification procedure step (i.e., EPIP-2, -3, -4, and -5). If situations were to exist, where in the judgment of the Shift Manager/Site Emergency Director, (SED), it become prudent to initiate the process of Assembly and accountability and/or evacuation, this procedure can be entered and initiated via that judgment.
- CSEE'
2.0 REFERENCES
2.1, Industry Documents S"
- 'A. NUREG-0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants rB. 10 CFR 50.47, Code of Federal Regulations
- ~,
C. NRC Information Notice 2002-14, Ensuring aCapability to Evacuate Individuals, Including Members of the Public, from the Owner-Controlled Area 2.2 Plant Instructions
, A:TVA Radiological Emergency Plan B. EPIP - 2, Notification of Unusual Event, C. EPIP 7 3, Alert
, ý -
I "
D. EPIP - 4, Site Area Emergency E. EPIP -5, General Emergency F. EPIP - 14, Radiological Control Procedures 3.0 INSTRUCTIONS r,
3.1 Activation of the Assembly and Accountability Process A.
Shift Manager/Site Emergency Director
- 1.
The Shift Manager or Site Emergency Director shall initiate the activation of the
, assembly and accountability process.,
- a.
-TheShift Manager or Site Emergency Director can delegate a designee to carry out the actions of this process, but can not delegate the decision
-to activate the process.. ;.
- r'*
- 2.
Referto Appendix C for activation.
3.2 General Personnel Information A.
Normal Entering and Exiting the plant Protected Area (PA)
- 1.
Individuals entering the plant Protected Area shall:
Swipe their badge into the entry card reader, Enter the Protected Area in accordance with security procedures.
PAGE '1 OF 21 --r,
REVISION 15
BROWNS FERRY PERSONNEL ACCOUNTABILITY, AND
~
D
.S EVACUATION 8-~*'
- 2.
Individuals exiting the Protected Area shall:
Swipe their badge into the exit card reader in the appropriate exit portals.
Exit the protected area in accordance with'security procedures.
- 3. -
Entry and exit card readers function as accountability card readers for personnel
- exiting the PA.
3.3 Particular Area Evacuation Plant conditions delegate operations to evacuate or request the evacuation of particular plant areas through the TSC.
A The Shift Manager/Site Emergency Director (SED)'or designee shall make a public address (PA) announcement similar to; 1,
"Attention all personnel. Conditions in the (area to be evacuated) require an evacuation of the area. Leave the (area to be evacuated) immediately."
B.
Personnel in the affected area(s), upon hearing the public address announcement or being notified of the 'particular area evaciuation by any m eans shall do the following:
- 1. If working in a contaminated zone, exit the zond ir accordance with Radiological Control (RADCON) procedures, unless instructed otherwise by RADCON.
- 2. Exit the affected area in an orderly manner.
C.
Personnel not in the affected area(s), should continue assigned tasks if not instructed otherwise and should not enter the affected area(s) until the-"All Clear" has been announced or directed through emergency response processes.
3.4 Site Assembly and Accountability A three-minute undulating siren (a siren that raises and lowers in volume and pitch), strobe lights, or public address announcements are the general methods for notifying personnel that:
emergency conditions exists requiring the assembly and accountability of site personnel. Upon recognition that the assembly and accountability process has been activated, all personnel shall begin immediately to take applicable actions.
A.
Non-Emergency Responders With Assigned Assembly Areas
- 1.
Upon recognition of the assembly and accountability process, non-emergency responders with assigned assembly areas, shall proceed immediately to their 1 designated assembly areas as listed on Appendix A.
- 2.
Arriving at the assembly area, personnel shall:
- a.
Swipe their badge into the accountability card reader (applies only to those assembly areas within the protected area),
- b.
Remain in the designated assembly area until released by the Site Emergency Director (SED) or a plant evacuation is ordered, follow the instructions of Nuclear Security.
PAGE 2 OF 21R REVISION 15
BROWNS FERRY PERSONNEL ACCOUNTABILITY AND EVACUATION EPIP-8 PAGE 3 OF 21 R
B.
Non-Emergency Responders With No Assigned Assembly Area
- 1.
Non-Emergency Responders with no assigned assembly area represent unescorted visitors; contractorsfconstruction personnel, and others persons in public accessareas on or passing within the Owner Controlled Area.
- 2.
Upon recognition of the assembly and accountability process, non-emergency responders with no assigned assembly area, shall proceed immediately to their vehicle and exit the Owner Controlled Area.
C.,-
Emergency Responders
- 1.
Upon recognition ofthe Assembly and Accountability process, emergency responders, shall proceed immediately to their designated assembly area as
, listed on Appendix B.,:
- 2.
Arriving at the designated assembly area, personnel shall:
a.-,
Swipe their badge into the accountability card reader,
- b.
'Sign the Accountability Roster Form, Appendix I, c
'Review their emergency responsibilities and begin work,
- d.
If a plant evacuation is ordered, all emergency responders will remain in their designated assembly area.
D.
-Emergency Responders Having Escort Responsibilities
- ,-Emergency Responders,,will take the applicable steps to have their visitor transferred to a non-emergency responder for relocation to an appropriate assembly area.
E.
Visitors,-,- -.
Visitors shall remain with escorts and swipe their badge into the appropriate accountability card reader.
r F.
r Special Conditions Concerning Assembly and Accountability 1._.
If a person cannot'reach his designated assembly area within 20 minutes, he should go to the nearest designated area and swipe his badge into the card reader., He should remain in that assembly area. Review Appendix A and B list assembly area locations.
'2.-
If the accountability card reader will not accept a badge, Nuclear Security should be contacted immediately at extension 3238 or 2219.
- 3.
If a card reader or assembly area cannot be accessed, Nuclear Security should S
,be contacted immediately at extension 3238 or 2219:.
G.
Shift Manager/Site Emergency Director When conditions have been met that require the activation of the assembly and accountability process, the Shift Manager/Site Emergency Director will implement Appendix C of this procedure.
REVISION 15
BROWNS FERRY PERSONNEL ACCOUNTABILITY AND EVACUATION E P1 -
H.
Nuclear Security,,
SWhen notified that conditions have been met that require the activation of the assembly and accountability process, or upon indications that assembly and accountability has been initiated, Nuclear Security will implement Appendix D of this procedure.
Radiological Control (RADCON)
When notified that conditions have been met that require the activation of the assembly and accountability process, or upon indication that assembly and accountability has been initiated, Radiological Control will implement Appendix E of this procedure.
3.5 Evacuation of Non-Emergency Response Personnel-A site evacuation will be conducted upon an order issued by the Shift Manager/Site Emergency Director. This Order will be issued to the TSC Nuclear Security Manager or the Nuclear Security Shift Supervisor or their designee, following the completion of assembly and accountability.
A. -
- Non-Emergency Responders Within the Plant Protected Area.
- 1.
All personnel assembled in designated assembly areas within the protected area shall remain in those areas until released for the purpose of evacuation. Visitors shall remain with escorts until visitors have exited the protected area.
- 2.
Nuclear Security will by public address announcement or dispatching security personnel, brief and release persons in assembly areas.
- 3.
Once released, personnel shall go immediately to their appropriate protected area exit portal. Personnel shall swipe their badge into the exit card reader or as "instructed by Nuclear Security. The protected area shall be exited in accordance with security procedures unless otherwise instructed.
- a.
If for any reason personnel can not go directly to their designated Protected Area exit portal, Nuclear Security should be contacted immediately.
- b.
If for any reason the exit card reader will not properly acknowledge a
_, badge, Nuclear Security should be contacted immediately.
- 4.
Personnel shall proceed to their vehicle and evacuate from the site to their place "of residence, following all briefing information provided to you by Nuclear Security. Exit routes leading away from the plant may be suggested by Nuclear Security.
5._
All personnel evacuating should anticipate that Owner Controlled Area road blocks will be established and if conditions require, RADCON will be monitoring vehicles and personnel as they exit.
6.-
Upon exiting the Owner Controlled Area, personnel shall follow all guidance of state and local authorities.
¶ PAGE 4 OF 21 REVISION 15
BROWNS FERRY PERSONNEI EACCOUNTABILITY AND EVACUATION EPIP B.
Non-Emergency Responders Within the Owner Controlled Area Excluding the Plant Protected Area.
- 1.
All personnel assembled in designated assembly areas within Owner Controlled Area excluding the Protected Area shall remain in those areas until released for the purpose of evacuation.
1
- 2.
Nuclear Security will dispatch security personnel directly to Owner Controlled Area Assembly Areas, brief and release assembled personnel.
- 3.
Once released personnel shall proceed to their vehicle and evacuate from the "site to their place of residence, following all briefing information provided to you by Nuclear Security. Exit routes leading away from the plant may be suggested by Nuclear Security.
If for any reason personnel can not proceed directly to their vehicle and evacuate, the site Nuclear Security shall be contacted immediately.
- 4.
All personnel exiting the site Protected Area should anticipate that Owner Controlled Area road blocks will be established and if conditions require, RADCON will be monitoring vehicles and personnel as they exit.
- 5.
Upon exiting the Owner Controlled Area, personnel shall follow all guidance of state and local authorities.
C.
Emergency Responders Emergency Responders shall remain in Emergency Centers and shall not evacuate from the site.
D.
Shift Manager/Site Emergency Director When conditions have been met that require an order to evacuate non-emergency response personnel, the Shift Manager/Site Emergency Director will implement Appendix F of this procedure.
E.
Nuclear Security When notified that an order to evacuate site non-emergency response personnel has been issued by the Shift Manager/Site Emergency Director, Nuclear Security will implement Appendix G of this procedure.
F.
Radiological Control When notified that an order to evacuate site non-emergency response personnel has been issued by the Shift Manager/Site Emergency Director, Radiological Control will implement Appendix H of this procedure.
PAGE 5 OF 21 REVISION 15
BROWNS FERRY PERSONNEL ACCOUNTABILITY AND EVACUATION EP IP-8, 4.0 DOCUMENTATION 5.0 ILLUSTRATIONS /APPENDICES Appendix A -
Non-Emergency Responders Assembly Areas - -
t Appendix B -
'Emergency Responders Emergency Facility/Assembly Areas Appendix C -
Shift Manager/Site Emergency Director - Assembly and Accountability Actions Appendix D -
Nuclear Security - Assembly and Accountability Actions Appendix E Radiological Control - Assembly and Accountability Actions Appendix F -
Shift Manager/Site Emergency Director-Evacuation -Actions Appendix G -
Nuclear Security - Evacuation Actions, Appendix H -
Radiological Control - Evacuation Actions Appendix I -
Accountability Roster LAST TEXT PAGE 6 OF 21 REVISION 15
, I
- BROWNS FERRY PERSONNELACCOUNTABILITY AND EVACUATION P
APPENDIX A Page 1 of 1 NON-EMERGENCY RESPONDERS ASSEMBLY AREAS Designated Assembly Areas Within "the Plant Protected Area Reporting Organizations Maintenance Shop(s)
Maintenance Production personnel (except for Instrument Mechanic Shop personnel)
Maintenance Program Support personnel"-
Work Control Center personnel Plant Assembly Room Work Control/Outage personnel 4
Maintenance Building Instrument Mechanic (IM) Shop personnel Maintenance Support personnel',
Plant Engineering Building Site Engineering - System Engineering personnel
...Radwaste personnel, Rad-Chem Engineers West Access Portal Exit Personnel from all other organizations not listed who utilize-the west portal as their regular entry point.
East Access Portal Exit Personnel from all other organizations not listed who~utilize the east portal as their regular entry point.
Plant Manager's Office Foyer Area Plant Manager's office staff Operations office staff Maintenance office staff RADCON office staff Outage office staff Designated Assembly Areas within Reporting Organizations Owner Controlled Area (Outside the.,
Plant Protected Area)
Administration Building All personnel exiting the east or west security portals Common Maintenance Building BEN Training and Visitor Center All personnel within the Owner Controlled Area excluding the Materials Procurement Complex Protected Area Modifications Fabrication Shop Modifications Administration Building Contractor Facility Complex (CFC)
PAGE 7 OF 21 :,
REVISION 15
BROWNS FERRY, PERSONNEL ACCOUNTABILITY AND EVACUATION APPENDIX B Page 1 of 1 EMERGENCY RESPONDERS EMERGENCY FACILITY/ASSEMBLY AREAS Designated Assembly Area,,. I Reporting Organizations.
Unit 1 and 2 Control Rooms All operations personnel in Control Bays, Unit 1/2 U-nit 3 Control Room All operations personnel in Control Bays, Unit 3 Technical Support Center TSC staff Operations Support Center-OSC staff Document Control 'and Records,,
Management, personnel from plant office building information center.
OSC Staging Area Maintenance personnel assigned to staging area Fire Protection personnel _
Tool Room personnel AUO Operations personnel-assigned to Staging Area Radiological Control RADCON Field Operations personnel (RADCON)
Radiochemistry Laborat6ry
'Chemistry Control personnel I
PAGE 8 OF 21 REVISION 15
PERSONNEL ACCOUNTABILITY AND EVACUATION EPIP'8 IAPNI
- APPENDIX C Page 1 of 3 SHIFT MANAGER/SITE EMERGENCY DIRECTOR--ASSEMBLY AND ACCOUNTABILITY ACTIONS The following appendix shall be Utilzed-by theSht Manager/Site Emergency Director (SM/SED) or designee fo!
the purpose of conducting site assembly and accountability actions.
- 1.
The SM/SED has determined that conditions require the activation of the assembly and accountability siren system and process.
Initials Time,
- 2.
NOTIFY... Nuclear Security (NS) at extension 3238 or 2219 that:
El A.
The assembly and accountability sirens will be activated immediately.
AND B.
NS should implement EPIP-8, Appendix D.
- 3.
NOTIFY... Radiological Control (RADCON) at extension 7865 that:
El A.
The assembly and accountability sirens will be activated immediately.
AND B.
RADCON should implement EPIP-8, Ap'pendix E.
- 4.
MAKE... a public address announcement similar to:
"Attention all plant personnel, the site assembly and accountability process has been initiated. All personnel report immediately to your assigned assembly areas."
(REPEAT)
- 5.
ACTIVATE... the assembly and accountability sirens.
Irfitials Time
- 6.
WHEN... the Assembly and Accountability Sirens have-completed the 3-minute cycle and silenced.
MAKE... a PA announcement similar to:
"Attention all plant personnel, the site assembly and accountability process has been initiated. All personnel report immediately to your assigned assembly areas."
(REPEAT)
PAGE 9 OF 21 R
i BROWNS FERRY I
, -.1 ; -
C. 1" REVISION 15
BROWNS FERRY PERSONNEL ACCOUNTABILITY AND EVACUATION EPIP8 APPENDIX C Page 2 of 3 SHIFT MANAGER/SITE EMERGENCY DIRECTOR - ASSEMBLY'AND ACCOUNTABILITY ACTIONS Ii-i f*-rl
- 7.
NOTIFY... Central Emergency Control Center (CECC) Director either by the direct ring-down telephone in the TSC or at extension 751-1614.
OR If the CECC Director can not be reached, notify the Operations Duty Specialist (ODS) at extension 751-1700 that:
A.
The assembly and accountability sirens have been activated.
AND B.
BFN EPIP-8 is currently being implemented for assembly and accountability.
- 8.
WHEN... Notified by NS that the assembly and accountability process has been completed.
THEN.... MAKE a public address announcement similar to:
"Attention all plant personnel, the site assembly and accountability process has been completed. All personnel remain in your assigned assembly areas."
(REPEAT)
- 9.
VERIFY with the SM/SED, that conditions at this time require an order to evacuate all non-emergency response personnel from the Owner Controlled Area.
- 10.
IF...
Conditions at this time, DO require an order to evacuate all non emergency response personnel from the Owner Controlled Area.
11 Initials Time THEN... Initiate Appendix F of this procedure (EPIP-8).
PAGE 10 OF 21 IJ'.J I *.
If at any time during the assembly and accountability process RADGON determines that radiation guidelines for an assembly area(s) have been exceeded, request NS to re-locate affected personnel to another assembly area or evacuate affected personnel off-'ite" REVISION 15
BROWNS FERRY PERSONNEL ACCOUNTABILITY AND SEVACUATION EP P-8 APPENDIX C Page 3 of 3 SHIFT MANAGER/SITE EMERGENCY DIRECTOR'- ASSEMBLY AND ACCOUNTABILITY ACTIONS
- 11.
IF...
Conditions at this time, DO NOT require an order to evacuate all non emergency response personnel from the Owner Controlled Area. -
THEN... Exit this procedure. Re-enter this procedure at Appendix F when it has been determined by the SM/SED that conditions require an order to evacuate all non-emergency response personnel.
II PAGE 11 OF21 R
I
,, j REVISION 15
BROWNS FERRY PERSONNEL ACCOUNTABILITY
- AND IEPIP EVACUATION APPENDIX D SPage 1 of 3 NUCLEAR SECURITY. - ASSEMBLY AND ACCOUNTABILITY ACTIONS The following appendix shall be utilized by the TSC Security Manager or if unavailable the Security Shift Supervisor or designee for the purpose of conducting a Site Assembly and Accountability actions.
- 1.
Notified that activation of the assembly and accountability process and actions has been initiated by the SM/SED or designee.-
Initials Time
- 2.
CONTROL and RESTRICT access to the Protected Area, except for those individuals El designated for emergency response, per the Emergency Access List or as authorized for emergency response by the Shift Manager/Site Emergency Director.
- 3.
ESTABLISH Owner Controlled Area road blocks and on-site traffic controls.
El
- 4.
NOTIFY... RADCON at extension 7865 that, Owner Controlled Area road blocks and El on-site traffic control actions are in progress.
AND REQUEST... RADCON dispatch personnel to the Owner Controlled Area road blocks if determined by RADCON that survey conditions requiring vehicle survey exist.
- 5.
CONTROL and RESTRICT access to the Owner Controlled Area, except for those El individuals designated for emergency response, per the Emergency Access List or as authorized for emergency response by the Shift Manager/Site Emergency Director.
- 6.
DISPATCH officer(s) to search areas within the Owner Controlled Area outside the El Protected Area.
A.
IF... Visitors, contractors/construction personnel, and other persons in public El access areas on or passing within the Owner Controlled Area and not assigned a designated assembly areas are located; THEN... NS will:
Wam and advise individuals of current actions to conduct assembly and accountability.
Advise individuals on exits routes and request that they immediately exit the Owner Controlled Area.
REVISION 15 PAGE 12 OF 21
BROWNS FERRY PERSONNEL ACCOUNTABILITY AND EVACUATION I EPIP-8 APPENDIX D Page 2 of 3 NUCLEAR SECURITY - ASSEMBLY AND ACCOUNTABILITY ACTIONS B.
IF... Visitors, contractors/construction personnel,; and other persons in public.
Ej access areas on or passing within the Owner Controlled Area and assigned a designated assembly areas are located; THEN... NS will:
Warn and advise individuals of current actions to conduct
-,'assembly and accountability. -
I I Advise personnel to report immediately to their designated assembly area.
C.
IF... Employees having emergency response assignments are located LI THEN... NS will:
S.
Warn and advise individuals of current actions to conduct assembly and accountability, Advise personnel.to report immediately to their designated emergency response center.
D.
IF..:" Employees not having 'emergency response assignments are located El THEN... NS will:'
Warn and advise individuals of current'actions to conduct assembly and accountability.
Advise personnel to report immediately to the nearest designated assembly area. See Appendix A.
- 7.
REPORT the results of accountability to the SM/SED within 30 minutes after the assembly and accountability sirens have sounded.
- 8.
Unaccounted Individuals IF...
Individuals remain unaccounted, 45 minutes following the activation of the assembly and accountability sirens, THEN... REQUEST permission from the SM/SED to form security search teams to locate the missing individual(s),
AND NOTIFY RADCON and request that they accompany all security search teams Initials Time PAGE 13 OF 21 R
I REVISION 15
BROWNS FERRYj PERSONNEL ACCOUNTABILITY"AND EVACUATION APPENDIX D "Page 3 of 3 NUCLEAR SECURITY - ASSEMBLY AND ACCOUNTABILITY ACTIONS
- 9.
Two Person (Line of Sight) Rule, Public Address Announcement.
[]
A.
WHEN...Assembly and Accountability have been completed, AND Nuclear Security has determined that the Two Person (Line of Sight)
Rule is required.
THEN... REQUEST permission from the SM/SED to make the following Public Address Announcement:
Initials Time "Attention all personnel. A credible insider threat exists.
Effective immediately,- all'personnel enterin" the Vital Areas must observe the 2-person' rule. This rule requires that all persons ina vital a*ea must'r~main ih visual' contact (i.e.
line of sight) with one another uhnless personnel or plant safety would be adversely impacted. This does not require that the two pe'rs6ns possess similar skills or knowledge. I repeat. The 2-person rule is being implemented.
immediately."
(REPEAT)
PAGE 14OF21 -R 1
REVISION 15
BROWNS FERRY PERSONNEL'ACCOUNTABILITYAND SI EPIP-8 EVACUATION APPENDIX E Page 1 of 1 RADIOLOGICAL CONTROL-ASSEMBLY.AND'ACCOUNTABILITY ACTIONS The following Appendix shall be utilized by the TSC Radiological Control Manager or if he is unavailable the Radiological Control Shift Supervisor or designee, for the purpose of conducting a site assembly and accountability actions.
1.:
Notified that activation of the assembly and accountability process and actions has been initiated by the SM/SED or designee.
Initials Time
- 2.
IF... Radiological conditions require, El THEN... ESTABLISH a survey routine for all assembly areas, including the Emergency Centers.
- 3.
IF... Radiological conditions in any assembly area(s) meet or exceed the listed El guidelines:
"* Radiation levels that would result in a radiation dose of 100 mrem in one hour, or
"* airborne radioactivity above 10CFR 20.1201 DAC limits.
THEN... NOTIFY the SM/SED and recommend that the personnel within the affected area be re-located to another assembly area or evacuated from the site.
- 4.
WHEN... Notified by Nuclear Security that Owner Controlled Area Roadblocks have been established, Initials Time THEN... EVALUATE radiological cornditions to determine if a RADCON survey checkpoint at the Owner Controlled Area road block should be established.
- 5.
IF... Radiological conditions require that a RADCON survey checkpoint be established,
[]
THEN... DISPATCH RADCON personnel to the Owner Controlled Area road block.
AND',-.
ESTABLISH a RADCON survey checkpoint.,
- 6.
WHEN... Notified by Nuclear Security that assembly and accountability search teams are required.
THEN... DISPATCH RADCON personnel to assist security search teams.
II' PAGEr15 OE 21 R
I REVISION 15
AND B.
NS Should implement EPIP-8, Appendix G'.
- 4.
NOTIFY... Radiological Control at 'extension 7865 that:
A.
An order to evacuate site non-emergency response personnel has beenr issued, AND B.
RADCON should implement EPIP-8, Appendix H.
- 5.
NOTIFY... Central Emergency Control Center (CECC) Director either by the direct ring-down telephone in the TSC or at extension 751-1614, OR If the CECC Director can not be reached, Operations Duty Specialist (ODS) at extension 751-1700 that:
A.
An order to evacuate site non-emergency response personnel has been issued, AND B.
BFN EPIP-8 is currently being implemented for evacuation of site non-emergency response personnel.
El PAGE 16 OF 21 I
]
REVISION 15 BROWNS FERRY PERSONNEL ACCOUNTABILITY AND EVACUATION E I APPENDIX F Page 1 of 1 SHIFT MANAGER/SITE EMERGENCY DIRECTOR - EVACUATION ACTIONS The following appendix shall be utilized by the Shift Manager/Site Emergency Director or designee for the purpose of conducting a evacuation of site' non-emergency response personnel.
- 1.
Conditions have been met that require an order to evacuate site non-emergency response personnel.
Initials Time
- 2.
Assembly and accountability has been completed.
El
- 3.
NOTIFY... Nuclear Security (NS) at extension 3238 or 2219 that:
E A.
An order to evacuate site non-emergency response personnel has been issued.
BROWNS FERRY PERSON N ELACCOU NTABILITY AND EVACUATION EPIP-8 APPENDIX G Page I of 3 NUCLEAR SECURITY - EVACUATION ACTIONS The following appendix shall be utilized by the TSC Security Manager or if unavailable the Security Shift Supervisor or designee for the purpose of conducting a evacuation of site non-emergency response personnel.
- 1.
Notified that an order to evacuate site non-emergency response personnel has been initiated by the SM /SED.
Initials Time
- 2.
CONTINUE to control and restrict access to the Plant Protected Area, except for those El individuals designated for emergency-response; per the Emergency Access List or as authorized for emergency response by the Shift Manager/Site Emergency Director.
- 3.
CONTINUE to maintain Owner Controlled Area road blocks and on-site traffic controls.
- 4.
CONTINUE to control and restrict access to the Owner Controlled Area, except for _l those individuals designated for emergency response, per the Emergency Access List or as authorized for emergency response by the Shift Manager/Site Emergency S:
-*Director.
- 5.
NOTIFY... RADCON at extension 7865 that, Owner Controlled Area road blocks El and on-site traffic control actions are in progress,
-AND, REQUEST... RADCON dispatch personnel to the Owner Controlled Area road blocks if it is determined by RADCON that conditions requiring vehicle survey exist.
- 6.
EVALUATE evacuation route:
- ~
Initials -Time A.
Consult with RADCON information concerning off-site environmental
-radiological hazards (potential..umerpathways).
r B.
Consider local weather information to determineif hazardous weather conditions exist.
C.
Consider, all information concerning terrorist activity within a 10 mile radius of the site.
PAGE 17,OF 21 RI 1
REVISION 15
BROWNS FERRYJ PERSONNEL ACCOUNTABILITY AND EVACUATION E
IP APPENDIX G Page 2 of 3 NUCLEAR SECURITY - EVACUATION ACTIONS
- 7.
DETERMINE evacuation route based upon information obtained in step 6 of this El appendix:
L-Shaw Road (North) only, El Nuclear Plant Road (East) only, El Either Shaw Road or Nuclear Plant Road.,
- 8.
VERIFY that all prior listed items are complete before continuing in this action list.
El
='
- 9.
DISPATCH Security personnel to evacuate the following assembly areas BFN Training and Visitor Center, Administration Building, Materials and Procurement Complex, Common Maintenance Building, Modifications Fabrication Shop, 0
Modification Administration Building, 0
Contractor Facility Complex (CFC).
Initials Time PAGE 18 OF 21 I
NOTE The order in which assemnbly areas are evacuatdd is at the discretion of Nuclear Security. The list of assembly areas is not intended to suggest a order for completion.
"I I*
N O TE Brief and advise all individuals in assembly areas of:
"* Current actions to conduct an evacuation of all non-emergency response personnel, AND
"* Recommended exits routes, directing all personnel to follow the instructions of local law enforcement officers upon leaving the Owner Controlled Area.
REVISION 15
- I PAGE 19 OF 214 '.
BROWNS FERRY PERSONNEL ACCOUNTABILITY AND Y
~EVACUATION P
' APPENDIX G Page 3 of 3 "NUCLEAR SECURITY_- EVACUATION ACTIONS
- 10.
DISPATCH Security personnel or utilize the public address system to evacuate the following assembly areas:
nitials Time Maintenance Shop Area, Plant Assembly Room, Maintenance Building, Plant Engineering Building, Plant Manager's Office Foyer Area.
- 11.
NOTIFY the Shift Manager/Site Emergency Director upon completion of evacuation site non-emergency response personnel.
Initials Time REVISION 15
BROWNS FERRY PERSONNEL ACCOUNTABILITY AND EVACUATION E
I APPENDIX H Page 1 of 1 RADIOLOGICAL CONTROL - EVACUATION ACTIONS The following appendix shall be utilized by the TSC Radiological Control Manager, or if he is unavailable the Radiological Control Shift Supervisor or designee, for the purpose of conducting a evacuation of site non emergency response personnel.
- 1.
Notified of order to evacuate site non-emergency response personnel has been initiated by the SM /SED.
- 2.
IF... a radiological survey checkpoint has not been established at the Owner Controlled Area Roadblock, then:
THEN... DISPATCH RADCON personnel to the Owner Controlled Area road block.
AND ESTABLISH a RADCON survey checkpoint.
- 3.
IF... Radiological concerns merit the activation of the off-site decontamination facility, THEN... Implement EPIP-14, Step 3.8, Activation of the Browns Ferry Alternate Personnel Decontamination Facility.
Initials Time El Initials Time PAGE 20 OF 21R S
'i.
L REVISION 15
BROWNS FERRY PERSONNEL ACCOUNTABILITY AND EPIP-8 EVACUATION APPENDIX I Page 1 of 1 ACCOUNTABILITY ROSTER Date:
Emergency Response Facility:_
SSN Name (Last, First MI)
ERO Position Filled (Staging Area Personnel, OSC Board Writer, etc.)
1 1
LAST PAGE PAGE 21 OF 21 i
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i REVISION 15