HL-6265, Emergency Implementing Procedures Revision
| ML022060215 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 07/19/2002 |
| From: | Sumner H Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| HL-6265 73-EP-EIP-005-0, Rev 7, 73-EP-EIP-009-0, Rev 7.0, 73-EP-EIP-011-0, Rev 4.0, 73EP-EIP-001-0, Rev 14.3 | |
| Download: ML022060215 (76) | |
Text
Lewis Sumner Southern Nuclear Vice President Operating Company, Inc.
Hatch Project Support 40 Inverness Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205-992 7279 Fax 205.992.0341 k
SSOUTHERN N COMPANY July 19, 2002 Energy to Serve Your WorldM Docket Nos. 50-321 HL-6265 50-366 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Edwin I. Hatch Nuclear Plant Emergency Implementing Procedures Revision Ladies and Gentlemen:
In accordance with 10 CFR 50, Appendix E, Section V, Southern Nuclear Operating Company hereby submits the following revision to the Plant Hatch Emergency Implementing Procedures (EIPs):
EIP No.
Version Effective Date 73EP-EIP-001-0 14.3 07/09/02 73EP-EIP-005-0 7.0 07/09/02 73EP-EIP-009-0 7.0 07/09/02 73EP-EIP-011-0 4.0 07/12/02 These revisions incorporate comments identified during our review of the interim compensatory measures (ICMs).
By copy of this letter, Mr. L. A. Reyes, NRC Region II Administrator, will receive two copies of the revised procedures.
Should you have any questions in this regard, please contact this office.
Respectfully submitted, "Sn4 H. L. Sumner, Jr.
CKB/eb
Enclosures:
73EP-EIP-001-0, Emergency Classification and Initial Actions 73EP-EIP-005-0, On-Shift Operations Personnel Emergency Duties 73EP-EIP-009-0, Nuclear Security Duties 73EP-EIP-0 11-0, Assembly, Accountability and Evacuation
U.S. Nuclear Regulatory Commission Page 2 July 19, 2002 cc:
Southern Nuclear Operating Company (w/o)
Mr. P. H. Wells, Nuclear Plant General Manager SNC Document Management (R-Type A02.001)
U.S. Nuclear Regulatory Commission, Washington, D.C.(w/o)
Mr. L. N. Olshan, Project Manager - Hatch U.S. Nuclear Regulatory Commission, Region II Mr. L. A. Reyes, Regional Administrator (with 2 copies)
Mr. J. T. Munday, Senior Resident Inspector - Hatch (w/o)
HL-6176
SOUTHERN NUCLEAR DOCUMENT TYPE:
PAGE PLANT E.I. HATCH EMERGENCY PREPAREDNESS PROCEDURE 1 OF 46 DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISIONNERSION EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0 NO:
14.3 EXPIRATION APPROVALS:
EFFECTIVE DATE:
DEPARTMENT MANAGER JCL DATE 10/28/99 DATE:
7/9/2002 N/A NPGM/POAGM/PSAGM CTM DATE 10/28/99 1.0 OBJECTIVE This procedure establishes the methodology for emergency classification. Specific Emergency Action Levels (EALs) and minimum initial actions to respond to a given emergency are established in this procedure.
2.0 APPLICABILITY This procedure applies to emergency classification determinations and associated initial responses. This procedure is performed as required.
3.0 REFERENCES
3.1 10AC-MGR-006-0, Hatch Emergency Plan 3.2 73EP-EIP-004-0, Duties of Emergency Director 3.3 73EP-EIP-005-0, On-Shift Operations Personnel Emergency Duties 3.4 73EP-EIP-015-0, Offsite Dose Assessment 3.5 73EP-EIP-018-0, Prompt Dose Assessment 3.6 73EP-EIP-073-0, Offsite Emergency Notifications 3.7 Hatch Unit 1 Technical Specifications (TS), Sections 2.0, 3.2 through 3.9, 3.11 3.8 Hatch Unit 2 Technical Specifications (TS), Sections 2.0, 3.2 through 3.9, 3.11 3.9 Edwin I. Hatch Nuclear Plant Unit 1 and Unit 2 System Evaluation Document MGR-0002 Rev. 8
SOUTHERN NUCLEAR PAGE 2 OF 46 PLANT E.I. HATCH DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISIONNERSION EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0 NO:
14.3 4.0 REQUIREMENTS 4.1 PERSONNEL REQUIREMENTS 4.1.1 Any personnel trained and qualified as an Emergency Director (ED) may use this procedure.
4.1.2 The Emergency Director may modify emergency plan implementing procedures and staffing to meet the needs of emergency response.
4.1.3 Personnel who have received instruction in applicable emergency procedures are required to perform this procedure.
4.1.4 Initially, the Emergency Director position is filled by the Superintendent of Shift (SOS). If the SOS is unavailable, then the affected unit's Shift Supervisor (SS) will become the Emergency Director. IF the SOS is unavailable and the event involves both units, the Unit 1 Shift Supervisor (SS) will become the Emergency Director. Any of these persons will assume the position of Emergency Director in the Control Room until a qualified relief, as specified in step 4.1.5, can arrive on site and receive an adequate turnover.
4.1.5 Any one of the following persons may assume the Emergency Director (ED) duties after he is given proper turnover from the off going ED.
"* Nuclear Plant
- General Manager
"* Plant Operations - Assistant General Manager (POAGM)
"* Plant Support
-Assistant General Manager (PSAGM)
"* Vice President
- Plant Hatch
"* Other qualified Emergency Director 4.2 MATERIAL AND EQUIPMENT N/A - Not applicable to this procedure 4.3 SPECIAL REQUIREMENTS 4.3.1 Portions of this procedure require the results from calculations of projected doses at or beyond the site boundary to determine the appropriate emergency classification. Refer to procedures 73EP-EI P-015-0 and 73EP-EIP-018-0.
4.3.2 Portions of this procedure will require actual dose measurements (onsite OR off-site) to determine the appropriate emergency classification. Refer to procedures 73EP-EIP-015-0 and 73EP-EIP-018-0.
MGR-0001 Rev. 3
SOUTHERN NUCLEAR PAGE 3 OF 46 PLANT E.I. HATCH DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISIONiVERSION EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0 NO:
14.3 5.0 PRECAUTIONSILIMITATIONS 5.1 PRECAUTIONS The value of any emergency actions, which may require movement of plant personnel, must be judged against the danger to personnel or nuclear safety.
5.2 LIMITATIONS 5.2.1 The Operating Facility is defined to be areas within the Protected Area and the 230 Kv and 500 Kv switchyards.
5.2.2 Onsite is defined to be anywhere within the Owner Controlled Area.
7.0 PREREQUISITES This procedure will be utilized for drills, exercises and actual emergencies.
REFERENCE 7.0 PROCEDURE 7.1 EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 7.1.1 Upon notification of an abnormal condition OR observation of abnormal instrument readings, notify the Unit Shift Supervisor immediately.
7.1.2 Confirm abnormal conditions by comparing redundant instrument channels OR other related parameters, observation AND field reports, as applicable.
7.1.3 Assess the abnormal condition and classify the emergency by referring to subsection 7.2, Emergency Classification Chart.
MGR-0001 Rev. 3
PAGE 4 OF 46 SOUTHERN NUCLEAR PLANT E.I. HATCH DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISIONNERSION EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0 NO:
14.3 7.1.3.1 The Emergency Classification Chart details abnormal plant conditions that meet specific emergency class entrance requirements. These emergency classes are defined, in theory, in steps 7.1.3.1.1 through 7.1.3.1.4.
CAUTION IN THE UNLIKELY EVENT AN ABNORMAL CONDITION MEETS THE DEFINITIONS STATED IN 7.1.3.1.1 THROUGH 7.1.3.1.4 BUT ARE NOT COVERED IN THE EMERGENCY CLASSIFICATION CHART, OR THE INITIATING CONDITION IS MET BUT EQUIPMENT STATUS PARAMETERS VALUES ARE NOT, THE SOS/ED WILL USE HIS JUDGMENT, BASED ON THE AVAILABLE INFORMATION, TO DECLARE THE APPROPRIATE LEVEL OF EMERGENCY.
I 7.1.3.1.1 NOTIFICATION OF UNUSUAL EVENT (NUE)
Unusual events are in progress OR have occurred which indicate a potential degradation of the level of safety of the plant. No releases of radioactive material requiring offsite response OR monitoring are expected UNLESS further degradation of safety systems occurs.
7.1.3.1.2 ALERT EMERGENCY Events are in progress ORF have occurred which involve an actual OR potential substantial degradation of the level of safety of the plant. Any releases are expected to be limited to small fractions of the Environmental Protection Agency (EPA) Protective Action Guideline (PAG) exposure levels.
7.1.3.1.3 SITE AREA EMERGENCY Events are in progress OR have occurred which involve actual OR likely major failures of plant functions needed for protection of the public. Any releases are NOT expected to exceed PAG exposure levels, except near the site boundary.
MGR-0001 Rev. 3 I
CAUTION THE REVIEW OF ALL EMERGENCY CLASSES ASSOCIATED WITH A GIVEN CONDITION IS ESSENTIAL.
FAILURE TO DO SO COULD RESULT IN A LOWER CLASSIFICATION THAN WARRANTED.
SOUTHERN NUCLEAR PAGE 5 OF46 PLANT E.I. HATCH DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISIONNERSION EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0 NO:
14.3 7.1.3.1.4 GENERAL EMERGENCY Events are in progress OR have occurred which involve actual OR imminent substantial core degradation OR melting with potential for loss of containment integrity. Releases can be reasonably expected to exceed PAG exposure levels offsite for more than the immediate site area.
7.1.4 IF a potentially declarable emergency exists, inform the SOS immediately. The SOS will evaluate the abnormal condition and operator actions.
7.1.5 IF a declarable emergency exists, the SOS shall assume the duties of the Emergency Director in accordance with 73EP-EIP-004-0, Duties of Emergency Director AND declare the appropriate emergency classification within 15 minutes of the condition requiring the classification.
7.2 EMERGENCY CLASSIFICATION CHART Refer to the applicable section of the emergency classification chart to assess an abnormal condition and classify the emergency. An index of each emergency action level in the chart is listed on the next page for reference. The key words of an initiating condition are indicated in BOLD print. The supporting data / parameters are listed below each emergency action level.
The logical connectors (AND and OR) used in the supporting data / parameters are to be used as described in Technical Specification section 1.0 "Use and Application", part 1.2 "Logical Connectors."
MGR-0001 Rev. 3
PAGE 6 OF 46 SOUTHERN NUCLEAR PLANT EFI HATCH DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISION/VERSION EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0 NO:
14.3 Index of Emergency Action Levels Page 1.0 AUTOMATIC INITIATION OF EGS 7
2.0 RADIOLOGICAL EFFLUENTS ------------------------------------------------------------------------------
8 3.0 COREDAMAGE ---------------------------------------------------------------------------------------------
11 4.0 PRIMARY SYSTEM (STEAM) LINE BREAK OR SAFETY RELIEF VALVE FAILURE------------------
12 5.0 LoSS OF AC POWER ----------------------------------------------------------
14 6.0 LOSS OF ONSITE DC POWER -----------------------------------------------------------------------------
15 7.0 Loss OF CONTAINMENT -----------------------------------------------------------------------------------
16 8.0 FIRE IN PLANT ----------------------------------------------------------------------------------------------
17 9.0 SECURITY EVENT ------------------------------------------------------------------------------------------
18 10.0 NATURAL PHENOMENON ----------------------------------------------------------------------------------
19 EARTHQUAKE --------------------------------------------------------------------------------------------
19 HIGH WINDS ----------------------------------------------------------------------------------------------
21 HIGH RIVER WATER LEVEL -----------------------------------------------------------------------------
22 LOW RIVER WATER LEVEL ------------------------------------------------------------------------------
22 11.0 HAZARDS TO PLANT OPERATIONS -----------------------------------------------------------------------
23 AIRCRAFT ACTIVITY -------------------------------------------------------------------------------------
23 EXPLOSIONS ---------------------------------------------------------------------------------------------
24 TOXIC GAS ------------------------------------------------------------------------------------------------
25 FLAMMABLE GAS -----------------------------------------------------------------------------------------
26 TURBINE FAILURE/MISSILE IMPACT 27 12.0 THIS SECTION INTENTIONALLY LEFT BLANK 29 13.0 CONTROL ROOM EVACUATION ---------------------------------------------------------------------------
29 14.0 CONTROL ROD DROP 30 15.0 FAILURE OF REACTOR PROTECTION SYSTEM 31 16.0 Loss OF CONTROL ROOM INDICATION/ ALARMS/ ANNUNCIATORS 32 17.0 LoSS OF SHUTDOWN FUNCTIONS -----------------------------------------------------------------------
33 18.0 FUEL DAMAGE BY FUEL HANDLING ACCIDENT 34 19.0 HIGH RADIATION OR AIRBORNE CONTAMINATION 35 20.0 LoSS OF COOLANT ----------------------------------------------------------------------------------------
36 21.0 Loss OF ENGINEERED SAFETY FEATURES ---------------------------------------.--------------------
37 22.0 MULTIPLE SYMPTOMS AND OTHER CONDITIONS 38 TECHNICAL SPECIFICATION SAFETY LIMITS 38 PRECAUTIONARY ACTIVATION OF TSC G--------------------------------------------------------------
39 PRECAUTIONARY ACTIVATION OF MONITORING TEAMS 40 POTENTIAL LARGE RELEASES OF RADIOACTIVITY 41 FIRE IN PLANT --------------------------------------------------------------------------------------------
43 CLADDING/CONTAINMENT/COOLANT BOUNDARY PARAMETER ASSESSMENT TABLE --------
44 23.0 IS FS I O PERATIO NS --------------------------------------------------------------------------------------
45 LOSS OF CASK CONFINEMENT BOUNDARY FOR ANY LOADED SPENT FUEL CASK -------------
45 DEGRADATION OF SPENT FUEL CASK - AN OPERATIONAL EVENT -----------------------
45 DEGRADATION OF SPENT FUEL CASK - ENVIRONMENTAL PHENOMENA EXTERNAL EVENTS ---------------------------------------------------------------------------------------------------
46 MGR-0001 Rev. 3
IPAGE 7 OF 46 DOCUMENT NUMBER:
REVISIONNERSION 73EP-EIP-001-0 I
NO:
1.0 - AUTOMATIC INITIATION OF ECCS Emergency conditions exist WHEN:
NA S G
AUTOMATIC INITIATION, OR DEMAND FOR ECCS, TO RECOVER WATER LEVEL as indicated by:
E E E N R
T HPCI, Core Spray, or LPCI Automatic Initiation has occurred.
AND HPCI, Core Spray, or LPCI is discharging to the vessel.
AND Reactor Water Level < - 113 inches OR Drywell Pressure > 1.92 PSIG (TS)
See Section 20.0, Loss of Coolant, for determination of Site Area Emergency Classification.
See Section 22.0, Multiple Symptoms and Other Conditions, for determination of the General Emergency Classification.
i END AUTOMATIC INITIATION OF ECCS MGR-0001 Rev. 3
SOUTHERN NUCLEAR PLANT E.I. HATCH PAGE 8 OF 46 DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISIONNERSION EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0 NO:
14.3 2.0 - RADIOLOGICAL EFFLUENTS Emergency conditions exist WHEN:
N A U L E E R
T LIMITS FOR GASEOUS EFFLUENT RELEASES BEYOND THE SITE BOUNDARY HAVE EXCEEDED TS as indicated by either actual field measurements OR effluent monitor readings corresponding to:
> 0.057 mR (TEDE) in an hour*
(*TS yearly limit divided by the number of hours in a year)
> 500 mR (TEDE) in a year (TS)
LIMITS FOR LIQUID EFFLUENTS HAVE BEEN EXCEEDED [as given in the Offsite Dose Calculation Manual (ODCM)] as indicated by Chemistry analysis as follows:
> 1.5 mR to the total body in a quarter OR
> 3.0 mR to the total body in a year A GASEOUS EFFLUENT RELEASE IS UNDERWAY WITH OFFSITE DOSE RATES BEYOND THE SITE BOUNDARY, as indicated by either field measurements OR effluent monitor readings corresponding to:
> 0.57 mR (TEDE) in an hour**
(** 10 times the TS yearly limit divided by the number of hours in a year.)
> 5000 mR (TEDE) in a year (10 X T.S.)
S A
E G
E N
+ [CONTINUE TO THE NEXT PAGE] -->
MGR-0001 Rev. 3
SOUTHERN NUCLEAR PLANT E.I. HATCH DOCUMENT TITLE:
DOCUMENT NUMBER:
EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0 PAGE 9 OF 46 REVISION/VERSION NO:
14.3 2.0 - RADIOLOGICAL EFFLUENTS (continued)
Emergency conditions exist WHEN:
NASG R
T NOTE Adverse meteorological conditions is defined as Stability Class F AND 1 m/sec (= 2 mph) wind speed, OR inclement weather.
A GASEOUS EFFLUENT RELEASE IS UNDERWAY WITH OFFSITE DOSE AT THE SITE BOUNDARY, as indicated by either field measurements OR effluent monitor readings (using adverse meteorological conditions) corresponding to:
> 50 mR (TEDE)in an hour for > 1/2 hr but< 1000 mR (TEDE) in an hour OR
> 500 mR (TEDE)in an hour for 2 min. but < 1000 mR (TEDE) in an hour OR
> 250 mR (CDE thyroid) in an hour for 1/2 hr but < 5 REM (CDE thyroid) in an hour OR
> 2500 mR (CDE thyroid) in an hour for 2 min. but < 5 REM (CDE thyroid) in an hour DOSE BEYOND THE SITE BOUNDARY IS PROJECTED TO BE > EPA PAGS based on dose projections from plant parameters as follows:
[CONTINUE TO THE NEXT PAGE]->
MGR-0001 Rev. 3
SOUTHERN NUCLEAR PLANT E.I. HATCH DOCUMENT TITLE:
DOCUMENT NUMBER:
EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0 2.0 - RADIOLOGICAL EFFLUENTS (continued)
Emergency conditions exist WHEN:
A GASEOUS EFFLUENT RELEASE IS UNDERWAY WITH OFFSITE DOSE BEYOND THE SITE BOUNDARY, as indicated by either field measurements OR effluent monitor readings (using actual meteorological conditions) corresponding to:
> 5 REM(CDE thyroid) in an hour DOSE BEYOND THE SITE BOUNDARY IS PROJECTED TO BE > EPA PAGs based on dose projections from plant parameters as follows:
A gaseous release is ongoing or imminent AND
PAGE 10 OF 46 REVISIONNERSION NO:
14.3 N
U E
A L
E R
T S G A E E N IT T
I-1I
-I END RADIOLOGICAL EFFLUENTS MGR-0001 Rev. 3
SOUTHERN NUCLEAR PAGE 11 OF 46 PLANT E.I. HATCH DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISION/VERSION EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0o NO:
14.3 3.0 - CORE DAMAGE Emergency conditions exist WHEN:
NA S G
UL A E EE E N R
T CORE DAMAGE IS INDICATED BY HIGH OFF-GAS ACTIVITY WITH PRETREAT MONITOR (D11 K601) AT HI ALARM PLUS Pretreat Monitor reading exceeding either of following as indicated on pretreat graph located in Unit 1 OR Unit 2 OFF-GAS Release Curve book.
> 500,000 gCi/sec OR
>_ 100,000 g*Ci/sec increase WITHIN a 30 minute period CORE DAMAGE IS INDICATED BY HIGH OFF-GAS ACTIVITY WITH PRETREAT MONITOR (D1 1 K601) AT Hi-HI ALARM PLUS > 5 CI/SEC as indicated on pretreat graph located in Unit 1 OR Unit 2 Off-Gas Release Curve book CORE DAMAGE IS INDICATED BY HIGH COOLANT ACTIVITY LAB SAMPLE WITH 1-131 DOSE EQUIVALENT COOLANT ACTIVITY > 100 gCi/gm CORE DAMAGE IS INDICATED BY HIGH COOLANT ACTIVITY LAB SAMPLE WITH 1-131 DOSE EQUIVALENT COOLANT ACTIVITY > 300 jiCi/gm CORE DAMAGE IS INDICATED BY DEGRADED CORE WITH POSSIBLE LOSS OF CORE GEOMETRY as indicated by the following:
Containment Post LOCA Hi Rad Alarm > 138 REM/hr (TS)
AND Reactor Low, Low, Low, Level Alarm < -113 inches OR Noble Gas Fission Product Monitor (D11 -K630) upscale (7.0 x 105 cpm)
OR Noble Gas Fission Product Monitor (D1 1-K630) (variable setpoint) Hi-Hi Radiation Alarm See Section 22.0, Multiple Symptoms and Other Conditions for determination of General I
Emergency Classification.
END CORE DAMAGE MGR-0001 Rev. 3
SOUTHERN NUCLEAR PAGE 12 OF 46 PLANT E.I. HATCH r
DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISIONNERSION EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0 NO:
14.3 4.0 - STEAM LINE BREAK OR SAFETY RELIEF VALVE (SRV) FAILURE Emergency conditions exist WHEN:
NASG R
T A MAIN STEAM LINE RELIEF VALVE FAILED TO CLOSE WHEN system pressure is reduced below setpoint of safety relief valve (S/RV) and fuses pulled as indicated by:
S/RV tailpipe temperature remaining > 2300 F AND S/RV tailpipe pressure switch remaining > 80 psig AND Temperature continuing to increase on any suppression pool local water temperature indicator A PRIMARY SYSTEM (AS DEFINED BY EOPs) STEAM LINE BREAK OCCURS OUTSIDE CONTAINMENT WITH significant isolation valve leakage as indicated by the following:
Any valid Reactor or Turbine Bldg. leak detection indication OR Hi MSL Tunnel Temperature > 1940 F (TS)
AND Any Reactor Bldg. ARM above maximum Normal Operating Values AND increasing OR Any Turbine Bldg. ARM above alarm setpoint AND increasing
+--[CONTINUE TO THE NEXT PAGE]-> --
MGR-0001 Rev. 3
PAGE 13 OF 46 SOUTHERN NUCLEAR PLANT E.I. HATCH DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISION/VERSION EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0 NO:
14.3 4.0 - STEAM LINE BREAK OR SAFETY RELIEF VALVE (SRV) FAILURE (continued)
Emergency conditions exist WHEN:
N ASlG R
T AN UNISOLABLE PRIMARY SYSTEM (AS DEFINED BY THE EOPs) BREAK OUTSIDE CONTAINMENT as indicated by:
A primary containment isolation failure (cannot be isolated automatically OR manually) has occurred on the affected primary system.
AND Entry conditions into Secondary Containment Control Emergency Operating Procedures OR Any indications of significant leakage into the Turbine Bldg. from the Main Steam system WITH Turbine Bldg. ARMs above alarm setpoint AND increasing.
OR SOS/ED judgment See Section 22.0, Multiple Symptoms and Other Conditions, for determination of General Emergency Classification.
END STEAM LINE BREAK OR SAFETY RELIEF VALVE (SRV) FAILURE MGR-0001 Rev. 3
SOUTHERN NUCLEAR PAGE 14 OF 46 PLANT E.I. HATCH DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISION/VERSION EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0 NO:
14.3 5.0 - LOSS OF AC POWER Emergency conditions exist WHEN:
N A S G
U L A E A LOSS OF OFFSITE POWER OR LOSS OF ONSITE AC POWER CAPABILITY HAS OCCURRED and E
E E
N is indicated as follows:
R T
Loss OF OFFSITE POWER is indicated by:
Zero voltage on all 500 kV incoming lines AND Zero voltage on all 230 kV incoming lines OR Loss of startup transformers (SUTs) 1C AND 1D OR Loss of startup transformers (SUTs) 2C AND 2D Loss OF ONSITE AC POWER CAPABILITY is indicated by:
Loss of all emergency diesel generators on Unit One OR Unit Two for any reason Loss OF OFFSITE POWER WITH LOSS OF ALL ONSITE AC POWER <15 MINUTES (on Unit One OR Unit Two) is indicated by:
All 4.16 kV buses (Unit One OR Unit Two) reading zero volts AC AND The inability to energize at least one Unit One AND one Unit Two 4.16 kV bus WITH diesel generators Loss OF OFFSITE POWER WITH LOSS OF ALLn ONSITE AC POWER >1 5 MINUTES (on Unit One OR Unit Two) is indicated by:
All 4.16 KV buses (Unit One ORt Unit Two) reading zero volts AC AND The inability to energize at least one Unit One AND one Unit Two 4.16 kV bus WITH diesel generators See Section 22.0, Multiple Symptoms and Other Conditions, for Determination of General Emergency Classification.III END LOSS OF AC POWER MGR-0001 Rev. 3
SOUTHERN NUCLEAR PLANT E.I. HATCH DOCUMENT TITLE:
EMERGENCY CLASSIFICATION AND INITIAL ACTIONS PAGE 15 OF 46 DOCUMENT NUMBER:
73EP-EIP-001-0 REVISIONNERSION NO:
14.3 6.0 - LOSS OF ONSITE DC POWER Emergency conditions exist WHEN:
"A LOSS OF ALL VITAL ONSITE DC POWER OCCURS and is indicated as follows:
"A LOSS OF ALL VITAL ONSITE DC POWER OCCURS FOR < 15 MINUTES as indicated by:
Low voltage AND/OR fuse trouble on ALL the affected unit's 125v/250v station batteries AND Low voltage AND/OR fuse trouble on the affected unit's 125v D/G batteries (including the swing D/G)
"A LOSS OF ALL VITAL ONSITE DC POWER OCCURS FOR > 15 MINUTES as indicated by:
Low voltage AND/OR fuse trouble on ALL the affected unit's 125v/250v station batteries AND Low voltage AND/OR fuse trouble on the affected unit's 125v D/G batteries (including the swing D/G)
END LOSS OF ONSITE DC POWER MGR-0001 Rev. 3
SOUTHERN NUCLEAR PLANT E.I. HATCH "PAGE 16 OF 46 DOCUMENT TITLE:
DOCUMENT NUMBER:
EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0 REVISIONNERSION NO:
14.3 7.0 - LOSS OF CONTAINMENT Emergency conditions exist WHEN:
NA UL EE R
T NOTE NUE is to be declared upon commencing Load Reduction.
A LOSS OF PRIMARY OR SECONDARY CONTAINMENT INTEGRITY OCCURS as indicated by the inability to meet any one of the requirements WITHIN the time limit established by the applicable unit's TS.
See Section 11.0, Hazards to Plant Operation, for determination of Alert Classification.
See Section 11.0, Hazards to Plant Operation for determination of Site Area Emergency Classification.
See Section 22.0, Multiple Symptoms and Other Conditions, for determination of General Emergency Classification.
END LOSS OF CONTAINMENT S
A E
G E
N MGR-0001 Rev. 3 I
SOUTHERN NUCLEAR I
PAGE 17 OF 46 PLANT E.I. HATCH I
DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISIONNERSION EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0 NO:
14.3 8.0 - FIRE IN PLANT Emergency conditions exist WHEN:
NASG R
T A FIRE CONTINUING > 10 MINUTES (AFTER DISCOVERY) EXISTS WITHIN THE PROTECTED AREA, INCLUDING 230 KV AND 500 KV SWITCHYARDS, as indicated by:
Fire Alarm WITH visual confirmation OR SOS/ED judgment NOTE Refer to the System Evaluation Document (SED) for a listing of safety systems.
A FIRE CONTINUING > 10 MINUTES (AFTER DISCOVERY) EXISTS POTENTIALLY AFFECTING SAFETY SYSTEMS, required for the present mode of operation, as indicated by:
Fire Alarm AND Location, observation AND judgment of SOS/ED A FIRE CONTINUING > 10 MINUTES (AFTER DISCOVERY) COMPROMISING THE FUNCTIONS OF SAFE SHUTDOWN SYSTEMS as indicated by:
Fire defeating redundant safety system trains required for the current mode of operation OR Loss of safety system due to fire that affects shutdown capability by the inability to perform ONE of the following functions:
"* Prevent excessive reactor pressurization
"* Provide adequate makeup inventory
"* Depressurize the reactor
"* Remove decay heat from the reactor OR Location, observation AND judgment of SOS/ED See Section 22.0, Multiple Symptoms and Other Conditions for determination of General Emergency Classification.
END FIRE IN PLANT MGR-0001 Rev. 3
SOUTHERN NUCLEAR PAGE 18 OF 46 PLANT E.I. HATCH r
DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISIONNERSION EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0 NO:
14.3 9.0 - SECURITY EVENT Emergency conditions exist WHEN:
NASG R
T A SECURITY ALERT OCCURS as indicated by 2
Nuclear Security Shift Supervisor advises SOS/ED of Security Alert condition AND SOS/ED judgment A SECURITY EMERGENCY OCCURS as indicated by:
Nuclear Security Shift Supervisor advises the SOS/ED of a Security Emergency condition AND SOS/ED judgment A LOSS OF PHYSICAL CONTROL OF THE PLANT IS IMMINENT as indicated by:
Loss of physical barrier capability or control of the protected area OR Attempted unauthorized entry into the protected area by force or covert action AND SOS/ED judgment based on Nuclear Security Shift Supervisor advice A LOSS OF PHYSICAL CONTROL OF THE PLANT IS IMMINENT as indicated by:
Loss of physical barrier capabilities of any vital building OR Loss of control of any vital area including:
"* Intake Structure
"* Main Control Room
"* Diesel Generator Bldg.
CAS/SAS Power Block AND SOS/ED judgment based on Nuclear Security Shift Supervisor advice END SECURITY EVENT MGR-0001 Rev. 3
SOUTHERN NUCLEAR PAGE 19 OF 46 PLANT E.I. HATCH I
DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISION/VERSION EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0 NO:
14.3 10.0- NATURAL PHENOMENON Emergency conditions exist WHEN:
NASG EARTHQUAKE DETECTED:
EEEN R
T ANY EARTHQUAKE IS DETECTED WITHIN THE PLANT as indicated by:
Felt by Personnel OR Confirmed "Seismic Instrumentation Triggered" (Unit 1) alarm indicating horizontal acceleration > 0.005 g ANY EARTHQUAKE IS DETECTED WITHIN THE PLANT as indicated by:
"Seismic Instrumentation Triggered" (Unit 2) alarm indicating horizontal acceleration
_>0.08g Operating Basis Earthquake (OBE Level)
OR Any horizontal (N-S, E-W) peak shock annunciator 12.7 hz AMBER light illuminated indicates 100% OBE actuated on Panel 1 H1 1-P701 AND "Seismic Instrumentation Triggered" (Unit 1) alarm indicating horizontal acceleration > 0.005g Unit 1 AND/OR Unit 2 Seismic Peak Shock Recorder High "G" Alarm OR Unit 1 AND Unit 2 Time-History Recorders start
> [CONTINUE TO THE NEXT PAGE]->
MGR-0001 Rev. 3
SOUTHERN NUCLEAR PLANT E.I. HATCH DOCUMENT TITLE:
DOCUMENT NUMBER:
EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0 PAGE 20 OF 46 REVISIONNERSION NO:
14.3 10.0 - NATURAL PHENOMENON, (continued)
Emergency conditions exist WHEN:
N AS G EARTHQUAKE DETECTED: (continued)
E E E N R
T NOTE The actual maximum g acceleration may be determined by having I & C play back the Time-History Recorder's tapes per the Earthquake Response Manual, SX1 8271 (located in Document Control) and the applicable I & C procedure(s).
ANY EARTHQUAKE IS DETECTED WITHIN THE PLANT as indicated by:
Same parameters as in the Alert classification AND Any horizontal (N-S, E-W) peak shock annunciator, 12.7 hz RED light illuminated on Panel 1 H 11 -P701 indicating maximum g level measured by Time-History Recorders as -> 0.15g Design Basis Earthquake (DBE)
AND EITHER unit NOT in Cold Shutdown AN EARTHQUAKE THAT COULD CAUSE MASSIVE DAMAGE TO ANY -PLANT SYSTEM WHICH COULD LEAD TO CORE DEGRADATION OR CORE MELT as indicated by:
Loss of systems needed to maintain integrity of all three fission product barriers:
"* Fuel Integrity
"* RCS Integrity
"* Containment Integrity OR Observation and judgment of SOS/ED.
END - EARTHQUAKE
[NATURAL PHENOMENON - CONTINUED TO NEXT PAGE]-->
MGR-0001 Rev. 3 I
SOUTHERN NUCLEAR PAGE 21 OF 46 PLANT E.I. HATCH DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISION/VERSION EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0 NO:
14.3 10.0 - NATURAL PHENOMENON, (continued)
Emergency conditions exist WHEN:
NASG HIGH WINDS EXIST:
EEEN R
T HIGH WINDS are indicated by:
Any tornado observed onsite Any hurricane force winds projected onsite with windspeed > 75 mph Any tornado observed striking the operating facility (areas within the protected area and the 230 Kv and 500 Kv switchyards)
OR Any hurricane observed onsite with sustained windspeeds at design level LŽ 94.5 mph)
OR SOS/ED judgment CAUTION The wind speed instrumentation will not reflect the actual wind speeds of a tornado. Consideration should be given to the distance of a reported tornado from the met tower and the extent of the reported damage when attempting to determine if the wind speed "exceeds the range of the instrumentation (> 100 mph)".
The observation of damage from an onsite tornado with windspeed in excess of meteorological instruments range (>100 mph)
OR Sustained windspeeds in excess of meteorological instruments range (>100 mph)
AND Either unit NOT in Cold Shutdown END - HIGH WINDS
-4
[NATURAL PHENOMENON - CONTINUED TO NEXT PAGE]-
MGR-0001 Rev. 3
SOUTHERN NUCLEAR PAGE 22 OF 46 PLANT E.I. HATCH DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISION/VERSION EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0 NO:
14.3 10.0- NATURAL PHENOMENON, (continued)
Emergency conditions exist WHEN:
NA S G
UL A E HIGH / LOW RIVER WATER LEVEL INDICATED:
E E N R
T HIGH RIVER WATER LEVEL is indicated by:
Plant Service Water Intake Pump well level indication > 88.6 ft Mean Sea Level (MSL)
Plant Service Water Intake Pump well level indication > 100 ft MSL Plant Service Water Intake Pump well level indication _> 120 ft MSL OR Actual OR projected hurricane surge OR flood levels > 120 ft MSL AND Either unit NOT in Cold Shutdown Low RIVER WATER LEVEL is indicated by:
Plant Service Water Intake Pump well level indication < 60.7 ft Mean Sea Level (MSL)
Plant Service Water Intake Pump well level indication < 59.9 ft MSL Plant Service Water Intake Pump well level indication < 57.2 ft MSL AND Either unit NOT in Cold Shutdown END - HIGH I LOW RIVER WATER LEVEL END NATURAL PHENOMENON MGR-0001 Rev. 3 I
SOUTHERN NUCLEAR PAGE 23 OF 46 PLANT E.I. HATCH DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISION/VERSION EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0 NO:
14.3 11.0 - HAZARDS TO PLANT OPERATION Emergency conditions exist WHEN:
NASG AIRCRAFT ACTIVITY EEEN R
T UNUSUAL AIRCRAFT ACTIVITY IS OBSERVED over the operating facility (areas within the protected area and the 230 Kv and 500 Kv switchyards)
OR AIRCRAFT CRASH OCCURS within the owner controlled area AND SOS/ED judgment AIRCRAFT CRASH OCCURS WITHIN THE OPERATING FACILITY (areas within the protected area and the 230 Kv and 500 Kv switchyards)
AIRCRAFT CRASH OCCURS AFFECTING VITAL OPERATING PLANT STRUCTURES by impact OR fire including:
"* Intake Structure
"* Main Control Room
"* Diesel Generator Bldg.
"* CAS/SAS
"* Power Block AND Either unit NOT in Cold Shutdown OR SOS/ED judgment END - AIRCRAFT ACTIVITY MGR-0001 Rev. 3
-> [HAZARDS TO PLANT OPERATION - CONTINUED TO NEXT PAGE]->
SOUTHERN NUCLEAR PAGE 24 OF 46 PLANT E.I. HATCH I
DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISION/VERSION EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0 NO:
14.3 11.0 - HAZARDS TO PLANT OPERATION, (continued)
Emergency conditions exist WHEN:
N. A S
G UAlE EXPLOSIONS EEE N
R T
ANY EXPLOSION OBSERVED WITHIN THE OPERATING FACILITY (areas within the protected area and the 230 Kv and 500 Kv switchyards)
KNOWN EXPLOSION DAMAGE TO FACILITY (ONSITE) AFFECTING PLANT OPERATION SEVERE DAMAGE TO SAFE SHUTDOWN EQUIPMENT FROM MISSILES OR EXPLOSION THAT AFFECTS SHUTDOWN CAPABILITY by the inability to perform ONE of the following functions:
Prevent excessive reactor pressurization OR Provide adequate makeup inventory OR Depressurize the reactor OR Remove decay heat from the reactor AND Either unit NOT in Cold Shutdown END - EXPLOSIONS
--> [HAZARDS TO PLANT OPERATION - CONTINUED TO NEXT PAGE]-->
MGR-0001 Rev. 3
SOUTHERN NUCLEAR PLANT E.I. HATCH PAGE 25 OF 46 DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISION/VERSION EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0 NO:
14.3 11.0 - HAZARDS TO PLANT OPERATION, (continued)
Emergency conditions exist WHEN:
NASG TOXIC GAS RELEASED:
EEEN R
T OBSERVATION OF SIGNIFICANT TOXIC GAS RELEASE WITHIN the operating facility (areas within the protected area and the 230 Kv and 500 Kv switchyards)
AND SOS/ED judgment UNCONTROLLED TOXIC GAS ENTRY INTO PROTECTED AREA FACILITY ENVIRONS UNCONTROLLED TOXIC GAS ENTRY INTO A VITAL AREA restricting access and constituting a safety problem:
Intake Structure Main Control Room Diesel Generator Bldg.
CAS/SAS Power Block AND Either unit NOT in Cold Shutdown END - TOXIC GAS
-- [HAZARDS TO PLANT OPERATION - CONTINUED TO NEXT PAGE]-
MGR-0001 Rev. 3 NOTE Toxic gas releases may hamper the ability of personnel to perform activities related to plant safety. Releases within the protected area of the plant may jeopardize the operation of equipment or safety functions necessary to establish or maintain cold shutdown. Releases which may fall into this category include, but are NOT limited to Carbon Dioxide, Nitroqen and Chlorine.
CAUTION DO NOT LIMIT EVALUATION OF THE CONDITION BASED ON THE CHEMICAL DEFINITION OF THE MATERIAL IN QUESTION. THE WORD "TOXIC" IN THESE EALS IS A BROAD CATEGORY OF MATERIALS WHICH HAVE THE POTENTIAL FOR LIMITING THE ABILITY OF PERSONNEL TO PERFORM WORK ACTIVITES ASSOCIATED WITH PLANT SAFETY.
PAGE 26 OF 46 SOUTHERN NUCLEAR PLANT E.I. HATCH DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISIONTERSION EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0 NO:
114.3 11.0 - HAZARDS TO PLANT OPERATION, (continued)
Emergency conditions exist WHEN:
NASG FLAMMABLE GAS RELEASED:
EEEN R
T NOTE Flammable gas releases may jeopardize the operation of equipment or safety functions necessary to establish or maintain cold shutdown.
OBSERVATION OF SIGNIFICANT FLAMMABLE GAS RELEASE WITHIN the operating facility (areas within the protected area and the 230 Kv and 500 Kv switchyards)
OR PIPING RUPTURE IN ANY FLAMMABLE GAS SYSTEM (i.e., hydrogen, propane, etc.)
OR SOS/ED judgment UNCONTROLLED FLAMMABLE GAS ENTRY into any Protected Area facility environs UNCONTROLLED FLAMMABLE GAS ENTRY INTO VITAL AREAS INCLUDING:
"* Intake Structure
"* Main Control Room
"* Diesel Gen. Bldg.
CAS/SAS Power Block AND Either unit not in cold shutdown END - FLAMMABLE GAS MGR-0001 Rev. 3
-> [HAZARDS TO PLANT OPERATION - CONTINUED TO NEXT PAGE]--
SOUTHERN NUCLEAR IPAGE 27 OF 46 PLANT E.I. HATCH DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISION/VERSION EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0 NO:
14.3 11.0 - HAZARDS TO PLANT OPERATION, (continued)
Emergency conditions exist WHEN:
NASG TURBINE FAILURE/MISSILE IMPACT EEEN R
T A TURBINE FAILURE GENERATING PROJECTILES is indicated by:
Main Turbine Trip AND Confirmation of rotating component failure OR SOS/ED judgment A TURBINE FAILURE GENERATING PROJECTILES is indicated by:
Main turbine trip AND Turbine casing penetration by internal components OR Projectile from any source, affects plant operation OR SOS/ED judgment END - TURBINE FAILURE/MISSILE IMPACT END HAZARDS TO PLANT OPERATION MGR-0001 Rev. 3
SOUTHERN NUCLEAR PAGE 28 OF 46 PLANT E.I. HATCH DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISION/VERSION EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0o NO:
14.3 12.0 - THIS SECTION INTENTIONALLY LEFT BLANK MGR-0001 Rev. 3
SOUTHERN NUCLEAR PLANT E.I. HATCH PAGE 29 OF 46 DOCUMENT TITLE:
DOCUMENT NUMBER:
EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0 REVISION/VERSION NO:
14.3 13.0 - CONTROL ROOM EVACUATION Emergency conditions exist WHEN:
N A S G
AN EVACUATION OF THE MAIN CONTROL ROOM IS IMMINENT as indicated by:
E E E N R
T Entry into the Remote Shutdown procedures used to shutdown the plant from outside the Control Room.
An evacuation of the Main Control Room is ordered AND Control of shutdown systems from local stations is NOT established within 15 minutes after Main Control Room evacuation.
END CONTROL ROOM EVACUATION MGR-0001 Rev. 3
SOUTHERN NUCLEAR PAGE 30 OF 46 PLANT E.I. HATCH DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISIONNERSION EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0 NO:
14.3 14.0 - CONTROL ROD DROP Emergency conditions exist WHEN:
N A S
G U L A E A CONTROL ROD DROP ACCIDENT OCCURS as indicated by:
E E
N R
T Local power range monitors (LPRM) indicate abnormal neutron flux in the vicinity of the suspected dropped rod AND MSL high rad monitors > 3X normal background OR Average power range monitor (APRM) upscale trip of RPS channels "A" and/or "B" Unit 1 > 120% RTP Unit 2 > 120% RTP OR Intermediate range monitor (IRM) upscale trip of RPS channels "A" and/or "B" Either unit > 120/125 divisions of full scale END CONTROL ROD DROP MGR-0001 Rev. 3
SOUTHERN NUCLEAR PAGE 31 OF 46 PLANT E.I. HATCH I
DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISIONNERSION EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0 NO:
14.3 15.0 - FAILURE OF REACTOR PROTECTION SYSTEM Emergency conditions exist WHEN:
NA S G
UL A E EE E N R
T A FAILURE OF THE REACTOR PROTECTION SYSTEM (RPS) TO INITIATE A SCRAM as indicated by:
Valid automatic scram signal AND Reactor NOT subcritical OR subcriticality cannot be maintained A FAILURE OF THE REACTOR PROTECTION SYSTEM (RPS) TO INITIATE AND COMPLETE A SCRAM which brings the reactor subcritical, is indicated by:
Valid automatic AND manual scram signal AND Reactor NOT subcritical OR subcriticality cannot be maintained A TRANSIENT REQUIRING OPERATION OF SHUTDOWN SYSTEMS WITH FAILURE TO SCRAM (continued power generation but no core damage immediately evident) is indicated by Valid automatic AND manual scram signal AND
< 3% power generation cannot be achieved OR maintained AND Standby Liquid Control initiation required See section 22.0, Multiple Systems and Other Conditions, for determination of the General Emergency Classification END FAILURE OF REACTOR PROTECTION SYSTEM MGR-0001 Rev. 3
SOUTHERN NUCLEAR PAGE 32 OF 46 PLANT E.I. HATCH DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISIONNERSION EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0 NO:
14.3 16.0 - LOSS OF CONTROL ROOM INDICATION/ALARMS/ANNUNCIATORS Emergency conditions exist WHEN:
NASG R
T ANY SIGNIFICANT LOSS OF ANY ONE OF THE FOLLOWING MAIN CONTROL ROOM INDICATION OR ALARMS, THAT REDUCE ASSESSMENT CAPABILITY TO THE EXTENT REQUIRING PLANT SHUTDOWN BY TS:
"* Plant Process Computer
"* Safety Parameter Display System
"* Radioactive Effluent Instrumentation AND The plant NOT shut down WITHIN the time limit specified by TS MOST OR ALL MAIN CONTROL ROOM ALARMS (ANNUNCIATORS) LOST as indicated by:
Observation OR failure in alarm check OR SOS/ED iudgment MOST O.R ALL MAIN CONTROL ROOM ALARM (ANNUNCIATORS) LOST WITH PLANT TRANSIENT INITIATED OR IN PROGRESS as indicated by:
Observation of plant transient (i.e., reactor trip, turbine trip, loss of feedwater, etc-)
OR SOS/ED judgment END LOSS OF CONTROL ROOM INDICATION/ALARM/ANNUNCIATORS MGR-0001 Rev. 3
SOUTHERN NUCLEAR PLANT E.I. HATCHI PAGE 33 OF 46 DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISION/VERSION EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0 NO:
17.0 - LOSS OF SHUTDOWN FUNCTIONS Emergency conditions exist WHEN:
NASG R
T A COMPLETE LOSS OF ANY FUNCTION NEEDED FOR PLANT COLD SHUTDOWN is indicated by:
Both trains of RHR shutdown cooling mode unavailable for any reason AND Loss of alternate shutdown cooling modes AND Inability to maintain reactor coolant temperature < 2120 F, WHEN required.
See section 22.0, Multiple Symptoms and Other Conditions, for determination of the General Emergency Classification END LOSS OF SHUTDOWN FUNCTIONS MGR-0001 Rev. 3 SOUTHERN NUCLEAR I
PLANT E.I. HATCH
DOCUMENT NUMBER:
REVISIONNERSION 73EP-EIP-001-0 NO:
14.3 18.0 - FUEL DAMAGE BY FUEL HANDLING ACCIDENT Emergency conditions exist WHEN:
NASG R
T A FUEL HANDLING ACCIDENT WITH RELEASE OF RADIOACTIVITY TO REACTOR BUILDING is indicated by:
Valid Refueling Floor ARM Hi Alarm > 50 mR/hr OR Valid "REFUELING FLOOR VENT EXHAUST RADIATION HI-HI" Alarm (601-403)
AND Any of the following process radiation monitors indicating > 20 mR/hr
"* 1D11-K611A-D
"° 2D11-K611A-D
"° 2D11-K634A-D
"* 2D11-K635A-D OR Valid "REFUELING FLOOR VENT FLTR DISCH RADIATION HIGH" Alarm (601-42 AND Any of the following process radiation monitors indicating > 20 mR/hr
"* 1D11-K616A,lB
"* 2D11-K616A, B MAJOR DAMAGE TO SPENT FUEL IN REACTOR BUILDING as indicated by:
Spent Fuel Storage Pool Low Level Alarm AND More than one Refuel Floor ARM exceeding Max Safe Operating Value OR Large object damages spent fuel in pool AND SOS/ED judgment (based on refueling floor radiation levels)
END FUEL DAMAGE BY FUEL HANDLING ACCIDENT MGR-0001 Rev. 3
SOUTHERN NUCLEAR PAGE 35 OF 46 PLANT E.I. HATCH DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISIONNERSION EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0 NO:
14.3 19.0 - HIGH RADIATION OR AIRBORNE CONTAMINATION Emergency conditions exist WHEN:
NA S
G U
LA E
EE E
N R
T HIGH RADIATION LEVELS OR HIGH AIRBORNE CONTAMINATION WHICH INDICATE A SEVERE DEGRADATION IN CONTROL OF RADIOACTIVE MATERIAL is indicated by:
ARMs are offscale high (readings confirmed)
OR An increase by factor of 1,000 in direct radiation readings END HIGH RADIATION OR AIRBORNE CONTAMINATION MGR-0001 Rev. 3
SOUTHERN NUCLEAR PAGE 36 OF 46 PLANT E.I. HATCH I
DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISIONNERSION EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0 NO:
14.3 20.0 - LOSS OF COOLANT Emergency conditions exist WHEN:
N A S G
L EEE R
T NOTE NUE is to be declared based upon commencing Load Reduction.
ANY CONFIRMED REACTOR COOLANT SYSTEM (RCS) OPERATIONAL LEAKAGE AS DEFINED BY TS is indicated by:
Any RCS pressure boundary leakage ANY CONFIRMED REACTOR COOLANT SYSTEM (RCS) LEAK O.R UNISOLABLE SYSTEM LEAK 7
CAUSING THE DIRECT LOSS OF VESSEL INVENTORY GREATER THAN 50 GPM as indicated by:
Calculation of RCS leak rate greater than 50 gpm using Drywell Equip AND/OR Floor Drain Sump level integrators on Panel H1 1-P613 OR SOS/ED judgment that an unisolable RCS leak greater than 50 GPM into the Reactor Building has occurred and may be indicated by one OR more of the following indications:
"* Reactor Building Equip AND/OR Floor Drain Sump level high alarms
"* Valid leak detection alarms
"* Any confirmed ARM in the Reactor Building above Max Normal Operating Values.
OR SOS/ED judgment ANY CONFIRMED REACTOR COOLANT SYSTEM (RCS) LEAK is indicated by:
RCS leak greater than all available ECCS pump capacities AND Reactor low, low, low level alarm < -113 inches AND level decreasing with available makeup pumps running and discharging to vessel AND Drywell High Temp Alarms AND Drywell temperature increasing OR Drywell high pressure initiation alarm > 1.92 psig AND increasing See section 22.0, Multiple Symptoms and Other Conditions for determination of the General Emergency Classification END LOSS OF COOLANT MGR-0001 Rev. 3 T
SOUTHERN NUCLEAR PLANT E.I. HATCH PAGE 37 OF 46 DOCUMENT TITLE:
DOCUMENT NUMBER:
EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0 REVISION/VERSION NO:
14.3 21.0 - LOSS OF ENGINEERED SAFETY FEATURES Emergency conditions exist WHEN:
N A S G
!U L A E E E E N R
T THE LOSS OF ENGINEERED SAFETY FEATURES (ESF) WITH CONTINUED OPERATION OF EITHER UNIT BEYOND THE TIMEFRAME SPECIFIED IN THE APPLICABLE TS REQUIRED ACTION STATEMENT (RAS):
The following are engineered safety features (ESFs):
Automatic Depressurization System Containment Heat Removal System Containment Isolation System Control Rod Velocity Limiters Core Spray CRD Housing Supports Diesel Generators High Pressure Coolant Injection System Low Low Set Relief Logic System Low Pressure Coolant Injection System Main Control Room Environmental Control System Main Steam Line Flow Restrictor Main Steam Line Isolation Valves Post LOCA Hydrogen Recombiner System (i.e., Combustible Gas Control System)
Reactor Protection System Standby Gas Treatment System END LOSS OF ENGINEERED SAFETY FEATURES MGR-0001 Rev. 3
PAGE 38 OF 46 SOUTHERN NUCLEAR PLANT E.I. HATCH DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISIONNERSION EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0 NO:
14.3 22.0 - MULTIPLE SYMPTOMS AND OTHER CONDITIONS Emergency conditions exist WHEN:
N A S G
U L A E TECHNICAL SPECIFICATION SAFETY LIMITS ARE EXCEEDED:
E E E N R
T PLANT CONDITIONS THAT EXCEED ANY SAFETY LIMIT AS REQUIRED IN TS are indicated by the following categories:
Thermal Power OR Minimum Critical Power Ratio (MCPR)
OR Low reactor water level with irradiated fuel in the reactor vessel
< -139" in Unit 1 OR < -158" in Unit 2 OR Reactor vessel steam dome pressure > 1325 psig with irradiated fuel in the reactor vessel OR Other condition that in the SOS/ED judgement warrant increased awareness of the plant operating staff or State and/or local authorities.
END - TECHNICAL SPECIFICATION SAFETY LIMITS
[MULTIPLE SYMPTOMS AND OTHER CONDITIONS CONTINUED TO NEXT PAGE]-
-4 MGR-0001 Rev. 3
22.0 - MULTIPLE SYMPTOMS AND OTHER CONDITIONS, (continued)
Emergency conditions exist WHEN:
PRECAUTIONARY ACTIVATION OF TSC IS WARRANTED:
Plant conditions exist that warrant precautionary activation of the TSC and placing the EOF AND other key emergency responders on standby, as indicated by the following:
Observation AND SOS/ED judgment END - PRECAUTIONARY ACTIVATION OF TSC N
U E
[MULTIPLE SYMPTOMS AND OTHER CONDITIONS CONTINUED TO NEXT PAGE]---->
MGR-0001 Rev. 3 S
A E
G E
N A
L E
R T
SOUTHERN NUCLEAR PLANT E.I. HATCH P AGE 40 OF 46 DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISION/VERSION EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0 NO:
1A Z 22.0 - MULTIPLE SYMPTOMS AND OTHER CONDITIONS, (continued)
Emergency conditions exist WHEN:
N A S G
UIL A E PRECAUTIONARY ACTIVATION OF MONITORING TEAMS IS WARRANTED:
E E
E N
R T
Plant conditions exist that warrant activation of emergency centers and monitoring teams, OR a precautionary notification to the public near the site, as indicated by the following:
Observation AND SOS/ED judgment END - PRECAUTIONARY ACTIVATION OF MONITORING TEAMS
[MULTIPLE SYMPTOMS AND OTHER CONDITIONS CONTINUED TO NEXT PAGE]--> -4 MGR-0001 Rev. 3 PAGE 40 O
46
SOUTHERN NUCLEAR PLANT E.I. HATCH PAGE 41 OF 46 DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISIONNERSION EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0 NO:
I 14_3 22.0 - MULTIPLE SYMPTOMS AND OTHER CONDITIONS (continued)
Emergency conditions exist WHEN:
N A S G
U L A E POTENTIAL LARGE RELEASE OF RADIOACTIVITY EXISTS:
E E E N R
T PLANT CONDITIONS EXIST WHERE THE POTENTIAL RELEASE OF LARGE AMOUNTS OF RADIOACTIVITY IN A SHORT TIME PERIOD ARE POSSIBLE (e.g., any core melt situation) is indicated by the following conditions:
Transient (e.g., scram, loss of offsite power, etc.)
AND Failure of required core shutdown system (could lead to core melt in several hours)
[e.g., CRD system, SLC system, RPS, ECCS, DG'S, RHRSW]
AND Containment failure likely OR Small or large LOCA AND Failure of ECCS to perform (leading to core degradation or melt in minutes to hours)
AND Loss of containment imminent OR Small or large LOCA AND Containment performance is unsuccessful (affecting longer term success of ECCS. Could lead to core degradation OR melt in hours)
[CONTINUE TO THE NEXT PAGE]-> ->
MGR-0001 Rev. 3 FPAGE 41 OF 46
SOUTHERN NUCLEAR PLANT E.I. HATCH.I PAGE 42 OF 46 DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISION/VERSION EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0 NO:
14.3 22.0 - MULTIPLE SYMPTOMS AND OTHER CONDITIONS (continued)
Emergency conditions exist WHEN:
N A S G
U LIA E
POTENTIAL LARGE RELEASE OF RADIOACTIVITY EXISTS: (continued)
E E E N R
T OR Shutdown occurs AND Required decay heat removal systems (e.g., RHR) are rendered unavailable or non-safety systems heat removal capabilities are rendered unavailable AND Core degradation OR melt could occur in about ten hours WITH subsequent containment failure OR Any major internal OR external event which could cause massive damage to plant systems resulting in any of the conditions listed in multiple symptoms of potential larger releases of radioactivity OR SOS/ED judgment END - POTENTIAL LARGE RELEASE OF RADIOACTIVITY
+ [MULTIPLE SYMPTOMS AND OTHER CONDITIONS CONTINUED TO NEXT PAGE]--
MGR-0001 Rev. 3 SOUTHERN NUCLEAR I
PLANT E.I. HATCH
SOUTHERN NUCLEAR PLANT E.I. HATCH PAGE 43 OF 46 DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISIONIVERSION EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0 NO:
1A 'I 22.0 - MULTIPLE SYMPTOMS AND OTHER CONDITIONS (continued)
Emergency conditions exist WHEN:
N A S G
U LIA E
FIRE IN PLANT OCCURS:
E E E N
R T
A FIRE IN THE PLANT THAT COULD CAUSE MASSIVE DAMAGE TO ANY PLANT SYSTEM WHICH COULD LEAD TO CORE DEGRADATION OR CORE MELT as indicated by the following:
Loss of systems due to fire, needed to maintain integrity of all three fission product barriers.
"* Fuel Integrity
"* RCS Integrity
"* Containment Integrity OR Location, observation AND judgment of SOS/ED (Based upon Fire Brigade Leader's report.)
END - FIRE IN PLANT
[MULTIPLE SYMPTOMS AND OTHER CONDITIONS CONTINUED TO NEXT PAGE]--
MGR-0001 Rev. 3
SOUTHERN NUCLEAR PLANT E.I. HATCH PAGE 44 OF 46 DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISIONNERSION EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0 NO:
14.3 22.0 - MULTIPLE SYMPTOMS AND OTHER CONDITIONS (continued)
N A
S G
Emergency conditions exist WHEN:
U L
A E
Any of the following are indicated, using the Parameter Assessment Table below:
R T
A F-allure ot the Fuel Cladding AND Primary Containment with a potential loss of the Primary Coolant Boundary OR A Failure of the Fuel Cladding AND Primary Coolant Boundary with a potential loss of Primary Containment OR A Failure of the Primary Coolant Boundary AND Primary Containment with a potential loss of the Fuel Cladding
-I-I-i-A General Emergency should be declared when TWO boundaries (cladding, coolant, or containment) have an ACTUAL failure AND a THIRD boundary has an ACTUAL or POTENTIAL failure. IF a parameter is approaching emergency action level criteria and mitigation systems are unavailable, assume the barrier will be lost.
Exceeding ONE of the parameters below is an indication of an actual or potential loss of the associated boundary.
PARAMETER ASSESSMENT TABLE I
CLADDING COOLANT CONTAINMENT Actual Actual Actual 01 1-131 > 100liCi/cc 0
Unisolable primary system break E Integrity breached outside containment 0l DWRRM > 500 R/hr El Significant leakage in TB With TB ARMs E Drywell OR Torus _ 6%
above alarm setpoints and increasing, hydrogen with _>
5% oxygen El DW Pressure -> 25 psig 0 SOS judgement that containment is lost OR loss is imminent 0
DW Temperature > 300'F E1 Gap activity in DW Potential Potential Potential El Failure of ECCS to El Failure of SRVs to open with pressure E Containment pressure maintain RWL high off-scale approaching 56 psig El RWL -- -158" for 3.5 min 0
All 4160/600 V buses undervoltage E Drywell OR Torus Ž6%
AND MCUTL hydrogen with _ 5% oxygen 01 All 4160/600 V buses El Failure of ECCS to maintain RWL SOS/ED judgement that undervoltage containment loss is imminent END MULTIPLE SYMPTOMS AND OTHER CONDITIONS MGR-0001 Rev. 3
SOUTHERN NUCLEAR PLANT E.I. HATCHI PAGE 45 OF 46 DOCUMENT TITLE:
DOCUMENT NUMBER:
EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0 REVISION/VERSION NO:
1 4.
23.0 - ISFSI OPERATIONS Emergency conditions exist WHEN:
NASG ULA EEE R
T A Loss OF CASK CONFINEMENT BOUNDARY FOR ANY LOADED SPENT FUEL CASK OCCURS as indicated by:
Direct Radiation levels outside the ISFSI protected area boundary exceed 2 mrem in an hour AND Contamination levels outside the ISFSI protected area boundary exceed the technical specification limits for spent fuel storage cask surface contamination OR Direct Radiation Readings for a Loaded Spent Fuel Cask exceed the technical specification limit for overpack average surface dose rates.
DEGRADATION OF ANY SPENT FUEL CASK DUE To AN OPERATIONAL EVENT as indicated by:
Direct observation of a loaded spent fuel cask indicates cask confinement boundary or shielding damage due to an operational event
"* Cask handling
"* Cask drop
"* Cask tip-over AND SOS/ED judgment
[ISFSI OPERATIONS - CONTINUED TO NEXT PAGE]-> --
MGR-0001 Rev. 3 rýGE 45 OF 46' SOUTHERN NUCLEAR I
PLANT E.I. HATCH
SOUTHERN NUCLEAR PLANT E.I. HATCH PAGE 46 OF 46 DOCUMENT TITLE:
DOCUMENT NUMBER:
EMERGENCY CLASSIFICATION AND INITIAL ACTIONS 73EP-EIP-001-0 REVISIONN/ERSION NO:
111 _q 23.0 - ISFSI OPERATIONS (continued)
Emergency conditions exist WHEN:
N A
S G
U L A
E E
E E
N R
T A Loss of cask confinement boundary for any loaded spent fuel cask occurs as indicated by:
Degradation of any Spent Fuel Cask due to environmental phenomena or external events Direct observation of a loaded spent fuel cask indicates cask confinement boundary or shielding damage due to environmental phenomena or external events Tornado Explosion Lightning Flooding Earthquake Extreme environmental temperatures Burial under debris Fire Explosion Aircraft Crash Missile or projectile impact Security Event AND SOS/ED judgment END ISFSI OPERATIONS MGR-0001 Rev. 3
SOUTHERN NUCLEAR DOCUMENT TYPE:
PAGE PLANT E.I. HATCH EMERGENCY PREPAREDNESS PROCEDURE 1 OF 9 DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISION/VERSION ON-SHIFT OPERATIONS PERSONNEL EMERGENCY DUTIES 73EP-EIP-005-0 NO:
7 EXPIRATION APPROVALS:
EFFECTIVE DATE:
DEPARTMENT MANAGER JCL DATE 7/1/2002 DATE:
7/9/2002 N/A NPGM/POAGM/PSAGM JAB DATE 7/3/2002 1.0 OBJECTIVE This procedure provides guidance to on-shift operations personnel emergencies.
for response to declared TABLE OF CONTENTS Section 2.0 Title APPLICABILITY Paqe 1
3.0 REFERENCES
1 4.0 REQUIREMENTS 2
5.0 PRECAUTIONS/LIMITATIONS 2
6.0 7.0 7.1 7.2 7.3 7.4 7.5 PREREQUISITES PROCEDURE SUPERINTENDENT OF SHIFT (SOS)
SHIFT SUPERVISOR (SS)
SHIFT SUPPORT SUPERVISOR CONTROL ROOM OPERATOR SYSTEM OPERATOR 2
3 3
5 6
7 9
2.0 APPLICABILITY This procedure applies to responses and actions taken by on-shift operations personnel. This procedure is performed as required.
3.0 REFERENCES
3.1.
10AC-MGR-006-0, Hatch Emergency Plan 3.2. Edwin I. Hatch Unit 1 and Unit 2 Emergency Plan 3.3. FULL SIZE FORM TRN-0144, Emergency Page Announcement Guide MGR-0002 Rev. 8
SOUTHERN NUCLEAR PAGE PLANT E.I. HATCH 2 OF 9 DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISION/VERSION ON-SHIFT OPERATIONS PERSONNEL EMERGENCY DUTIES 73EP-EIP-005-0 NO:
7 4.0 REQUIREMENTS 4.1.
PERSONNEL REQUIREMENTS On-shift operations personnel who have received emergency response training are required to perform this procedure.
4.2.
MATERIAL AND EQUIPMENT N/A - Not applicable to this procedure 4.3. SPECIAL REQUIREMENTS N/A - Not applicable to this procedure 5.0 PRECAUTIONS/LIMITATIONS 5.1.
PRECAUTIONS N/A - Not applicable to this procedure 5.2.
LIMITATIONS This procedure is NOT intended for use by the Emergency Director (ED).
6.0 PREREQUISITES A declared emergency or an emergency drill/exercise must exist before using this procedure.
MGR-0001 Rev. 3
SOUTHERN NUCLEAR PAGE PLANT E.I. HATCH 3OF9 DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISION/VERSION ON-SHIFT OPERATIONS PERSONNEL EMERGENCY DUTIES 73EP-EIP-005-0 NO:
7 I
REFERENCE 7.0 PROCEDURE 7.1 SUPERINTENDENT OF SHIFT (SOS) 7.1.1 Review the event and classify the emergency in accordance with 73EP-EIP-001-0, Emergency Classification and Initial Actions.
7.1.2 Assume the duties of the ED in accordance with 73EP-EIP-004-0, Duties of Emergency Director.
7.1.3 After turnover of ED duties, perform the following:
7.1.3.1 Direct operation of the plant to mitigate consequences of the event and to restore to a safe operating condition.
7.1.3.2 Analyze plant conditions and assist the ED with reclassifications and protective action recommendations.
7.1.3.3 Advise the ED and TSC Manager on degrading plant conditions, initiation of any release or changes in the magnitude of any release as soon as practical.
7.1.3.4 Ensure communications is established and maintained with the emergency response facilities (ERFs), NRC, and Security, as appropriate.
MGR-0001 Rev. 3 NUE ALERT SITE-GENERAL AREA x
x x
x x
x x
x x
x x
x x
x x
x x
x x
x x
x x
SOUTHERN NUCLEAR PAGE PLANT E.I. HATCH 4 OF 9 DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISION/VERSION ON-SHIFT OPERATIONS PERSONNEL EMERGENCY DUTIES 73EP-EIP-005-0 NO:
7 7.2 SUPERINTENDENT OF SHIFT (SOS) (CONT'D)
NUE ALERT SITE- [GENERAL AREA 7.1.3.5 IF the main access road can not be used as a site exit route, coordinate with the X
X X
X Emergency Director and Security to open the alternate site exit route(s) to allow evacuating personnel to leave the plant site.
7.1.3.6 IF the following conditions are present which X
X X
may prevent facility activation, protected area evacuation or site evacuation, THEN consult with the ED and Security prior to dispatching Control Room personnel, making PA announcements or augmenting on-shift staffing:
security events severe weather conditions other hazards that affect personnel safety END OF 7.1, SUPERINTENDENT OF SHIFT (SOS)
MGR-0001 Rev. 3
SOUTHERN NUCLEAR PAGE PLANT E.l. HATCH 5 OF 9 DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISION/VERSION ON-SHIFT OPERATIONS PERSONNEL EMERGENCY DUTIES 73EP-EIP-005-0 NO:
7 7.2 SHIFT SUPERVISOR (SS)
NUE ALERT SITE-GENERAL AREA 7.2.1 IF the SOS is unavailable or incapacitated, x
x x
x assume the duties of SOS and perform the SOS duties in accordance with section 7.1 of this procedure. IF available, assign any qualified SRO to assume the unit SS duties.
7.2.2 Direct operation of the plant to mitigate x
x x
x consequences of the event and to restore to a safe operating condition.
7.2.3 Activate emergency response teams, IF X
x x
x necessary, by contacting the TSC (or the Health Physics office and other support departments IF the TSC is not activated) and provide directions regarding needed actions.
7.2.4 Assist in the performance of prompt offsite X
x x
x dose assessments, as needed.
7.2.5 Advise the SOS on any degradation of plant X
x x
x equipment, onset of a release, and changes in release magnitude as soon as possible.
7.2.6 Establish communications with the ERFs, x
x x
Plant Security, the ED and the NRC as requested by SOS.
END OF 7.2, SHIFT SUPERVISOR (SS)
MGR-0001 Rev. 3
SOUTHERN NUCLEAR PLANT E.I. HATCH DOCUMENT TITLE:
DOCUMENT NUMBER:
ON-SHIFT OPERATIONS PERSONNEL EMERGENCY DUTIES 73EP-EIP-005-0 7.3 SHIFT SUPPORT SUPERVISOR (SSS) 7.3.1 Maintain accountability of all SOs dispatched from the Control Room.
NOTE:
PAGE 6OF9 REVISION/VERSION NO:
7 All entries to areas with higher than normal radiological conditions must be dispatched from the OSC.
NUE ALERT SITE-GENERAL AREA 7.3.2 Ensure SOs are logged on the Operations X
X X
rounds blanket RWP to track their dose.
NOTE:
SOs can be dispatched with no limitations provided radiological conditions are not degraded.
NUE ALERT SITE-GENERAL AREA 7.3.3 Dispatch SOs to perform various tasks to X
X X
assist in mitigation of an emergency condition.
7.3.4 Coordinate with Control Room Operators to X
X X
monitor ARM readings and plant conditions for the location where SOs have been dispatched. IF conditions change, THEN withdraw all personnel dispatched to that location.
7.3.5 Send extra SOs to the OSC as conditions X
X X
allow. SOs for shutdown activities will remain in the Control Room.
END OF 7.3, SHIFT SUPPORT SUPERVISOR (SSS)
MGR-0001 Rev. 3
SOUTHERN NUCLEAR PAGE PLANT E.I. HATCH 7 OF 9 DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISION/VERSION ON-SHIFT OPERATIONS PERSONNEL EMERGENCY DUTIES 73EP-EIP-005-0 NO:
7 7.4 CONTROL ROOM OPERATOR NUE ALERT [SITE-GENERAL
-- AREA 7.4.1 Take actions to place the plant in a safe X
X X
X condition in accordance with annunciator response procedures, emergency operating procedures and Technical Specifications.
7.4.2 Periodically report plant status to the SS.
X X
X X
7.4.3 Notify the SS or SOS of any degradation to X
X X
X plant equipment.
7.4.4 Perform prompt offsite dose assessment X
X X
calculations in accordance with 73EP-EIP 018-0, Prompt Offsite Dose Assessment, as required. Refer to "Prerequisites" section of 73EP-EIP-018-0 to determine necessity to perform prompt offsite dose assessment calculation. Notify the SOS or SS of the onset of a release or any change in the magnitude of release. When the TSC is activated, turnover dose assessment duties to the TSC and exit procedure 73EP-EI P-01 8-0.
7.4.5 Notify the SSS of changes in plant conditions, X
X X
radiological conditions or radiological releases.
MGR-0001 Rev. 3
SOUTHERN NUCLEAR PLANT E.I. HATCH DOCUMENT TITLE:
DOCUMENT NUMBER:
ON-SHIFT OPERATIONS PERSONNEL EMERGENCY DUTIES 73EP-EIP-005-0 PAGE 8OF9 REVISION/VERSION NO:
7 7.4 CONTROL ROOM OPERATOR (CONT'D)
CAUTION:
CHANGES IN WIND DIRECTION MAY REQUIRE CHANGING RALLY POINTS AND EVACUATION ROUTES; THEREFORE, USE OF AVERAGE WIND DIRECTION IS ACCEPTABLE AND DESIRED. BE AWARE OF CHANGING
[NUE ALERT SITE-1GENERAL AREA 7.4.6 Complete form TRN-01 44, Emergency Page Announcement Guide, filling in the X
X X
X required sections.
7.4.7 Obtain concurrence from the SOS for PA x
x x
x announcements being made for the following circumstances:
"* security events
"* severe weather conditions
"* other hazards that affect personnel safety.
I NOTE:
The purpose of making announcements is to inform plant personnel of an event or change in conditions that warrants a response. The timeliness and accuracy of the announcement will have a direct effect on the implementation of that response.
Announcements are normally concise statements containing sufficient detail to elicit the appropriate response.
NUE ALERT SITE-GENERAL AREA 7.4.8 Sound the applicable warning tone, THEN make the appropriate announcement and, X
X X
X as directed by the SOS or SS and using the applicable section of TRN-01 44, Emergency Page Announcement Guide.
The appropriate announcement/tone will be made as soon as practicable upon initial emergency declaration, and every thirty (30) minutes for the first two (2) hours of the declared emergency. After the first two (2) hours, repeat the announcement/ tone as directed by the SS.
END OF 7.4, CONTROL ROOM OPERATOR MGR-0001 Rev. 3 I
SOUTHERN NUCLEAR PLANT E.I. HATCH PAGE 9 OF 9 DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISION/VERSION ON-SHIFT OPERATIONS PERSONNEL EMERGENCY DUTIES 73EP-EIP-005-0 NO:
7 7.5 SYSTEM OPERATOR (SO)
NUE I ALERT SITE AREA GENERAL 7.5.1 Complete current assigned task OR restore X
X X
equipment to a safe condition and report status to the Control Room.
7.5.2 Report to the SSS in the Control Room and X
X X
remain under his direction until dispatched to the OSC.
NOTE:
Unusual circumstances may require personnel to immediately terminate work activities and exit the area. These circumstances include, but are not limited to:
o an ARM alarms in the work area
- the worker's digital dosimeter alarms, or o a radiological event is announced and personnel are directed to evacuate the area NUE ALERT SITE-GENERAL 7.5.3 IF unusual circumstances occur in or near X
X X
your present location, THEN terminate your work activities, exit the area and report back to the SSS in the Control Room.
END OF 7.5, SYSTEM OPERATOR (SO)
MGR-0001 Rev. 3
SOUTHERN NUCLEAR PLANT E.I. HATCH DOCUMENT TYPE:
EMERGENCY PREPAREDNESS PROCEDURE PAGE 1 OF 12 DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISION/VERSION NUCLEAR SECURITY DUTIES 73EP-EIP-009-0 NO:
7.0 EXPIRATION APPROVALS:
DATE:
DEPARTMENT MANAGER N/A NPGM/POAGM/PSAGM JCL JAB DATE 7/1/2002 DATE 7/3/2002 EFFECTIVE DATE:
7/9/2002 1.0 OBJECTIVE This procedure establishes the minimum measures which are taken by the Nuclear Security Department to respond to declared emergencies.
TABLE OF CONTENTS Section Title Paqe 7.0 PROCEDURE 7.1 EOF SECURITY MANAGER 3
7.2 TSC SECURITY SUPERVISION 4
7.3 SECURITY SHIFT SUPERVISOR 5
7.4 SECURITY POST 200 CAS AND SAS 7
7.5 SECURITY POST 200 CHARLIE [PLANT 8
ENTRY SECURITY BUILDING (PESB)]
7.6 SECURITY POST 200 BRAVO (GATE 1) 8 7.7 TSC AND OSC ACCESS CONTROL 9
7.8 EOF ACCESS CONTROL 9
RIVER PATROL 10 7.10 EMERGENCY NEWS CENTER (ENC) 10 ACCESS CONTROL 7.11 7.12 7.13 ADDITIONAL SECURITY POSTS GATE 17 ACCESS CONTROL ACCOUNTABILITY 11 11 12 2.0 APPLICABILITY This procedure is applicable to responses taken by the Nuclear Security Department to declared emergencies, which implement the Hatch Emergency Plan. This procedure is performed as required.
MGR-0002 Rev. 8
SOUTHERN NUCLEAR PLANT E.I. HATCH DOCUMENT TITLE:
NUCLEAR SECURITY DUTIES DOCUMENT NUMBER:
73EP-EIP-009-0 PAGE 2 OF 12 REVISION/VERSION NO:
7.0
3.0 REFERENCES
3.1 10AC-MGR-006-0, Hatch Emergency Plan 3.2 Edwin I. Hatch Unit 1 & Unit 2 Emergency Plan, Section E 3.3 Emergency Response Facility Position Matrix 3.4 FULL-SIZE FORM
= TRN-0147, Plant Hatch Owner-Controlled Area 4.0 RESPONSIBILITIES 4.1 PERSONNEL REQUIREMENTS 4.1.1 Security Personnel who have received instruction in applicable emergency implementing procedures are required to perform this procedure.
4.1.2 Off-duty Nuclear Security officers may be called in to man the various posts/patrols, including access control at the Emergency News Center.
4.2 MATERIAL AND EQUIPMENT N/A - Not applicable to this procedure 4.3 SPECIAL REQUIREMENTS N/A - Not applicable to this procedure 5.0 PRECAUTIONS/LIMITATIONS 5.1 PRECAUTIONS Uncertain or higher than normal radiological conditions may be encountered during actual emergencies. Maintain radiation exposure ALARA 5.2 LIMITATIONS N/A - Not applicable to this procedure 6.0 PREREQUISITES A declared emergency OR an emergency drill/exercise must exist before using this procedure.
MGR-0001 Rev. 3
SOUTHERN NUCLEAR PLANT E.I. HATCH PAGE 3 OF 12 DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISION/VERSION NUCLEAR SECURITY DUTIES 73EP-EIP-009-0 NO:
7.0 REFERENCE 7.0 PROCEDURE NOTE:
The Emergency Response Facility (ERF) Position Matrix may be used to determine those individuals who may assume the following emergency response positions.
7.1 EOF SECURITY MANAGER NUE ALERT SITE-GENERAL
_I
_[AREA 7.1.1 Report to EOF to assume the position of EOF Security X
X X
Manager.
7.1.2 Ensure Security staff personnel for the TSC, OSO and X
X X
EOF are dispatched as required. Additional support persons may be brought in to assist the EOF Security Manager, as needed.
7.1.3 Contact the Public Information (PI) Director to determine X
X X
when Security personnel will be needed for access control at the Emergency News Center complex. Refer to the Emergency Call List for applicable phone number(s).
7.1.4 Inform the Security Shift Supervisor when Security X
X X
personnel will be needed at the Emergency News Center complex.
7.1.5 Coordinate security activities as requested by the X
X X
Emergency Director or EOF Manager.
NOTE:
The Emergency Director may order evacuation of non-essential personnel at any I
emergency classification.
A.
NUE IALERT SITE-IGENER AREA 7.1.6 Establish contact with local law enforcement representatives (in the applicable County Emergency Operations Centers) to coordinate the release of non essential personnel from the plant site, as necessary.
7.1.7 Evaluate the event and make recommendations to Emergency Response Management, as required.
X X
X X
X X
END OF 7.1, EOF SECURITY MANAGER MGR-0001 Rev. 3
SOUTHERN NUCLEAR PAGE PLANT E.I. HATCH 4 OF 12 DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISION/VERSION NUCLEAR SECURITY DUTIES 73EP-EIP-009-0 NO:
7.0 7.2 TSC SECURITY SUPERVISION NUE ALERT ASITE-GENERAL AREA 7.2.1 Report to the TSC to assume the position of TSC X
X X
Security Supervisor.
7.2.2 Ensure that actions taken by Security shift supervisor X
X X
are appropriate.
7.2.3 Confer with TSC HP/Chemistry Supervision concerning x
x x
radiological conditions as they pertain to Security personnel assignments.
7.2.4 Ensure radiological condition information is relayed to x
x x
applicable security posts/patrols.
7.2.5 Report protected area accountability and evacuation X
X X
status to the TSC Manager and EOF Security Manager after receipt of this information from the Security shift supervisor.
7.2.6 As appropriate, evacuate and/or relocate security X
X posts/patrols based on radiological conditions.
7.2.7 Interface with EOF Security Manager to direct emergency x
x response activities.
END OF 7.2, TSC SECURITY SUPERVISION MGR-0001 Rev. 3
SOUTHERN NUCLEAR PAGE PLANT E.I. HATCH 5 OF 12 DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISION/VERSION NUCLEAR SECURITY DUTIES 73EP-EIP-009-0 NO:
7.0 7.3 SECURITY SHIFT SUPERVISOR NUE I ALERT SITE-GENERAL I
AREA 7.3.1 Ensure all Nuclear Security personnel are notified of the X
X X
X emergency and are accounted for.
7.3.2 Direct an NSO to activate the Simulator & Skills Buildings' X
X X
X public address system. This may be activated either in the Secondary Alarm Station (SAS) or in the Simulator Building mechanical room (near the Cafeteria).
7.3.3 Ensure that Nuclear Security Officers (NSOs) are X
X X
X available to escort emergency vehicles and expedite access to the plant, as necessary.
7.3.4 Ensure the applicable sections of the Emergency Call X
X X
List are initiated.
7.3.5 Direct Alarm Station Operator to relay radiological X
X X
condition information to applicable security posts/patrols, as directed by TSC Security Supervisor.
7.3.6 Direct two NSOs to report to the EOF to initiate access X
X X
control. Refer to section 7.8 for EOF Access Control instructions.
7.3.7 When directed, dispatch a NSO to the Emergency News X
X X
Center (ENC) to initiate access control. Refer to section 7.10 for ENC Access Control instructions.
7.3.8 Dispatch NSOs to the owner-controlled area to inform X
X X
personnel of an emergency. Efforts should be made to notify persons in public areas first, THEN all other locations, as identified in form TRN-0147, Plant Hatch Owner Controlled Area. Guidance is also provided in form TRN-01 47 on information to provide to personnel in these locations.
NSOs must ensure the main recreational area gate and the contractor access road gate are secured so that site access is restricted to the main access road.
MGR-0001 Rev. 3
SOUTHERN NUCLEAR PLANT E.I. HATCH PAGE 6 OF 12 DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISION/VERSION NUCLEAR SECURITY DUTIES 73EP-EIP-009-0 NO:
7.0 7.3 SECURITY SHIFT SUPERVISOR (CONT'D)
NOTE:
The Emergency Director may order evacuation of non-essential personnel at any emergency classification.
NUE ALERT SITE-I GENERAL
__AREA 7.3.9 Provide crowd control at rally points, IF necessary.
X X
X X
7.3.10 WHEN advised by the Emergency Director OR Control X
X X
X Room, dispatch roving patrol to open and man Gate 17 for protected area evacuation. Dispatch additional NSOs to assist at Gate 17, as necessary.
7.3.11 Ensure evacuation instructions are conveyed to X
X X
X evacuating personnel by NSOs at the PESB AND/OR Gate 17 rally points, as necessary.
7.3.12 IF the main access road can not be used as a site exit X
X X
X route, coordinate with the Superintendent of Shift
/Emergency Director (SOS/ED) to open the alternate site exit route(s) to allow evacuating personnel to leave the plant site.
7.3.13 Dispatch two NSOs to initiate river patrol.
X X
7.3.14 Dispatch NSO to the TSC and NSO(s) to OSC for X
X X
access control IF the TSC and OSC card readers fail to operate. Refer to section 7.7 for TSC & OSC Access Control instructions.
7.3.15 Compile all accountability reports from locations within X
X X
the Protected Area. Attempt to contact those that have not reported, including determination of the last known location of unaccounted personnel. Refer to 7.13 for instructions to perform accountability.
7.3.16 Report accountability results to the TSC Security X
X X
Supervisor as soon as possible.
7.3.17 Report to the TSC Security Supervisor for further X
X X
instructions.
END OF 7.3, SECURITY SHIFT SUPERVISOR MGR-0001 Rev. 3
SOUTHERN NUCLEAR PAGE PLANT E.I. HATCH 7 OF 12 DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISION/VERSION NUCLEAR SECURITY DUTIES 73EP-EIP-009-0 NO:
7.0 7.4 SECURITY POST 200 CAS AND SAS NUE JALERT SITE-GENERAL AREA 7.4.1 Activate the Emergency Accountability System and x
x x
THEN run an accountability report on the security computer. Forward this report to the Security shift supervisor as soon as possible.
7.4.2 Notify all posts and patrols of emergency and account X
X X
X for all Nuclear Security personnel by using a radio or other means.
7.4.3 Initiate applicable sections of the Emergency Call List, as X
X X
directed.
7.4.4 When directed by the Security shift supervisor, notify x
x x
roving patrol to open and man Gate 17 for protected area evacuation. Dispatch additional NSOs to assist at Gate 17, as necessary.
7.4.5 Relay radiological condition information to applicable x
x x
security posts/patrols, as directed.
END OF 7.4, SECURITY POST 200 CAS AND SAS MGR-0001 Rev. 3
SOUTHERN NUCLEAR PLANT E.I. HATCH PAGE 8 OF 12 DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISION/VERSION NUCLEAR SECURITY DUTIES 73EP-EIP-009-0 NO:
7.0 7.5 SECURITY POST 200 CHARLIE [PLANT ENTRY SECURITY BUILDING (PESB)]
I NUE ALERT SITE-GENERAL AREA 7.5.1 Restrict personnel access to the following groups:
X X
X Southern Company personnel, NRC personnel, and other personnel as authorized by the Emergency Director.
7.5.2 Prepare to assist with protected area evacuation.
X X
X X
7.5.3 IF the computer accountability system is inoperable, X
X X
perform accountability per subsection 7.13 of this procedure.
END OF 7.5, SECURITY POST 200 CHARLIE (PESB)]
7.6 SECURITY POST 200 BRAVO (GATE 1)
NUE ALERT SITE-GENERAL I
AREA j
7.6.1 Restrict personnel access to the following groups:
Southern Company personnel, NRC personnel, and other personnel as authorized by the Emergency Director.
7.6.2 Direct members of the press and the public to the Emergency News Center.
END OF 7.6, SECURITY POST 200 BRAVO (GATE 1)
X X
X x
X X
MGR-0001 Rev. 3
SOUTHERN NUCLEAR PLANT E.I. HATCH PAGE 9 OF 12 DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISION/VERSION NUCLEAR SECURITY DUTIES 73EP-EIP-009-0 NO:
7.0 7.7 TSC AND OSC ACCESS CONTROL NOTE:
TSC and OSC access control are required only IF card readers are inoperable.
NUE ALERT SITE-GENERAL AREA 7.7.1 Restrict personnel access to the following groups:
X X
X Southern Company personnel, NRC personnel, and other personnel as authorized by the Facility (TSC or OSC) Manager.
7.7.2 Log personnel entering OR leaving the facility.
x x
x 7.7.3 Report the names and security badge numbers of facility x
x (TSC or OSC) personnel to the Supervisor Nuclear Security (Shift) as soon as possible.
END OF 7.7, TSC AND OSC ACCESS CONTROL 7.8 EOF ACCESS CONTROL NUE JALERT RE SITE-GENER 7.8.1 Restrict personnel access to the following groups:
Southern Company personnel, NRC personnel, and other personnel as authorized by the EOF Manager.
7.8.2 Log personnel entering OR leaving the EOF.
x x
x x
x x
END OF 7.8, EOF ACCESS CONTROL MGR-0001 Rev. 3
SOUTHERN NUCLEAR PLANT E.I. HATCH PAGE 10 OF 12 DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISION/VERSION NUCLEAR SECURITY DUTIES 73EP-EIP-009-0 NO:
7.0 7.9 RIVER PATROL NUE ALERT SITE-GENERAL AREA 7.9.1 Attach boat to security vehicle, proceed to boat ramp X
X and launch boat.
7.9.2 NSOs will man the boat and patrol the river adjacent to X
X the plant to inform personnel of the declared emergency and request they leave the plant vicinity.
END OF 7.9, RIVER PATROL 7.10 EMERGENCY NEWS CENTER (ENC) ACCESS CONTROL NUE ALERT SITE-GENERAL I
AREA 7.10.1 When directed, NSOs will report to the Emergency News Center (ENC) complex to establish access control.
Contact ENC Facilities/Operations Coordinator upon arrival for instructions.
7.10.2 Direct personnel requesting entry to present a picture ID and state their reason for requesting access. Log all personnel entering the facility and issue the appropriate identification badge.
7.10.3 Restrict access of unauthorized personnel to the Main ENC media building.
X X
X X
X X
END OF 7.10, ENC ACCESS CONTROL MGR-0001 Rev. 3 I
X X
X
SOUTHERN NUCLEAR PLANT E.I. HATCH PAGE 11 0F12 DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISION/VERSION NUCLEAR SECURITY DUTIES 73EP-EIP-009-0 NO:
7.0 7.11 ADDITIONAL SECURITY POSTS NUE ALERT SITE-GEN ERAL AREA "Hotel", "Golf", "Foxtrot", "Echo", "Sierra" and all other security X
X posts not specifically mentioned will perform duties as normal during drills, exercises or actual emergencies unless notified otherwise by the Security Shift Supervisor.
END OF 7.11, ADDITIONAL SECURITY POSTS 7.12 GATE 17 ACCESS CONTROL NOTE:
The Emergency Director may order evacuation of non-essential personnel at any emergency classification.
ý ALERT SITE-GENERAL
-AREA IF the rally point is established at this location, collect the protected area badges of the personnel leaving the protected area. Collected protected area badges will be brought to the PESB to log personnel out of the protected area. IF the security computer is not operable, THEN Security will compare the collected badges to the most recent accountability report to determine those personnel remaining in the protected area.
X X
X X
END OF 7.12, GATE 17 ACCESS CONTROL MGR-0001 Rev. 3
SOUTHERN NUCLEAR PLANT E.I. HATCH PAGE 12 OF 12 DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISION/VERSION NUCLEAR SECURITY DUTIES 73EP-EIP-009-0 NO:
7.0 7.13 ACCOUNTABILITY NOTE:
The Emergency Director may order evacuation of non-essential personnel at any emergency classification.
NUE f ALERT [ SITE- [ GENERAL
__[AREA 7.13.1 Security will ensure that accountability is achieved within 30 minutes of declaration of a Site Area Emergency, General Emergency, or Protected Area evacuation order. Accountability is achieved when all personnel within the Protected Area AND the Vital Area are identified by name or badge number as being in the Protected AND/OR Vital Area at the time of the accountability check. Personnel logged into emergency accountability regions (i.e., control room, OSC, and TSC), after accountability is initiated, will not appear on the emergency accountability report.
7.13.2 Accountability will be conducted in accordance with the following:
IF Security System Computer (SSC) is:
Operational Operational AND Accountability Function is:
Operational NOT Operational THEN:
!Run an Accountability report. The Site-Specific Alarm Station Operators Manual will be utilized for specific steps to access and utilize the accountability function.
Run an ALL REGION ENROLLMENT report.
7.13.3 In the event the Security Access Control system is not operable, Security will collect the protected area badge of each evacuating person. Security will compare the collected badges to the most recent accountability report to determine those personnel remaining in the protected area.
x X
X L
L ______________ L X
X X
END OF 7.13, ACCOUNTABILITY MGR-0001 Rev. 3 I
I
SOUTHERN NUCLEAR DOCUMENT TYPE:
PAGE PLANT E.I. HATCH EMERGENCY PREPAREDNESS PROCEDURE 1 OF 7 DOCUMENT TITLE:
DOCUMENT NUMBER:
REVISIONNERSION ASSEMBLY, ACCOUNTABILITY AND EVACUATION 73EP-EIP-011-0 NO:
4.0 EXPIRATION JAPPROVALS:
DATE:
DEPARTMENT MANAGER N/A NPGM/POAGM/PSAGM JCL JAB DATE 7/10/02 DATE 7/11/02 EFFECTIVE DATE:
7/12/2002 1.0 OBJECTIVE This procedure provides instructions for assembly, accountability, and evacuation of site personnel during a declared emergency.
TABLE OF CONTENTS Section 7.0 7.1 7.2 7.3 Title PROCEDURE INVOLVED PERSONNEL NON-INVOLVED PERSONNEL (INSIDE THE PROTECTED AREA)
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4 NON-INVOLVED PERSONNEL (OUTSIDE THE PROTECTED AREA)
Page 2
3 5
2.0 APPLICABILITY This procedure applies to the activities and responses of personnel that are necessary to assemble, account for, and evacuate site personnel during an emergency. This procedure is performed as required.
3.0 REFERENCES
3.1 3.2 3.3 10AC-MGR-006-0, Hatch Emergency Plan Edwin I. Hatch Unit 1 & Unit 2 Emergency Plan 73EP-EIP-009-0, Nuclear Security Duties 4.0 RESPONSIBILITIES 4.1 PERSONNEL REQUIREMENTS Personnel who conduct assembly, accountability, and evacuation of personnel will receive indoctrination and training in applicable emergency implementing procedures.
4.2 MATERIAL AND EQUIPMENT N/A - Not applicable to this procedure MGR-0002 Rev. 8 L
I
SOUTHERN NUCLEAR PLANT E.I. HATCH PAGE 2OF7 DOCUMENT TITLE:
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REVISION/VERSION ASSEMBLY, ACCOUNTABILITY AND EVACUATION 73EP-EIP-01 1-0 NO:
4.0 4.3 SPECIAL REQUIREMENTS N/A - Not applicable to this procedure 5.0 PRECAUTIONS/LIMITATIONS 5.1 PRECAUTIONS Uncertain or varying levels of radiation and/or contamination may be encountered.
5.2 LIMITATIONS N/A - Not applicable to this procedure 6.0 PREREQUISITES A declared emergency OR an emergency drill/exercise must exist before using this procedure.
REFERENCE 7.0 PROCEDURE 7.1 INVOLVED PERSONNEL INUE [ALERT] SITE-fGENERAL
___AREA 7.1.1 Report incident status to the Control Room and take actions to limit the incident, IF possible. Retreat to an X
X X
X unaffected area.
7.1.2 Report to the Health Physics Office for contamination surveys and decontamination, IF applicable.
X 7.1.3 Contact Health Physics in the Operations Support Center (OSC) for contamination surveys and X
X decontamination.
END OF 7.1, INVOLVED PERSONNEL MGR-0001 Rev. 3
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4.0 7.2 NON-INVOLVED PERSONNEL (INSIDE THE PROTECTED AREA)
NOTE:
Personnel actions (i.e., emergency response facility activation, escorting visitors to the PESB, evacuation from the site, etc.) may be delayed as a result of a security event, severe weather conditions or other hazards to personnel safety.
I NUE ALERT SITE- [GENERAL
____________________________ AREA 7.2.1 Observe the Public Address (PA) announcements and/or warning signals for emergency information (i.e.,
X X
X X
declaration, upgrades in severity and evacuation orders). Stay clear of affected areas.
7.2.1.1 Remain at your present location until further notice IF a security emergency is occurring.
X X
X X
7.2.2 Stand by for an escalation in emergency classification and continue normal work activities until advised x
otherwise.
7.2.3 Emergency Response Organization members will report to assigned facility [Technical Support Center (TSC),
X X
x Operations Support Center (OSC) or Emergency Operations Facility (EOF)].
7.2.4 Escort all escorted personnel to Plant Entry Security Bui ding (PESB) for processing out. These persons will X
X X
be firected to report to the Simulator cafeteria and await furti er instructions on actions to be taken.
7.2.5 Department supervisory personnel will account for personnel under their supervision. The names of X
personnel who are unaccounted must be immediately repo rted to Security at the PESB.
7.2.6 Sec ure your work location. IF in a contaminated area, follow normal undressing and frisking procedures as x
time allows. THEN, go to your reporting area and await further instructions.
7.2.7 Secure your work location. IF in a contaminated area, follow normal undressing and frisking procedures as X
time allows.
MGR-0001 Rev. 3
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REVISION/VERSION ASSEMBLY, ACCOUNTABILITY AND EVACUATION 73EP-EIP-011-0 NO:
4.0 7.2 NON-INVOLVED PERSONNEL (INSIDE THE PROTECTED AREA) (CONT'D)
NOTE "
The Emergency Director may order evacuation of non-essential personnel at any emergency classification.
Unless otherwise specified, the rally points designated for use are the Plant Entry Security Building (PESB) or Gate 17 (Northwest section of the protected area).
NUE 1 ALERT SITE-GENERAL AREA 7.2.8 Leave the protected area, using the designated rally X
X X
X point, as directed by PA announcement and/or Nuclear Security personnel. Turn in your protected area badge, IF directed to do so by Security personnel. Submit to radiological monitoring as directed by the Rally Point Team. Report to the Simulator cafeteria and await further instructions on actions to be taken.
7.2.9 Leave the plant site using specified site exit routes as directed by PA announcement and/or Nuclear Security X
X X
X personnel.
IF DIRECTED, report to the appropriate State Reception Center for contamination monitoring IF a radiological release is underway AND radiological monitoring at the plant site is not feasible. Areas designated as State Reception Centers are shown in Attachments 1 & 2.
END OF 7.2, NON-INVOLVED PERSONNEL (INSIDE THE PROTECTED AREA)
MGR-0001 Rev. 3
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REVISION/VERSION ASSEMBLY, ACCOUNTABILITY AND EVACUATION 73EP-EIP-01 1-0 NO:
4.0 7.3 NON-INVOLVED PERSONNEL (OUTSIDE THE PROTECTED AREA)
NOTE:
Personnel actions (i.e., emergency response facility activation, escorting visitors to the PESB, evacuation from the site, etc.) may be delayed as a result of a security event, severe weather conditions or other hazards to personnel safety.
NUE ALERT SITE-GENERAL AREA 7.3.1 When notified, Emergency Response Organization members will report to their assigned facility (TSC, OSC, X
X X
or EOF).
7.3.2 IF in areas with a PA system, personnel will observe PA announcements/ warning tones and stay clear of X
X X
X affected areas.
7.3.3 IF in areas without a PA system, personnel will observe instructions provided by Security, stay clear of affected X
X X
areas, secure their work location and THEN report to the Simulator Building cafeteria for further instructions.
NOTE :
0 The Emergency Director may order evacuation of non-essential personnel at any emergency classification.
Unless otherwise specified, the rally points designated for use are the Plant Entry Security Building (PESB) or Gate 17 (Northwest section of the protected area).
NUE ALERT SITE-GENERAL 7.3.4 Leave the plant site using specified site exit routes as directed by PA announcement and/or Nuclear Security X
X X
personnel. IF DIRECTED, report to the State Reception Center IF DIRECTED, report to the appropriate State Reception Center for contamination monitoring IF a radiological release is underway AND radiological monitoring at the plant site is not feasible. Areas designated as State Reception Centers are shown in Attachments 1 & 2.
END OF 7.3, NON-INVOLVED PERSONNEL (OUTSIDE THE PROTECTED AREA)
MGR-0001 Rev. 3
SNC PLANT E.I. HA:TFCýH Pg. 6 of 7 DOCUMENT TITLE:
DOCUMENT NUMBER:
Rev/Ver No:
ASSEMBLY, ACCOUNTABILITY AND EVAUCATION 73EP-EIP-011-0 4.0 ATTACHMENT 1 TITLE: STATE RECEPTION CENTER-APPLING COUNTY Att. Pg.
1 of 1 To Lyons N
W -44.t~ll E
s To Hazlehurst Plant Hatch To Bristol BAXLEY Appling Co High School To Alma Directions to State Reception Center (at Appling Co. High School):
Travel south from Plant Hatch on U.S. Hwy 1 for approximately 13 miles to Hwy 15. Bear left on Hwy 15 and travel approximately 3/4 mile to the school (on the right).
MGR-0009 Rev. 4
SNC PLANT E.I. HATCH I
DOCUMENT TITLE:
ASSEMBLY, ACCOUNTABILITY AND EVAUCATION ATTACHMENT 2 TITLE: STATE RECEPTION CENTER - TOOMBS COUNTY N
V S
To Vidalia DOCUMENT NUMBER 73EP-EIP-011-0 LYONS 1
Plant Hatch To Baxley Directions to State Reception Center (at Toombs Co. High School):
Travel north from Plant Hatch on U.S. 1 for approximately 15 miles to County Road 115 (Aimwell Road Extension). Turn left onto County Road 115 and travel until it intersects with County Road 337 (Lyons Center Road). Turn right onto County Road 337 and travel approximately 2 miles to the school (on your left).
MGR-0009 Rev. 4 Pg. 7 of 7 Rev/Ver No:
4.0 Att. Pg.
1 of 1